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Neutron production cross sections and energies for the reactions T(p,n)3He, D(d,n)3He, and T(d,n)4He
NUCLEAR DATA TABLES 11, 569-619 (1973)
NEUTRON PRODUCTION CROSS SECTIONS AND ENERGIES FOR THE REACTIONS T{p,n)me,
D(4ii)3He, AND T(4n)*He
HORST LISKIEN and ARNO PAULSEN Joint Nuclear Research Center Central Bureau for Nuclear Measurements, Geel, Belgium Center-of-mass best values for the normalized Legendre coefficients and the 0° differential cross section as functions of input energy have been derived from various experimental results for the reactions T(jp,n)^He, Y>{d,nfHe, and T(cf,«)''He. This information has been used to calculate laboratory differential cross sections as functions of laboratory input energy and neutron emission angle which are given in tabular form with the corresponding neutron energy.
^
• U * /5^ i m T
U
A
J
•
n
T
Copyright © 1973 by Academic Press, Inc. All rights of reproduction in any form reserved.
569
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H. LISKIEN AND A. PAULSEN
CONTENTS
INTRODUCTION Scope Procedure Conclusions References for Introduction
570
REACTION T{p,nfHe a (0° cm.), Legendre Coefficients (cm.), a (total): Recommended and Experimental Values
574
a (0 lab), E„ (0 lab): Recommended Values REACTION D(4«)3He a (0° cm.), Legendre Coefficients (cm.), a (total): Recommended and Experimental Values
586
a (0 lab), E„ (6 lab): Recommended Values REACTION T(4n)4He a (0° cm.), Legendre Coefficients (cm.), a (total): Recommended and Experimental Values
601
a (6 lab), E^ (0 lab): Recommended Values APPENDIX. Program for Calculation of Laboratory a's from cm. Values
616
REFERENCES FOR EXPERIMENTAL DATA
618 It was restricted to the proton or deuteron laboratory input energy range (from threshold) up to 10 MeV which is most important from the point of view of neutron production. Experimental results above 10 MeV were taken into account for determining the recommended curves near 10 MeV. The scope of this work does not include data about spurious neutrons from the break-up of the product nucleus (tertiary reactions) which appear at higher input energies. The same is true for all (p,n) or (d,n) reactions with the material of the target support. This review includes a tabulation of recommended neutron energies. For the calculation of these neutron energies and other kinematic parameters needed for the transformation between the laboratory (lab) and the center-of-mass (cm.) system the most recent nuclear mass tables'^ and relativistic formulas* were used. The following table presents the reaction g-values and compares thresholds with those for possible tertiary reactions.
INTRODUCTION There is an urgent need for an evaluation of data on the neutron source reactions T(^,«)^He, D{d,n)^lie, and T(4«)*He which are known as monoenergetic neutron sources (for a given neutron emission angle 0) and which play an important role in neutron metrology. The earlier reviews in this field^"^ are about ten years old and do not contain recommended results in numerical form. The present paper is a result of the completion and reevaluation of the authors' recent work*'^ with December 1972 as cutoff date. Scope This work presents recommendations based on a data compilation of differential and integrated (with respect to the neutron observation angle ^) cross sections.
Reaction
g-Value, MeV
Threshold, MeV
T(p,n)^He
-0.764
1.019 forew. 1.147 backw.
D{d,nfiie
Tid,n)me
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
Break-up Reaction
Threshold, MeV
T(p,np)D
8.35
-(-3.269
D(d,np)D
4.45
-1-17.590
T(d,npyT T(d,2nfiie
3.71 4.92
570
NEUTRON PRODUCTION CROSS SECTIONS
cosine serial expansion or as asymmetry or Legendre coefficients. In the cases where only differential cross sections have been given the data were least-squares fitted. The number of coefficients at a given energy was limited in such a way that the last coefficient was shown to be nonzero by the compilation. If the number of reported coefficients disagreed, a refitting procedure with the right number of coefficients was carried out as far as possible. The recommended curves were obtained by starting from smooth eye guides through the experimental Ai values. Then an iterative procedure was followed for renormalizing and resmoothening of these Ai curves. No attempt was made to fit the energy dependence of the Legendre coefficients to theoretical expressions from direct interaction theory because it is known that the considered data are at least partially in contradiction to the direct interaction mechanism.
Procedure The collected data were transformed, if necessary, into the T(p,nfne, D(d,nfne, and T(4n)*He centerof-mass systems, respectively. The compilation comprises, of course, experimental results which were obtained with exchange of target and projectile particles, or by observation of the product nucleus instead of the neutron. Experimental results obtained with thick targets were not taken into consideration. The validity of time reversal allows the calculation of cross sections from those of the inverse reaction by means of the reciprocity theorem. This principle is very strict and is not subject to any correction. Therefore data of this kind were considered. Only integrated cross sections of the reactions ^Hc{n,p)T and ^}ie(n,d)D had to be converted. This was done by means of the equations: «p.»(£p) = On,,(E„) -^
for mc(n,p)
data
with
0° Differential Cross Sections The compilation of 0° differential center-of-mass cross sections includes data which have been obtained by conversion by means of the recommended ^^ values and the expression
Ep = E„+ 1.019 MeV, and '^a,niEa) = ^nAiK) -r
for 3He(«,<^) data
with E^=. 1.499 £ „ - 6 . 5 3 8 MeV.
-(0°) = dui
Similar cross sections for reactions in which an involved neutron is replaced by a proton or vice versa [for example D(J,/?)T and Y>(d,nf\it or 3He(^,/>)*He and T(4n)*He] are predicted if nuclear forces are charge independent. However, the necessary corrections due to the influence of the Coulomb force are model dependent. Therefore such data have not been taken into account. For the parametrization of the differential centerof-mass cross sections we chose the form
^ -
Air Ac,
au)
2 A,p,(e)
The determination of the 0° differential centerof-mass cross section "best curve" following the eyeguide method was the next step. For the reaction T(d,nyKc the deuteron energy range from 0 to 300 keV forms an exceptional case. Within this range the reaction is isotropic in the centerof-mass system. This range contains also a dominating cross-section resonance with a peak value at 107 keV. Therefore the 0° differential center-of-mass crosssection data (which differ only by a factor of 477 from the integrated cross sections) were fitted to the BreitWigner-Eisenbud resonance formula
which implies the normalization
^(P:0)
do:^ ' ^
££2
= J:
3kl 4(£'o + ^^ + ^2- Ef + (r, -i- v^f'
In this formula index 1 indicates the scattering and index 2 the reaction channel. Two simplifications are made, namely that the entrance channel contains only j-waves and that the reaction radius a is identical for both entrance and exit channel. The widths are given by
i
This representation eliminates from the angular distributions systematic errors in the absolute cross-section scale. Relative Angular Distributions
'
Normalized Legendre coefficients have been calculated if the results were reported as coefficients of a
FHx^,7,) + G^ (x^,yi)
and 571
Nuclear Data Tables, Vol. U , No. 7, 1973
H. LISKIEN AND A. PAULSEN
r.
2-k.
Consequently there are four fitting parameters: the reaction radius a, the reduced widths yf and y|, which should not exceed the Wigner Umit 31i^/2n^a, and the resonance energy EQ. The solid line shown in the figure for the T(4n)*He 0° c m . cross section is the result of this fit. Special care was taken to match the eye-guide curve to this fit at 300 keV. The final parameters are compared below with those of earlier fits:
2 • Y2 ' ^ 2
where F and G are Coulomb functions for / = 0, rj is the charge parameter e^^^/fi^k^ (jx = reduced mass) and x^ = k^a and X2 = k2a. The level shifts are given by Ai = - - i {FF' + G G')
and
Aj =
r, 3 + 2x1
Ref.
yf(MeV . fm)
Yi(MeV • fm)
^o(MeV)
a(fm)
9 9 10 11 this evaluation
3.3 5.0 10.0 6.0 6.5
O.Il 0.12 0.28 0.12 0.15
-0.067 -0.126 -0.464 -0.144 -0.179
7 7 5 7 6
It seems that A2, which is nearly constant, is included in the value for E(, for the sets reported in Ref 9 and 10.
Conclusions Although "uncertainties" are often quoted in the published articles, they often are explained insufficiently or account only for a part of the error sources involved (for example uncertainties given for Legendre coefficients typically reflect only the consistency between data and the polynomial fit). Therefore the recommended curves do not account for the uncertainties quoted by the experimentalists. The best curves are of course subject to some arbitrariness as the authors have their own opinion about the reliability of the different measurements. Unfortunately in several publications the results are given only as plots which are difficult to read accurately. In these cases it was best to read the results by means of an elastometer. It is strongly recommended to publish all results in numerical form together with sufficient information about the uncertainty contribution of the different error sources.
Integrated Cross Sections The applied procedure fixes a "best curve" for the integrated cross section a according to the equation a = 4ITAQ [da/du (0°)]. An iterative smoothening procedure applied to 6?a/fi?w(0°) and a was allowed for. The comparison of the resulting integrated cross-section curve with experimental integrated cross sections directly reported as such in the literature was considered only as a cross-check. Differential Laboratory Cross Sections and Neutron Energies Finally recommended values of differential lab cross sections, a (6 lab) were calculated for practical use from the recommended center-of-mass Legendre coeflficients and the 0° cross sections. Neutron energies E„ (6 lab) are presented on the facing page. For the input energy, steps of 10 keV were chosen between 20 and 100 keV, of 50 keV between 0.1 and 1 MeV, of 100 keV between 1 and 3 MeV, and of 500 keV between 3 and 10 MeV. Steps of 5° were chosen for the emission angle. If laboratory data at intermediate energies are needed, it is recommended not to interpolate the tabulated laboratory values but instead the center-of-mass input data and to use the provided FORTRAN program (APPENDIX) to calculate the lab differential cross sections. The three dimensional plots^^ allow a quick survey of the lab differential cross sections.
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
The absence of reliable information on the uncertainties of the measured quantities, as mentioned in the paragraph above, implies the difficulty in stating accuracies for the evaluated quantities. The mean deviation between the experimental data (as far as they influenced the evaluation, see figures) and the recommended curve reflects the consistency of the data. However, if there are sufficient independent data (which can be confirmed for the largest part of these evaluations) this mean deviation can be considered also as a measure of the uncertainty of the recommended curve. Here are the results averaged over the considered energy range and for the Legendre coeflicients also averaged over all indices:
572
NEUTRON PRODUCTION CROSS SECTIONS
Reaction
very useful in these energy regions. The present evaluation indicates that the data for the reaction D{d,n)^iie can be considered as being satisfactory with respect to completeness and consistency. For the reaction T(d,«)*He the number of reported angular distributions is not satisfying. Here, especially at energies above 5 MeV, further investigations would be worthwhile. Finally, it should be mentioned that according to the reciprocity theorem for nuclear reactions (see Procedure) the presented evaluations can be converted easily to the corresponding data for the inverse reactions. For the reactions ^He(«,^)T and ^He(«,^)D, which are of practical interest for neutron detectors, this conversion was already carried out.^^
Legendre 0° c m . Integrated Coefficients, Cross Section, Cross Section, Abs. Dev. Rel. Dev. Rel. Dev.
T(/7,«)3He D(4«)3He
0.03 0.01
0.07 0.04
0.07 0.05
T(rf,«)*He
0.01^
0.03* 0.041-
0.07+
* below 300 keV only + above 300 keV For the reaction T(/7,n)^He there are no reliable experimental data about the angular distributions between foreward and backward threshold. Therefore the evaluation for this reaction was limited to the energy region between backward threshold and 10 MeV, but also between backward threshold and 2 MeV the Legendre coefficients are markedly more uncertain than at higher energies. Further experimental work will be
Acknowledgments The authors gratefully acknowledge the cooperation of M. D. Goldberg, J. E. Simmons, J. D. Seagrave, and J. L. Weil in sending unpublished material and proposing ameliorations.
References for Introduction 1. J. L. Fowler and J. E. Brolley, Jr., Rev. Mod. Phys. 28, 103 (1956)
7. A. H. Wapstra and N. B. Gove, Nucl. Data Tables 9, 265 (1971)
2. J. E. Brolley, Jr., and J. L. Fowler, Fast Neutron Physics (J. B. Marion and J. L. Fowler, ed.) Vol. I, p. 73, Interscience Publishers, Inc., New York (1960)
8. H. Horstmann and H. Liskien, "Relativistic Calculations of Kinematic Parameters for Nuclear Reactions," Report EUR 3668.e (1968)
3. M. D. Goldberg, Progress in Fast Neutron Physics (G. C. Phillips, J. B. Marion, and J. R. Risser, ed.) p. 3, University of Chicago Press, Chicago (1963)
9. H. V. Argo et al., Phys. Rev. 87, 612 (1952) 10. J. P. Conner, T. W. Bonner, and J. R. Smith, Phys. Rev. 88, 468 (1952)
4. H. Liskien and A. Paulsen, "An Evaluation for Cross Sections of the Reaction D(d,n)^He" Report EANDC(E)-143"L" (1971)
11. E. M. Balabanov et al., Atomnaya Energiya Suppl. 5, 43 (1957)
5. A. Paulsen and H. Liskien, "An Evaluation for Cross Sections of the Reaction T(d,nyHe," Report EANDC(E)-144"L" (1972)
12. G. Nastri and C. Cervini, "The Three-Dimensional Plotting Program TRICE," Report EUR 4484.e (1970)
6. H, Liskien and A. Paulsen, "An Evaluation for Cross Sections of the Reaction T(p,n)^He" Report EANDC(E)-152"L" (1972)
13. A. Paulsen and H. Liskien, Proc. Second IAEA Panel on Neutron Standard Reference Data, Vienna (1972) to be published
573
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
H. LISKIEN AND A. PAULSEN
Jip,n)me a(0° cm.), Legendre Coefficients (cm.), a(total) Recommended and Experimental Values a(e lab), E„{e lab) Recommended Values
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
5 7 4
NEUTRON PRODUCTION CROSS SECTIONS
T(p,n)^He. 0(0" cm.), Legendre Coefficients, a(total) Recommended and Experimental Values SIGMA-0 AO, A l , . . . SIGMA-T
(7(0° cm.) Legendre coefficients a(total)
Recommended Data ENERGY (MEV)
SIGMA-0 (MB/SR)
AO
Al
A2
A3
215. 246. 274. 302. 328. 354. 380. 406. 432.
1.200 1.300 1.400 1.500 1.600 1.700 1.800 1.900 2.000
16.2 17.6 19.1 20.7 22.3 24.0 25.8 27.7 30.0
1.056 1.112 1.142 1.161 1.170 1.174 1.172 1.166 1.146
-0.076 -0.220 -0.340 -0.435 -0.516 -0.580 -0.627 -0.660 -0.674
0.020 0.108 0.198 0.274 0.346 0.406 0.455 0.494 0.528
2.100 2.200 2.300 2.400 2.500 2.600 2.700 2,800 2.900 3.000
33.0 36.3 40.4 44.7 48.7 52.5 55.2 57.4 58.6 59.4
1.100 1.047 0.980 0.909 0.H56 O.BIO 0.783 0.764 0.752 0.745
-0.660 -0.631 -0.582 -0.533 -0.502 -0.477 -0.463 -0.455 -0.451 -0.450
0.563 0.591 0.613 0.639 0.664 0 . 6 90 0.708 0.724 0.740 0.753
-0.003 -0.007 -0.011 -0.015 -0.018 -0.023 -0.028 -0.033 -0.041 -0.048
3.500 4.000 4.500 5.000 5.500 6.000 6.500 7.000 7.500 8.000 8.500 9.000 9.500 10.000
58.1 50.9 42.2 35.3 29.4 24.8 21.1 18.4 16.4 15.2 14.5 14.0 14.1 14.4
0.738 0.753 0.784 0.827 0.888 0.963 1.039 1.104 1.153 1.167 1.146 1.107 1.050 0.984
-0.472 -0.520 -0.576 -0.635 -0.699 -0.768 -0.840 -0.901 -0.933 -0.900 -0.831 -0.751 -0.667 -0.560
0.832 0.910 0.990 1.069 1.148 1.228 1.301 1.367 1.361 1.273 1.159 1.036 0.920 0.796
-0.098 -0.167 - 0 . 2 54 -0.355 -0.478 -0.617 -0.760 -0.901 -0.979 -1.000 -0.987 -0.945 -0.879 -0.801
575
SIGMA-T (MB)
/44
456. 477. 497. 511. 524. 534. 543. 551. 554. 556. 0 .. 0 2 4 0 ,. 0 5 6 0 ., 0 9 4 0 ,. 1 4 1 0 .. 1 9 4 0 .. 2 6 0 0 ,. 3 3 1 0 .. 3 9 8 0 ,. 4 6 0 0 .. 5 1 3 0 ,. 5 5 3 0 ,. 5 7 6 0 ,. 5 8 1
539. 482. 416. 367. 328. 300. 275. 255. 238. 223. 209. 195. 186. 178.
Notleor Dato Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(p,n)^lie.
o
• AL56 OBASS * BOSS + C»70 o 6159 A G0«1B V JA56B • MASS 0 MC73A ® m « A • o
knb/sr)
)hL
° T(p.n
o
Ref. 60-
o(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values
'•i
/J?
SA61 SEGO srs6 VL56 WIS3 WI61
g«
0
•
^ 0
A
o
Jo-
1
oJ
jro
rf 0
^ \
mJr^v
V!^
020
3a
40
Ep [MeV|
5J0 SO 70 8.0 9.0100
2X)
•
Ep
3.0 io [MeVl
i.0
e.0 70
aoaoKto
•
Legendre Coefficients Experimental and Recommended Values
a(0° cm.)- Experimental and Recommended Values
T(p.n)'He
2.0
M Ep
lM*|
4X1
5.0
M
70 8iJ 9X) mO 0'
«•
30"
60*
90'
120'
150'
180'
a(9, Ep). Recommended Values
a(total). Experimental and Recommended Values
Solid line shows recommended values. Only experimental data which contributed to the recommended values are plotted. References are on page 618
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
576
NEUTRON PRODUCTION CROSS SECTIONS
T(p,«)3He. a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values EXPERIMENTAL 0 DEGREE C M .
EP(MeV) 1.150 1.160 1.170 1.174 1.179 1.180 1.190 1.195 1.203 1.208 1.220 1.220 1.227 1.232 1.237 1.237 1.248 1.250 1.250 1.260 1.261 1.266 1.280 1.301 1.307 1,330 1.330 1.343 1.350 1.350 1.356 1.370 1.380
l:t?8 1.410
1.420 1.420 1.430 1.454 1.467 1.470 1,470 1.490 1.500 1.520 1.550 1.550 1.550 1.560 1.569 1.580 1.583 1.590 1.600 1.613 1.620 1.620 1.620 1.640 1.688 1.690 1.700 1.704 1.750 1.760 1.770 1.800 1.800 1.804 1.810 1.812 1.820 1.828 1.840 1.920 1.920 1.923 1.958 1.960 1.966 1.970 1.997 2.000 2.000 2.020
SIGMA-0 14.7 13.1 12.9 15.5 15.5 12.7 11.3 16.2 16.5 16.3 13.5 14.1 18.9 17.0 16.9 16.0 16.8 14.9 15.0 12.1 18.0 17.8 14.9 17.5 18.9 17.2 16.2 18.0 16.9 15.7 18.4 16.3 17.6
11:^7
16.3 18.9 17.0 14.6 20.2 19,2 20.1 19.2 21.7 21.7 19.4 21.8 17.8 18.2 20.5 22.8 19.8 22.2 21.6 18.2 23.2 19.0 23.5 20.3 23.2 23.8 20.5 24.4 23.4 24.7 25.7 25.9 22.5 22.8 26.9 28.5 26.5 21.8 24.4 26.2 27.3 23.5 28.0 26.3 28.7 27.4 20.3 29.8 31.0 30.0 31.9
REF. MA65 AL56 WI53 MA65 MA65 WI53 JA56B GI59 MA65 MA65 WI53 BA55 GI59 MA65 MA65 GI59 GI59 WI53 AL56 JA56B MA65 MA65 WI53 GI59 MA65 AL56 WI53 GI59 WI53 BA55 GI59 C070 WI53 VL55 cn50 cnso WI63 BASS JA56B GI59 GI59 WIb3 C070 AL56 PE69 BA55 WI53 C050 C050 C050 GI59 C050 GI59 C070 C050 PE59 JA56B AL56 BA55 WI53 GI59 BA55 WI53 GI59 PE59 C070 WI53 C050 C050 GI59 GI59 GI59 BA55 GI59 WI53 WI53 JA56B PE59 GI59 WI53 GI59 SA61 GI59 WI53 AL56 C070
EP(MEV)
2.020 2.020 2.080 2.091 2.099 2.180 2.196 2.220 2.240 2.249 2.250 2.260 2.260 2.260 2.320 2.404 2.420 2.458 2.460 2.480 2.500 2.560 2.600 2.619 2,620 2.620 2.660 2.666 2.690 2.720 2.740 2.770 2.790 2.800 2.820 2.820 2.840 2,841 2.845 2.850 2.870 2.872 2.880 2.900 2.920 2.950 2.970 2.970 3.000 3.010 3,020 3,040 3.074 3.078 3.080 3.090 3.110 3.150 3.240 3,284 3.290 3.290 3.300 3.309 3,450 3.488 3.490 3.520 3.520 3.520 3.520 3.550 3.559 3.650 3.690 3.690 3.693 3.740 3.819 3.819 3.850 3.897 3.900 3,900 3.940
CROSS SECTION FOR THE REACTION T ( P , N » H e 3 SIGMA-0
31.5 30.2 32.4 29.6 30.0 35.7 36.4 32,9 32.1 38.4 35.1 37.7 32.4 33.1 40.4 46.2 43.8 46.0 42.1 45.1 45.6 44.7 48.2 55.8 42.3 45.8 48,2 52,4 49,1 49.7 50.0 50.5 51.1 50.4 50.4 54.5 50.5 61.2 62.9 51.9 49.7 56,3 50,8 51,0 51,5 52,1 52.6 52,0 52.2 52.5 51.6 53.1 64.4 57.9 53.7 53,5 52,3 52,7 52,0 57,9 50.7 52.5 51.0 62.8 49.2 56.6 49.9 34.0 38.4 42.2 42.5 48.1 60.7 47.1 45.5 56.5 54.1 45.6 57.3 55,6 44,6 51.2 43.6 44.7 44.3
577
REF. SE60 BA55 WI53 GI59 GI59 WI53 GI59 BA55 C050 PE59 JA56B WI53 C050 C050 WI53 GI59 WI53 PE59 JA56B WI53 VL55 JA56B WI53 GI59 C050 C050 JA56B PE59 WI53 WI53 WI53 WI53 WI53 WI53 WI53 AL56 WI53 GI59 GI59 WI53 JA56R PE59 WI53 WI53 WI53 WI53 MI53 JA56B WI53 W153 SE60 WI53 GI59 PE59 JA56B WI53 WI53 WI53 WI53 PE59 W153 JA56B VL55 GI59 WI53 PE59 JA56B C050 C050 C050 C050 WI53 GI59 WI53 JA56B SA61 PE59 WI53 GI59 GI59 WI53 PE59 VL55 JA56B WI53
EP(MEV) 4.000 4.020 4.070 4.079 4,100 4.101 4.160 4.200 4,250 4,300 4,359 4.370 4.400 4.500 4.520 4.600 4.619 4.630 4.700 4.720 4.840 4.920 .923 .940 .940 .000 .000 _.060 5.216 5.250 5.300 5,440 5,500 5,900 5,940 6,000 6.000 6.000 6.020 6.100 6.400 6.440 6.450 6.500 6.700 6.800 6.850 6,940 7.000 7.000 7.100 7.250 7.400 7.430 7.600 7.700 7.750 7.930 8.000 8.000 3.000 8.100 8.100 8.300 8.450 8.450 8.600 8.650 8.800 8.800 8.800 8.800 8.930 9.000 9.000 9.090 9.150 9.350 9,420 9,500 9,700 9.800 9.850 9.920 10.000
SIGMA-0
REF.
51.5 43.9 41.6 52.8 40.6 47.8 40.6 42.1 39.6 40.6 47.6 38.2 43.5 37.1 33.8 36.7 43.5 36.9 38.9 35.5 34.9 40.3 38.3 33.8 35.4 35.1 37.8 33.0 35.9 30.7 31.8 29.6 28.7 24.9 25.0 23.1 24.9 26.1 23.2 22.3 19.9 21.3 22.7 19.4 18.3 17.7 20.4 19.0 18.8 19.5 19.5 18.6 18.3 16.7 17.2 16.0 16.9 15,2 13.7 15,8 15,7 15,6 15,4 14.9 14.9 14.6 14.4 14.6 14.5 14.8 14.6 9.8 14.3 14.5 14.8 13.6 14.5 14.5 14.1 13.9 14.0 14.1 13.9 14.4 15.2
MC73A 0050 W153 GI59 JA56B PES? WI53 VL55 WI53 G061B GI59 WI53 PE59 WI53 SE60 VL5B GI59 WI53 PE59 WI53 WI53 GI59 GI59 WI53 WI61 PE59 MC73A WI53 GI59 PE59 VL55 WI61 PE59 VL55 WI61 8059 PE59 MC73A SA61 8059 VL55 WI61 B059 G061R VL55 VL55 8059 WI61 8059 MC73A 8059 8059 B059 WI61 8059 B059 8059 WI61 G061B 8059 MC73A B059 B059 B059 WI61 B059 MC73A B059 B059 G061B B059 ST56 WI61 B059 MC73A SA61 8059 B059 WI61 B059 B059 B059 B059 WI61 MC73A
Nuclear Data Tables, Vol. ) I , No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(p,n)^He. a(0° cm.), Legendre Coefficients, o(total) Recommended and Experimental Values NORMALIZED EXPERIMENTAL LEGENDRE COEFFICIENTS FOR THE REACTION
EP(MEV)
1.190 1.200 1.260 1.400 1.400 1.430 1.500 1.600 1.613 1.620 1.690 1.750 1.920 1.923 2.060 2.249 2.250 2.450 2.458 2.460 2.500 2.500 2.560 2.660 2.666 2.850 2.870 2.872 2.970 3.000 3.000 3.000 3.078 3.OHO 3.2S0 ^.i>bl.) 3.2H4 3.290 3.300 3.400 3.488 3.490 3.690 3.693 3.700 3.897 3.900 3.900 4.100 4.101 4.101 4.140 4.300 4.400 4.600 4.610 4.700 4.940 5.000 5.000 5.090 5.250 5.300 5.440 5.500 5.900 5.940 6.000 6.400 6.440 6.500 6.800 6.800 6.940 7.000 7.430 7.930 8.000 8.450 8.800 8.900 8.930 9.420 9.920 10,000
Nuclear Data Tables, Val. I I , No. 7, 1973
AO
0.919 1.065 1.064 1.074 1.349 1.110 1.163 1.109 1.192 1.136 1.154 1.217 1.138 1.196 1.064 1.002 0.951 0.822 0.875 0.840 0.957 0.845 0.847 0.768 0.802 0.771 0.749 0.761 0.736 0.758 0.791 0.760 0.728 0.719 0.756 0.R07 0.731 0.72H 0.R95 0.738 0.722 0.732 0.828 0.766 0.812 0.770 0.808 0.938 0.820 0.773 0.776 0.880 0.788 0.803 0.965 0.886 0.816 0.827 0.975 0.848 0.716 0.857 0.966 0.910 0.922 1.188 0.948 0.958 1.333 1.022 1.111 1.304 1.174 1.101 1.088 1.156 1.170 1.184 1.144 1.112 1.324 1.090 1.057 1.058 1.031
Al
0.112 -0.083 -0.074 -0.282 -0.694 -0.357 -0.509 -0.393 -0.511 -0.398 -0.588 -0.695 -0.592 -0.713 -0.542 -0.615 -0.519 -0.449 -0.536 -0.472 -0.351 -0.500 -0.499 -0.428 -0.488 -0.472 -0.395 -0.451 -0.424 -0.469 -0.476 -0.504 -0.437 -0.405 -0.497 -0.531 -0.452 -0.43H -0.454 -0.400 -0.459 -0.470 -0.565 -0.519 -0.538 -0.519 -0.540 -0.502 -0.561 -0.502 -0.543 -0.681 -0.568 -0.584 -0.594 -0.705 -0.609 -0.593 -0.883 -0.642 -0.455 -0.661 -0.619 -0.700 -0.731 -0.963 -0.733 -0.734 -1.141 -0.811 -0.990 -1.063 -0.942 -0.905 -0.874 -0.919 -0.953 -0.844 -0.830 -0.734 -1.103 -0.751 -0.644 -0.630 -0.559
A2
A3
-0.031 0.018 0.010 0.208 0.661 0.247 0.346 0.284 0.319 0.262 0.462 0.478 0.454 0.517 0.551 0.629 0.563 0.631 0.707 0.651 0.480 0.687 0.667 0.665 0.720 0.715 0.699 0.726 0.717 0.796 0.775 0.790 0.76? 0.724 0.H75 0.846 0.7HR 0.770 0.694 0.734 0.822 0.818 0.906 0.872 0.880 0.884 0.891 0.780 0.912 0.894 0.949 1.000 0.967 0.983 0.852 1.003 1.013 1.009 1.320 1.062 0.840 1.200 0.934 1.133 1.158 1.251 1.195 1.224 1.507 1.267 1.437 1.583 1.483 1.340 1.305 1.347 1.277 1.197 1.155 1.049 1.138 1.048 0.889 0.818 0.791
578
A4
-0.424
0.108
-0.090
0.062
-0.039 -0.016 0.005 -0.018 -0.046 -0.019 -0.071 -0.032 -0.015 -0.005 -0.034 -0.043 -0.053 -0.036 -0.029 -0.085 -0.090 -0.046 -0.053 -0.038 -0.084 -0.115 -0.067 -0.060 -0.163 -0.072 -0.085 -0.080 -0.145 -0.136 -0.140 -0.143 -0.141 -0.242 -0.190 -0.185 -0.219 -0.218 -0.245 -0.251 -0.267 -0.199 -0.303 -0.310 -0.570 -0.377 -0.114 -0.496 -0.413 -0.442 -0.488 -0.673 -0.583 -0.577 -1.035 -0.727 -0.824 -1.125 -0.995 -0.890 -0.848 -0.985 -1.020 -0.993 -0.988 -0.951 -0.786 -0.964 -0.856 -0.838 -0.837
-0.034 0.014 -0.015
0.029
-0.007 0.026 -0.024 0.017 -0.014 0.008 -0.018 0.026 0.019 0.020 0.037 0.019 0.058 0.049 0.044 0.015 0.083 0.067 0.158 0.109 0.013 0.100 0.132 0.099 0.139 0.197 0.173 0.129 0.336 0.249 0.266 0.301 0.280 0.354 0.329 0.401 0.526 0.456 0.519 0.524 0.427 0.577 0.554 0.592 0.574
T(P,N)HE3
REF.
JA56B G056 JA56B G056 VL55 JA56B PE59 G056 Pff^ JA56B WI53 PE59 JA56B PE59 WI53 PE59 JA56B WI53 PE59 JA56B VL55 PE68 JA56B JA56B PE59 WI53 JA56B PE59 JA56B KN70 PA66 PA70 PE59 JA56B PEb9 WI53 PE59 JA56R VL55 Gn61B PE59 JA56B JA56B PE59 WI53 PE59 JA56B VL55 JA56B PE59 PE59 WI53 G061B PE59 VL55 WI53 PE59 WI61 G061B PE59 WI53 PE59 VL55 WI61 PE59 VL55 WI61 MC73A VL55 WI61 G061B VL55 B059 WI61 MC73A WI61 WI61 G061B WI61 G061B B059 WI61 WI61 WI61 MC73A
NEUTRON PRODUCTION CROSS SECTIONS
T(p,n)^He. a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values EXPERIMENTAL TOTAL SIGMA-T EP(MEV) 51. 1.024 54. 1.024 57. 1.025 57. 1.025 59. 1.025 62. 1.026 63. 1.026 65. 1.027 69. li027 69. 1.028 82. 1.028 60. 1.028 73. 1.029 73. 1.029 77. 1.030 81. 1.031 81. 1.031 85. 1.033 86. 1.033 88. 1.034 95. 1.037 97. 1.037 98. 1.038 101. 1.040 103. 1.041 109. 1.044 109. 1.044 115. 1.047 127. 1.047 117. 1.050 123. 1.054 130. 1.057 119. 1.058 132. 1.061 136. 1.064 146. 1,066 140. 1.068 133. 1.069 149. 1.077 151. 1 .081 160. 1 .09X 161. l.0'J4 169. 1.09'> 155. 1.097 169. 1.104 171. 1.109 176. 1.118 178. 1.122 186. 1.133 186. 1.137 174. 1.137 160. 1.140 191. 1.145 190. 1.150 203. 1.174 204. 1.179 123. 1.190 215. 1.195 219. 1.203 217. 1.208 189. 1.220 254. 1.227 230. 1.232 229. 1.237 217. 1.237 229. 1.248 158. 1.260 246. 1.261 244. 1.266 245. 1.301 264. 1.307 253. 1.343 223. 1.350 261. 1.356 230. 1.370 295. 1.400 226. 1.410 234. 1.410 245. 1.420 210. 1.430 293. 1.454 279. 1.467 279. 1.470 317. 1.500 283. 1.520 260. 1.550 266. 1.550 301. 1.560 334. 1.569 290. 1.580 326. 1.583 317. 1.590 268. 1.600 347. 1.613 264. 1.620 298. 1.620 351. 1.688 302. 1.690 345. 1.704 378. 1.750 379. 1.760 331. 1.800 336. 1.800
CROSS SECTIONS FOR THE THE REACTION T(P,N)HE3 EPIME REF. SIGMA-T REF. GI59 396. 1.804 MA65 GI59 420. 1.810 MA65 GI59 390. 1.812 MA65 BA55 321. 1.820 MA65 GI59 359. 1.828 MA65 JA56B 342. 1.920 MA65 PE59 421. 1.923 MA65 382. GI59 1.958 MA65 397. GI59 1.966 MA65 294. SA61 1.970 MA65 429. GI59 1.997 GI59 456. C070 2.020 GI59 450. SE60 2.020 MA65 431. BA55 2.020 MA65 410. GI59 2.091 MA65 414. GI59 2.099 MA65 480. GI59 2.196 MA6 5 427. BA55 2.220 MA6 5 411. C050 2.240 MA65 483. PE59 2.249 MA65 417. JA56B 2.250 MA6 5 410. C050 2.260 MA65 419. C050 2.260 GI59 527. GI59 2.404 MA65 506. PE59 2.458 MA65 447. JA568 2.460 MA65 553. VL55 2.500 MA65 477. JA56B 2.560 MA65 564. GI59 2.619 GI59 428. C050 2.620 MA65 463. Cn50 2.620 MA65 462. JA56B 2.660 MA65 528. PE59 2.666 GI59 584. GI59 2.841 MA65 600. GI59 2.845 MA65 470. JA56B 2.870 GI59 538. PF59 2.872 MA65 479. JA56B 2.970 Gl^iq 483. SF60 3.020 MA65 602. GI59 MAft'v 3.074 529. PF59 3.07H Ma65 481. JA56B 3.OHO MA6S 532. PF59 3.284 Glbq 495. JA56B 3.290 GI59 580. VL55 3.300 MA65 585. GI59 3.309 MA65 491. G061B 3.400 MA65 513. PF59 3.488 MA65 471. JA56B 3.490 MA65 315. Cn50 3.520 MA65 356. C050 3.520 GI69 391. C050 3.520 BA55 394. C050 3.520 GI69 564. GI59 3.559 MA65 468. JA56B 3.690 MA65 528. SA61 3.690 MA65 521. PE59 3.693 JA56B 538. GI59 3.819 GI59 523. GI59 3.819 MA65 495. PE59 3.897 MA65 512. VL55 3.900 eA55 439. JA56B 3.900 GI59 415. C050 4.020 MA6 5 503. GI59 4.079 MA65 419. JA56B 4.100 GI59 465. PE59 4.101 GI59 465. PE59 4.101 JA56B 408. G061B 4.300 MA65 464. GI59 4.359 MA65 439. PE59 4.400 GI59 333. 4.520 MA65 SE60 445. 4.600 GI59 VL55 434. GI59 4.619 BA55 399. 4.700 GI59 PE59 415. C070 GI5g 4.920 395. VL55 GI59 4.923 372. WI61 4.940 C050 374. 5.000 C050 PE59 345. 5.000 BA55 G061B 385. 5.216 JA56B GI59 331. 5.250 GI59 PE59 380. 5.300 GI59 VL55 335. 5.440 C070 WI61 332. PE59 5.500 PE59 350. VL55 5.900 BA55 298. WI61 5.940 C050 282. SA61 6.020 C050 300. VL55 6.400 C060 271. WI61 6.440 GI59 278. G061B 6.500 C060 260. VL55 6.800 GI59 305. B059 6.800 C070 254. W161 6.940 C050 240. WI61 7.430 PE59 233. WI61 7.930 JA56B 219. G061B 8.000 BA55 213. W161 8.450 GI59 200. G061B 241. 8.800 BA55 B059 201. 8.900 GI69 WI61 187. 8.930 PE59 SA61 191. 9.090 C070 MI61 194. 9.420 C050 WI61 9.920 C050
579
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
H. LISKIEN AND A. PAULSEN
a(e lab), Eje lab): Recommended Values
T(p,nfHe. ENERGY(WEVI
1.300
1.200
U-SIGMA-0(MB/SR) A 0 A 1 A 2
) )
16.20C 1.056 -0.07a 0.020
IT.60C 1.112 -0.220
o.lot
) > i
VALUEi;
I N P U I"
19.IOC1 1.14;1 -0.34C 0.19£1
20.70C 1.161 -0.435 0.274
)
DIFFERENTIAL
ANGLE(l)EGREei
)
FOR
)
C R U S S - S F C T I O N !;
)
1.700
) ) ) IN
-o.bac1
1.60C
1 . 5 0C
1.400
C E N T E R - • U F - •MASS
THE R E A C T I O N 22.30C 1.17C -0.516 0.34f
(MB/SR)
1.80C
T(P,N)HE3
24.00C1 1.174
1 .900
25.80C1 1.172 - 0 . 5 2 1r 0.45;
0.406
THE
)
LABORATtlRY
27.700 1.165 -0.550 0.494
)
SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.561E 0.559E 0.553E 0.544E 0.530E 0.514E 0.494E
02 02 02 02 02 02 02
0.520E 0.518e 0.511E 0.499E 0.485E 0.468E 0.449E
0 2 0 . 5 1 4 E 02 02 0 . 5 1 1 6 02 02 0 . 5 0 2 E 02 02 0 . 4 8 9 6 02 02 0 . 4 7 I E 02 02 0 . 4 5 2 E 02 02 0 . 4 3 1 E 02
0.523E 0.520E 0.5096 0.4936 0.4736 0.4516 0.42«e
02 02 02 02 02 02 02
0.539E 0.5356 0.523E 0.604E 0.480E 0.454E 0.428E
02 02 02 02 02 02 02
0.6606 0.565E 0.642E 0.520E 0.493E 0.464E 0.4356
02 02 02 02 02 02 02
0.685E 0.581E 0.565E 0.641E 0.5116 0.4786 0.446E
02 02 02 02 02 02 02
0.6156 0.6106 0.6926 0.566E 0.632E 0.495E 0.4596
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.471E 0.4466 0.416E 0.384E 0.3506 0.313E
02 02 02 02 02 02
0.4296 0.409E 0.388E 0.367E 0.344E 0.321E
02 02 02 02 02 02
0.411E 0.392E 0.374E 0.357E 0.341E 0.325E
0.406E 0.3fi6E 0.369E 0.355E 0.3426 0.3306
02 02 02 02 02 02
0.404E 0.3836 0.356E 0.352E 0.342E 0.334E
02 02 02 02 02 02
0.4076 0.384E 0.365E 0.363E 0.3446 0.3396
02 02 02 02 02 02
0.415E 0.390E 0.370E 0.357E 0.349E 0.346E
02 02 02 02 02 02
0.425F 0.3986 0.375E 0.362E 0.3546 0.3526
02 02 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.275E 0.235E 0.195E 0.157E 0.123E 0.931E
02 02 02 02 02 01
0.295E 0.2696 0.241E 0.213E 0.185E 0.1586
02 0 . 3 0 7 E 02 0 . 2 8 9 E 02 0 . 2 5 9 E 02 0 . 2 4 7 E 02 0 . 2 2 5 E 02 0 . 2 O 2 E
§1 000 ... 323 091 518 EEE
02 02 0 . 2 7 5 6 02 0 . 2 5 7 6 02 0 . 2 3 7 6
0 2 0 . 3 2 5E 0 2 0 . 3 3 4 E 02 0 . 3 1 8 E 02 0 . 3 3 0 E 02 0 . 3 0 8 E 02 0 . 3 2 5 E 02 0 . 2 9 7 E 02 0 . 3 1 7 E 02 0 . 2 8 3 E 02 0 . 3 0 7 E 0 2 0 . 2 5 7 6 02 0 . 2 9 4 F
02 02 02 02 02 02
0.343E 0.342E 0.340E 0.3366 0.329E 0.3196
02 02 02 02 02 02
0.352E 0.353E 0.3546 0.353E 0.3496 0.3436
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0 . 5 89E 0 1 0.503E 01 0.367E 01 0 . 2 7 0 6 01 0.2016 01 0.154E 01
0.134E 0.113E 0.948E 0.793E 0.666E 0.562E
02 02 01 01 01 01
0.180E 0.159E 0.140E 0.1236 0.1086 0.951E
02 0 . 2 1 8 E 02 0 . 1 9 8 6 02 0 . 1 7 9 6 02 0.1526 02 0 . 1 4 5 6 01 0.1316
02 02 02 02 02 02
0.2506 0.2326 0.214E 0.197E 0.181E 0.1556
02 02 02 02 02 02
0.2806 0.264E 0.247F 0.230E 0.214E 0.199E
02 02 02 02 02 02
0.307E 0.293E 0.278E 0.2526 0.246E 0.230E
02 02 02 02 02 02
0.3336 0.3216 0.3076 0.2916 0.276E 0.260E
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.120E 0.9656 0.792E 0.6666 0.573E 0.504E
01 0.4796 00 0.413E 00 0 . 3 6 0 6 00 0 . 3 1 8 6 00 0.285E 00 0.259E
01 0.8416 01 0.748E 01 0 . 6 7 1 E 01 0 . 6 0 8 E 01 0.5566 01 0.5146
01 0 . U 8 6 01 0 . 1 0 7 6 01 0.984E 01 0.905E 01 0.839E 01 0.7846
02 0.152E 0! 0.1406 01 0.129E 01 0.120E 01 0.112E 01 0.105E
02 02 02 02 02 02
0.184E 0.1716 0.160E 0.150E 0.1416 0.1346
02 02 02 02 02 02
0.216E 0.2026 0.1906 0.179E 0.1706 0.1526
02 02 02 02 02 02
0.245E 0.2326 0.219E 0.207E 0.197E 0.1896
02 02 02 02 02 02
155.0 160.0 165.0 170.0 175.0 180.0
0.452E 0.4156 0.3886 0.3706 0.360E 0.3566
00 00 00 00 00 00
0.481E 0.455E 0.436E 0.4236 0.4156 0.412E
01 0 . 7 4 0 6 01 Q.706E 01 0.680E 01 0.6626 01 0 . 6 5 1 6 01 0.5486
01 O.IOOE 01 0.957E 01 0 . 9 3 6 6 01 0.914E 01 0 . 9 0 1 6 01 0.8956
02 0 . 1 2 8 E 01 0 . 1 2 3 6 01 0 . 1 1 9 E 01 0.117E 01 0 . 1 1 5 E 01 0.1166
02 02 02 02 02 02
0.155E 0.150E 0.145E 0.1436 0.1416 0.140E
02 02 02 02 02 02
0.1826 0.175E 0.171E 0.168E 0.166E 0.155E
02 02 02 02 02 02
ENERGY(MEV)
0.239E 0.224E 0.212E 0.206E 0.200E 0.199E
01 01 01 01 01 01
2.200
2.100
2.000
C E N T E R -•OF- -MASS U-SIGMA-0(MR/SR) A 0 A 1 A 2 A 3
DIFFERENTIAL
ANGLE(DEGREE)
C R O S S - ;S E C T I O N S
0.6556 0.648E 0.6296 0.5996 0.5616 0.5206 0.4786
02 02 02 02 02 02 02
0.709E 0.702E 0.679E 0.6446 0.601E 0.5526 0.504E
02 02 02 02 02 02 02
0.770E 0.7516 0.7356 0.6956 0.6456 0.5906 0.5336
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.4406 0.4096 0.3856 0.3696 0.3606 0.3586
02 02 02 02 02 02
0.459E 0.421E 0.392E 0.3736 0.3636 0.360E
02 02 02 02 02 02
0.4816 0.435E 0.400fc 0.3766 0.353E 0.359E
65.0 70.0 75.0 80.0 85.0 90.0
0 . 3 6 0E 0.3646 0.3676 0.3696 0.3686 0.3646
02 02 02 02 02 02
0.3626 0.368E 0.374E 0.380E 0.3e2E 0.381E
02 02 02 02 02 02
0.351E 0.358E 0.3776 0.3856 0.3916 0.3946
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0.3576 0.3476 0.334E 0.3206 0.3056 0.290E
02 02 02 02 02 02
0.377E 0.3706 0.3596 0.3476 0.333E 0.3186
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.2756 0.261E 0.2486 0.2366 0.2256 0.216E
02 02 02 02 02 02
0.304E 0.290E 0.276E 0.264E 0.254E 0.2446
155.0 160.0 165.0
0.209E 0.2036 0.198E 0.1946 0.1926 0.1926
02 02 02 02 u2 02
0.2356 0.2306 0.2256 0.2216 U.2I9E 0.218E
Iru.U
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
FOR
40.400 0.980 -0.582 0.513 -0.01]L
0.0 5.0 10.0 15.0 20.0 25.0 30.0
175.0 180.0
VALU6S
2.500
2.400
2.300
I N P U l'
36.300 1.047 -0.531 0.591 -O.OOT
33.000 1.100 -0.660 0.563 -0.003
30.000 1.146 -0.674 0.528 0.000
02 02 02 02 02 02
THE
REACTIUIM
44.700
) )
o.9o;
-0.533 0.63^ -0.015 (MB/SR>
iIN
)
48.70C 0.856 -0.502 0.654 - O . O I E1 •r H E
2.700
2.600
TIP,NIHE3 55.200 0.783 -0.453 0.708 -0.028
52.500 0.810 - 0 . 4 7 " ir 0.690 -0.02 3
LABORATORY
SYSTEM
02 0.9286 02 0 . 9 1 6 E 02 0 . 8 8 2 E 02 0.828E 02 0 . 7 6 0 6 02 0 . 5 8 3 6 02 0.605E
02 02 02 02 02 02 02
O.IOOE 0.989E 0.9606 0.e89£ 0.812E 0.7256 0.6356
03 02 02 02 02 02 02
0.107E 0.105E O.IOIE 0.947E 0.861E 0.7646 0.654E
03 03 03 02 02 02 02
0.112E 0.1106 0.105E 0.9876 0.8956 0.7926 0.6856
03 03 03 02 02 02 02
02 0 . 5 0 8 6 02 0 . 4 5 3 E 02 0 . 4 1 0 6 02 0 . 3 8 0 6 02 0 . 3 6 2 6 02 0 . 3 5 5 6
02 0 . 5 3 0 E 02 0 . 4 5 5 6 02 0.412E 02 0 . 3 7 4 E 02 0.351E 02 0 . 3 4 1 E
02 02 02 02 02 02
0.550E 0.4756 0.4136 0.368E 0.340E 0.328E
02 02 02 02 02 02
0.568E 0.482E 0.412E 0.360E 0.327E 0.312E
02 02 02 02 02 02
0.5816 0.489E 0.413E 0.3556 0.3196 0.3016
02 02 02 02 02 02
0.357E 0.3646 0.3756 0.3856 0.3966 0.402E
02 0 . 3 4 2 E 02 0.351E 02 0.364E 02 0 . 3 7 8 E 02 0.3926 02 0.4026
02 02 02 02 02 02
0.328E 0.3386 0.3646 0.372E 0.389E 0.404E
02 02 02 02 02 02
0.311E 0.3226 0.3406 0.3626 0.383E 0.403E
02 02 02 02 02 02
0.3006 0.311E 0.3306 0.3546 0.3796 0.4016
02 02 02 02 02 02
0.3936 0.3886 0.3806 0.369E 0.357E 0.344E
02 0 . 4 0 4 E 02 0 . 4 0 9 6 02 0 . 4 0 3 6 0 2 0 . 4 1 1 6 02 0 . 3 9 8 E 02 0 . 4 1 0 6 02 0 . 3 8 9 E 02 0 . 4 0 5 6 02 0 . 3 7 9 6 02 0 . 3 9 6 E 02 0 . 3 6 7 6 02 0 . 3 8 6 E
02 02 02 02 02 02
0.4156 0.4216 0.4236 0.4216 0.4156 0.407E
02 02 02 02 02 02
0.418E 0.428E 0.434E 0.435E 0.432E 0.426E
02 02 02 02 02 02
0.4206 0.4346 0.4426 0.445E 0.445E 0.4416
02 02 02 02 02 02
02 02 02 02 02 02
0.3306 0.3166 0.3036 0.2806 0.2706
02 0 . 3 5 4 6 02 0 . 3 4 1 E 02 0 . 3 2 8 E 02 0.316E 02 0 . 3 0 5 6 02 0 . 2 9 5 6
02 0.375E 02 0 . 3 6 3 E 02 0 . 3 5 1 E 02 0 . 3 4 0 6 02 0.3296 02 0 . 3 2 0 6
02 02 02 02 02 02
0.397E 0.3856 0.375E 0.364E 0.3546 0.344E
02 02 02 02 02 02
0.418E 0.408E 0.398E 0.388E 0.378E 0.369E
02 02 02 02 02 02
0.4356 0.426E 0.417E 0.4076 0.3986 0.3896
02 02 02 02 02 02
02 02 02 02 02 U2
0.2526 0.2556 0.2506 0.2466 0.244E 0.^4:>c
02 02 02 02 02 02
02 02 02 02 02 02
02 02 02 02 02 02
0.335E 0.3296 0.324E 0.320E 0.318E 0.3176
02 02 02 02 02 02
0.351E 0.354E 0.349E 0.346E 0.343E 0.342E
02 02 02 02 02 02
0.3816 0.3756 0.3696 0.356E 0.3536 0.3526
02 02 02 02 02 02
0.29ie
0.847E 0 . 8 37 E 0.8076 0.7516 0.703E 0.6376 0.5706
0.287E 0.2816 0.2756 0.2716 0.269E U.268E
580
0.3U6 0.3056 0.2996 0.2956 0.2936 0.2926
NEUTRON PRODUCTION CROSS SECTIONS
T0>,«)3He. ENERGY(MEV)
1.200
aid lab), EJO lab): Recommended Values 1.300
1.400
1.500
1.600
1.700
INPUT VALUES FOR THE REACTION T ( P , N ) H E 3 REST ENERGY IN MEV FOR PRUJECTILE TARGET PRODUCT RESIDUAL NUCLEUS
Tl= 938.282 T2=2808.951 T3= 9 3 9 , 5 7 6 T4=2808.421
ENERGY OF PARTICLE-3 (MEV)
ANGLE(DEGREe)
0.463 0.420 0.379 0.341 0.307 0.275
0.996 0.992 0.981 0.962 0.937 0.905 0.867 0.825 0.780 0.732 0.682 0.631 0.58 1 0.532 0.485 0.440 0.399 0.360 0.325
1.099 1.095 1 .083 1.063 1.036 1.001 0.962 0.917 0.868 0.816 0.763 0.708 0.654 0.601 0.550 0.501 0.456 0.413 0.375
0.200 0.179 0.159 0.143 0.129 0.117
0.247 0.221 0.199 0.180 0.163 0.149
0.293 0.265 0.240 0.217 0.198 0.181
0.340 0.308 0.280 0.256 0.233 0.214
0.136 0.126 0.117 0.109 0.103 0.098
0.167 0.155 0.144 0.135 0.128 0.121 0.116 0.112 0.109 0.107 0.106 0.106
0.198 0.184 0.172 0.162 0.153 0.146
0.050 0.048 0.047 0.046 0.045 0.045
0.106 0.098 0.090 0.084 0.079 0.075 0.071 0.069 0.067 0.065 0.064 0.064
2.300
2.400
2.300
0.32 3 0.288 0.256 0.226 0.199 0.175
0.108 0.094 O.OBl 0.071 0.062 0.055
0.154 0.136 0.120 0.107 0.095 0.085
0.024 0.021 0.019 0.017 0.016 0.015
0.049 0.045 0.040 0.037 0.034 0.032
0.077 0.070 0.065 0.060 0.056 0.053
0.014 0.013 0.013 0.012 0.012 0.012
0.031 0.029 0.028 0.028 0.027 0.027
2.200
0.351 0.349 0.342 0.331 0.316 0.297 0.275
0.466 0.463 0.456 0.443 0.426 0.406 0.381
0.575 0.573 0.564 0.561 0.532 0.509 0.482
0.683 0.680 0.670 0.655 0.635 0.610 0.5B0
35.0 AO.O 45.0 50.0 55.0 60.0
0.251 0.226 0.199 0.172 0.146 0.121
0.354 0.325 0.295 0.265 0.234 0.205
0.462 0.420 0.386 0.352 0.317 0.283
0.547 0.512 0.474 0.436 0.397 0.359
65.0 70.0 75.0 80.0 85.0 90.0
0.099 0.078 0.061 0.046 0.035 0.026
0.177 0.152 0.129 0.108 0.091 0.075
0.251 0.221 0.193 0.168 0.145 0.125
95.0 100.0 105.0 110.0 115.0 120.0
0.019 0.014 0.011 0.008 0.006 0.005
0.063 0.053 0.044 0.037 0.032 0.028
125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
0.004 0.003 0.003 0.003 0.002 0.002 0.002 0.002 0.002 0.001 0.001 0.001
2.000
-0.764
I N THE LABORATORY SYSTEM 0.788 0.785 0.775 0.759 0.737 0.709 0.677 0.641 0.602 0.561 0.519 0.476 0.434 0.393 0.354 0.318 0.284 0.253 0.225
0.0 5.0 10.0 15.0 20.0 25.0 30.0
ENERGY(MEV)
0-VALUE I N MEV 0=
0.893 0.889 0.878 0.861 0.837 0.807 0.773 0.734 0.691 0.647 0.601 0.554 0.508
0.093 0.090 0.088 0.086 0.08 5 0.084
0.140 0.135 0.132 0.129 0.128 0.128
2.700
INPUT VALUES FUR THE REACTION T ( P , N ) H E 3 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
Tl= 938.282 T2=2808.951 T3= 9 3 9 . 5 7 6 74=2808.421
ENERGY OF PARTICLE-3 (MEV)
0-VALUE
IN MEV 41=
-0.764
I N THE LABORATORY SYSTEM
1.406 1.401 1.387 1.363 1.330 1.290 1.242 1.188 1.130 1.068 1.003 0.937 0.871
1.508 1.503 1.487 1.462 1.428 1.385 1.335 1.278 1.217 1.151 1.083 1.013 0.943
1.609 1.604 1.588 1.562 1.525 1.481 1.428 1.368 1.303 1.234 1.162 1.089 1.015
1.7U 1.705 1.688 1.661 1.623 1.576 1.520
1.B12 1.806 1.788 1.760 1.720 1.671 1.613
1.913 1.907 1.888 1.858 1.817 1.766 1.705
1.008 0.955 0.900 0.843 0.785 0.727
1.304 1.300 1.286 1.263 1.232 1.194 1.149 1.098 1.043 0.984 0.923 0.861 0.799
1.458 1.390 1.317 1.242 1.164 1.087
1.547 1.476 1.400 1.321 1.240 1.159
1.637 1.562 1.4B3 1.400 1.315 1.230
0.670 0.615 0.562 0.513 0.467 0.425
0.738 0.679 0.623 0.570 0.520 0.474
0.806 0.744 0.683 0.626 0.573 0.524
0.875 0.808 0.744 0.683 0.627 0.574
0.943 0.872 0.804 0.740 0.680 0.624
1.011 0.936 0.865 0.797 0.733 0.674
1.078 I . 000 0.925 0.853 0.786 0.724
1.146 1.054 0.985 0.910 0.839 0.773
0.386 0.351 0.321 0.293 0.269 0.248
0.433 0.395 0.361 0.331 0.305 0.282
0.479 0.439 0.402 0.370 0.341 0.315
0.526 0.482 0.443 0.408 0.377 0.349
0.573 0.526 0.484 0.446 0.413 0.383
0.619 0.570 0.525 0.485 0.449 0.418
0.666 0.614 0.566 0.523 0.485 0.452
0.713 0.657 0.607 0.562 0.522 0.486
0.230 0.214 0.200 0.188 0.179 0.171 0.164 0.159 0.155 0.152 0.150 0.150
0.261 0.244 0.229 0.216 0.205 0.196 0.188 0.182 0.178 0.175 0.173 0.172
0.293 0.274 0.257 0.243 0.231 0.221 0.213 0.206 0.202 0.198 0.196 0.195
0.325 0.304 0.286 0.271 0.258 0.247 0.238 0.231 0.225 0.221 0.219 0.218
0.357 0.335 0.315 0.299 0.284 0.273 0.263 0.255 0.249 0.245 0.243 0.24<:
0.390 0.366 0.345 0.327 0.311 0.298
0.422 0.396 0.374 0.355 0.338 0.325
0.455 0.427 0.403 0.383 0.365 0.351
0.288 0.280 0.273 0.26 9 0.266 u.^65
0.313 0.304 0.297 0.293 U.2vu U.2B9
0.339 0.329 0.322 0.317 U.314 0.313
1.202 1.198 1.185 1.163 1.134 1.098 1.055
581
Nuclear Data Tables, Vol. H , No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(/>,ii)3He. ENERGY(MEV)
2.800
a(6 lab), £^^(6 lab): Recommended Values 3.0UU
2.90U
3.500
4.000
4.500
5.500
5.000
CENTER--OF--MASS INPUT VALUES FOR THE REACTION T ( P , N ) H E 3 o-iIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 ANGLEIDEGREE)
58.600 0.75; -0.451 0.740 - 0 . 0 4 1I 0.000
57.400 0.764 -0.455 0.724 -0.033 0.000
)
59.400 0.745 -0.450 0.753 -0.048 0.000
5 0 . 9 00 0.753 -0.520 0.910 -0.167 0.024
58.100 0.738 -0.472 0.832 -0.098 0.000
29.400 0.888 -0.699 1.148 -0.478 0.141
35.300 0.827 -0.635 1.069 -0.355 0.094
42.200 0.784 -0.576 0.990 -0.254 0.056
DIFFERENTIAL CROSS-:SECTIONS (MB/SRI 1; N IrH£ LABORATORY SYSTEM
0.0 5.0 lO.O 15.0 20.0 25.0 30.0
0.115E 0.114E 0.109E O.IOIE 0.923E 0.815E 0.702E
03 03 03 03 02 02 02
0.117E 0.115E O.lllE 0.103E 0.937E 0.827E 0.711E
03 03 03 03 02 02 02
0.118E 0.116E O.lllE 0.104E 0.946E 0.835E 0.718E
03 03 03 03 02 02 02
0.113E 0.112E 0.107E O.IOOE 0.918E 0.814E 0.703E
03 03 03 03 02 02 02
0.981E 0.9686 0.9316 0.872E 0.796E 0.708E 0.613E
02 02 02 02 02 02 02
0.805E 0.794E 0.765E 0.718E 0.658E 0.5886 0.514E
02 02 02 02 02 02 02
0.668E 0.6606 0.6366 0.599E 0.5526 0.497E 0.4406
02 02 02 02 02 02 02
0.553E 0.546E 0.528E 0.5006 0.454E 0.424E 0.381E
02 02 02 02 02 02 02
35.0 'fO.O 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 UO.O 115.0 120.0 125.0 130.0 135.0 I'tO.O 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
0.593E 0.495E 0.414E 0.353E 0.313E 0.293E 0.290E 0.301E 0.322E 0.34BE 0.375E 0.400E 0.422E 0.439E 0.450E 0.456E 0.457E 0.455E
02 02 02 02 02 02 02 02 02 02 02 02
0.599E 0.498E 0.413E 0.349E 0 . 3 0 6E 0.284E 0.280E 0.291E 0.312E 0.339E 0.368E 0.395E
02 02 02 02 02 02 02 02 02 02 02 02
02 02 02 02 02 02 02 02 02 02 02 02
0.591E 0.487E 0.397E 0.324E 0.272E 0.2416
02 02 02 02 02 02
0.519E 0.430E 0 . 3 5 IE 0.2866 0.238E 0.207E
0.338E 0.297E 0.257E 0.2216 0.189E 0.162E
02 02 02 02 02 02
0.193E 0.1946 0.2086 0.2326 0.2626 0.2956
02 02 02 02 02 02
0.3826 0.3276 0.276E 0.232E 0.195E 0.166E 0.148E 0.140E 0.142E 0.153E 0.171E 0.195E
02 02 02 02 02 02
02 02 02 02 02 02
0.4406 0.369E 0.3066 0.2526 0.210E 0.180E 0.164E 0.1606 0.1686 0.185E 0.2096 0.2376
02 02 02 02 02 02
0.230E 0.236E 0.256E 0.285E 0.3196 0.3536
02 02 02 02 02 02 02 02 02 02 02 02
02 02 02 02 02 02
0.142E 0.130E 0.1266 0.1316 0.144E 0.163E
02 02 02 02 02 02
02 02 02 02 02 02
0.420E 0.439E 0.452E 0.46ie 0.464E 0.464E
02 02 02 02 02 02
0.604E 0.501E 0.413E 0.347E 0.301E 0.278E 0.273E 0.283E 0.304E 0.332E 0.362E 0.391E 0.417E 0.439E 0.454E 0.465E 0.470E 0.471E
02 02 02 02 02 02
0.3866 0.416E 0.440E 0.459E 0.4726 0.480E
02 02 02 02 02 02
0.3296 0.3606 0.388E 0.4126 0.430E 0.445E
02 02 02 02 02 02
0.2686 0.2986 0.327E 0.353E 0.374E 0.3926
02 02 02 02 02 02
0.222E 0.251E 0.279E 0.306E 0.329E 0.349E
02 02 02 02 02 02
0.186E 0.212E 0.239E 0.265E 0.290E 0.311E
02 02 02 02 02 02
0.450E 0.443E 0.434E 0.425E 0.416E 0.408E
02 02 02 02 02 02
0.4606 0.454E 0.447E 0.438E 0.430E 0.422E
02 02 02 02 02 02
0.469E 0.464E 0.457E 0.449E 0.442E 0.434E
02 02 02 02 02 02
0.4846 0.485E 0.483E 0.479E 0.474E 0.469E
02 02 02 02 02 02
0.4546 0.461E 0.464E 0.465E 0.464E 0.462E
02 02 02 02 02 02
0.406E 0.416E 0.423E 0.428E 0.431E 0.432E
02 02 02 02 02 02
0.3666 0.3796 0.3896 0.3976 0.4026 0.4056
02 02 02 02 02 02
0.330E 0.345E 0.358E 0.3676 0.374E 0.380E
02 02 02 02 02 02
0.400E 0.394E 0.389E 0.385E 0.382E 0.382e
02 02 02 02 02 02
0.415E 0.408E 0.403E 0.400E 0.397E 0.397E
02 02 02 02 02 02
0.427E 0.421E 0.416E 0.413E 0.410E 0.410E
02 02 02 02 02 02
0.4646 0.460E 0.4566 0.4536 0.451E 0.451E
02 02 02 02 02 02
0.460E 0.458E 0.4566 0.4546 0.4536 0.4526
02 02 02 02 02 02
0.4326 0.4326 0.431E 0.4316 0.430E 0.430E
02 02 02 02 02 02
0.4086 0.409E 0.410E 0.410E 0.4106 0.4106
02 02 02 02 02 02
0.383E 0.386E 0.388E 0.389E 0.389E 0.3906
02 02 02 02 02 02
ENERGY(MEV)
6 . 0 0 01
6 . 5 0 01
7.5O01
7.OO01
8.00C f
8.5O01
9 . 0 0 01
9.500
CENTER-•OF--MASS INPUT VALUES, FOR THE REACTION T(P,N1HE3 0-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4
24.80C 1 0 . 9 6 31 -0.768 1.228 1 -0.617 0.194
ANGLE(DEGREE)
14.100 15.20C 1 14.500 14.00C 1 16.40C 1 1.050 1.167 1.146 1.107 1.152 I -0.667 - 0 . 9 0C1 -0.831 -0.751 - 0 . 9 3 2I 0.920 1.036 1.273 1 1.15' t 1.361 -0.879 -0.945 -l.OOC -0.987 - 0 . 9 7 Si 0.576 0.553 0.460 0 . 5 1 3I 0 . 3 9 61 DIFFERENTIAL CROSS-SECTIONS. (MB/SR) IN THE LABORATORY SYSTEM 21.IOC 1 1.039 - 0 . 8 4 C1 1.301 -0.760 0.26C1
18.40C 1 1.104 -0.901 1.367 -0.901 0.331
)
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.464E 0.459E 0.445E 0.424E 0.398E 0.368E 0.338E
02 02 02 02 02 02 02
0.393E 0.389E 0.378E 0.361E 0.341E 0.320E 0.298E
02 02 02 02 02 02 02
0.342E 0.338E 0.329E 0.315E 0.299E 0.283E 0.267E
02 02 02 02 02 02 02
0.304E 0.300E 0,2916 0.27,8 6 0.254E 0.250E 0.2386
02 02 02 02 02 02 02
0.2816 0.277E 0.267E 0.254E 0.239E 0.226E 0.217E
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.307E 0.276E 0.246E 0.216E 0.188E 0.162E
02 02 02 02 02 02
0.277E 0.255E 0.233E 0.210E 0.186E 0.162E
02 02 02 02 02 02
0.253E 0.238E 0.222E 0.204E 0.183E 0.161E
02 02 02 02 02 02
0.229E 0.220E 0.210E 0.197E 0.181E 0.162E
02 02 02 02 02 02
0.211E 0.207E 0.202E 0.194E 0.182E 0.166E
65.0 70.0 75.0 80.0 85.0 90.0
0.141E 0.126E 0.117E 0.117E 0.125E 0.139E
02 02 02 02 02 02
0.141E 0.123E O.lllE 0.107E O.llOE 0.121E
02 02 02 02 02 02
02 02 02 01 01 01
0.159E 0.183E 0.209E 0.235E 0.259E 0.282E
02 02 02 02 02 02
0.138E 0.159E 0.183E 0.208E 0.232E 0.255E
02 02 02 02 02 02
02 02 02 01 01 02 02 02 02 02 02 02
0.142E 0.123E 0.107E 0.975E 0.944E 0.985E
95.0 100.0 105.0 IIO.O 115.0 120.0
0.139E 0.120E 0.106E 0.989E 0.989E 0.106E 0.120E 0.139E 0.162E 0.186E 0.210E 0.234E
0.109E 0.125E 0.145E 0.167E 0.190E 0.2126
02 02 02 02 02 02
0.1486 0.1286 0.1126 0.9966 0.9326 0.936E O.IOOE 0.113E 0.1306 0.149 6 0.170E 0.1906
02 02 02 02 02 02 02 02 02 01 01 01 02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.302E 0.319E 0.333E 0.344E 0.353E 0 . 3 5 9E
02 02 02 02 02 02
0.276E 0.294E 0,309E 0.322E 0.332E 0.340E
02 02 02 02 02 02
0.255E 0.274E 0.290E 0.304E 0.315E 0.324E
02 02 02 02 02 02
0.2336 0.251E 0.267E 0.2816 0.292E 0.302E
02 02 02 02 02 02
0.2106 0.2286 0.243E 0.257E 0.268E 0.277E
02 02 02 02 02 02
155.0 160.0 165.0 170.0 175.0 180.0
0.364E 0.368E 0.370E 0.372E 0.373E 0.373E
02 02 02 02 02 02
0.346E 0.350E 0.353E 0.355E 0,357E 0.357E
02 02 02 02 02 02
0.330E 0.336E 0.339E 0.342E 0.343E 0.3446
02 02 02 02 02 02
0.3096 0.314E 0.3186 0.3216 0.3226 0.3236
02 02 02 02 02 02
0.285E 0.290E 0.2946 0.297E 0.2996 0.299E
02 02 02 02 02 02
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
582
0.2676 0.263E 0.252E 0.2376 0.2216 0.2086 0.2006 0.196E 0.1946 0.1936 0.1906 0.1816 0.1686 0.151E 0.132E 0.114E O.IOOE 0.911E 0.883E 0.9196 O.lOlE 0.115E 0.132E 0.151E 0.170E
02 02 02 02 02 02 02
0.188E 0.2056 0.2216 0.2346 0.245E 0.254E 0.2626 0.268E 0.272E 0.275E 0.276E 0.277E
02 02 02 02 01 01 01 02 02 02 02 02
0.257E 0.253E 0.241E 0.224E 0.206E 0.1926 0.183E 0.180E 0.1816 0.183E 0.183E 0.178E 0.168E 0.152E 0.1346 0.1166 O.IOOE 0.8896 0.8356 0.842E 0.908E 0.102E 0.116E 0.133E 0.151E
02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 01 01 01 01 02 02 02 02
02 02 02 02 02 02
0.168E 0.184E 0.199E 0.212E 0.223E 0.232E
02 02 02 02 02 02
02 02 02 02 02 02
0.239E 0.245E 0.249E 0.252E 0.254E 0.254E
02 02 02 02 02 02
02 02 02 02 02 02
0.2596 0.2546 0.240E O.220E 0.200E 0.184E 0.1736 0.1706 0.172E 0.176E 0.179E 0.176E 0.168E 0.1546 0.137E 0.H8E O.IOIE 0.885E 0.8096 0.7956 0.8396 0.932E 0.106E 0.1216 0.138E 0.1546 0.170E 0.ie4E 0.197E 0.207E 0.217E 0.224E 0.230E 0.234E 0.2376 0.2396 0.2396
02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 01 01 01 01 01 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02
NEUTRON PRODUCTION CROSS SECTIONS
T(p,n)3He. ENERGYlMEVI
2.800
a(8 lab), Efl(O lab): Recommended Values 2.900
4.000 4.500 3.000 3.500 INPUT VALUES FOR THE REACTION TIP,NIHE3
REST ENERGY IN MEV FOR PRUJECTI LE Tl~ 938.282 TARGET T2~2808.951 PRUDUCT T3= 939.576 RESIDUAL NUCLEUS T4=2808.421
5.000
5.5 0 0
Q-VALUE IN MEV (,)=
-0.764
0.0 5.0 10.0 15.0 20.0 25.0 30.0
2.015 2.008 1.989 1.<)58 1.915 1.861 1.798
35.0 40.0 45.0 50.0 55.0 60.0
1.727 1.649 1.566 1.479 1.391 1.302
ENERGY OF PAR TI CL E-3 (MEV) IN THE LABORATORY SYSTEM 3.724 3.222 2.720 2.217 4.225 3.213 3.713 2.210 2.712 4.213 2.18<) 3.184 3.681 2.687 4.177 2.647 2.155 4.118 ~:~~~ ~:m 2.592 2.108 4.037 3.466 2.995 2.050 2.523 3.936 3.359 2.901 1.982 2.442 3.817 3.239 2.795 1.816 2.351 1.905 3.682 2.679 3.107 1.735 2.250 1.821 3.534 2.966 2.555 1.648 2.143 3.376 1.731 2.818 2.425 1.558 2.032 1.637 3.211 2.666 1.917 2.292 3.041 1.466 1.541 2.158 2.513 1.802 2.869 1.373 1.445
65.0 70.0 75.0 80.0 85.0 90.0
1.214 1.128 1.045 0.966 0.892 0.823
1.105 1.023 0.945 0.873
l:m
1.349 1.256 1.166 1.080 0.999 0.923
1.687 1.575 1.466 1.362 1.264 1.172
2.024 1.893 1.166 1.644 1.529 1.421
2.361 2.211 2.066 1.926 1.794 1.670
2.697 2.529 2.365 2.208 f·059 .919
2.6 6 5 2.490 2.324 2.1 68
95.0 100.0 105.0 110.0 fl5.0 20.0
0.759 0.701 0.648 0.601 0.558 0.521
0.806 0.145 0.690 0.640 0.595 0.555
0.853 0.789 0.731 0.678 0.631 0.590
1.087 1.008 0.931 0.872 0.814 0.762
1.321 1. 228 1.143 1.067 0.998 0.936
1.554 1.448 1.350 1.261 1.181 1.11 0
1.188 1.667 1.557 1.456 1.365 1.284
2.022 1.887 1.7 6 3 1. 651 1.54<) 1.458
125.0 130.0 135.0 140.0 145.0 150.0
0.487 0.458 0.433 0.411 0.393 0.377
0.520 0.489 0.463 0.439 0.420 0.403
0.553 0.520 0.492 0.468 0.447 0.430
0.717 0.676 0.641 0.611 0.585 0.563
0.881 0.833 0.791 0.754 0.723 0.696
1.046 0.990 0.941 0.898 0.861 0.831
1.211 1.147 1.091 1.042 1.000 0.965
1.376 1.304 1.241 1.186 1.139 1.100
155.0 160.0 165.0 170.0 175.0 180.0
0.364 0.354 0.346 0.341 0.338 0.337
0.390 0.378 0.371 0.365 0.362 0.360
0.416 0.404 0.395 0.389 0.386 0.384
0.545 0.530 0.519 0.511 0.507 0.505
0.675 0.657 0.644 0.634 0.629 0.627
0.805 0.785 0.769 0.758 0.752 0.749
0.936 0.912 0.895 0.882 0.874 0.672
1.067 1.040 1.020 1.006 0.998 0.995
6.000
6.500
8.500 7.500 6.000 7.000 INPUT VALUES FOR THE REACTION TlP,NIHE3
9.000
9.500
ANGLE (DEGREE)
ENERGY lMEV I
2.116 2.109 2.089 2.056 2.012 1.956 1.890
REST ENERGY IN MEV FOR PROJECT I LE TARGET PRODUCT RESIOUAL NUCLEUS ANGLE l DEGREE)
ENERGY OF PAR TICL 6.230 6.213 6.162 6.077 5.962 5.816 5.648
Tl= 938.282 T2=2808.951 73= 939.576 T4=2808.421
4.726 4.712 4.673
~:gn
4.406 4.274
4.125 3.962 3.186 3.603 3.414 3.224
~:gU
Q-VALUE IN MEV
E-3 I MEV I IN THE LA80RATORY SYST EM 6.730 7.231 7. 731 8.230 6.208 7.709 6.712 7.211 7.647 8.142 6.657 7.152 7.544 8.032 6.566 7.055 6.923 7.403 7.683 6.442 7.226 7.695 6.267 6.757 7.018 7.474 6.105 6.561
Q~
-0.764
0.0 5.0 10.0 15.0 20.0 25.0 30.0
5.229 5.214 5.171 5.099 5.001 4.878 4.733
5.730 5.714 5.666 5.586 5.482 5.348 5.191
35.0 40.0 45.0 50.0 55.0 (,0.0
4.570 4.390 4.198 3.996 3.789 3.579
5.012 4.817 4.607 4.388 4.162 3.934
5.455 5.244 5.017 4.780 4.536 4.288
5.897 5.670 5.427 5.172 4.909 4.643
6.340 6.097 5.836 5.563 5.282 4.997
6.782 6.523 6.246 5.955 5.655 5.352
7.224 6.949 6.655 6.346 6.028 5.70(,
7.666 7.376 7.064 6.736 6.401 6.060
65.0 70.0 75.0 80.0 85.0 90.0
3.370 3.164 2.964 2.772 2.589 2.416
3.706 3.481 3.263 3.053 2.853 2.665
4.042 3.799 3.562 3.335 3.118 2.914
4.377 4.116 3.861 3.616 3.382 3.162
4.713 4.433 4.160 3.897 3.647 3.411
5.049 4.750 4.459 4.178 3.911 3.659
5.384 5.0(,7 4.757 4.459 4.176 3.907
5.719 5.383 5.056 4.741 4.440 4.15b
95.0 100.0 105.0 110.0 115.0 120.0
2.256 2.107 1.970 1.846 1.733 1.632
2.489 2.326 2.177 2.041 1.917 1.806
2.723 2.546 2.384 2.235 2.101 1.980
2.956 2.76b 2.590 2.430 2.285 2.154
3.190 2.985 2.797 2.625 2.469 2.329
3.423 3.205 3.003 2.819 2.653 2.503
3.657 3.424 3.210 3.014 2.837 2.677
3.890 3.643 3.416 3.209 3.020 2.851
125.0 130.0 135.0 140.0 145.0 150 .0
1.542 1.462 1.392 1.331 1.279 1.235
1.707 1.620 1.543 1.476 1.418 1.370
1.873 1.777 1.693 1.620 1.558 1.505
2.038 1.935 1.844 1.765 1.697 1.640
2.203 2.092 1.995 1.910 1.837 1.775
2.369 2.250 2.145 2.054 1.976 1.910
2.534 2.407 2.296 2.199 2.115 2.045
2.699
155.0 160.0 l65.0 70.0 175.0 180.0
1.198 1.169 1.147 1.131 1.121 1.118
1.330 1.297 1.273 1.255 1.245 1.241
1.461 1.426 1.399 1.380 1.368 1.365
1.592 1.554 1.525 1.504 1.4"12 1.488
1.724 1.682 1. 651 1.629 1. 615 1.611
1.855 1.811 1.777 1.753 1.739 1.734
1.986 1.939 1.903 1.878 1.862 1.857
2.117 2.067 2.029 2.002 1.986 1.981
583
8.730 8.707 8.636 8.521 8.362 6.164 7.931
~.565
.446 2.343 2.255 2.180
Nudeor Data Tables, Vol. 1 L No.7, 1973
H. LISKIEN AND A. PAULSEN
a(B lab), En(B lab): Recommended Values ENERGY IMEV 1
10.000
U-SIGMA-OIMB/SRI A 0
~ ~
A 3 A 4
CENTER-Of-MASS INPUT VALUES fUR THE REACTION TIP,N1HE3 14.400 0.984 -0.560 0.796 -0.801 0.581
ANGLE (DEGREE I
0.264E 0.25BE O.243E 0.221E 0.19BE o .180E 0.lb8E
02 02 02 02 02 02 02
35.0 40.0 45.0
0.165E 0.167E 0.173E O.l77E 0.176E 0.lb9E 0.157E 0.139E o .120E 0.102E o .878E 0.783E 0.747E 0.769E 0.842E 0.955E 0.109E o .124E
02 02 02 02 02 02 02 02 02 02 01 01 01 01 01 01 02 02
50.0
55.0 60.0 65.0
70.0
75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0
160.0 165.0 170.0 175.0 180.0
Noeloar Data Tablo., Val. 11, No.7, 1973
DIfFERENTIAL CRUSS-SECTIUNS 1MB/SRI IN THE LABURATURY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
o .139E
02 0.154E 02 0.lS1E 02 O.l'llE 02 0.200E 02
0.16 BE 02
0.20SE 02 02 02 02 02 02
o .213E 0.21SE 0.221E 0.223E 0.223E
584
NEUTRON PRODUCTION CROSS SECTIONS
a«() lab), En«(j lab): Recommended Values ENERGY (MEV 1
10.000
INPUT VALUES FUR THE REACTIUN TlP,NIHE3 REST ENERGY IN MEV FOR PRUJECTILE T1~ 938.282 Q-VALUE IN MEV Q= TARGET T2~28D8. 951 PRUUUCT T3~ 939.516 RESIDUAL NUCLEUS T4~28D8.421 ANGL E(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0
ENERGY OF PARTICLE-3 lMEV) IN THE LABORATORY SYSTEM 9.230 9.206 90131 9.010 8.843 8.634 8.388
35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0
80108 7.802 7.413 70129 6.774 6.414 6.055 5.700 5.354
95.0 100 .0 L05.0 110.0
4.123 3.863 3.623 3.403 3.204 3.025
125.0 130.0 135.0 140.0 145.0 150.0
2.864
155.0 160.0 165.0
2.249 2.196 2.155 2.127 2.109 2.104
Hfi:8
ng:8
180.0
-0.764
5.021
4.704 4.404
2.722
2.597 2.488 2.394 2.315
585
Nuclear Dalo Table.s, Vol. 1I, No.7, 1973
H. LISKIEN AND A. PAULSEN
0'(0 c.m.), Legendre Coefficients (c.m.), a(total) Recommended and Experimental Values 0
a(O lab), En(B lab) Recommended Values
Nu"l.o, Data Tobl••, Vol. 11, No.7, 1973
586
NEUTRON PRODUCTION CROSS SECTIONS
D(~n)3He.
0(0 0 c.m.),
Legendre Coefficients, o(total) Recommended and Experimental Values SIGMA-O
AD, AI, ...
SIGMA-T
c.rn.) Legendre coefficients o(total) 0(0
0
Recommended Data AO
A2
A4
A6
A8
AlO
SIGMA-T
ENE RG Y (MEV)
SIGMA-O
0.020 0.030 0.040 0.050
0.025 0.125 0.31 0.52
0.819 0.785 0.758 0.737
0.181 0.215 0.241 0.261
0.001 0.002
0.060 0.070 0.080 0.090 0.100
0.78 1.06 1.35 1.66 2.00
0.719 0.705 0.692 0.681 0.671
0.279 0.292 0.304 0.314 0.323
0.002 0.003 0.004 0.005 0.006
7.0 9.4 11.7 14.2 16.9
0.150 0.200 0.250 0.300 0.350 0.400 0.450 0.500
3.33 4.6 5.9 7.1 8.3 9.4 10.4 11.4 12.4 13.4 14.3 15.1 15.8 16.5
0.356 0.379 0.395 0.408 0.418 0.426 0.433 0.437 0.440 0.443 0.444 0.445 0.446 0.445 0.444 0.443 0.441 0.43'J
0.011 0.016 0.022 0.028 0.035 0.042 0.049 0.057
0.550 0.600 0.650 0.700 0.750 0.800 0.R50 0.900 0.Q50 1.000 1.100 1.200 1.300 1.400 1.500 1.600 1.700 1.800 1.900 2.000
0.3 HI 0.370 0.360 0.351 0.342 0.334 0.326 0.318
0.434 0.478 0.422 0.'t16 0.410 0.404 0.398 0.392 0.387 0.382
0.158 0.174 0.189 0.203 0.216 0.228 0.240 0.251 0.260 0.270
0.001 0.003 0.005 0.008 0.011 0.014 0.017 0.020 0.023 0.027 0.030
26.5 35.0 43.0 50.0 57.0 63.0 67.7 72.5 77 .0 81.3 A5.2 88.2 90.5 92.7 94.9 96.9 98.3 99.A
20.0 21.0 21. ':I
0.633 0.605 0.583 0.564 0.547 0.532 0.518 0.506 0.494 0.483 0.474 0.465 0.456 0.447 Cl.439 0.432 0.4"5 0.418 0.40')
101.8 103.7 104.9 105.5 105.9 105.9 105.8 105.7 105.5 105.3
0.311 0.304 0.298 0.293 0.287 0.282 0.217 0.272 0.268 0.262
0.377 0.372 0.367 0.362 0.357 0.353 0.349 0.345 0.341 0.337
0.279 0.287 0.294 0.301 0.308 0.314 0.320 0.326 0.331 0.337
0.033 0.037 0.041 0.044 0.048 0.051 0.054 0.057 0.060 0.064
105.2 105.0 104.8 104.5 104.3 104.0 103.8 103.5 103.2 102.9
0.240 0.221 0.206 0.192 0.182 0.174 0.168 0.163 0.159 0.156 0.153 0.150 0.148 0.147
0.322 0.308 0.295 0.284 0.274 0.265 0.257 0.250 0.244 0.239 0.234 0.230 0.227 0.224
0.356 0.367 0.372 0.374 0.374 0.373 0.370 0.366 0.362 0.358 0.354 0.350 0.346 0.342
0.082 0.098 0.112 0.125 0.137 0.148 0.159 0.169 0.178 0.187 0.195 0.202 0.209
2.100 2.200 2.300 2.400 2.500 2.600 2.700 2.800 2.900 3.000 3.500 4.000 4.500 5.000 5.500 6.000 6.500 7.000 7.500 8.000 8.500 9.000 9.500 10.000
(MB/SR)
17. II
17.A 18.4 19.0 22. "r
23.4 24.0 24.6 25.2 25.8 26.4
26.9 27.5 28.0 28.4 28.9 29.3 29.8 30.3 30.7 31.2 33.5 35.7 37.8 40.0 41.5 42.9 43.8 44.6 45.2 45.7 46.1 46.4 46.5 46.5
0.3'13
0.066 0.074 0.082 0.090 0.098 0.10A 0.117 0.125 (l.134 0.147
587
1MB)
0.26 1.23 2.95 4.8
o .1l5
0.004 0.012 0.020 0.027 0.032 0.037 0.042 0.046 0.049 0.052 0.055 0.056 O. e-58
0.002 0.003 0.005 0.006 0.008 0.009 0.010 0.011 O.Oll 0.012 0.013 0.014 0.014
101.0 99.2 97.7 96.4 95.1 93.9 92.7 91.5 90.5 89.5 88.6 87.7 86.8 86.0
Nuclear Dato TabI8.s~ Vol. 11 1 No.7 I 1973
H. LISKIEN AND A. PAULSEN
0'(0 0 c.m.), Legendre Coefficients, Recommended and Experimental Values
a (total)
D(~n)3He.
f--~ef,-
50
D(d.ln)3~
~.
.....
• III
~(o')
CR56 9' .oA'58 IX EL53
f
GAfi7
~o
(mb/srl
c.m.
+ PRS4
~
o
ROS? 5C12
• SMS7 • 5T56
• THIl9 v ~~
30
legendre C"lMftlcl-nts Ai
not'tn
Ai
.I
•e fo+C51 G060A
/
20
!!.!!.
o
0.01
0.02
0,05
0,1
I
Ed
D.5
1.0
• IWIl M!II8 MUll
AI
o • )(
e
0'
[mb] 100
• THtO
• '9'
" "
0.2
2.0
5,0
TH611 vos,
O'01==I==~+5~~~:t=::I=~~
1Q.0
0.01 0.02
005
0.1
0.2
[MeV] -
~.f.
Ed
0.5
1.0
2.0
5.D
100
[Me'/l - -
Legendre Coefficients Experimental and Recommended Values
J
D(b.n)3~e
,A~5'
Intotgro led Cro.s Se(:tlon d
f1L4!S BOIS! BR!57 GA'57 G060A 1ilJ.45
----t00 PR54 st12 MC51
I
• THEIS
80
.,
/P ~
."q,
\•
Po
/
80
20
o
• $<:72
0.4
0
•
.-.• II
0'(0 c.m.). Experimental and Recommended Values
120 f--....
)::( EL53 ' o FU51 o CW7
• ooeo.
V 0.2
·""'"
0.6
V
....,., V
" "
0.8
• BW
oJ
10
D(d,n) He
•
,;.....
0056 -BRS7
+<0>9
~(O') 40
1.0
I'
O'C,I!l, CrQSS 5e-c1lon
All.. ...• BUB
om
../ 0.02
lJ
0.05
I
I
.
I !'
0.1
0.2
0.5
1.0
Eel [MeV]--.
2.0
5.0
10.0 0"
a(total). Experimental and Recommended Values
3()&
60'
90'
120'
ISO'
ISG'
O'((), E p )' Recommended Values
Solid line shows recommended values. Only experimental data which contributed to the recommended values are plotted. References are on page 618
Nudeor Data Tobl... Vol. 11, No.7, 1973
588
NEUTRON PRODUCTION CROSS SECTIONS
D(~n)3He.
0(0 0 c.m.),
Legendre Coefficients, o(total) Recommended and Experimental Values
EXPERIMENTAL O-DEGREE C.M. CROSS SECTIDNS FOR THE REACTION DlD,NlHE3 EDIMEVl O.013DO 0.01521 0.01789 0.01900 0.02161 0.02200 0.02500 0:02705 0.03000 0.03300 0.03346 0.03600 0.04000 0.04285 0.0460 0.0522 0.0530 0.0600 0.0670 0.0730 0.0800 0.0869 0.093 0.100 0.107 0.110 0.113 0.120 0.130 0.140 0.156 0.160 n.162 0.195 o.2n'i o.;>o{, (). ;>l ()
().;> ',0 (). ii" 0
SIGMA-O
AR54 EL53 EL53 AR54 EL53 AR54 AR54 EL53 AR54 AR54 EL53 AR54 AR54 EL53 AR54 B056 AR54 AR54 AR54 AR54 AR54 8056 AR54 AR54 AR54 AR54 AR54 MC51 GA57 MC51 PR54 MC51 GII?7 GI\'i7 GI\">7 PR',4 Gil '>7
(" 1
r;I\',7 (;11',7 (;11',7
0 .. ?&.,I.)
r,.ft 'I.A 6.1
I
fl ...~
().i'('o
() • i'f)
().i'70
(). ill? (). :3;> ~J
0.330 0.362 0.365 0.380 0.400 0.405 0.425 0.447 0.466 0.470 0.400 0.490 0.500 0.500 0.510 0.554 0.595 0.600 0.660 0.668 0.675 0.700 0.700 0.750 0.760 0.770 0.791 0.825 0.850 0.884 0.925 0.960 0.960 0.980 0.990 0.990 1.000 1.150 1.340 1.430 1.550 1.750 1.750 1.850 1.960 1.960
REF.
0.003 0.008 0.018 0.020 0.039 0.037 0.062 0.090 0.118 0.160 0.175 0.21 0.28 0.35 0.40 0.50 0.58 0.77 0.98 1.18 1.41 1.38 1.81 2.06 2.28 2.34 2.41 2.5 2.8 3.6 3.7 3.6 ::1.6 4.R 4.R 'i.n 'i.o
6.7 h., R.? 7.A R.4
H.A
9.3 6.7 10.5 10.6 10.3 10.8 11.5 10.9 7.8 11.4 8.9 11.5 12.1 12.1 11.0 14.8 14.4 11.9 14.3 11.3 13.5 16.1 16.0 16.3 13 .3 18.1 17 .3 18.6 17 .5 7.7 18.9 16.6 16.1 18.4 19.8 17 .3 23.0 23.5 25.0 19.8 27.4 26.0 25.1
ED(MEVl 2.000 2.010 2.150 2.150 2.300 2.450 2.490 2.510 2.540 2.600 2.800 2.830 3.020 3.020 3.020 3.070 3.110 3.150 3.350 3.400 3.400 3.500 3.520 3.600 3.750 3.850 4.000 4.100 4.150 4.500 4.550 4.600 4.620 4.630 4.750 4.790 'i.OOO 5.000 'i.OOO 5.130 '5.130 'i.250 5.300 5.3 AO 5 .390 5.500 5.500 5.500 5.550 5.630 5.800 5.800 5.800 5.920 6.000 6.200 6.250 6.310 6.320 6.380 6.500 6.830 6.900 7.000 7.200 7.250 7.250 7.440 7.500 7.500 7.650 7.750 7.890 8.000 8.150 8.250 8.320 B.400 8.400 8.500 8.500 8.750 8.800 8.880 8.940 9.000 9.420 9.870 9.920 10.000
Mr.'" ClI',,, PRI}/,.
(;11"7 (;11',7 GA"7 PR'>4 GA57 GA'j7 CH% GAS7 GA57 GA57 PR54 GA57 GA57 HU49 V057 CH56 GA57 GA57 GA57 CH56 GA57 GA57 CH56 V057 HU49 CH56 GA57 GA57 GA57 CH56 GA57 GA57 GA57 BL48 SA61 GA57 R057 HU49 V057 5T56 HU49 BL48 ST 51'> 5M57 HU49 5T56 BL48 SC72
589
SIGMA-O
REF.
27.4 26.5 25.9 20.8 28.0 31.1 28.7 28.4 21.3 29.2 30.5 21.4 32.5 32.2 29.8 32.3 21.4 31.5 32.4 33.2 21.2 34.2 34.6 34.8 34.4 35.5 36.0 36.2 35.7 37.6 33.7 38.2 37.6 35.5 39.'5 38.4 40.5 37.1 39.A 37.0 39.1 37.4 41.9 3A.3 42.A 38.6 41.6 43.0 31.2 38.5 42.4 42.7 44.1 42.6 40.7 43.4 44.5 40.4 44.8 44.4 40.2 44.8 46.4 42.2 44.6 45.4 41.5 46.0 46.5 42.8 46.4 43.• 1 45.9 44.4 45.5 44.2 46.2 46.0 43.2 48.0 44.5 50.5 47.7 45.9 48.2 43.4 48.2 46.7 46.4 43.1
SM57 R057 ST56 HU49 SM57 ST56 BL48 SC72 HU49 SM57 S,.,57 HU49 R057 BL48 SC72 5"'57 HU49 5T56 S,.,57 G060A HU49 SC72 BL48 5,.,57 ST56 S,.,57 scn S,.,57 5T56 SC72 5T56 5T56 5M57 5M57 FlR64 WI60
sen
SM57 TH69 SM57 5M57 5"'57 G060A 5M57 WI60 S,.,57 SC72 BR64 SA61 SM57 SC72 TH69 BR57 WI60 5,.,57
5en
BR64 CR56 C059 WI60 5,.,57 C059 WI60 5,.,57 G060A C059 5,.,57 WI60 BR64 SM57 C059 S,.,57 WI60 5,.,57 BR57 5M57 C059 WI60 OA58 G060A SM57 BR64 C059 WI60 C059 TH69 WI60 C059 WI60 TH69
Nuclear Dolo Table., Val. 11, No.7. 1973
H. LISKIEN AND A. PAULSEN
D(d,n)3He.
Legendre Coefficients, Recommended and Experimental Values 0(0 0 c.m.),
a(total)
NORMALIZED EXPERIMENTAL LEGENDRE COEFFICIENTS FOR THE REACTION OfO,NIHE3 EDCMEVI 0.01425 0.01521 0.01689 0.01789 0.01950 0.02139 0.02161 0.02595 0.02690 0.02705 0.03050 0.03200 O. 03346 0.03506 0.04048 0.04285 0.0451 0.0522 0.0610 0.0710 0.08b9 0.0930 0.09b6 0.1000 0.1220 0.1475 0.1560 0.1940 0.2000 0.2060 0.24B3 0.2500 0.2670 0.2700 0.2985 0.3000 0.3300 0.34!l7 0.3b2 0.303 0.400 0.400 0.447 0.46b 0.490 0.500 o.~oo
o.~nn
0 • .,.,4 !l.bOO 0.600 0.600 0.600 0.6bB 0.675 0.700 0.100 0.100 0.150 0.191 0.800 0.825 0.BB4 0.900 0.960 0.980 0.990 1.000 1.340 1.430 1.600 1.750 1.960 1.960 2.150 2.490 2.510 2.540 2. B30 3.020 3.020 3.110 3.400 3.500 3.520 4.000 4.500 5.000 5.000 5.000 5.100 5.500 5.800 5.BOO 5.BOO 5.BOO 6.000 6.200 6.310 7.000 7.600 B.OOO 8.150 8.400 9.000 9.000 9.600 10.000 10.000
Nuclear Dala Table., Val. 11, No.7. 1973
AD 0.778 0.824 0.796 0.790 0.889 0.806 0.810 0.793 0.784 0.761 0.793 0.795 0.775 0.787 0.772 0.753 0.746 0.736 0.702 0.703 0.679 0.684 0.664 0.750 0.642 0.615 0.636 0.587 0.b40 0.583 0.565 0.640 0.575 0.549 0.540 0.590 0.552 0.535 0.522 0.540 0.542 0.539 0.514 0.472 0.740 0.497 0.';47 0.0;10 0.441\ 0.5U 0.500 0.472 0.533 0.492 0.470 0.710 0.464 0.480 0.457 0.411 0.450 0.440 0.447 0.450 0.453 0.424 0.670 0.421 0.640 0.373 0.338 0.610 0.314 0.322 0.570 0.282 0.291 0.550 0.530 0.259 0.269 0.520 0.510 0.234 0.241 0.226 0.207 0.194 0.183 0.195 0.188 0.184 0.179 0.178 0.185 0.178 0.180 0.175 0.172 0.161 0.166 0.154 0.161 0.152 0.139 0.155 0.158 0.142 0.138
A2 0.222 0.176 0.204 0.210 0.111 0.194 0.190 0.207 0.21b 0.239 0.207 0.205 0.225 0.213 0.228 0.247 0.248 0.264 0.298 0.296 0.321 0.31b 0.324 0.250 0.341 0.365 0.373 0.379 0.350 0.394 0.402 0.349 0.429 0.427 0.407 0.380 0.42b 0.413 0."37 0."20 0.42fl 0.357 0.4"0 0.450 0.250 0.4;'>0
O.4Jt~
0.""0 0.444 0.463 0.440 0.413 0.365 0.4~ 0.4 4 0.2b~ 0.42 0.440 0.475 0.457 0.440 0.431 0.45B 0.450 0.400 0.411 0.270 0.425 0.290 0.426 0.405 0.280 0.379 0.387 0.290 0.353 0.364 0.290 0.280 0.343 0.342 0.280 0.270 0.311 0.332 0.308 0.288 0.276 0.24 0.2B 0.274 0.274 0.260 0.270 0.279 0.272 0.263 0.258 0.232 0.240 0.242 0.238 0.239 0.250 0.230 0.231 0.203 0.224 0.229
6
A6
A4
A8
AID
0.006 0.001 0.012 0.017 0.020 -0.009 0.034 0.010 0.023 0.033 0.011 -0.00" 0.02" 0.053 0.030 0.022 0.052 0.041 0.040 0.030 0.104 0.0"1> 0.07R 0.010 Il.OH3 -a.oot; 0.070 n.I08 n.Ol4 0.060 0.115 0.102 0.053 0.076 0.030 0.113 O.OBO 0.Ob8 0.072 0.110 0.129 0.095 0.100 0.147 0,105 0.060 0.148 0.070 0.201 0.257 0.100 0.267 0.262 0.130 0.303 0.306 0.150 O.lBO 0.338 0.335 O.lBO 0.200 0.35B 0.356 0.372 0.374 0.374 0.34B 0.377 0.356 0.377 0.374 0.368 0.379 0.37B 0.3Bl 0.379 0.376 0.360 0.352 0.355 0.361 0.359 0.345 0.355 0.343 0.342 0.341
590
0.010 0.040 0.029 0.010 0.062 0.039 0.010 0.010 0.060 0.054 0.020 0.020 0.085 0.071 0.088 0.111 0.131 0.162 0.126 0.150 0.139 0.146 0.134 0.132 0.144 0.136 0.151 0.180 0.173 0.181 0.186 0.183 0.172 0.20B a .19B 0.201 0.213 0.205
0.012 0.006 0.020 0.025 0.036 0.022 0.006 0.026 0.032 0.025 0.016 0.02B 0.035 0.037 0.030 0.049 0.048 0.047 0.036 0.034 0.056 0.048 0.081 0.066 0.066
0.026 0.026 0.009 0.025 0.009 0.005 0.010 0.017 0.011 0.020 0.014 0.033 0.022 0.013 0.014 0.013 0.021
REF. EL53 EL53 El53 EL53 TH66 EL53 EL53 EL53 TH66 EL53 EL53 TH66 EL53 ELS3 EL53 EL53 7H66 8056 PR54 THb6 B056 KA59 TH6b FU57 TH66 TH66 PR54 THbb FU57 PR54 THb6 CH56 GA57 PR54 THb6 FU57 GA57 TH66 PR54 FU57 ~H56 Ob08 GA57 PRS4 HU49 VOS7 (H56 FU'>7 GA'>7 CH56 FU'>7 MI61 G06011 GA57 CH56 HU49 V057 FU57 CH56 GA57 FU57 CH56 GA57 FU57 8l4B GA51 HU49 V057 HU49 Bl48 Mlb1 HU49 8148 scn HU49 BL48 SC72 HU4'l HU49 Bl4B SC 72 HU49 HU49 SC72 8l4B SC72 scn THb9 G060A SC72 SM51 scn TH69 SM57 BR57 S(n
KE6B Se72 CR56 KE68 G060A KE68 BR57 OA5R KE68 TH69 G060A TH69 KE68
NEUTRON PRODUCTION CROSS SECTIONS
D{d,n)^He. a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values EXPERIMENTAL TOTAL CROSS SECTIONS FOR THE REACTION D ( D , N ) H E 3
ED(MEV) 0.013 0.019 0.022 0.025 0.030 0,033 0.036 0.040 0.046 0.052 0.053 0,060 0.06 7 0.073 0.0 HO 0.0H7
0.0 93 O.IOO 0.10 7 0. 110 0.113 0.120 0.130 0. 140 0.156 0.160 0.162 0.195 0.205 0.206 0.210 0.250 0.250 0.255 0.260 0.267 0.270 0.275 0.325 0.330 0.362 0.365 0.380 0.400 0.405 0.425 0.447 0.466 0.470 0.480 0.490 0.500
SIGMA-T 0.033 0.200 0.367 0.592 l.OB 1.46 1.88 2.43 3.42 4.64 4.78 6,25 7.86 9.30 10.90 11.85 13,6 15.? 16.6 17.0 17.4 19.0 23.0 26.0 29,0 26.0 28.0 37.0 36.0 38.3 38.0 38,0 25.0 46,0 44.0 45.0 51.0 47.0 57.0 54.0 60.0 60.0 63.0 45.0 70.0 70.0 67,0 73.3 74.0 70.0 51.0 58,0
REF.
ED(MEV)
AR54 AR54 AR54 AR54 AR54 AR54 AR54 AR54 AR54 8056 AR54 AR54 AR54 AR54 AR54 RnS6 ARb4 AR^>4 AR54 AR54 ARb4 MCbl GA57 MC51 PR54 MC51 GA57 GA57 GA57 PR54 GA5T MC51 CH56 GA57 GA57 GA57 PR54 GA57 GA57 GA57 PR54 GA57 GA57 CH56 GA57 GA57 GA57 PR54 GA57 GA57 HU49 CH56
0.510 0.554 0.595 0.600 0,660 0.668 0.675 0.700 0.750 0.760 0,770 0,791 0,825 0,850 0,884 0,925 0.960 0.980 0.990 1.340 1.430 1.750 1.960 1.960 2.150 2.490 2.510 2.540 2.830 3.020 3,020 3,110 3,400 3,500 3,520 3,690 4.000 4.500 5.000 5.000 5.000 5.500 5,550 5,800 5,800 5.800 6,200 7,600 8.150 9,000 9,600 10,000
591
SIGMA-T
REF.
72.0 76.0 74.0 67.0 88.0 83.0 72.0 72.0 82.0 92.0 91.0 89.0 74.0 100.0 94.0 100.0 41.0 98.0 97.0 107.0 104.0 107.0 105.0 104.3 106.0 102.0 104.6 105.0 102.0 103.0 103.8 101.0 96.0 101.4 102.0 106,0 99,8 98,6 94,6 97,3 96,1 94,9 71,0 93,0 93,7 94,1 93,4 96,5 88,0 83.2 93.7 82.6
GA57 GA57 GA57 CH56 GA57 GA57 CH56 HU49 CH56 GA57 GA57 GA57 CH56 GA57 GA57 GA57 SA61 GA57 HU49 HU49 BL48 HU49 BL48 SC72 HU49 BL48 SC72 HU49 HU49 BL48 SC72 HU49 HU49 SC72 BL48 HU49 SC72 SC72 G060A SC72 TH69 SC72 SA61 BR57 SC72 TH69 SC72 G060A BR57 TH69 G060A TH69
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
H. LISKIEN AND A. PAULSEN
D(4n)^He. ENERGY(MEV1
0.020
a(0 lab), E^iO lab): Recommended Values 0.040
0.030
0.050
0.050
0.070
0.090
0.080
CENTER--OF--MASS INPUT VALUES FDR THE REACTION 0 ( D , N ) H 6 3 U-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4
0.025 0.819 0.000 0.181 0.000 0.000
0.310 0.758 0.000 0.241 0.000 0.001
0.125 0.785 0.000 0.215 0.000 0,000
ANGLE(DEGREE)
0.780 0.719 0.000 0.279 0.000 0.002
0.520 0.737 0.000 0 . 2 6 1L 0.000 0.002
DIFFERENTIAL CROSS- S6CTIt)NS
IN •rHE LABORATORY SYSTEM
(MB/SR)
01 01 01 01 01 01 01
0.189E 01 0.188E 01 0.185E 01 0 . 1 8 I E 01 0.175E 01 0 . 1 5 8 E 01 0.150E 01
00 00 00 00 00 00
0 . 6 8 9 E 00 0 . 6 5 6 E 00 0 . 5 3 0 E 00 0 . 6 1 1 E 00 0 . 5 9 9 6 00 0 . 5 9 4 E 00
0.123E 0.1156 0.109E 0.103E 0.955E 0.9076 0.855E 0.812E 0.7786 0.753E 0.738E 0.7316
01 01 01 01 00 00 00 00 00 00 00 00
0.151E 01 0.142E 01 0.133E 01 0 . 1 2 5 E 01 0.115E 01 0 . 1 0 9 6 01 0.102E 01 0.974E 00 0 . 9 3 1 E 00 0 . 9 0 0 6 00 0 . 8 8 1 E 00 0 . 8 7 4 6 00
0.4536 0.4596 0.459E 0.4826 0.4986 0.5156
00 00 00 00 00 00
0.596E 00 0 . 7 3 4 6 0 . 5 0 4 E 00 0 . 7 4 5 6 0 . 5 1 7 E 00 0 . 7 6 3 6 0.536E 00 0.788E 0 . 6 5 9 E 00 0 . 8 1 8 E 0 . 5 8 5 E 00 0 . 8 5 2 E
00 00 00 00 00 00
0.878E 0.892E 0.915E 0.9476 0.985E 0.1026
00 00 00 00 00 01
00 00 00 00 00 00
0.5366 0.5576 0.5786 0.5996 0.6196 0.5386
00 00 00 00 00 00
0 . 7 1 3 E 00 0 . 8 8 9 6 0 . 7 4 2 E 00 0 . 9 2 8 6 0 . 7 7 2 E 00 0 . 9 6 7 6 0 . 8 0 2 6 00 O.IOOE 0 . 8 3 0 6 00 0 . 1 0 4 E 0 . 8 5 5 6 00 0 . 1 0 7 E
00 00 00 01 01 01
0.1076 0.1126 0.117B 0.122E 0.125E 0.131E
01 01 01 01 01 01
00 00 00 00 00 00
0.655E 0.569E 0.680E 0.689E 0.694E 0.595 6
00 00 00 00 00 00
0.879E 0.899E 0.9156 0.927E 0.934E 0.9376
O.llOE 0.113E 0.1156 0.1176 0.1186 0.1186
01 01 01 01 01 01
0.1346 0.1386 0.140E 0.142E 0.143E 0.144E
01 01 01 01 01 01
0 . 2 6 6 E -- 0 1 0 . 2 6 5 E --01 0 . 2 6 3 E -- 0 1 0.26OE--01 0 . 2 5 6 E --01 0 . 2 5 1 E --01 0 . 2 4 5 E -- 0 1
0 . 1 3 4 E 00 0 , 3 3 8 6 0 . 1 3 4 E 00 0 . 3 3 7 6 0 . 1 3 3 E 00 0 . 3 3 4 6 0 . 1 3 1 E 00 0 . 3 2 8 6 0 . 1 2 8 E 00 0 . 3 2 1 6 0 . 1 2 5 6 00 0 . 3 1 2 6 0 . 1 2 2 6 00 0 . 3 0 1 E
35.0 *0.0 45.0 50.0 55.0 60.0
0 . 2 3 8 8 --01 0 . 2 3 1 E -- 0 1 0 . 2 2 4 E -- 0 1 0 . 2 1 7 E -- 0 1 0 . 2 1 0 E -- 0 1 0 . 2 0 3 E -- 0 1
0 . 1 1 8 6 00 0 . 1 1 3 6 00 0 , 1 0 9 6 00 0 , 1 0 5 E 00 O.IOIE 00 0 . 9 7 2 6 -- 0 1
0 . 2 9 0 E 00 0 . 4 8 3 6 0 . 2 7 8 6 00 0 . 4 5 1 6 0 . 2 6 5 6 00 0 . 4 3 8 E 0 . 2 5 4 6 00 0 . 4 1 6 6 0 . 2 4 2 E 00 0 . 3 9 5 6 0 . 2 3 1 6 00 0 . 3 7 6 6
00 00 00 00 00 00
0.721E 0.6856 0.6496 0.5136 0.579E 0.548E
00 00 00 00 00 00
0.975E 0.924E 0.872E 0.821E 0.772E 0.728E
65.0 70.0 75.0 80.0 85.0 90.0
0 . 1 9 7 6 --01 0 . 1 9 2 E -- 0 1 O.ISBE-- 0 1 0 . 1 8 5 E --01 0 . 1 8 3 E --01 0 . 1 8 2 E --01
0 . 9 3 7 6 --01 0 . 9 0 8 E --01 0 . 8 8 3 6 --01 0 . 8 6 5 6 --01 0 . 8 5 2 6 --01 0 . 8 4 6 6 --01
0.222E 0.214E 0.207E 0.202E 0.199E 0.197E
00 00 00 00 00 00
0.3596 0.3446 0.3326 0.3246 0.3186 0.3156
00 00 00 00 00 00
0.521E 0.497E 0.479E 0.4556 0.4566 0.4526
95.0 100.0 105.0 110.0 115.0 120.0
0 . 1 8 1 E -- 0 1 0 . 1 8 2 E -- 0 1 0 . 1 8 4 E -- 0 1 0 . 1 8 7 E -- 0 1 0 . 1 9 0 E -- 0 1 0 . 1 9 4 E -- 0 1
0 . 8 4 6 E -- 0 1 0 . 8 5 2 6 --01 0 . 8 6 3 E -- 0 1 0 . 8 7 9 6 --01 0 . 8 9 9 6 --01 0 . 9 2 1 6 --01
0.1976 0.1996 0.2026 0.2076 0.2126 0.2186
00 00 00 00 00 00
0.315E 0.319E 0.3256 0.333E 0.3436 0.354E
00 00 00 00 00 00
125.0 130.0 135.0 140.0 145.0 150.0
0 . 1 9 8 E '- 0 1 0 . 2 0 3 E -- 0 1 0 . 2 0 7 E -- 0 1 0 . 2 1 2 E -- 0 1 0 . 2 1 6 E '- 0 1 0 . 2 2 1 E -- 0 1
0 . 9 4 7 6 -- 0 1 0 . 9 7 3 E -- 0 1 O.IOOE 00 0 . 1 0 2 6 00 0 . 1 0 5 E 00 0 . 1 0 7 6 00
0.225E 0.2336 0.2406 0.2486 0.2556 0.2526
00 00 00 00 00 00
0.3576 0.380E 0.394E 0.407E 0.420E 0.431E
155.0 160.0 155.0 170.0 175.0 180.0
0 . 2 2 4 E -- 0 1 0.228E -01 0 . 2 3 0 E -- 0 1 0 . 2 3 2 E '- 0 1 0 . 2 3 3 E -- 0 1 0.234E -01
0.1106 O.lllE 0.U3E 0.114E 0.115E 0.115E
00 00 00 00 00 00
0.2676 0.273E 0.277E 0.280E 0.2826 0.282E
00 00 00 00 00 00
0.4426 0.4516 0.4596 0.454E 0.457E 0.468E
ENERGY(MEV)
0.1001
0.2001
0.1501
0.5736 0.5716 0.565E 0.555E 0.541E 0.524E 0.504E
1.550 0.581 0.000 0.314 0.000 0.005
00 0 . 8 6 8 E 00 0 . 1 1 9 E 0 1 0 . 1 5 2 6 00 0 . 8 6 5 E 00 0 . 1 1 8 E 0 1 0 . 1 5 2 E 00 0 . 1 1 5 E 0 1 0 . 1 4 9 6 on 00.. 88 35 74 EE 00 0 . 1 1 4 E 01 0 . 1 4 6 E 00 00 0 . 8 1 5 E 00 O . l l l E 0 1 0 . 1 4 2 E 00 0 . 7 8 7 E 00 0 . 1 0 7 E 0 1 0 . 1 3 5 6 00 0 . 7 5 5 E 00 0 . 1 0 2 E 0 1 0 . I 3 O E
0.0 5,0 10.0 15.0 20.0 25.0 30.0
00 00 00 00 00 00 00
1.350 0.692 0.000 0.304 0.000 0.004
1.050 0.705 0.000 0.292 0.000 0.003
0.2501
0 . 3 0 C1
00 00 00 00 00 00
00 00 00 00 00 00
O . 3 5 01
0.450
0.400
CENTER-•OF-•MASS INPUT VALUES, FUR TH6 R6ACTI0N D ( D . N ) H 6 3 D-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4
2.0001 0.671 O.OOC1 0.323 O.OOC1
0.006
ANGLE(DEGREE)
5.900 0.583 0.0001 0.395 0.0001 0.022
4 . 6 0 C1 0.605 O.OOC1 0 . 3 7 91 O.OOC1
3 . 3 3 C1 0.633 0.0001 0 . 3 5 61 O.OOC1 0,011
o.oie
DIFF6R6NTIAL
7.1O01 0.55'if O.OOC1 0 . 4 0 81 O.OOC1 0 . 0 2 61
C R 0 S S - S 6 C T I 0 N S. (MB/SR)
8.300 0.547 O.OOC 0.418 0.000 0.035
)
9 . 4 0 C1 0.532 O.OOC1 0 . 4 2 61 O.OOC1 0.042
10.400 0.518 0.000 0.433 0.000 0.049
IN THE LABORATORY SYSTE^1
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.229E 0.228E 0.2246 0.219E 0.212E 0.203E 0.193E
01 01 01 01 01 01 01
0.3936 0.3906 0.3646 0.3736 0.3586 0.3406 0.3206
01 01 01 01 01 01 01
0.55Ae 0.5526 0.5416 0.524E 0.500E 0.4736 0.4426
01 01 01 01 01 01 01
0.7286 0.7236 0.7076 0.6826 0.6486 0.509 6 0.5656
01 01 01 01 01 01 01
0.8926 0.8856 0.8646 0.8316 0.7856 0.7346 0.6776
01 01 01 01 01 01 01
0.1066 0.105E 0.1026 0.981E 0.925E 0.8596 0.7876
02 02 02 01 01 01 01
0.1216 0.1206 0.1176 0.1126 0.1056 0.9736 0.8856
02 02 02 02 02 01 01
0 . 1 3 5 E 02 0 . 1 3 5 E 02 0 . 1 3 1 6 02 0 . 1 2 5 E 02 0 . 1 1 7 E 02 0 . 1 0 7 E 02 0.974E 01
35.0 40.0 45.0 50.0 55.0 60.0
0.182E 0.170E 0.159E 0.148E 0.138E 0.129E
01 01 01 01 01 01
0.2996 0.2776 0.256E 0.2356 0.2166 0.2006
01 01 01 01 01 01
0.4096 0.3756 0.3436 0.3126 0.2846 0.260E
01 01 01 01 01 01
0.5196 0.4736 0.4286 0.3866 0.349E 0.316E
01 01 01 01 01 01
0.6176 0.558E 0.502E 0.449 E 0.4036 0.3636
01 01 01 01 01 01
0.7136 0.640E 0.571E 0.508E 0.4536 0.4066
01 01 01 01 01 01
0.7976 0.7116 0.530E 0.557E 0.494E 0.441E
65.0 70.0 75.0 80.0 85.0 90.0
01 01 01 01 01 01
0.1856 0.173E 0.1546 0.158E 0.1546 0.1536
01 01 01 01 01 01
0 . 2 3 9 6 01 0 . 2 8 9 6 0 . 2 2 2 6 01 0 . 2 5 8 6 0.2096 01 0.2526 0.2016 01 0.2416 0 . 1 9 6 6 01 0 . 2 3 5 6 0 . 1 9 5 6 01 0 . 2 3 4 6
01 01 01 01 01 01
0.3306 0.3046 0.2856 0.273E 0.2576 0.2666
01 01 01 01 01 01
0.3686 0.3386 0.3176 0.303E 0.2966 0.295E
01 01 01 01 01 01
0.398E 0.365E 0.342E 0.3276 0.320E 0.320E
0.871E 01 0 . 7 7 1 E 01 0.679E 01 0.597E 01 0 . 5 2 5 6 01 0 . 4 6 8 E 01 0 . 4 2 2 E 01 0.387E 01 0.352E 01 0.346E 01 0 . 3 3 9 6 01 0.339E 01
95.0 100.0 105.0 110.0 115.0 120.0
0.121E 0.114E 0.109E 0.105E 0.1036 0.102E 0.103E 0.1046 0.1076 O.lllE 0.116E 0.121E
01 01 01 01 01 01 01 01 01 01 01 01
01 01 01 01 01 01
0.1546 0.1586 0.163E 0.1706 0.179E 0.188E
01 01 01 01 01 01
0.1976 0.2026 0.2106 0.2206 0.2326 0.2456
01 01 01 01 01 01
0.237E 0.244E 0.2556 0.258E 0.2846 0.301E
01 01 01 01 01 01
0.2706 0.2796 0.2926 0.308E 0.327E 0.348E
01 01 01 01 01 01
0.3016 0.3116 0.3256 0.3456 0.3576 0.3926
01 01 01 01 01 01
0.3256 0.3386 0.355E 0.3766 0.401E 0.4296
01 01 01 01 01 01
0.3456 0.359E 0.3776 0.401E 0.428E 0.4596
01 01 01 01 01 01
125.0 130.0 135.0 140.0 145.0 150.0
0.127E 0.133E 0.139E 0.145E 0.151E 0.1566
01 01 01 01 01 01
0.198E 0.209E 0.219E 0.230E 0.240E 0.249E
01 01 01 01 01 01
0.260E 0.275E 0.290E 0.3066 0.3196 0.332E
01 01 01 01 01 01
0.3206 0.3406 0.3596 0.3786 0.397E 0.4146
01 01 01 01 01 01
0 . 3 7 IE 0.3956 0.4196 0.4426 0.4646 0.4856
01 01 01 01 01 01
0.4196 0.447E 0.4746 0.5026 0.5286 0.5526
01 01 01 01 01 01
0.4596 0.4916 0.522E 0.5546 0.5836 0,6116
01 01 01 01 01 01
0.493E 0.527E 0.5536 0.5976 0.631E 0.551E
01 01 01 01 01 01
155.0 160.0 165.0 170.0 175.0 180.0
0.151E 0.165E 0.1686 0.170E 0.1726 0.1726
01 01 01 01 01 01
0.257E 0.2546 0.2706 0.2746 0.2766 0.277E
01 01 01 01 01 01
0.3446 0.3546 0.3626 0.3586 0.3716 0.3726
01 01 01 01 01 01
0.4296 0.4426 0.4526 0.4596 0.4546 0.466E
01 01 01 01 01 01
0.5036 0.518E 0.531E 0.540E 0.5466 0.5486
01 01 01 01 01 01
0.574E 0.5926 0.507E 0.618E 0.625E 0.6276
01 01 01 01 01 01
0.5356 0,5576 0,5746 0,685E 0.594E 0,6966
01 01 01 01 01 01
0.5896 0.7126 0.7316 0.7456 0.7536 0.756E
01 01 01 01 01 01
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
592
NEUTRON PRODUCTION CROSS SECTIONS
D(4/i)3He.
aid lab), EJfi lab): Recommended Values 0.030
ENERGY(MEV)
REST ENERGY I N MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET T 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6
o.oyo
0.080
O.O'hO 0.050 0.060 0.070 INPUT VALUES FOR THE REACTION DID,N)H63 0-VALUE
IN MEV U=
3.269
RESIDUAL NUCLEUS T't=2808.42l
ENERGY OF PARTICLE-3 IHEV) IN THE LABORATORY SYSTEM
ANGLE(DEGREE*
0.0 S.O 10.0 15.0 20, 25. 30, 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165-.0 170.0 175.0 180.0 ENERGY(MEV)
2.673 2.659 2.643 2.626 2.607 2.588
2.751 2.750 2.746 2.741 2.733 2.723 2.711 2.697 2.681 2.663 2.645 2.624 2.603
2.778 2.777 2.773 2.76 7 2 . 7 58 2.747 2.734 2.719 2.702 2.683 2.662 2.640 2.617
2.804 2.802 2.798 2.792 2.78 2 2.770 2.756 2.740 2.721 2.701 2.679 2.655 2.631
2.828 2.827 2.822 2.815 2.805 2.793 2.777 2.760 2.740 2.718 2.695 2.670 2.643
2.568 2.547 2.526 2.504 2.482 2.461
2.581 2.558 2.535 2.511 2.487 2.463
2.59 3 2.568 2.543 2.517 2.491 2.466
2.605 2.578 2.551 2.523 2.496 2.468
2.616 2.588 2.559 2.529 2.500 2.471
2.439 2.420 2,401 2,383 2,366 2,350
2.439 2.418 2.397 2.377 2.358 2.340
2.440 2.416 2.394 2.372 2,351 2.331
2.440 2.415 2.391 2.36 7 2.344 2.323
2.441 2.414 2.388 2.363 2.339 2.316
2.442 2.413 2.386 2.359 2.334 2.309
2.348 2.335 2.324 2.313 2.303 2,295
2.334 2.320 2,306 2.294 2.283 2.273
2.288 2.282 2.277 2.274 2.272 2,271
2.265 2.258 2.253 2.249 2.247 2.246
2.322 2.306 2.291 2.278 2.265 2.255 2.246 2.238 2.232 2.228 2.225 2.225
2.312 2.294 2.278 2.263 2.250 2.238 2.229 2.220 2.214 2.209 2.207 2.206
2.303 2.284 2.266 2.250 2.236 2.224 2.213 2.204 2.197 2.192 2.189 2.189
2.294 2.274 2.255 2.239 2.224 2.210 2,199 2.190 2.182 2.177 2.174 2.173
2.286 2.265 2.246 2.228 2.212 2.198 2.186 2.176 2.168 2.163 2.160 2.159
0.300
0.350
2.538 2.522 2.506 2.489 2.473 2.456
2.691 2.690 2.687 2.682 2.676 2.668 2.658 2.647 2,634 2.620 2.605 2.589 2.572 2.554 2.535 2.516 2.497 2.478 2.458
2.440 2.426 2.413 2.400 2.388 2.376
2.439 2.423 2.406 2.391 2.376 2.361
2.365 2.354 2.345 2.336 2.328 2.321 2.315 2.310 2.306 2.304 2.302 2.301
2.615 2.615 2.613 2.610 2.605 2.600 2.593
2.656 2.655 2.653 2.649 2.643 2.636 2.628
2.585 2.576 2.567 2.556 2.545 2.533
2.618 2.608 2.596 2.582 2.569 2.554
2.520 2.507 2.494 2.481 2.467 2.453
0.100
0.150
0.200
2.722 2.721 2.718 2.713 2.706 2.696 2.686
0.250
0.400
0
INPUT VALUES FOR THE REACTION 0 ( D . N ) H E 3 REST ENERGY I N MEV FOR PROJECTILE TARGET PRUDUCT RESIDUAL NUCLEUS ANGLE(DEGREE)
ENERGY OF PARTICLE-3
Tl=1875.633 72=1875.633 T3= 9 3 9 . 5 7 6 T4=2808 . 4 2 1 (MEV)
Q-VALUE IN MEV 0=
IN THE LABORATORY SYSTEM
0.0 5.0 10,0 15,0 20.0 25.0 30,0 35,0 40,0 45,0 50,0 55.0 50.0 65.0 70.0 75.0 80.0 85.0 90.0
2.851 2.850 2,845 2,838 2,827 2,814 2,798
2,957 2,955 2,950 2,940 2,927 2,910 2,889
3,051 3 k 049 3.042 3,031 3,015 2,995 2,971
3.138 3.135 3.127 3.114 3.096 3.073 3.046
3.219 3.216 3.207 3.193 3.172 3.147 3.116
3.295 3.293 3.283 3.267 3.245 3.217 3.183
3.370 3.367 3.356 3.339 3.314 3.284 3.247
3.442 3.438 3.427 3.408 3.381 3.348 3.309
2,779 2,758 2,735 2.710 2,683 2,656 2.626 2.596 2,566 2,535 2,504 2,473
2,866 2,840 2,811 2,779 2,745 2,711
2,943 2,912 2,878 2,841 2.802 2.761
3.014 2.979 2.940 2.698 2.854 2.807
3.081 3.041 2.998 2.951 2.902 2 . 8 50
3.144 3.101 3.053 3.002 2.948 2.89 2
3.205 3.158 3.105 3.051 2.992 2.931
3.253 3.213 3.157 3.098 3.035 2.970
2,675 2,638 2,600 2,552 2,523 2,485
2.719 2.675 2.631 2,586 2,542 2,498
2.759 2.710 2.660 2.610 2.560 2.510
2.797 2.743 2.687 2.632 2.577 2.523
2.833 2.774 2.714 2.554 2.594 2.535
2.868 2.804 2.740 2.575 2.611 2.548
2.902 2.834 2.755 2.695 2.527 2,560
95.0 100.0 105.0 IIO.O 115.0 120.0
2,442 2,413 2,383 2,355 2,329 2,303
2,448 2,411 2,375 2,342 2,309 2,278
2,455 2,412 2,372 2,332 2,295 2,260
2.452 2.415 2.359 2.325 2.284 2.245
2.470 2.418 2.358 2.321 2.275 2.233
2.478 2.422 2.358 2.317 2.269 2.223
2.486 2.427 2.369 2.315 2.253 2.215
2,495 2.432 2.371 2,313 2.259 2.207
125.0 130,0 135,0 140,0 145,0 150,0
2,279 2,257 2,236 2,218 2,201 2.186 2.174 2.164 2.156 2.150 2.146 2.145
2,250 2,223 2,198 2,175 2,156 2.138
2,227 2,196 2,168 2,143 2,120 2.100
2.209 2 . 175 2.144 2 . 116 2.091 2.059
2.193 2.157 2.123 2.093 2.055 2.043
2.180 2.141 2.105 2.073 2.045 2.020
2.169 2.128 2.090 2.056 2.026 1.999
2.150 2.115 2,075 2.040 2.009 1.981
2.123 2. I l l 2.10 2 2.095 2.091 2.089
2,084 2,070 2,059 2,051 2,047 2,045
2.051 2.035 2.024 2.015 2.010 2.009
2.023 2.007 1.994 1.985 1.979 1.977
1.999 1.981 1.968 1.958 1.952 1.950
1.977 1.959 1.945 1.934 1.928 1.925
1.958 1.939 1.924 1.913 1.907 1.905
155,0 160.0 165.0 170.0 175.0 180.0
593
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
a(0 lab), £^(0 lab): Recommended Values
D(d,nfHe. ENERGYIMEV)
0.500
0.550
0.600
0.650
0.7C0
0.750
O.SOO
0.850
CENTER-UF-MASS INPUT VALUES FUR THE REACTION DIU,IM|HE3 0-SIGMA-0IM6/SR) A 0 A 1 A 2 A 3 A 4
ll.AOO 0.506 0.000 0.437 0.000 0.057
12.400 0.494 0.000 0.440 0.000 0.066
ANGLE(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0
13.400 0.483 0.000 0.443 0.000 0.074
14.300 0.474 0.000 0.444 0.000 0.082
15.100 0.465 0.000 0.445 0.000 0.090
DIFFERENTIAL CROSS-SECTIONS IMB/SRl
15.800 0.456 0.000 0.446 0.000 0.098
16.500 0.447 0.000 0.445 0.000 0.108
17.200 0.439 0.000 0.444 0.000 0.117
IN THE LABORATORY SYSTEM
0.151E 0.1506 0.145E 0.138E 0.128E 0.117E 0.105E
02 02 02 02 02 02 02
0.1676 0.166E 0.159E 0.151E 0.140E 0.127E 0.114E
02 02 02 02 02 02 02
0.182E 0.180E 0.1746 0.164E 0.151E 0.137E 0.122E
02 02 02 02 02 02 02
0.197E 0.194E 0.187E 0.176E 0.162E 0.146E 0.129E
02 02 02 02 02 02 02
0.210E 0.207E 0.1996 0.187E 0.171E 0.153E 0.135E
02 02 02 02 02 02 02
0.222E 0.219E 0.210E 0.196E 0.179E 0.160E 0.1406
02 02 02 02 02 02 02
0.234E 0.230E 0.221E 0.206E 0.187E 0.166E 0.144E
02 02 02 02 02 02 02
0.246E 0.242E 0.232E 0.215E 0.195E 0.172E 0.148E
02 02 02 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.4466 0.409E 0.383E 0.367E 0.359E 0.3596
01 01 01 01 01 01
0.4686 0.430E 0.403E 0.386E 0.3786 0.3786
01 01 01 01 01 01
0.489E 0.449E 0.4226 0.405E 0.396E 0.396E
01 01 01 01 01 01
0.508E 0.468E 0.440E 0.4236 0.414E 0.413E
01 01 01 01 01 01
0.522E 0.482E 0.454E 0.437E 0.427E 0.4266
01 01 01 01 01 01
0.367E 0.3806 0.4006 0.425E 0.455E 0.488E
01 01 01 01 01 01
0.386E 0.400E 0.420E 0.447E 0.478E 0.514E
01 01 01 01 01 01
0.404E 0.418E 0.4406 0.467E 0.501E 0.539E
01 01 01 01 01 01
0.420E 0.435E 0.457E 0.4856 0.5206 0.5616
01 01 01 01 01 01
0.4336 0.447E 0.469E 0.498E 0.534E 0.577E
01 01 01 01 01 01
01 01 01 01 01 01 01 01 01 01 01 01
0,.541E 0.,503E 0,.476E 0,.459E 0 .,448E 0..4456
95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
0,.4506 0..4626 0..483E 0..5136 0..550E 0,.5956
01 01 01 01 01 01 01 01 01 01 01 01
0.5526 0.515E 0.489E 0.4716 0.4606 0.4556 0.4596 0.4706 0.490E 0.5196 0.5586 0.604E
01 01 01 01 01 01 01 01 01 01 01 01
0.524E 0.562E 0.6016 0.639E 0.6766 0.710E
01 01 01 01 01 01
0.553E 0.595E 0.637E 0.679E 0.719E 0.756E
01 01 01 01 01 01
0.582E 0.626E 0.672E 0.717E 0.761E 0.801E
0.605E 0.653E 0.7016 0.750E 0.796E 0.840E
01 01 01 01 01 01
0.623E 0.673E 0.725E 0.776E 0.825E 0.871E
01 01 01 01 01 01
01 01 01 01 01 01
0 .6466 0 .7006 0,.757E 0 .814E 0..868E 0 .920E
01 01 01 01 01 01
0.656E 0.713E 0.772E 0.832E 0.8896 0.9436
01 01 01 01 01 01
155.0 160.0 165.0 170.0 175.0 180.0
0.740E 0.7666 0.787E 0.802E 0.8126 0.815E
01 01 01 01 01 01
0.7e9E 0.818E 0.8416 0.8586 0.868E 0.872E
01 01 01 01 01 01
0.838E 0.869E 0.894E 0.9126 0.9236 0.927E
01 01 01 01 01 01 01 01 01 01 01 01
0.8796 0.9126 0.939E 0.959E 0.971E 0.9756
01 01 01 01 01 01
0.913E 0.948E 0.9776 0.9976 0.1016 O.IOIE
01 01 01 01 02 02
0.531E 0.4926 0.4646 0.4466 0.437E 0.435E 0.441E 0.4556 0.477E 0.506E 0.5446 0.587E 0.636E 0.688E 0.742E 0.796E 0.848E 0.8966 0.940E 0.977E O.IOOE 0.102E 0.1046 0.104E
01 01 02 02 02 02
0,.965E 0..lOOE 0,.103E 0,. 106E 0 .107E 0..107E
01 02 02 02 02 02
0.991E 0.1036 0.1066 0.109E 0.1106 O.lllE
01 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
ENERGY(MEV)
0.900
0.950
1.000
1.100
1.200
1.300
1.400
1.500
CENTER-OF-MASS INPOT VALUES FOR THE REACTION DIU,N)HE3 D-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 6
17.800 0.43; 0.000 0.443 0.000 0.125 0.000 0.000
»
ANGLE(DEGREE 1
19.000 0.416 1 0.000 0.439 0.000 0.142 0.000 0.001
18.400 0.425 0.000 0.441 0.000 0.134 0.000 0.000
20.000 0.405 0.000 0.434 0.000 0.158 0.000 0.003
21.000 0.393 0.000 0.428 0.000 0.174 0.000 0.005
21.900 0.381 0.000 0.42; 0.000 0.189 0.000 0.008
23.400 0.360 0.000 0.410 0.000 0.216 0.000 0.014
22.700 0.370 0.000 0.416 0.000 0.203 0.000 0.011
DIFFERENTIAL CROSS-:SECTIONS (MB/SR) 1[N THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.257E 0.2536 0.2416 0.2236 0.2016 0.177E 0.152E
02 02 02 02 02 02 02
0.267E 0.2636 0.2516 0.2326 0.208E 0.181E 0.155E
02 02 02 02 02 02 02
0.278E 0.274E 0.260E 0.2406 0.214E 0.186E 0.158E
02 02 02 02 02 02 02
0.297E 0.2926 0.276E 0.2536 0.2246 0.193E 0.162E
02 02 02 02 02 02 02
0.316E 0.310E 0.293E 0.266E 0.234E 0,199E 0,165E
02 02 02 02 02 02 02
0.334E 0.327E 0.307E 0.2786 0.2416 0.2036 0.1676
02 02 02 02 02 02 02
0.3516 0.343E 0.321E 0.2886 0.248 6 0.2076 0.1686
02 02 02 02 02 02 02
0.365E 0.357E 0.333E 0.296E 0.2536 0.2096 0.1686
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.129E 0.1086 0.9176 0.784E 0.6846 0.612E
02 02 01 01 01 01
0.131E 0.1096 0.923E 0.7886 0.6896 0.6196
02 02 01 01 01 01
02 02 01 01 01 01
0.134E O.lllE 0.9296 0.7936 0.699E 0.635E
02 02 01 01 01 01
0.1346 0.1086 0.901E 0.778E 0.7026 0.6586
02 02 01 01 01 01
0.1336 0.106E 0.8846 0.7676 0.699E 0.662E
02 02 01 01 01 01
01 01 01 01 01 01
0.570E 0.536E 0.511E 0.493E 0.4806 0.472E
01 01 01 01 01 01
01 01 01 01 01 01
0.593E 0.5626 0.539E 0.519E 0.502E 0.4906
0.6086 0.5816 0.5596 0.5376 0.518E 0.502E
01 01 01 01 01 01
0.1356 0.1106 0.915E 0.786E 0.7036 0.6526 0.6206 0.5966 0.673E 0.5516 0.5286 0.5086
02 02 01 01 01 01
0.5616 0.525E 0.500E 0.481E 0.4696 0.464E
02 02 01 01 01 01 01 01 01 01 01 01
0.135E O.lllE 0.926E 0.7926 0.7036 0,6466
65.0 70.0 75.0 80.0 85.0 90.0
0.132E O.UOE 0.9296 0.7936 0.6956 0.626E 0.579E 0.546E 0.5226 0.5036 0.488E 0.480E
01 01 01 01 01 01
0.6306 0.609E 0.586E 0.562E 0.536E 0.5136
01 01 01 01 01 01
0.639E 0.620E 0.5986 0.5716 0.5436 0.516E
01 01 01 01 01 01
95.0 100.0 105.0 110.0 115.0 120.0
0.4656 0.475E 0.4956 0.5246 0.5636 0.6106
01 01 01 01 01 01
0.472E 0.480E 0.499E 0.527E 0.566E 0.614E
01 01 01 01 01 01
0.478E 0.485E 0.5026 0.5306 0.5706 0.618E
01 01 01 01 01 01
0.485E 0.489E 0.504E 0.531E 0.569E 0.619E
01 01 01 01 01 01
0.492E 0.492E 0.504E 0.5306 0.5686 0.6196
01 01 01 01 01 01
0.4956 0.492E 0.5016 0.6246 0.5626 0.613E
01 01 01 01 01 01
0.496E 0.4896 0.495E 0.5176 0.554E 0.605E
01 01 01 01 01 01
0.495E 0.4846 0.4886 0.5086 0.5446 0.5966
01 01 01 01 01 01
125.0 130.0 135.0 140.0 145.0 150.0
0.664E 0.7236 0.7846 0.8466 0.905E 0.9616
01 01 01 01 01 01
0.670E 0.730E 0.794E 0.6586 0.920E 0.9786
01 01 01 01 01 01
0.6756 0.7386 0.8036 0.870E 0.934E 0.994E
01 01 01 01 01 01
0.678E 0.743E 0.812E 0.883E 0.951E O.lOlE
01 01 01 01 01 02
0.679E 0.7486 0.8206 0.895E 0.967E 0.1036
01 01 01 01 01 02
01 01 01 01 01 02
0.669E 0.743E 0.e22E 0.903E 0.983E 0.105E
01 01 01 01 01 02
0.6616 0.7366 0.818E 0.902E 0.9866 0.1066
01 01 01 01 01 02
155.0 160.0 165.0 170.0 175.0 180.0
0.1016 0.1056 0.1086 O.lllE 0.1126 0.113E
02 02 02 02 02 02
0.1036 0.1076 O.lllE 0.113E 0.1156 0.1156
02 02 02 02 02 02
0.1046 0.1096 0.1136 0.1166 0.117E 0.118E
02 02 02 02 02 02
0.107E 0.1126 0.1166 0.119E 0.1216 0.1216
02 02 02 02 02 02
0.1096 0.1156 0.119E 0.122E 0.124E 0.125E
02 02 02 02 02 02
0.676E 0.747E 0.8236 0.901E 0.977E 0.105E O.lllE 0.1176 0.1216 0.1256 0.1276 0.127E
02 02 02 02 02 02
0.112E 0.1186 0.1236 0.1276 0.1296 0.1306
02 02 02 02 02 02
0.1136 0.1196 0.1246 0.1286 0.1306 0.1316
02 02 02 02 02 02
Nucleor Data Tables, VoL 1 1 , No. 7, 1973
5 9 4
NEUTRON PRODUCTION CROSS SECTIONS
D(4n)^He. ENERGY(MEV)
0.500
a(0 lab), E„(e lab): Recommended Values
0.550
0.600
0.650
0.700
0.750
0.800
0
INPUT VALUES FOR THE REACTION n l D , N ) H E 3 REST ENERGY I N MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET T 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS T * = 2 a 0 8 . * 2 l ENERGY OF PARTICLE-3
ANGLE(OEGREE)
Q-VALUE
IN MEV g=
(MEVI IN THE LABORATORY SYSTEll
0.0 5.0 10.0 15.0 20.0 25.0 30.0
3.511 3.507 3.495 3.475 3.447 3.411 3.369
3.579 3.575 3.562 3.540 3.610 3.472 3.427
3.645 3.641 3.627 3.604 3.572 3.532 3.485
3.710 3.705 3.591 3.666 3.633 3.691 3.641
3.774 3.769 3.753 3.728 3.593 3.649 3.596
3.837 3.831 3.815 3.788 3.752 3.705 3.650
3.899 3.893 3.876 3.848 3.810 3.751 3.703
3.960 3.954 3.935 3.907 3.867 3.816 3.756
35.0 'tO.O '^5.0 50.0 55.0 60.0
3.320 3.266 3.207 3.143 3.076 3.007
3.430 3.369 3.303 3.232 3.167 3.079
3.483 3.419 3.349 3.274 3.196 3.114
3.535 3.468 3.395 3.316 3.234 3.148
3.687 3.510 3.527 3.438 3.345 3,248
2.935 2.862 2.789 2.716 2.643 2.572
2.999 2.918 2.837 2.756 2.676 2.597
3.030 2.945 2.860 2.775 2.592 2.610
3.061 2.972 2.883 2.794 2.707 2.522
3.587 3.515 3.439 3.357 3.271 3.182 3.09 1 2.998 2.905 2.814 2.723 2.635
3.537 3.564 3.484 3.398 3.308 3.215
65.0 70.0 75.0 80.0 85.0 90.0
3.376 3.318 3.255 3,188 3.117 3.043 2.957 2.890 2.813 2.736 2.660 2.685
3.120 3.024 2.928 2.832 2.739 2.547
3.150 3 . 0 50 2.950 2.851 2.754 2.660
95.0 100.0 105.0 110.0 115.0 120.0
2.503 2.437 2.373 2.312 2.255 2.201
2.612 2.442 2.375 2.312 2.252 2.196
2.522 2.448 2.378 2.312 2.250 2.191
2.631 2.455 2.382 2.313 2.248 2.188
2.540 2.451 2.386 2.314 2.247 2.185
2.650 2.458 2.389 2.315 2.246 2.182
2.559 2.474 2.394 2.318 2.246 2.180
2.569 2.481 2.398 2.320 2.245 2.178
125.0 130.0 135.0 140.0 145.0 150.0
2.151 2.106 2.064 2.027 1.993 1.965 1.940 1.921 1.905 1.894 1.887 1.885
2.144 2.096 2.053 2.014 1.980 1.950 1.925 1.904 1.888 1.877 1.870 1.867
2.137 2.088 2.043 2.003 1.967 1.936 1.910 1.889 1.873 1.861 1.854 1.851
2.132 2.081 2.034 1.993 1.955 1.924 1.897 1.875 1.858 1.846 1.839 1.836
2.127 2.074 2.025 1.983 1.945 1.913
2.119 2.063 2.012 1.957 1.927 1.893
2.115 2.058 2.006 1.960 1.919 1.884
1.885 1.8 63 1.845 1.833 1.825 1.823
2.122 2.068 2.019 1.975 1.936 1.902 1.874 1.851 1.833 1.820 1.812 1.810
1.864 1.840 1.822 1.809 1.801 1.798
1.8 54 1.830 1.811 1.798 1.790 1.'787
0.900
0.950
1.000
1.100
1.200
1.300
1.400
1.500
155.0 160.0 165.0 170.0 175.0 180.0
ENERGYIMEV)
INPUT VALUES FOR THE REACTION D ( 0 , N ) H E 3
ANGLE(DEGREE)
REST ENERGY I N MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 Q-VALUE IN MEV Q= TARGET 7 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS 7 4 = 2 8 0 8 . 4 2 1 ENERGY OF PARTICLe-3 (MEV) I N THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
4.020 4.014 3.995 3.965 3.923 3.871 3.808
35.0 40.0 45.0 50.0 55.0 60.0
3.736 3.556 3.570 3.478 3.381 3.280
65.0 70.0 75.0 80.0 85.0 90.0
3.178 3.075 2.972 2.869 2.769 2.572
95.0 100.0 105.0 110.0 115.0 120.0
2.578 2.488 2.402 2.322 2.245 2.176
125.0 130.0 135.0 140.0 145.0 150.0
2.112 2.053 2.000 1.953 1.911 1.875 1.845 1.820 1.801 1.788 1.779 1.777
155.0 160.0 165.0 170.0 175.0 180.0
4.079 4.073 4.054 4.022 3.979 3.924 3.859 3.785 3.702 3.612 3.517 3.416 3.313 3.207 3.100 2.993 2.888 2.785 2.584 2.588 2.495 2.407 2.324 2.247 2.175 2.109 2.049 1.995 1.947 1.904 1.868 1.837 1.812 1.792 1.778 1.770 1.767
4.138 4.132 4.112 4.079 4.034 3.978 3.910 3.833 3.747 3.555 3.555 3.452 3.345 3.235 3.125 3.015 2.906 2.800 2.597 2.597 2.502 2.412 2.327 2.248 2.175 2.107 2.046 1.991 1.941 1.898 1.861 1.829 1.803 1.784 1.759 1.761 1.758
4.255 4.248 4.226 4.191 4.143 4.083 4.011 3.928 3.837 3.738 3.632 3.521 3.407 3.291 3.174 3.058 2.943 2.831 2.722 2.517 2.517 2.423 2.334 2.251 2.174 2.104 2.040 1.982 1.931 1.885 1.848 1.815 1.789 1.768 1.763 1.745 1.742
595
4.359 4.362 4.339 4.302 4.250 4.186 4.109 4.022 3.924 3.819 3.707 3.590 3.469 3.347 3.223 3.100 2.979 2.861 2.747 2.537 2.532 2.433 2.341 2.254 2.175 2.102 2.035 1.976 1.923 1.876 1.836 1.803 1.775 1.754 1.739 1.730 1.727
4.482 4.474 4.450 4.410 4.355 4.288 4.205 4.114 4.011 3.900 3.781 3.658 3.530 3.401 3.271 3.142 3.015 2.891 2.772 2.557 2.548 2.445 2.348 2.259 2.176 2.100 2.032 1.970 1.916 1.86 8 1.827 1.792 1.76 4 1.742 1.727 1.718 1.715
4.593 4.585 4.560 4.518 4.460 4.388 4.302 4.205 4.095 3.979 3.854 3.724 3.591 3.455 3.319 3.184 3.051 2.921 2.797 2.577 2.554 2.457 2.357 2.264 2.178 2.100 2.029 1.955 1.910 1.850 1.818 1.783 1.754 1.732 1.716 1.706 1.703
3.2
4.703 4.595 4.668 4.524 4.563 4.487 4.397 4.294 4.180 4.057 3.927 3.790 3.550 3.508 3.366 3.225 3.086 2.951 2.821 2.697 2.580 2.469 2.366 2.259 2.181 2.101 2.028 1.962 1.905 1.854 1.811 1.775 1.745 1.722 1.706 1.696 1.593
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
D(4n)3He. ENERGYIMEV)
1.600
0(6 lab), £„(0 lab): Recommended Values 1.700
1.800
1.900
2.000
2.100
CENTER-•OF-•MASS INPUT VALU6S, FOR THE REACTION l ) ( U , N ) H E 3 D-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 6
2 4 . 5 0 C1 0.342 O.OOCi 0 . 3 9 61 O.OOC 0 . 2 4 C1 O.OOC1 0 . 0 2 C1
24.000 0.351 0.000 0.404 0.000 0.22E1 0.000 0.017
)
25.20C 0.33«t O.OOC1 0.392 0.000 0.25) 0.000 0 . 0 2 31
2 6 . 4 0 C1 0.3181 O.OOC1 0.382 O.OOCi 0.270 O.OOC1 0.030
2 5 . 8 0 C1 0.326 O.OOC1 0.387 O.OOC1 0.260 O.OOC1 0.027
)
DIFFERENTIAL CRUSS-!;6CTIUN!i (MB/SR)
ANGLE(DEGREE) 0 . 3 7 9 6 02 0 . 3 7 0 6 02 0 . 3 4 3 E 02 0 . 3 0 4 E 02 0 . 2 5 7 6 02 0 . 2 1 0 6 02 0 . 1 6 7 6 02
55.0 70.0 75.0 80.0 85.0 90.0
0.54BE 0 1 0 . 6 5 5 6 01 0 . 5 6 6 6 01 0 . 5 7 3 E 01 0 . 5 8 1 E 01 0 . 5 8 8 E 0.530E 01 0 . 6 4 0 E 01 0 . 6 5 2 6 01 0.659E 01 0.558E 01 0.575E 0 . 5 0 8 E 01 0 . 6 1 8 6 0 1 0 . 5 2 9 6 0 1 0 . 5 3 5 E 01 0 . 6 4 3 E 01 0 . 5 4 9 E 0 . 5 8 0 6 0 1 0 . 5 8 7 6 01 0 . 5 9 5 6 0 1 0 . 6 0 0 E 01 0 . 6 0 5 E 01 0 . 5 0 9 E 0 . 5 4 8 6 0 1 0 . 5 5 2 6 01 0 . 5 5 7 E 01 0 . 5 5 9 6 01 0 . 5 6 1 E 01 0 . 5 6 2 6 0.517E 01 0.517E 01 0 . 5 1 8 E 01 0 . 5 1 7 6 01 0.515E 01 0 . 5 1 3 6
95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 ENERGY(MEV)
0.1316 0.1046 0.8566 0.7556 0.5976 0 . 6 6 66
02 02 01 01 01 01
0.1296 0.102E 0.8466 0.744E 0.593E 0.570E
02 02 01 01 01 01
02 02 02 02 02 02 02
)> ) )
IN THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0
0 . 3 9 2 E 02 0 . 4 0 5 E 02 0 . 4 1 9 6 0 . 3 8 2 E 02 0 . 3 9 5 6 02 0 . 4 0 7 6 0 . 3 5 3 E 02 0 . 3 6 4 E 02 0 . 3 7 4 6 0 . 3 1 1 6 02 0 . 3 1 8 E 0 2 0 . 3 2 5 6 0 . 2 5 1 E 02 0 . 2 5 5 E 02 0 . 2 6 8 6 0 . 2 1 1 6 02 0 . 2 1 2 6 0 2 0 . 2 1 2 6 0 . 1 6 5 6 02 0 . 1 5 4 E 02 0 . 1 5 3 6
28.000 0.298 0.000 0.367 0.000 0.294 0.000 0.041
2 7 . 5 0 C1 0.30A O.OOC 0.372 O.OOC 0 . 2 8 1f O.OOC 0.031
26.900 0.311 0.000 0.377 0.000 0.27'= 1 0.000 0 . 0 3 31
0 . 4 3 3 E 0 2 0 . 4 4 4 6 02 0 . 4 5 8 E 02 0 . 4 2 0 E 0 2 0 . 4 3 1 E 0 2 0 . 4 4 4 E 02 0 . 3 8 4 E 02 0 . 3 9 3 6 0 2 0 . 4 0 3 E 0 2 0 . 3 3 2 E 02 0 . 3 3 7 6 02 0 . 3 4 4 E 02 0 . 2 7 2 E 0 2 0 . 2 7 4 6 02 0 . 2 7 7 E 02 0 , 2 1 2 £ 02 0 . 2 1 2 E 02 0 . 2 1 2 6 02 0 . 1 6 1 6 0 2 0 . 1 5 9 6 02 0 . 1 5 7 6 0 2
0 . 1 2 5 E 02 0.124E 02 0.122E 0.9996 01 0.977E 01 0.951E 0 . 8 2 B 6 01 0.813E 01 0.793E 0 . 7 3 5 6 0 1 0 . 7 2 8 6 01 0 . 7 1 7 E 0.693E 01 0.592E 01 0.6906 0 . 5 7 6 E 0 1 0 . 5 8 0 E 01 0 . 6 8 4 E
02 01 01 01 01 01
0.470E 0.454E 0.4116 0.349E 0.2796 0.211E 0.1556
02 02 02 02 02 02 02
0 . 1 1 9 6 02 0 . 1 1 5 6 0 . 9 2 5 6 01 0 . 9 0 4 6 0 . 7 7 5 6 01 0 . 7 6 0 6 0.7O7E 01 0 . 7 0 2 E 0.6a8E 01 0 . 6 9 0 E 0 . 5 8 8 6 01 0 . 6 9 5 6
02 01 01 01 01 01
0.114E 0.8826 0.748E 0.697E 0.5926 0.7016
02 01 01 01 01 01
01 01 01 01 01 01
0.5966 0.6846 0.6556 0.5146 0.564E 0.512E
01 01 01 01 01 01
0.704E 0.5926 0.662E 0.618E 0.555E 0.511E
01 01 01 01 01 01
0.4926 0.4786 0.4796 0.4976 0.5336 0.5B56
01 01 01 01 01 01
0 . 4 8 8 6 01 0 . 4 8 5 E 01 0 . 4 8 2 6 01 0.477E 01 0 . 4 7 1 6 0 . 4 7 1 6 01 0 . 4 5 5 E 01 0 . 4 5 9 6 01 0 . 4 5 0 E 01 0 . 4 4 2 E 0 . 4 6 9 6 01 0 . 4 5 0 E 01 0.452E 01 0 . 4 4 1 E 01 0.431E 0.4B5E 01 0 . 4 7 5 6 01 0 . 4 6 5 E 01 0 . 4 5 3 E 01 0 . 4 4 1 E 0 . 5 2 0 E 01 0 . 5 0 9 6 01 0 . 4 9 9 E 01 0 . 4 8 7 6 01 0 . 4 7 4 E 0 . 5 7 2 6 01 0 . 5 5 2 6 01 0 . 5 5 2 E 01 0 . 5 4 0 6 01 0 . 5 2 9 E
01 01 01 01 01 01
0 . 4 6 7 6 01 0 . 4 5 3 E 0 . 4 3 5 6 01 0 . 4 2 9 E 0 . 4 2 2 6 01 0 . 4 1 4 E 0 . 4 3 2 6 01 0 . 4 2 2 E 0 . 4 6 4 6 01 0 . 4 5 4 6 0 . 5 1 9 6 01 0 . 5 0 9 6
01 01 01 01 01 01
0.6516 0.72BE 0.812E 0.8996 0.9856 0.1066
01 01 01 01 01 02
0 . 6 4 0 6 01 0 . 5 3 0 E 0 . 7 1 9 6 01 0 . 7 1 1 E 0.805E 01 0.800E 0.895E 01 0 . 8 9 2 E 0 . 9 8 4 E 01 0 . 9 8 4 E 0 . 1 0 6 6 02 0 . 1 0 7 E
0 . 5 2 1 6 01 0 . 5 1 2 6 01 0 . 5 0 1 E 0 . 7 0 4 6 01 0.596E 01 Q.688E 0 . 7 9 5 6 01 0 . 7 9 0 6 01 0 . 7 8 3 E 0 . 8 9 0 6 01 0 . 6 8 8 6 01 0.883E 0 . 9 8 4 6 01 0 . 9 8 4 6 01 0 . 9 a 2 E 0 . 1 0 7 6 02 0 . 1 0 7 E 02 0 . 1 0 7 6 0 . 1 1 5 6 02 0 . 1 1 5 6 02 0 . 1 1 5 E 0 . 1 2 2 E 02 0 . 1 2 3 6 0 2 0 . 1 2 3 E 0 . 1 2 8 6 02 0 . 1 2 9 6 02 0 . 1 2 9 E 0 . 1 3 2 6 02 0 . 1 3 3 E 02 0 . 1 3 3 E 0 . 1 3 4 6 02 0 . 1 3 5 E 02 0 . 1 3 5 E 0 . 1 3 5 E 02 0 . 1 3 5 6 02 0 . 1 3 7 E
01 01 01 01 01 02
0.5936 0.6816 0.7796 0.8816 0.9836 0.107E 0.115E 0.1246 0.1306 0.1346 0.137E 0.138E
01 01 01 01 01 02
0.5846 0.673E 0.773E 0.8786 0.981E 0.1086
01 01 01 01 01 02
02 02 02 02 02 02
0 . 1 1 6 E 02 0 . 1 2 4 6 02 0.130E 02 0 . 1 3 5 E 02 0 . 1 3 8 6 02 0 . 1 3 8 6 02
0 . 1 1 4 6 02 0 . 1 1 4 6 02 0 . 1 2 0 6 0 2 0 . 1 2 1 6 02 0 . 1 2 5 6 02 0.126E 02 0 . 1 2 9 6 02 0 . 1 3 0 E 02 0 . 1 3 1 6 02 0 . 1 3 2 E 02 0 . 1 3 2 E 0 2 0 . 1 3 3 6 02 2.400
2.500
01 01 01 01 01 02
0 . 1 1 5 E 02 0 . 1 2 1 E 02 0 . 1 2 7 E 02 0 . 1 3 1 6 02 0 . 1 3 3 6 02 0 . 1 3 4 6 02 2.600
2.700
2.800
02 02 02 02 02 02
2.900
3.000
3.500
CENTER-OF-MASS INPUT VALUES FOR THE REACTION U ( U , N I H E 3 D-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 5
28.400 0.293 0.000 0.362 0.000 0.301 0.000 0.044
28.900 0.287 0.000 0.357 0.000 0.308 0.000 0.048
ANGLE(DEGREE)
29.300 0.282 0.000 0.353 0.000 0.314 0.000 0.051
29.800 0.277 0.000 0.349 0.000 0.320 0.000 0.054
DIFFERENTIAL CROSS-SECTIONS
30.300 0.272 0.000 0.345 0.000 0.325 0.000 0.057 (MB/SR)
30.700 0.258 0.000 0.341 0.000 0.331 0.000 0.050
31.200 0.262 0.000 0.337 0.000 0.337 0.000 0.054
33.500 0.240 0.000 0.322 0.000 0.355 0.000 0.082
I N THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.480E 02 0 . 4 9 2 E 0 . 4 5 4 E 02 0 . 4 7 5 E 0.419E 02 0.427E 0 . 3 5 3 E 02 0 . 3 5 8 6 0 . 2 8 0 6 02 0 . 2 8 2 E 0 . 2 1 0 6 02 0 . 2 0 9 6 0.153E 02 0.150E
02 02 02 02 02 02 02
0 . 5 0 2 E 02 0 . 5 1 4 E 02 0 . 5 2 5 E 02 0 . 5 3 5 E 0 . 4 8 4 E 02 0 . 4 9 5 E 02 0 . 5 0 5 E 02 0 . 5 1 5 E 0 . 4 3 4 E 02 0 . 4 4 3 6 02 0 . 4 5 1 E 02 0.45BE 0 . 3 6 2 E 02 0 . 3 6 8 6 02 0 . 3 7 3 E 02 0 . 3 7 7 6 0 . 2 8 3 6 02 0 . 2 8 5 6 02 0 . 2 8 5 E 02 0 . 2 8 7 6 0 . 2 0 8 6 02 0 . 2 0 7 E 02 0 . 2 0 7 E 02 0 . 2 0 5 F 0 . 1 4 8 6 0 2 0 . 1 4 5 6 02 0 . 1 4 3 6 02 0 . 1 4 1 E
35.0 40.0 45.0 50.0 65.0 60.0
O.lllE 0.861E 0.7346 0.6936 0.5956 0.708E
0.108E 0.837E 0.7206 0.688E 0.6976 0.714E
02 01 01 01 01 01
0 . 1 0 5 E 02 0 . 1 0 3 E 0 . 8 1 5 6 01 ~ 0.707E 01 0 . 5 8 4 6 01 0 . 5 9 9 6 01 0.719E 01
55.0 70.0 75.0 80.0 85.0 90.0
0.713E 01 0.720E 0.700E 01 0.707E 0.669E 01 0.6746 0 . 6 2 3 6 01 0.625E 0.557E 01 0.5586 0.510E 01 0.508E
01 01 01 01 01 01
0.727E 0.7136 0.679E 0.528E 0.5676 0.505E
, . . . . „ _ _. _. .. .. 0 . 7 2 1 6 01 0 . 7 2 8 6 01 0 . 7 3 6 E 01 0 . 7 3 8 E 0 . 5 8 5 6 01 0 . 6 9 1 6 0 1 0 . 6 9 5 6 01 0 . 5 9 7 E 0 . 5 3 1 6 01 0 . 6 3 5 E 01 0 . 5 3 8 E 01 0 . 5 3 7 E 0 . 5 6 8 6 01 0 . 5 6 9 6 01 0 . 5 7 0 E 01 0 . 5 5 7 E 0.503E 01 0.501E 01 0 . 4 9 9 6 01 0 . 4 9 4 E
01 01 01 01 01
__ 0.747E 0.699E 0.533E 0.555E 0.475E
_. 01 01 01 01 01
95.0 100.0 105.0 110.0 115.0 120.0
0 . 4 5 9 6 01 0 . 4 5 4 6 0.423E 01 0.415E 0 . 4 0 5 E 01 0 . 3 9 5 E 0.4126 01 0.4026 0.444E 01 0.433E 0.499E 01 0.488E
01 01 01 01 01 01
0 . 4 4 9 6 01 0.445E 01 0.440E 01 0.436E 01 0 . 4 2 8 6 0 . 4 0 8 E 0 1 0 . 4 0 1 E 01 0 . 3 9 4 E 01 0 . 3 8 8 6 01 0 . 3 7 7 6 0 . 3 8 7 6 0 1 0 . 3 7 9 6 01 0 . 3 7 0 6 01 0 . 3 5 2 6 01 0 . 3 5 1 6 0 . 3 9 2 6 0 1 0 . 3 8 3 E 01 0 . 3 7 3 6 01 0 . 3 5 4 6 01 0 . 3 5 2 6 0 . 4 2 3 E 01 0 . 4 1 3 6 01 0 . 4 0 4 6 01 0.395E 01 0.3B3E 0 . 4 7 9 E 01 0 . 4 7 0 E 01 0 . 4 5 2 6 01 0 . 4 5 4 E 01 0 . 4 4 2 E
01 01 01 01 01 01
0.4016 0.342E 0.3096 0.3076 0.339E 0.402E
01 01 01 01 01 01
125.0 130.0 135.'0 140.0 145.0 150.0
0.575E 01 0.555E 0.556E 01 0.558E 0 . 7 5 7 E 01 0 . 7 6 1 E 0.873E 01 0 . 8 6 9 E 0.9786 01 0.9766 0 . 1 0 7 6 02 0 . 1 0 7 6
01 01 01 01 01 02
0 . 5 5 5 6 0 1 0 . 5 4 9 6 01 0 . 5 4 2 6 01 0 . 5 3 5 E 0 . 5 5 1 6 01 0 . 5 4 5 6 01 0 . 5 4 0 6 01 0 . 5 3 5 6 0 . 7 5 5 6 0 1 0 . 7 5 2 6 01 0 . 7 4 9 E 01 0 . 7 4 5 6 0 . 8 5 5 E 0 1 0 . 8 6 4 6 01 0 . 8 6 3 6 01 0 . 8 5 0 6 0 . 9 7 4 6 0 1 0 . 9 7 5 6 01 0 . 9 7 5 E 01 0 . 9 7 4 E 0 . 1 0 7 E 0 2 0 . 1 0 7 6 02 0 . 1 0 8 6 02 0 . 1 0 8 6
0.525E 0.625E 0.7396 0.8576 0.9736 0.1086
01 01 01 01 01 02
0.491E 0.501E 0.723E 0.8506 0.974E 0.109E
01 01 01 01 01 02
155.0 160.0 155.0 170.0 175.0 180.0
0.1166 0.1246 0.130E 0.135E 0.138E 0 . 1 39E
02 02 02 02 02 02
0,1176 0.1246 0.1316 0.136E 0.1386 0.1396
0 . 1 1 7 E 0 2 0 . 1 1 7 6 02 0 . 1 1 8 6 0 . 1 2 5 6 02 0 . 1 2 5 6 02 0 . 1 2 6 6 0 . 1 3 2 6 02 0 . 1 3 2 6 02 0 . 1 3 3 E 0 . 1 3 7 E 0 2 0 . 1 3 7 6 02 0 . 1 3 8 6 0 . 1 4 0 E 02 0 . 1 4 0 6 02 0 . 1 4 1 6 0 . 1 4 1 E 02 0 . 1 4 1 6 02 0 . 1 4 2 6
02 02 02 02 02 02
0.1196 0.128E 0.135E 0.140E 0.143E 0.145E
02 02 02 02 02 02
NuclMr Data Tables, VoL 11, No. 7, 1973
02 01 01 01 01 01
02 02 02 02 02 02
0.117E 0.124E 0.13IE 0.1356 0.1386 0.139E
01 01 01 01 01 01
02 02 02 02 02 02
0 .. 1 1 7 6 0 ,, 1 2 5 6 0.. 1 3 1 6 0 ., 1 3 5 6 0 ,. 1 3 9 6 0 .. 1 4 0 6
596
02 02 02 02 02 02 02
0 . 5 4 8 E 02 0 . 5 0 4 E 0 . 5 2 6 E 02 0 . 5 7 7 E 0 . 4 6 5 E 02 0 . 5 0 4 E 0 . 3 8 1 E 02 0.401E 0 . 2 8 8 E 02 0 . 2 9 2 E 0 . 2 0 3 E 02 0 . 1 9 5 E 0 . 1 3 8 E 02 0 . 1 2 5 E
02 02 02 02 02 02 02
02 "•
02 02 02 02 02 02
01 01 01 01 01 02
NEUTRON PRODUCTION CROSS SECTIONS
a(e lab), E„(e lab): Recommended Values
D(d,n)^He. ENERGY(MEVI
1.600
1.700
1.800
1.900
2.000
2.100
2.200
2.300
INPUT VALUES FOR THE REACTUIN D I 0 , N ) H E 3 REST ENERGY I N MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS
ANGLE(OeGREE)
ENERGY OF PARTICLE-3
Tl=ie75.633 T2=1875.633 T3= 9 3 9 . 5 7 6 T't=2808.421
IMEVI
Q-VALUE
3.269
I N THE LABORATORY SYSTEM 5.449 5.437 5.401 5.342 5.261 5.159 5.038 4.901 4.750 4.587 4.415 4.236 4.053
5.553 5.540 5.503 5.442 5.358 5.252 5.128 4.986 4,829 4.651 4.483 4.298 4.109
3.859 3.68 5 3.504 3.328 3.158 2.995 2.841 2.696 2.561 2.435 2.320 2.214
3'Si2
3 . 7 30 3.544 3.362 3.188 3.020 2.862 2.713 2.574 2,446 2.328 2.220
1.743 1.710 1.684 1.566 1.656 1.652
2.119 2.033 1.957 1.890 1.831 1.782 1.740 1.706 1.581 1.652 1.651 1.648
2,123 2.036 1.958 1,890 1.830 1,780 1,738 1.704 1,677 1,559 1,647 1 ,544
2.900
3.000
3.500
0.0 5.0 10.0 15.0 20.0 25.0 30.0
4.813 4.803 4.775 4.729 4.665 4.586 4.491
4.921 4.911 4.681 4.833 4.766 4.683 4.584
5.028 5.017 4.987 4.936 4.867 4.779 4.676
5.134 5.123 5.091 5.039 4.966 4.875 4.768
5.240 5.228 5.195 5.140 5.065 4.970 4.858
5.346 5.333 5.298 5.241 5.163 5.056 4.949
35.0 'tO.O 45.0 50.0 55.0 60,0
4.383 4.264 4.134 3,998 3.855 3.709
4.471 4.346 4.211 4.068 3.920 3.767
4.558 4.428 4.287 4.139 3,984 3,825
4.645 4.509 4.363 4,208 4.047 3.883
4.731 4.590 4.438 4.278 4.111 3.940
4.816 4.670 4.513 4.346 4.173 3.99 7
65.0 70.0 75.0 80.0 85.0 90.0
3.560 3.412 3.265 3.121 2.981 2.846
3.613 3.458 3.305 3.156 3.010 2.871
3.665 3.504 3.346 3.190 3,040 2,896
3.716 3.550 3.386 3.225 3.070 2.921
3.767 3.595 3.425 3.260 3.099 2.946
3.818 3.540 3.46 5 3.294 3.129 2.971
95.0 100.0 105.0 110.0 115.0 120.0
2.717 2.595 2.481 2.374 2.275 2.184
2.738 2.612 2.493 2.383 2.282 2.188
2,758 2,628 2,506 2,393 2,288 2.193
2.779 2.645 2.520 2.403 2.296 2.197
2.800 2.662 2.533 2.414 2.303 2.203
2.820 2.679 2.547 2.424 2.311 2.208
125.0 130.0 135.0 140.0 145.0 150.0
2.101 2,027 1,960 1,900 1,849 1,804
2.103 2.026 1.958 1.897 1.844 1.799
2.105 2,027 1.956 1,894 1,840 1.794
2.108 2.028 1.956 1.892 1.637 1.790
2.111 2.029 1.956 1.891 1.835 1.787
2.115 2.031 1.956 1.890 1.833 1.784
155.0 160.0 165.0 170.0 175.0 180.0
1,767 1,737 1,714 1.697 1.687 1.684
1.761 1.730 1.706 1.689 1.679 1.676
1,755 1,724 1,700 1,683 1.672 1.669
1.751 1.719 1.694 1.676 1.666 1.663
1.747 1.714 1.689 1.671 1.660 1.657
2.400
2.500
2.600
2.700
2.800
ENERGY(MEV)
IN «FV 0=
INPUT VALUES FOR THE REACTION D(D,N)HE3 REST ENERGY I N MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0
i9«o
55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0
lop.o
105.0 110.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
71=1875.633 T2=1875.633 T3= 9 3 9 . 5 7 6 74=2808.421
ENERGY OF PARTICLE-3 (MEV) 5.556 5.643 5,605 5,541 5.454 5.345 5,216 5.069 4.907 4.733 4,549 4,359 4.164
5.759 5.746 5.706 5,640 5.550 5.438 5.304
3.968 3.773 3.582 3.395 3.216 3.044
4,018 3.818 3,621 3,429 3,245 3,069
2,882 2,730 2.588 2.457 2.336 2.226 2.127 2.038 1.959 1.890 1.830 1.778 1.736 1.701 1.674 1.655 1.644 1.640
0-VALUE
IN MEV 0=
3.269
I N THE LABORATORY SYSTEM
5.861 5.848 5.806 5.739 5.646 5.530 5.392 5.236 5.064 4.879 4.683 4.481 4.275
5.953 5.949 5.907 5 . 8 37 5.741 5,622 5.480
6.065 6.050 6.007 5.935 5.836 5.713 5.567
6.166 6.151 5.106 6.032 5.931 5.804 5.654
6.267 6.252 6.206 5.130 6.025 5.895 5.741
5.758 6.750 6.598 5.512 5,493 6.345 6.171
5.319 5.142 4.951 4.750 4.542 4.330
5.402 5.219 5.023 4.817 4.503 4.385
5.484 5.295 5.095 4.883 4.663 4.440
5.566 5.373 5.166 4.949 4.724 4.495
5.972 5.755 5.521 5,275 5,022 4.765
4.U7 3.906 3.698 3.497 3.303 3.119
4.167 3.950 3.737 3.531 3.333 3.144
4.216 3.993 3.776 3.554 3.362 3.169
4.265 4.037 3.814 3.598 3.391 3.194
4.508 4.253 4.005 3.755 3.536 3.319
2,903 2,747 2,602 2.468 2.345 2.233
4.068 3.862 3.660 3.463 3.274 3.094 2.924 2.765 2,616 2.480 2.354 2.240
2.945 2.782 2.631 2.491 2.363 2.247
2.966 2.800 2.645 2.503 2.373 2.255
2.987 2.818 2.650 2.515 2.383 2.262
3.009 2.835 2.675 2.527 2.392 2.270
3.115 2.925 2.750 2.590 2.444 2.312
2.132 2.042 1.961 1.891 1.830 1.777
2.137 2.045 1.964 1.892 1.830 1.777
2.143 2.049 1.966 1.893 1.830 1.777
2.148 2.053 1.959 1.895 1.831 1.777
2.154 2.058 1.972 1.897 1.833 1.777
2.160 2.062 1.975 1.900 1.834 1.778
2.194 2.088 1.996 1.915 1.845 1.786
1.734 1.699 1.672 1 .653 1.541 1.638
1.733 1.697 1.570 1.651 1.639 1.635
1.732 1.596 1.668 1.549 1.637 1.633
1.732 1.695 1.667 1.547 1.535 1.632
1.732 1.695 1.655 1.646 1.634 1.63 0
1.732 1.694 1.566 1.645 1.533 1.629
1.737 1.697 1.667 1.646 1.533 1.629
5,153 4,986 4.806 4.617 4.420 4.220
597
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
D(4n)^He.
0(6 lab), £„(6l lab): Recommended Values 5.500
4.600
ENERGY(MEV)
6.500
CENTER-OF-MASS INPUT VALUES FOR THE REACTIUN U ( U , N I H E 3 U-SIGMA-0(MB/SR) A 0 A I A 2 A 3 A 4 A 5 A 6 A 7 A 8 A 9 AlO
37.800 0.206 0.000 0.295 0.000 0.372 0.000 0.112 0.000 0.012 0.000 0.003
35.700 0.221 0.000 0.308 0.000 0.367 0.000 0.098 0.000 0.004 0.000 0.002
65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155, 160, '65, .70, 175, ENERGY IMEV)
0.658E 0.625E 0.537E 0.416E 0.292E 0.186E 0.113E 0.722E 0.574E 0.585E 0.661E 0.734E 0.775E 0.777E 0.748E 0.6966 0.625E 0.542E 0.454E 0.372E 0.308E 0.272E 0.270E 0.303E 0.370E 0.464E 0.5796 0.707E 0.840E 0.970E 0.109E 0.120E 0.129E 0.137E 0.143E 0.1466 0.1476
02 02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02 02
0.7106 0.6716 0.567E 0.4276 0.289E 0.177E 0.102E 0.6476 0.533E 0.571E 0.662E 0.744E 0.7876 0.788E 0.7556 0.6966 0.6176 0.5276 0.4336
7646 7186 596E 4376 285E 167E 933t 580E 497E 558E 662E 01 0 749E 01 0, 7926
01 01 01 -• 01 01 01
0.348E 0.283E 0.2476 0.245E 0.279E 0.347E
0.4436 0.5606 0.6926 0.829E 0.965E 0.1096 0.1216 0.1316 0.1396 0.1456 0.1486 0.150E
02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01
0.805E 0.7536 0.616E 0.441fc 0.2776 0.156E 0.844E 0.530E 0.478 6 0.557E 0.668E 0.7556 0.7956 0.7896 0.7476 0.6796 0.592E 0.4946 0.3956
0.7906 0.7536 0.6896 0.605E 0.510E 0.4126 0.324E 307E 0.2596 2426 0.2236 207E 0.223E 01 0, 206E 0.2586 01 0, 240E 0.327E 308E
0.843E 0.785E 0.633E 0.443E 0.270E 0.146E 0.770E
01 01 01 01 Ql 01 01 01 01 01 01 01 01 01 01 01 01 01
0.4906 0.4686 0.565E 0.683E 0.767E 0.7996 0.7866 0.741E 0.672E 0.584E 0.4856 0.3856 0. 2966 0 . 2296 0. 193E 0. 192E 0. 2256 0 . 293E
01 01 01 01 01 02
0. 390E 0. 511E 0 . 648 6 0. 7956 0 . 943E 0. 108E 0 121E 0 132E 0 141E 0 148E 0 152E 0 1546
4056 5256 6626 80 6E 952E 109E 121E 1326 1416 148 E 1526 1536
01 0.425E 0.544E 0.679E 0.8216 0.9636 02 0.1096 0 0.1226 0 0.1326 0 0.1416 0 0.147E 0 0.1516 0 0.1536
02 02 02 02 02 02
IN THE LAB(JRATURY SYSTEM
02 02 02 02 02 02 01" 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01
0.871E 0.808E 0.6446 0.4416 0.261E 0.137E 0.705E 0.466E 0.4736 0.5826 0.698E 0.774E 0.7966 0.777E 0.728E 0.660E 0.5746 0.477E 0.378E 0, 290E 0. 2236 0, 186E 0. 182E 0, 213E 0. 278E 374E .4936 631E ,778E .927E ,107E
02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 -_ 01 01 01 01 01 01 01 01 01
,1206 1316 ,1406 1476 ,1516 1526
02 02 02 02 02 02
01
01 01 01 01 02
0.897E 0.828E 0.6536 0.4386 0.2526 0.1286 0.653E 0.4546 0.4866 0.6016 0.7136 0.7786 0.7926 0.7666 0.716E 0.648E 0.5656 0.4716 0.374E 0.2876 0.2206 0.1816 0.1756 0.2046 0.266E 0.359E 0.478E 0.6166 0.763E 0.913E 0.105E 0.1186 0.130E 0.1396 0.1466 0.150E 0.1516
02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02
0.,9186 0.,8456 0,,6596 ,4346 243E 1206 6106 4486 ,5016 ,6226 ,7286 ,7826 ,7856 0,.753E 0,.7026 0,.5376 0 .5576 0 .466E 0 .3726 0 .2866 0 .2186 0 .1786 0 .1596 0 .1956 0 .2556 0 .3476 0 .4556 .6026 .749 6 0 .8996 .1046 0 .1176 .1286 .1376 .1446 .1486 ,1506
9.500
8.500
8.000
02 02 02 02 02 02 01
45.200 0.159 0.000 0.244 0.000 0.362 0.000 0.178 0.000 0.046 0.000 0.011
4 4 . 6 00 0.163 0.000 0.250 0.000 0.366 0.000 0.169 0.000 0.042 0.000 0.010
43.800 0.168 0.000 0.257 0.000 0.370 0.000 0.159 0.000 0.037 0.000 0.009
0.174 0.000 0.265 0.000 0.373 0.000 0.148 0.000 0.032 0.000 0.008
0.182 0.000 0.274 0.000 0.374 0.000 0.137 0.000 0.027 0.000 0.006
DIFFERENTIAL CRUSS-SECT IONS (MB/SR)
ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0
0.192 0.000 0.284 0.000 0.374 0.000 0.125 0.000 0.020 0.000 0.005
CENTER-OF-MASS INPUT VALUES FOR THE REACTION 0 ( U , N ) H 6 3 0-SlGMA-0(MB/SR) A 0 A 3 A 4 A 5 A 6 A 7 A 8 A 9 AlO
4 6 . 100 0 . 153 0 . 000 0 . 234 0 000 0 . 354 0 . 000 0 . 195 0 000 0 052 000 0 012 0
45.700 0.156 0,000 0.239 0.000 0.358 0.000 0.187 0.000 0.049 0.000 0.011
DIFFERENTIAL CROSS-SECTIONS
ANGLE(DEGREE)
0.937E 0.860E 0.665E 0.431E 0.235E 0.113E 0.574E
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0
0.741E 0.689E 0.627E 0.552E 0.465E 0.374E
95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155, 160, 165, 170. 175, 180.
0.2886 0.2206 0.1776 0.1656 0.1876 0.2456 0.3366 0.4546 0.5916 0.738E 0.888E 0.1036 0.1156 0.1276 0.135E 0.1436 0.147E 0.1486
Nuclear Data Tables, Vol, 11, No. 7, 1973
46.500 0.148 0.000 0.227 0.000 0.346 0.000 0.209 0.000 0.056 0.000 0.014
46.400 0.150 0.000 0.230 0.000 0.350 0.000 0.202 0.000 0.055 0.000 0.013
02 02 02 02 02 02 01
0.450E 0.525E 0.649E 0.745E 0.7B5E 0 . 7 7 7 E 01
01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02 02
0.9536 0.8726 0.6686 0.4266 0.2276 0.1066 0.5416 0.451E 0.544E 0.6716 0.7586 0.7866 0.7686 0.7266 0.6756 0.617E 0.547E 0.464E 0.374E 0.2896 0.2196 0.1746 0.1596 0.1806 0.2366 0.3256 0.4426 0.578E 0.7266 0.8756 O.IOIE 114E 125E 1346 1416 1456
,9666 02 ,6826 02 ,6706 02 ,4216 02 " • 219E 02 .9966 01 .5136 01 ,4526 01 .5596 01 ,6866 01 " ,76^6 01 ,7816 01 ,7536 01 ,7076 01 ,6586 01 .6056 01 .5396 01 .4606 0 1 .37 26 01
0.975E 0.888E 0.670E 0.4166 0.2126 0.9436 0.4916 0.4566 0.5796 0.7076 0.7766 0.7776 0,7366 0.685E 0.6396 0,593E 0.535E 0.460E 0.3746
.2886 .217E .1706 01 ,1546 .1726 .2276 .3156 .4316 .5576 ,7136 .8616 01 .1006 02 ,1136 02 .124E 02 .1336 02 .1396 02 .1436 02 . 144E 02
0.1686 0.1496 0.1666 0.2196 0.3076 0.4226 0.5576 0.7026 0.8496 0.9896 0.1116 0.122E 0.1316 0.1376 0.1416 0.1426
§:i?li
598
46.500 0.147 0.000 0.224 0.000 0.342 0.000 0.215 0.000 0.058 0.000 0.014 (MB/SR)
02 02 02 02 02 01 01 01 01 01 01 01 01
IN THE LABORATORY SYSTEM
01 01 01 01 01 01 01 01 01 01 01 01
0,,9826 0. 8936 0,.6696 0, 4106 0,.2056 0.,8996 0.,4796 .4726 ,606E .730E 785E .7756 7255 6726 .5286 5866 .5336 4626 3786
02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01 01 01
0,,2946 0. 2206 0,,1696 0 . 1486 0,,1626 0. 2146
01 01 01 01 01 01 02 02 02 02 02 02
0. 3006 0,.4156 0. 5496 - .6926 0 ,8376 0 ,9756 0,.1096 0. 1206 0.,1296 0. 1356 0.,139E 0. 1406
01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02
02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02 02
NEUTRON PRODUCTION CROSS SECTIONS
D(d,nfne. ENERGY(MEV)
4.000
a{fi lab), EJfi lab): Recommended Values 4.500
5.000
5.500
6.000
6.500
7.000
7.500
INPUT VALUES FUR THE REACTION D(D,N1HE3 REST ENERGY IN MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET T 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS T 4 = 2 8 0 8 . 4 2 1
ANGLE(DEGREE)
ENERGY OF PARTICLE-3
0.0 5.0 10.0 15.0 20.0 25.0 30.0
7.263 7.243 7.184 7.088 6.955 6.789 6.593
35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0
6.372 6.128 5.868 5.595 5.313 5.028
95.0 100.0 105.0 110.0 115.0 120.0
3.218 3.013 2.824 2.652 2.495 2,355
125.0 130.0 135.0 140.0 145.0 150.0
2.229 2.117 2.019 1.934 1.860 1.798 1.747 1.705 1.674 1.651 1.638 1.633
155.0 160.0 165.0 170.0 175.0 IBO.O
ENERGY(MEVI
4.744 4.463 4.190 3.927 3.676 3.440
8.000
9.690 9.660 9.570 9.422 9.220 8.968 8.671
3.541 3.290 3.062 2.854 2.668 2.501
9.209 9.181 9.097 8.960 8.771 8.536 8.260 7.947 7.605 7.241 6.860 6.470 6.076 5.686 5.304 4.935 4.582 4.249 3.938 3.649 3.384 3.142 2.924 2.728 2.553
2.354 2.223 2.110 2.011 1.927 1.856 1.798 1.751 1.716 1.690 1.675 1.670
2.398 2.262 2.144 2.041 1.954 1.880 1.820 1.771 1.734 1.708 1.693 1.688
8.241 8.217 8.146 8.029 7.868 7.668 7.431 7.164 6.871 6.558 6.231 5.895 5.556
8.726 8.700 8.62 3 8.495 8.321 8.103 7.847 7.557 7 . 2 39 6.900 6.546 6.183 5.817
4.981 4.675 4.378 4.092 3.820 3.564 3.326 3.105 2.902 2.718 2.561 2.402 2.268 2.150 2.047 1.957 1.880 1.816
6.218 4.886 4.564 4.256 3.963 3.689
5.452 5.095 4.750 4.419 4.106 3.813
3.433 3.197 2.982 2.786 2.609 2.451 2.310 2.186 2.077 1.983 1.902 1.834
1.761 1.718 1.686 1.661 1.647 1.643
1.778 1.733 1.699 1.674 1.660 1.655
9.000
9.500
REST ENERGY IN MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET 7 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS 7 4 = 2 8 0 8 . 4 2 1 ENERGY OF PARTICLE-3
(MEV)
11.125 11.088 10.980 10.802 10.658 10.254 9.897 9.494 9.054 8.586 8.099 7.602 7.103
11.601 11.563 11.448 11.259 11.002 10.681 10.304 9.879 9.415 8.921 8.408 7.884 7.358
12.077 12.036 11.915 11.717 11.445 11.107 10.710
12.551 12.509 12.382 12.173 11.888 11.533 11.116
10.263 9.775 9.256 8,716 8.165 7.614
10.646 10.134 9.589 9.023 8.446 7.868
6.609 6.129 5.667 5.228 4,816 4.433
7.069 6.540 6.032 5.661 5.100 4.682
7.299 6.745 6.214 5.712 5.241 4.806
95.0 100.0 105.0 110.0 115.0 120.0
4.080 3.759 3.468 3.207 2.975 2.769
6.840 6.334 5.849 5.389 4.958 4.567 4.189 3.864 3.651 3,280 3.038 2.825
4.298 3.949 3.634 3,353 3,102 2,881
4.407 4.044 3.718 3.426 3.166 2.938
13.026 12.981 12.847 12.629 12.33 0 11.958 11.521 11.029 10.492 9.922 9.330 8.727 8.123 7.528 6.950 6.396 5.873 5.383 4.931 4.516 4.140 3.801 3.499 3.231 2.995
125.0 130.0 135.0 140.0 145.0 150.0 165.0 160.0 165.0 170.0 175.0 180.0
2.587 2.429 2.292 2.174 2.074 1.990
2.637 2.473 2.331 2.210 2.106 2.020 1.949 1.89 3 1.860 1.819 1.801 1.795
2,687 2,518 2,371 2,246 2,140 2,051
2.737 2.563 2.412 2.283 2.174 2.082
2.788 2.608 2.453 2.320 2.208 2.114
1,978 1,920 1,876 1,845 1,826 1.820
2.007 1.948 1.902 1.870 1.851 1.845
2.037 1.976 1.930 1.897 1.877 1.871
599
8.336 7.970 7.579 7.172 6.755 6.336
10.169 10.137 10.041 9.883 9.667 9.398 9.081 8.724 8.333 7.917 7.483 7.039 6.593
5.919 5.512 5.119 4.746 4.392 4.062
6.151 5.719 5.303 4.907 4.534 4.187
10.648 1Q.613 10.5U 10.343 10.113 9.827 9.490 9.111 8.696 8 . 2 54 7.793 7.323 6.850 6.382 5.926 5.487 5.069 4.677 4.3U
3.757 3.47 8 3.224 2.994 2.789 2.606
3.866 3.572 3.306 3.066 2.851 2.660
3.974 3.667 3.388 3.137 2.913 2.715
2.446 2.303 2.179 2.073 1.982 1.906
2.492 2.344 2.216 2.106 2.012 1.933 1.868 1.816 1.777 1.749 1.733 1.727
2.540 2.387 2.254 2.140 2.043 1.961 1.8 94 1.841 1.800 1 .772 1.754 1.749
1.843 1.793 1.756 1.726 1.712 1.707
0(0,N>He3 Q-VALUE
IN MEV g=
IN THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0
1.921 1.866 1.824 1.795 1.777 1.772
3.269
10.000
INPUT VALUES FUR THE REACTION
ANGLE(DEGREE)
IN MEV 0=
(MEV I IN THE LABORATORY SYSTEM
7.7^4 7.732 7.667 7.560 7.413 7.230 7.014 6.769 6.501 6.214 5.914 5.605 5.293
8.500
O-VALUE
Nucleor Data Tables, VoL 1 1, No. 7, 1973
NEUTRON PRODUCTION CROSS SECTIONS
T(d,n)me a(0° cm.), Legendre Coefficients (cm.), a(total) Recommended and Experimental Values aie lab), E„(e lab) Recommended Values
6 0 1
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(d',n)*He.
a(0° cm.), Legendre Coefficients, a(totaI) Recommended and Experimental Values SIGMA-0 AO, Al, . . . SIGMA-T
a(0° cm.) Legendre coefficients o(total)
Recommended Data ENERGY (MEV)
SIGMA-0 (MB/SR)
AO
Al
A2
A4
A3
A5
A6
A7
A8
SIGMA-T (MB)
0.020 0.030 0.040 0.050
4.3 19.6 52.9 106.0
1.000 1.000 1.000 1.000
54. 246. 665. 1332.
0.060 0.070 0.080 0.090 0.100
175. 250. 315. 367. 3 94. 317. 199. 133. 95.2 77.5 63.5 53.0 45.5
1.000 1.000 1.000 1.000 1.000 l.QOO 1.000 1.000 1.000 1.000 0.999 0.998 0.997
2199. 3142. 3958. 4612. 4951.
0.550 0.600 0.650 0.700 0.750 0.800 0.8
39.4 35.5 31.9 29.4 27.0 25.0 23.4 22.0
1.100 1.200 1.300 1.400 1.500 1.600 1.700 1.800 1.900 2.000
17.9 16.7 16.8 15.0 14.3 13.8 13.3 12.9 12.6 12.3
2.100 2.200 2.300 2.400 2.500 2.600 2.700 2.800 2.900 3.000 3.500 4.000 4.500 5.000 5.500 6.000 6.500 7.000 7.500 8.000 8.500 9.000 9.500 10.000
0.150 0.200 0.250 0.300 0.350 0.400 0.450 0.500
0.004 0.013 0.021
-0.003 -O.OU -0.018
3984. 2501. 1671. 1196. 974. 797. 665. 570.
0.030 0.038 0.046 0.053 0.060 0.067 0.072 0.077 0.082 0.087
-0.025 -0.031 -0.035 -0.039 -0.043 -0.045 -0.045 -0.045 -0.045 -0.044
493. 443. 396. 364. 334. 307. 286. 268. 252. 238.
0.094 0.100 0.105 0.110 0.113 0.116 0.120 0.122 0.124 0.127
-0.040 -0.03? -0.023 -0.013 0.002 0.016 0.029 0.042 0.054 0.067
12.1 11.9 11.8 11.8 11.8 11.9 12.0 12.1 12.2 12.3
0.995 0.993 0.989 0.986 0.983 0.978 0.973 0.968 0.963 0.957 0.946 0.931 0.915 0.898 0.878 0.85 8 0.835 0.814 0.793 0.771 0.749 0.730 0.707 0.688 0.666 0.646 0.627 0.608 0.589 0.571
0 . 129 0.13C 0.132 0.132 0.133 0.133 0.132 0.131 0.130 0.130
13.8 15.2 17.0 18.2 18.7 18.9 18.7 18.0 17.4 16.9 16.4 16.0 15.8 15.7
0.490 0.426 0.384 0.359 0.343 0.328 0.314 0.302 0.291 0.280 0.271 0.263 0.254 0.246
0.126 0.123 0.119 0.115 0.111 0.107 0.101 0.094 0.087 0.080 0.072 0.065 0.057 0.048
IV.I
Nuclear Dota Tables, Vol. 1 1 , No. 7, 1973
0.080 0.091 0.104 0.115 0.127 0.137 0.148 0.159 0.169 0.180
0 ,, 0 0 0 0.000 0 ,, 0 0 0 0 ., 0 0 0 0.000 0 ,, 0 0 1 0, . 0 0 2 0, , 0 0 4 0, . 0 0 5 0, . 0 0 7 0, , 0 0 9 0.. 0 1 2 0 ., 0 1 5 0 ,, 0 1 9 0, , 0 2 3 0, , 0 2 7 0 ,, 0 3 1 0 ., 0 3 4 0, , 0 3 7
0, , 0 0 1 0, , 0 0 3 0 ,. 0 0 4 0.005 0 .• 0 0 7 0 ,, 0 0 8 0,. 0 0 9 0, , 0 1 1 0,. 0 1 2 0 .013 0,, 0 1 4 0 .016 0, , 0 1 7 0,. 0 1 8 0, , 0 2 0 0.. 0 2 1 0, , 0 2 2 0,. 0 2 4 0, , 0 2 5
0 ,, 0 0 0 0 ,, 0 0 0 0, , 0 0 1 0 ,, 0 0 4 0,. 0 0 7 0, , 0 1 0 0, . 0 1 3 0,. 0 1 6 0, , 0 1 9 0 .022 0 ., 0 2 5 0, , 0 2 8 0 ,, 0 3 1 0,. 0 3 4 0, , 0 3 7 0,. 0 4 0 0, , 0 4 2
0 ,. 0 0 1 0 ,, 0 0 2 0 ,, 0 0 2 0 ,, 0 0 3 0, , 0 0 4 0 ,. 0 0 4 0, , 0 0 5 0, . 0 0 6 0 ,. 0 0 7 0.. 0 0 7 0 ,, 0 0 8 0, , 0 0 9 0 ,, 0 1 0 0,. 0 1 1 0, . 0 1 2 0, , 0 1 4 0, . 0 1 5
0.223 0.256 0.268 0.264 0.248 0.231 0.214 0.202 0.192 0.184 0.17fi 0.173 0.170 0.167
0, , 0 5 1 0, , 0 5 8 0 ., 0 6 2 0, , 0 6 4 0, , 0 6 3 0, . 0 5 9 0 ., 0 5 0 0, . 0 3 9 0, , 0 2 6 0,. 0 1 3 0.001 - 0 ,.010 - 0 .,019 - 0 ,.027
0,, 0 3 1 0,. 0 3 7 0, , 0 4 3 0,. 0 5 1 0, , 0 6 0 0 .073 0 ,, 0 8 9 0,. 1 0 2 0, , 1 1 4 0 .124 0 ., 1 3 2 0 .138 0 ,, 1 4 2 0,. 1 4 3
0, , 0 5 7 0,. 0 7 1 0 ,, 0 8 7 0,. 1 0 3 0 ., 1 2 0 0,. 1 3 4 0 ,, 1 4 9 0, . 1 6 2 0 ,, 1 7 3 0,. 1 8 3 0 ,, 1 9 0 0,, 1 9 4 0 ,. 1 9 7 0, , 1 9 8
0, . 0 2 2 0, , 0 2 9 0 ., 0 3 7 0, , 0 4 4 0 ,, 0 5 2 0., 0 6 1 0 ., 0 7 1 0 ., 0 8 0 0 ,, 0 9 0 0,. 1 0 1 0 ,, 1 1 2 0 .. 1 2 4 0 ,, 1 3 6 0, , 1 5 1
6 0 2
213. 195. 182. 169. 158. 149. 140. 132. 126. 119. 114. 109. 105. 102. 98.6 96.5 94.7 92.1 90.1 88.5
0,. 0 0 2 0, , 0 0 4 0,. 0 0 7 0.011 0,. 0 1 6 0, , 0 2 1 0,. 0 2 7 0, , 0 3 3 0^. 0 4 0 0.047
0,. 0 0 1 0 ,, 0 0 3 0, . 0 0 5 0 ., 0 0 8 0,. 0 1 1 0 ,, 0 1 4 0,. 0 1 7 0 ,, 0 2 0 0 ,, 0 2 3 0 ,, 0 2 7
85.0 81.2 81.8 81.9 80.8 77.9 73.9 68.5 63.8 59.5 56.0 53.0 50.4 48.4
NEUTRON PRODUCTION CROSS SECTIONS
T(rf,n)4He.
a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values
0* cm. O-oss Section
o ARS2 a BAS7 6 • BA57C
^ 0')
+ C052 V 0AS6 & G061A <>HES5
sS*""' eoJ\
0 5I6a @ 5TS2 * STK
[mb/srj cm.
\
To
) Q
;i
o^ ^ • o
OM
a05
OK)
0.15 Ed 1M(«)
0.20
025
0 0.3
030
0.4
06
06 to
•
a(0° cm.). Experimental and Recommended Values
rf^v
2.0 Ed iMeV)
40
'
6.0
S)
&0 10.0
a(0° cm.). Experimental and Recommended Values 1
T(d.n)'He
Ref. 1200- °
o a •
AR52 eA57B BA57C GA56 G061 A HES5
— —
Imb) 1000-
1
8000
\« = .
2.0
3.0
40
5.0 60 Ed iMeV)
70
6.0
9.0
00.3
10.0
•
Legendre Coefficients. Experimental and Recommended Values
04
0.6
0.8 1.0
2.0 Ed iMeVl
4.0
6.0
60 10.0
a(total). Experimental and Recommended Values
Solid line shows recommended values. Only experimental data which contributed to the recommended values are plotted. References are on page 618 603
Nuclear Data Tables, Vol. 1 1 , IMo. 7 , 1973
H. LISKIEN AND A. PAULSEN
T(4ii)*He. a(0° cm.), Legendre CoefHcients, a(total) Recommended and Experimental Values
EXPERIMENTAL 0 DEGREE C M . CROSS SECTION FOR THE REACTION T(D,N)HEA
ED(MEV)
SIGMA-0
REF.
ED(MEV)
SIGMA-0
REF,
0.0103 0.0154 0.0207 0.0220 0.0250 0.0250 0.0258 0.0300 0.0310 0.0330 0.0345 0.0360 0.0363 0.0400 0.0400 0.0415 0.0425 0.0460 0.0467 0.0481 0.0485 0.0500 0.0500 0.0520 0.0520 0.0525 0.0530 0.0533 0.0537 0.0554 0.0571 0.0580 0.0600 0.0600 0.0623 0.0625 0.0640 0.0670 0.0671 0.0675 0.0693 0.0693 0.0700 0.0700 0.0725 0.0728 0.0730 0.0733 0.0760 0.0762 0.0767 0.0780 0.0793 0.0800 0.0800 0.0820 0.0825 0.0827 0,0833 0.0867 0.0867 0.0893 0.0900
0.13 1.35 4.91 6.84 11.5 3.0 12.5 22.1 23.3 31.4 34.8 41.3 40.1 57.5 23.0 59.3 40.0 88.3 84.5 111.0 93.9 50. 68. 127. 118. 88. 129. 140. 131. 141. 141. 176. 173. 97. 183. 142. 208. 224. 245. 224. 247. 238. 160. 220. 200. 260. 267. 274. 292. 279. 284. 284. 334. 303. 313. 240. 263. 329. 330. 338. 359. 364. 325.
cn52 cn52 cn52 AR54 AR54 0A57A C052 AR54 cn52 AR54 C052 AR54 cn52 AR54 0A57A cn52 DA57A AR54 Cn52 BA57B C052 DA57A DA57A BA57R Cn52 DA57A AR54 AR52 BA57B cn52 cn52 AR5? AR54 DA57A cn52 DA57A AR52 AR54 BA57B C052 AR52 C052 DA57A DA57A DA57A C052 AR54 BA57B AR52 C052 Kn66 C052 BA57B K066 AR54 DA57A DA57A AR52 C052 Kn66 BA57B AR52 DA57A
0.0900 0.0903 0.0913 0.0925 0.0930 0.0931 0.0933 0.0937 0.0954 0.0960 0.0971 0.1000 0.1000 0.1000 0.1000 0.1011 0.1025 0.1027 0.1040 0.1060 0.1062 0.1067 0.1070 0.1090 0.1093 0.1100 0.1100 0.1100 0.1100 0.1110 0.1130 0.1130 0.1133 0.1141 0.1150 0.1150 0.1153 0.1160 0.1200 0.1200 0.1200 0.1200 0.1200 0.1211 0.1225 0.1227 0.1250 0.1250 0.1250 0.1260 0.1267 0.1293 0.1297 0.1321 0.1325 0.1332 0.1333 0.1340 0.1350 0.1360 0.1360 0.1400
290. 351. 390. 330. 377. 380. 366. 3 84. 406. 3 84. 391. 335. 390. 392. 375. 414. 390. 3 90. 404. 415. 406. 404. 394. 406. 392. 404. 394. 382. 395. 405. 393. 402. 401. 409. 403. 401. 399. 3 90. 374. 375. 403. 3 98. 389. 381. 388. 382. 385. 400. 395. 379. 373. 367. 374. 340. 360. 351. 357. 363. 390. 360. 350. 339.
DA57A C052 BA57B DA57A AR54 BA57B K066 C052 BA57B AR52 C052 DA57A AR54 K066 DA57A BA57B DA57A AR52 C052 BA57B BA57R K066 AR54 C052 AR52 K066 AR54 DA57A DA57A cn52 AR54 BA57B K066 BA57B 0A57A C052 BA57B AR52 AR54 DA57A DA57A DA57A K066 BA57B DA57A AR52 C052 DA57A DA57A BA57B K066 AR52 BA57B BA57B DA57A BA57B K066 cn52 DA57A Cn52 AR52 Kn66
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
604
NEUTRON PRODUCTION CROSS SECTIONS
T(
a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values
EXPERIMENTAL 0 DEGREE C M . CROSS SECTION FOR THE REACTION (CONTINUED)
T(D,N)HE4
ED(MEV)
SIGMA-0
REF.
ED(MEV)
SIGMA-0
REF.
0.1400 0.1412 0.1427 0.1430 0.1458 0.1460 0.1467 0.1493 0.1500 0.1500 0.1525 0.1530 0.1532 0.1533 0.1560 0.1600 0.1620 0.1627 0.1659 0.1667 0,1670 0.1700 0.1700 0.1725 0.1730 0.1733 0.1760 0.1773 0.1800 0.1825 0.1830 0.1859 0.1867 0.1893 0.1933 0 . 193 6 0.2000 0.2000 0.2027 0.2050 0.2062 0.2067 0.2133 0.2151 0.2160 0.2200 0.2250 0.2265 0.2267 0.2270 0.2293 0.2333 0.2350 0.2400 0.2427 0.2467 0.2510 0.2513 0.2533 0.2548 0.2560 0.2600 0.2600
383. 307. 334. 339. 316. 329. 321. 316. 360. 350. 315. 309. 271. 305. 300. 288. 276. 282. 264. 272. 272. 308. 303. 278. 260. 256. 247. 239. 240. 255. 245. 209. 224. 221. 209. 198. 195. 242. 202. 198. 182. 182, 171. 174. 180. 162. 200. 158. 153. 167. 162. 146. 152. 139. 147. 134. 142. 133. 128. 134. 133. 123. 134.
DA57A BA57R AR52 C052 BA57B C052 K066 AR52 DA57A DA57A DA57A C052 BA57B K066 Cn52 K066 C052 AR52 8A57B Kn66 C052 0A57A DA57A DA57A C052 K066 AR52 BA57B K066 DA57A Cn52 BA57B K066 AR52 K066 BA57B K066 DA57A AR52 C052 BA57B K066 K066 BA57B AR52 K066 DA57A BA57B K066 Cn52 AR52 K066 BA57B K066 AR52 K066 C052 AR52 K066 BA57B AR52 K066 BA57B
0.2667 0.2675 0.2693 0.2733 0.2760 0.2800 0.2880 0.2933 0.2957 0.3020 0.3067 0.3098 0.3200 0.3290 0.3333 0.3348 0,3467 0.3570 0.3600 0.3733 0.3830 0.3854 0.3867 0.4000 0.4020 0.4133 0.4267 0.4400 0.4480 0.4533 0.4602 0.4667 0.4800 0.4810 0.4822 0.4933 0,4960 0.5067 0.5200 0.5330 0.5333 0.5350 0.5467 0 . 5 5 70 0.5600 0.5733 0.5867 0.6000 0.6070 0.6108 0.6133 0.6267 0.6300 0.6400 0.6530 0.6533 0.6667 0.6890 0.6933 0.7045 0.7200 0.7333
118. 120, 119. 113. 118. 108. 109.
K066 BA57B AR52 K066 cn52 K066 BA57B K066 BA57B C052 K066 BA57B K066 C052 K066 BA57B K066 C052 Kn66 Kn66 AR52 BA57B K066 K066 C052 K066 K066 K066 C052 K066 BA57B Kn66 K066 C052 BA57B K066 cn52 K066 K066 C052 K066 BA57R K066 BA57B K066 K066 K066 K066 C052 BA57B K066 K066 BA57B K066 AR52 K066 K066 C052 K066 BA57B K066 K066
605
99.
101. 98.9 92.9 97.0 86.8 87.5 81.7 92.0 77.7 76.6 73.6 70.1 61.3 68.0 66.9 63.6 65.5 60.5 57.5 54.8 54.6 52.3 60.0 50.0 47.8 50.5 53.0 45.8 48.6 44.0 42.4 43,2 40,9 47,0 39,6 46,0 38,4 37,3 36,0 35.1 34.8 41.0 34.2 33.3 38.0 32.4 30.6 31.7 30.9 27.8 29.5 34.0 28.5 27.9
Nucleor Data Tables, Vol. 1 1 , No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(d,n)*He.
a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values
EXPERIMENTAL 0 DEGREE C M . CROSS SECTION FOR THE REACTION T(D»N)HEA (CONTINUED)
ED(MEV)
SIGMA-0
0.7336 0.7500 0.7600 0.7740 0.7867 0.8000 0.8000 0.8267 0.8400 0.8640 0.8667 0.9000 0.9000 0.9333 0.9570 0.9667 1.0000 1.0000 1.0000 1.0000 1.0300 1.0333 1.0550 1.0667 1.100 1.150 1.156 1.200 1.250 1.263 1.267 1.300 1,300 1.300 1.330 1.374 1.400 1.400 1.489 1.500 1.500 1.600 1 .608 1.700 1.732 1.750 1.750 1.820 1.930 2.000 2.050 2.160 2.170 2.210 2.250 2.250 2.310 2.420 2.500 2.560 2.690 2.750 2.800
29.0 29.8 26.9 23.0 25.9 25.5 24.4 24.6 24.0 20.3 23.1 23.1 22.1 21.1 18.7 20.2 19.5 19.8 20.3 24.4 20.1 18.7 17.3 18.3 17.7 17.4 15.1 17.9 16.8 13.6 15.9 17.8 14.9 15.9 16.8 13.0 15.4 15.0 12.8 14.4 14.4 14.2 11.8 13.7 11.3 13.1 12.6 13.0 13.2 12.1 12.9 12.0 11.1 13.1 11.9 11.8 12.3 11.5 12,2 11.5 11.6 12.6 12.3
Nuclear Data Tables, Vol. 1 1 , No. 7, 1 973
RFF.
ED(MEV)
BA57B BA57C Kn66 C052 K066 K066 AR52 K066 K066 C052 Kn66 BA.57C Kn66 K066 Cn52 K066 Kn66 AL58 BA57C HE55 GA56 K066 Cn52 Kn66 Kn66 BA57C Cn52 GA56 BA57C C052 AL5R GA56 BA57C BA57C GA56 C052 GA56 BA57C CG52 GA56 BA57C GA5A C052 GA56 Cn52 BA57C BA57C GA56 GA56 BA57C GA56 GA56 GA56 ST52 BA57C BA57C GA56 GA56 BA57C GA56 GA56 BA57C GA56
2.950 3.000 3.060 3.130 3.230 3.250 3.250 3.320 3.400 3.500 3.500 3.600 3.700 3,750 3,800 3.900 3.980 4.000 4.000 4.090 4.170 4.250 4.250 4.250 4.320 4.380 4.480 4.500 4.570 4.670 4.750 4,800 4,890 5.000 5.000 5.250 5.250 5.500 5.600 5.750 6.000 6.000 6.100 6.250 6.250 6.400 6.500 6.750 6.800 7.000 7.000 7.000 7.250 7.900 8.000 8.400 8,500 9.000 9.100 9.500 9.900 0.000
606
SIGMA-0 11.7 13.1 13.1 12.3 12.8 13.3 13.5 12.7 12.5 12.6 14.3 13.7 14.5 15.1 14.0 14.2 15.0 14.5 15.7 15.2 16.0 16.4 16.8 16.6 18.2 16.7 16.3 17.3 17.6 17.5 17.5 16.4 17.8 17.5 18.5 18.5 18.1 19.0 17.0 18.8 19.1 18.6 17.8 19,0 18,7 18,8 18,7 18,2 16,9 18,2 18,6 17,9 18,2 17,2 16,5 16,4 15,0 16,5 18,0 16,8 15,0 15,9
RFF, GA56 BA57C GA56 GA56 GA56 BA57C BA57C GA56 GA5A GA56 BA57C GA56 GA56 PA57C GA56 GA56 GA56 BR64 BA57C GA56 GA56 GA56 BA57C BA57C GA56 GA56 GA56 BA57C GA56 GA56 BA57C GA56 GA56 GA56 BA57C BA57C BA57C BA57C BR64 BA57C BA57C BA57C ST60 BA57C BA57C Gn61A BA57C BA57C BR64 BA57C BA57C SI68 BA57C BR64 SI68 ST60 Gn61A SI68 BR64 BR64 ST60 SI68
NEUTRON PRODUCTION CROSS SECTIONS
T(4n)*He. a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values NORMALIZED EXPERIMENTAL LEGENDRE COEFFICIENTS FOR THE REACTION TID.NJHE'i
ED(MEV) 0.023 0.050 0.083 0.117 0.133 0.253 0.380 0.500 0.653 0.750 0.800 1.000 1.000 1.000 1.250 1.500 1.530 1.750 2.210 2.500 3.000 3.000 3.050 3.500 3.970 4.000 4.500 5.000 6.000 6.200 7.000 7.900 9.100
AO 1.000 1.000 1.000 1.000 1.000 1.000 1.000 0.983 1.007 0.988 0.885 0.946 0.959 0.921 0.922 0.B85 0.916 0.833 0.714 0.662 0.578 0.568 0.554 0.492 0.412 0.427 0.390 0.360 0.326 0.319 0.301 0.289 0.261
Al
0.034 0.033 0.055 0.108 0.090 0.073 0.125 0.105 0.113 0.070 0.123 0.130
o.iie
0.129 0.148 0.128 0.111 0.121 0.119 0.112 0.117 0.121 0.115 0.102 0.065 0.062
A2
-0.017 -0.040 -0.043 0.007 -0.036 -0.032 -0.046 -0.027 0.002 0.014 0.044 0.132 0.113 0.165 0.159 0.200 0.220 0.276 0.252 0.274 0,264 0.222 0.225 0.182 0.201 0.173
REF.
0.005 0.038 0.040 0.068 0.024 0.052 0.067 0.053 0.060 0.067 0.059 0.049 0.041 0.013 0.017
0.019 0.028 0.028 -0.019 0.041 0.034 0.026 0.046 0.042 0.046 0.072 0.069 0.110 0.124 0.139
0.032 0.043 0.063 0.029 0.062 0.055 0.071 0.087 0.103 0.135 0.149 0.180 0.178 0.196
0.009 0.017 0.013 0.024 0.029 0.043 0.032 0.035 0.043 0.065 0.065 0.084 0.094 0.127
0.005
0 004
0.019 0.034
0, 017 0 025
BR49 BR49 ALSO AL50 AL50 AR52 AR52 BA57C AR52 BA57C AR52 BA57C PA64 HE55 BA57C BA57C GA56 BA57C GA56 BA57C BA57C PA64 GA56 BA57C GA56 BA57C BA57C BA57C BA57C G061A BA57C G061A G061A
T(d,n)'He EXPERIMENTAL TOTAL CROSS SECTION FOR THE REACTION T(0,N>HE4 (ABOVE 300 KEV OEUTERON ENERGvT ED(MEV)
SIGMA-T
REF.
0.3098 0.3348 0.3800 0.3854 0.4602 0.4822 0.5000 0.5350 0.5570 0.6108 0.6300 0.6530 0.7045 0.7336 0.750 0.800 1.000 1.000 1.250 1.500 1.530 1.750 2.210 2.500 3.000 3.050 3.500 3.970 4.000 4.500 4. 980 5.000 5.790 6.000 6.200 7.000 7.900 9.100
1220. 1160. 770. 850. 750. 670. 644. 590. 570. 510. 470. 380. 420. 360. 369. 300. 245. 280. 191. 159. 165. 135. 108. 99,9 93.6 85,0 88.4 84.0 85,0 85 " 88 82 90 76 73 69 63 53
BA57B BA57B AR52 BA57B BA57B BA57B BA57C BA57B BA57B BA57B BA57B AR52 BA57B BA57B BA57C AR52 BA57C HE55 BA57C BA57C GA56 BA57C GA56 BA57C BA57C GA56 BA57C GA56 BA57C BA57C GA56 BA57C GA56 BA57C G061A BA57C G061A Gn61A
a(6, Ep). Recommended Values
607
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
H. USKIEN AND A. PAULSEN
0(6 lab), £^{6 lab): Recommended Values
T(d,nYHe. ENERGYIMEV)
0.020
0.030
0.040
0.050
0.060
0.070
0.080
0.090
CENTER-OF-MASS INPUT VALUES FUR THE REACTION T ( U , N ) H E 4 t)-SIGMA-0(MB/SR) A 0
4.300 1.000
ANGLE(UEGREE)
19.600 1.000
52.900 1.000
106.000 1.000
175.000 1.000
DIFFERENTIAL CROSS-SECTIONS (MB/SR)
250.000 1.000
315.000 1.000
367.000 1.000
IN THE LARORATURV SYSTEM
2'° 5.0 10.0 15.0 20-0 25.0 30.0
5'tl?i O'M'i 0.439| 9,'?|2i O'^lll 0'?38| 0.438E
2i 0} 01 0} 01 01 01
0'201f 9-201E 0.201E O'^Olf 0.200E 0.200E 0.200b
02 02 02 0? 02 02 02
0.545E 0.545E 0.545E 0.544E 0.544E 0.543E 0.543E
02 02 02 02 02 02 02
0.109E 0.109E 0.109E 0.109E 0.109E 0.109E 0.109E
03 03 03 03 03 03 03
0.181E 0.181E 0.181E 0.181E 0.181E O.iaOE 0.180E
03 03 03 03 03 03 03
0.260E 0.260E 0.260E 0.269E 0.259E 0.259E 0.258E
03 03 03 03 03 03 03
0.328E 0.328E 0.328E 0.328E 0.327E 0.327r 0.326E
03 03 03 03 03 03 03
0.3R4E 0.3R3E 0.383F 0.383E 0.3H2E 0.392E 0.381E
03 03 03 03 03 03 03
35.0 ?P'0 *5.0 ^§•0 55.0 60.0
0.437| 0«?37| 0.436E 2'?lll 0.435E 0.434E
01 01 01 2J 01 01
0.200E 0.199E 0.199E 0'}99e 0.19eE 0.198E
02 02 02 02 02 02
0.542E 0.541E 0.540E 0.539E 0.538E 0.537E
02 02 02 OZ 02 02
0.108E 0.108E 0.108E 0.108E 0.108E 0.107E
03 03 03 03 03 03
0.180E 0.180E 0.179E 0.179E 0.178E 0.178E
03 03 03 03 03 03
0.25eE 0.257E 0.257E 0.256E 0.255E 0.255E
03 03 03 03 03 03
0.326E 0.325E 0.324E 0.323E 0.322E 0.321E
03 03 03 03 03 03
0.380E 0.379E 0.378E 0.377E 0.376E 0.375E
03 03 03 03 03 03
65.0 19'0 J5.0 |0.0 85.0 90.0
0.433E 0.433| 0'*l?i 0.431E 0'*30E 0.429E
01 01 01 01 01 01
0.198E 0.197E 0.197E 0.196E 0.196E 0.195E
02 02 02 02 02 02
0.535E 0,534E 0.533E 0.531E 0.530| 0.528E
02 02 02 02 02 02
0.107E 0.107E 0.106E 0.106E 0.106E 0.105E
03 03 03 03 03 03
0.177E 0.177E 0.176E 0.176E 0.175E 0.174E
03 03 03 03 03 03
0.254E 0.253E 0.252E 0.251E 0.25OE 0.249E
03 03 03 03 03 03
0.320E 0.319E 0.318E 0.317E 0.316F 0.314E
03 03 03 03 03 03
0.374E 0.372E 0.371E 0.369E 0.36eE 0.366E
03 03 03 03 03 03
95.0 100.0 105.0 110.0 115.0 120.0
0'*??i 0.428| 0.427| S'S??i 0.426| 0.425E
01 01 01 8,1 01 01
0.195E 0.195E 0.194E 0.194E 0.193E 0.193E
OZ 02 02 02 02 02
0.527E 0.526E 0.524E 0.523E 0.b22E 0.520E
02 02 02 02 02 02
0.105E 0.105E 0.105E 0.104E 0.104E 0.104E
03 03 03 03 03 03
0.174E 0.173E 0.173E 0.172E 0.172E U.171E
03 03 03 03 03 03
0.249E 0.248E 0.247E 0.246E 0.245E 0.244E
03 03 03 03 03 03
0.313E 0.312E 0.311E 0.31QE 0.309E 0.3086
03 03 03 03 03 03
0.365E 0.363E 0.362E 0.361E 0.3591 0.358E
03 03 03 03 03 03
125.0 130.0 135.0 IJO.O 1*5.0 150.0
0.424E 0.424E 0.423E 0.422E 0.422| 0.421E
01 01 01 01 01 01
0.193E 0.192E 0.192E 0.192E 0.191E 0.191E
02 02 02 02 OZ 02
0.519E 0.518E 0.517E 0.516E 0.515E 0.515E
02 02 02 02 02 02
0.103E 0.103E 0.103E 0.103E 0.103E 0.102E
03 03 03 03 03 03
0.171E 0.170E 0.170E 0.170E 0.169E 0.169E
03 03 03 03 03 03
0.244E 0.243E 0.242E 0.242E 0.241F 0.241E
03 03 03 03 03 03
0.307E 0.306E 0.305E 0.304E 0.303E 0.303E
03 03 03 03 03 03
0.357E 0.356E 0.355E 0.354E 0.353E 0.352E
03 03 03 03 03 03
155.0 1*0.0 1^5.0 170.0 \l%'° 180.0
0.421E 0.421E 0'?21| 0'?|0e 5'??9i 0.420E
01 01 01 01 21 01
0.191E 0.191E 0.191E 0.190E 0.190E 0.190E
02 02 02 02 02 02
0.514E 0.513E 0.513E 0.513E 0.513E 0.512E
02 02 02 02 02 02
0.102E 0.102E 0.102E 0.102E 0.102E 0.102E
03 03 03 03 03 03
0.169E 0.168E 0.16e£ 0.168E 0.168E 0.1686
03 03 03 03 03 03
0.240E 0.240E 0.240E 0.240E 0.240E 0.239E
03 03 03 03 03 03
0.302E 0.302E O.loil 0.301E 0.301E 0.3016
03 03 03 03 03 03
0.351E 0.3516 0 350E 0.350E 0.350E 013501
03 03 03 03 03 03
6N6RGY(MEV)
0.100
0.150
0.200
0.250
0.300
0.350
0.400
0.450
CENTER-OF-MASS INPUT VALUES FOR THE REACTION TID,N1HE4 D-SIGMA-0(MB/SR) A 0 A 1 A 2
394,000 1.000 0.000 0.000
317.000 1.000 0.000 0.000
ANGLE(OEGREE)
199.000 1.000 0.000 0.000
133.000 1.000 0.000 0.000
95.200 1.000 0.000 0.000
DIFFERENTIAL CRUSS-SECTIUNS (MB/SRl
77.500 1.000 0.000 0.000
63.600 0.999 0.004 -0.003
53.000 0.9S8 0.013 -O.Oll
IN THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.413E 0.413E 0.412E 0.412E 0.412E 0.411E 0.410E
03 03 03 03 03 03 03
0.336E 0.335E 0.335E 0.335E 0.334E 0.334E 0.333E
03 03 03 03 03 03 03
0.212E 0.212E 0.212E 0.212E 0.211E 0.211E 0.210E
03 03 03 03 03 03 03
0.143E 0.143E 0.143E 0.142E 0.142E 0.142E 0.141E
03 03 03 03 03 03 03
0.103E 0.103E Q.103E 0.103E 0.102E 0.102E Q.102E
03 03 03 03 03 03 03
0.846E 0.846E 0.B45E 0.843E 0.841E 0.839E 0.836E
02 02 02 02 02 02 02
0.697E 0.697E 0.696E 0.695E 0.693E 0.691E 0.689E
02 02 02 02 02 02 02
0.585E 0.5S5E 0.584E 0.b83E 0.582E O.SBIE 0.579E
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.409E 0.408E 0.407E 0.406E 0.404E 0.403E
03 03 03 03 03 03
0.332E 0.331E 0.330E 0.329E 0.327E 0.326E
03 03 03 03 03 03
0.210E 0.209E 0.208E 0.207E 0.206E 0.205E
03 03 03 03 03 03
0.141E 0.140E 0.1406 0.139E 0.138E 0.138E
03 03 03 03 03 03
O.IOIE O.lOlE O.IOOE O.IOOE 0.997E 0.991E
03 03 03 03 02 02
0.e32E 0.829E 0.824E 0.820E 0.814E 0.809E
02 02 02 02 02 02
0.686E 0.683E 0.579E 0.675E 0.670E 0.666E
02 02 02 02 02 02
0.676F 0.574E 0.571E 0.567E 0.664E 0.5606
02 02 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.401E 0.400E 0.398E 0.397E 0.395E 0.393E
03 03 03 03 03 03
0.324E 0.323E 0.321E 0.320E 0.318E 0.3166
03 03 03 03 03 03
0.204E 0.203E Q.202E 0.201E 0.200E 0.198E
03 03 03 03 03 03
0.137E 0.136E 0.135E 0.134E 0.133E 0.132E
03 03 03 03 03 03
0.985E 0.978E 0.971E 0.965E 0.958E 0.951E
02 02 02 02 02 02
0.B04E 0.798E 0.792E 0.7b6E 0.780E 0.774E
02 02 02 02 02 02
0.661E 0.656E 0.650E 0.645E 0.639E 0.634E
02 02 02 02 02 02
0.555E 0.551E 0.5466 0.541E 0.5366 0.530E
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0.392E 0.390E 0.388E 0.387E 0.385E 0.384E
03 03 03 03 03 03
0.315E 0.313E 0.312E 0.310E 0.309E 0.307E
03 03 03 03 03 03
0.197E 0.196E 0.195E 0.194E 0.193E 0.192E
03 03 03 03 03 03
0.132E 0.131E 0.130E 0.129E 0.1286 0.127E
03 03 03 03 03 03
0.944E 0.937E 0.930E 0.924E 0.9186 0.912E
02 02 02 02 02 02
0.768E 0,762E 0.7566 0.750E 0.745E 0.739E
02 02 02 02 02 02
0.628E 0.623E 0.617E 0.612E D.607E 0.602E
02 02 02 02 02 02
0.525E 0.5196 0.514E 0.5096 0.5036 0.4986
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.383E 0.381E 0.380E 0.379E 0.378E 0.377E
03 03 03 03 03 03
0.306E 0.304E 0.303E 0.302E 0.301E 0.300E
03 03 03 03 03 03
0.191E 0.190E 0.189E 0.188E 0.188E 0.187E
03 03 03 03 03 03
0.127E 0.126E 0.125E 0.125E 0.124E 0.124E
03 03 03 03 03 03
0.906E 0.901E 0.896E 0.891E 0.887E 0.884E
02 02 02 02 02 02
0.734E 0.730E 0.726E 0.7226 0.718E 0.715E
02 02 02 02 02 02
0.597E 0.593E 0.589E 0.5856 0.5&2E 0.579E
02 02 02 02 02 02
0.493E 0.489F 0.4B4E 0.4806 0.4776 0.4746
02 02 02 02 02 02
155.0 160.0 165.0 170.0 175.0 160.0
0.376E 0.376E 0.375E 0.375E 0.375E 0.375E
03 03 03 03 03 03
0.300E 0.2996 0.299E 0.298E 0.298E 0.298E
03 03 03 03 03 03
0.186E 0.186E 0.186E 0.1856 0.185E 0.185E
03 03 03 03 03 03
0.123E 0.123E 0.123E 0.123E 0.1236 0.123E
03 03 03 03 03 03
0.881E 0.878E 0.8766 0.875E 0.874E 0.874E
02 02 02 02 02 02
0.712E 0.710E 0.709E 0.707E 0.707E 0.7066
02 02 02 02 02 02
0.576E 0.574E 0.573E 0.571E 0.671E 0.5706
02 02 02 02 02 02
0.4716 0.469E 0.467E 0.466E 0.4656 0.465E
02 02 02 02 02 02
Nuclear Data Tables, Vol. 11, No. 7, 1973
608
NEUTRON PRODUCTION CROSS SECTIONS
0(6 lab), E„(e lab): Recommended Values
T(d,n)*He. ENERGY(MEV)
0.020
0.030
0.040
0.050
0.050
0.070
0.080
INPUT VALUES FOR THE REACTION T { 0 , N ) H E 4 REST ENERGY IN MEV FUR PRUJECTILE
Tl=1875.633
TARGET T2=2808.951
0-VALUE IN HEV «=
17.590
PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS 7 4 = 3 7 2 7 . 4 1 8 ENERGY nF PARTICLE-3
ANGLE(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 IIO.O 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
14.341 14.340 14.336 14.331 14.322 14.312 14.300 14.285 14.269 14.251 14.231 14.210 14.188 14.164 14.140 14.114 14.089 14.063 14.036 14.010 13.984 13.958 13.934 13.910 13.886 13.865 13.844 13.825 13.807 13.792 13.778 13.766 13.756 13.748 13.743 13.739 13.738
14.414 14.413 14.409 14.402 14.392 14.379 14.364 14.346 14.326 14.304 14.280 14.254 14.226 14.197 14.167 14.136 14.104 14.072 14.040 14.008 13.976 13.945 13.915 13.885 13.857 13.830 13.805 13.782 13.760 13.741 13.724 13.710 13.698 13.688 13.682 13.677 13.676
ENERGY (MEV)
0.100
0.150
(MEV)
IN THE LABORATORY SYSTEM
14.477 14.476 14.471 14.462 14.451 14.436 14.418 14.398 14.375 14.349 14.321 14.291 14.259 14.226 14.191 14.155 14.118 14.081 14.044 14.007 13.970 13.934 13.899 13.865 13.833 13.802 13.773 13.745 13.721 13.699 13.680 13.663 13.649 13.639 13.631 13.625 13.624
14.533 14.531 14.52 6 14.516 14.504 14.487 14.467 14.444 14.418 14.389 14.358 14.324 14.289 14.251 14.212 14.172 14.131 14.090 14.048 14.007 13.966 13.925 13.886 13.848 13.812 13.777 13.745 13.715 13.688 13.563 13.541 13.623 13.607 13.595 13.587 13.581 13.580
14.584 14.582 14.576 14.566 14.552 14.534 14.512 14.487 14.458 14.425 14.392 14.355 14.316 14.275 14.232 14.188 14.143 14.098 14.052 14.007 13.962 13.918 13.875 13.833 13.793 13.756 13.720 13.688 13.658 13.631 13.607 13.587 13.570 13.557 13.547 13.542 13.540
14.532 14.630 14.623 14.612 14.597 14.577 14.554 14.525 14.495 14.461 14.424 14.384 14.341 14.297 14.251 14.203 14.155 14.105 14.056 14.007 13.959 13.911 1 3 . 86 5 13.820 13.777 13.736 13.698 13.653 13.631 13.60 2 13.576 13.554 13.536 13.522 13.511 13.505 13.503
14.677 14.674 14.667 14.655 14.639 14.616 14.593 14.563 14.530 14.493 14.453 14,411 14,365 14.317 14.268 14.217 14.155 14.113 14.050 14.008 13.956 13.905 13.856 13.808 13.762 13.718 13.678 13.640 13.506 13.575 13.547 13.524 13.505 13.489 13.479 13.472 13.470
14.719 14.716 14.709 14.596 14.679 14.656 14.630 14.598 14.563 14.524 14.482 14.436 14.388 14.337 14.285 14.231 14.176 14.120 14.054 14.008 13.953 13.899 13.847 13.796 13.748 13.702 13.559 13.619 13.582 13.550 13.521 13.496 13.476 13.459 13.448 13.441 13.439
0.200
0.250
0.300
0.350
0.400
0.450
INPUT VALUES FOR THE REACTION T ( D , N ) H E 4
ANGLE(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 IIO.O 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
REST ENERGY IN MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 0-VALUE I d MEV 0= TARGET T 2 - 2 8 0 8 . 9 5 1 PRODUCT T3= 9 3 9 . 5 7 5 RESIDUAL NUCLEUS 7 4 = 3 7 2 7 . 4 1 8 ENERGY OF PARTICLE-3 (MEV) IN THE LARORATORY SYSTEM
14.759 14.757 14.749 14.735 14.717 14.693 14.665 14.632 14.594 14.553 14.508 14.460 14.409 14.355 14.300 14.243 14.185 14.126 14.067 14.009 13.951 13.894 13.839 13.785 13.734 13.686 13.641 13.599 13.560 13.526 13.496 13.470 13.448 13.431 13.419 13.412 13.410
14.940 14.936 14.926 14.910 14.887 14.858 14.823 14.782 14.736 14.585 14.629 14.570 14.507 14.441 14.373 14.303 14.232 14.160 14.067 14.015 13.944 13.875 13.807 13.742 13.680 13.521 13.566 13.515 13.458 13.427 13.390 13.358 13.332 13.312 13.297 13.288 13.285
15.096 15 . 09 3 15.081 15.062 15.035 15.001 14.960 14.912 14.859 14.800 14.735 14.655 14.593 14.517 14.436 14.357 14.274 14.191 14.107 14.024 13.942 13.862 13.784 13.709 13.538 13.570 13.507 13.448 13.394 13.345 13.304 13.258 13.238 13.215 13.198 13.188 13.184
15.238 15.234 15.221 15.199 15.169 15.130 15.084 15.031 14.971 14.904 14.832 14.754 14.672 14.586 14.498 14.407 14.314 14.221 14.127 14.034 13.943 13.853 13.765 13.683 13.603 13.527 13.457 13.391 13.332 13.279 13.232 13.191 13.158 13.132 13.113 13.102 13.098
609
17.590
15.369 16.364 15.350 16.325 15.293 15.250 15.200 15.141 16.074 15.001 14.921 14.83 6 14.745 14.651 14.554 14.454 14.352 14.250 14.147
15.492 15.487 16.471 16.445 15.409 16.353 16.308 15.244 16.171 16.092 16.00 5 14.913 14.815 14.713 14.507 14.499 14.389 14.278 14.167
15.609 15.503 16.586 15.558 16.519 15.470 16.410 16.342 16.254 16.178 16.085 14.986 14.881 14.771 14.658 14.542 14.424 14.305 14.187
15.720 15.714 15.696 15.666 16.625 15.572 15.509 16.435 15.352 16.261 15.152 15.056 14.944 14.828 14.707 14.584 14.459 14.333 14.207
14.045 13.945 13.847 13.752 13.560 13.573
14.057 13.949 13.843 13.740 13.542 13.548
14.059 13.953 13.840 13.731 13.525 13.525
14.082 13.959 13.839 13.723 13.612 13.505
13.491 13.414 13.343 13.278 13.219 13.158 13.124 13.088 13.060 13.040 13.027 13.023
13.459 13.376 13.299 13.2 30 13.157 13.112 13.065 13.026 12.996 12.974 12.950 12.956
13.431 13.342 13.261 13.186 13.120 13.061 13.011 12.970 12.937 12.914 12.900 12.895
13.405 13.312 13.226 13.147 13.077 13.015 12.952 12.918 12.884 12.859 12.845 12.840
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
a(d lab), £^(6 lab): Recommended Values
Tid,n)*He. ENERGY(MEV1
0.50C1
0.55C
)
0.60C
C E N T E R - • U F - •MASS U-SIGMA-0(Me/SR) A 0 A 1 A 2
3 9.400 0.99; 0.030
45.500 0.997 0.021 -O.Olfi
0.6bC
-o.oae
)
V A L U E ;; 31.900 0.989 0.046 -0.035
35.500 0.993 0.038 - 0 . 0 3 !L
DIFFERENTIAL
ANGLe(DEGR£e]
)
INPUT
C R O S S - S E C T I O N S;
0.75C
0.700 FUR
THE R E A C T I U l M
1IN T H E
0.80C
)
0.850
23.400 0.973 0.072 -0.045
25.000 0.978 0.067 -0.045
27.000 0 . 9 8 ;i 0.06 0 -0.043
29.400 0.986 0.053 -0.039 (MB/SRI
)
T(U,NlHe4
LABORATURY
SYSTeM
0.0 5.0 10.0 15.0 20.0 2i>.0 30.0
0.505E 0.505E 0.504E 0.503E 0.503E 0.501E 0.300t
02 02 02 02 02 02 02
0.439E 0.4396 0.4396 0.438E 0.4376 0.4366 0.435E
02 02 02 02 02 02 U2
0.397E 0.397E 0.397E 0.397E 0.396E 0.395E 0.394E
02 02 02 02 02 02 02
0.3596 0.359E 0.358E 0.358E 0.3576 0.357E 0.366E
02 0 . 3 3 2 E 02 0 . 3 3 2 6 02 0 . 3 3 2 E 02 0 . 3 3 1 E 02 0 . 3 3 1 E 02 0 . 3 3 0 E 02 0 . 3 2 9 E
02 02 02 02 02 02 02
0.306E 0.3066 0.3066 0.3056 0.3056 0.304E 0.304E
02 02 02 02 02 02 02
0.2S4E 0.2846 0.2846 0.2846 0.2836 0.2836 0.2826
02 02 02 02 02 02 02
0.267E 0.267E 0.267E 0.2676 0.266E 0.2656 0.2656
02 02 02 02 02 02 02
35.0 40.0 'tS.O 50.0 55.0 60.0
0.498E 0.496E 0.493E 0.490E 0.487E 0.484E
02 02 02 02 02 02
0.434E 0.4326 0.430E 0.427E 0.424E 0.421E
02 02 02 02 02 02
0.393E 0.391E 0.389E 0.387E 0.384E 0.381E
02 02 02 02 02 02
0.354E 0.3536 0.3516 0.3496 0.3466 0.3436
02 0 . 3 2 8 6 02 0 . 3 2 7 E 02 0 . 3 2 5 E 02 0 . 3 2 3 6 02 0 . 3 2 0 6 02 0 . 3 1 7 E
02 02 02 02 02 02
U.3U2E 0.301E 0.299E 0.297E 0.2956 0.292E
U2 02 02 02 02 02
0.2bl6 0.27v6 0.278E 0.276E 0.2736 0.2716
02 0 . 2 6 3 6 1)2 0 . 2 6 2 t 02 0 . 2 6 0 6 02 0 . 2 5 8 E 02 0 . 2 5 6 E 02 0 . 2 5 3 6
02 o2 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.480E 0.475E 0.471E 0.466E 0.461E 0.456E
02 0 . 4 1 7 E 02 0 . 4 1 4 E 02 0 . 4 0 9 E 02 0.405E 02 0.400E 02 0 . 3 9 5 E
02 0 . 3 7 8 E 02 0.374E 02 0 . 3 7 0 E 02 0.366E 02 0 . 3 6 1 E 02 0 . 3 5 6 6
02 0 . 3 4 0 6 02 0 . 3 3 7 6 02 0 . 3 3 3 6 02 0.328E 02 0 . 3 2 4 6 02 0 . 3 1 9 6
02 0 . 3 1 4 E 02 0 . 3 1 1 E 02 0 . 3 0 7 E 02 0.303E 02 0 . 2 9 8 E 02 0 . 2 9 3 E
02 0 . 2 8 9 6 02 0 . 2 8 6 6 02 0 . 2 8 2 6 02 0 . 2 7 8 6 02 0 . 2 7 4 E 02 0 . 2 6 9 E
02 02 02 02 02 02
0.2686 0.2646 0.261E 0.2576 0.2526 0.2486
02 02 02 02 02 02
0.2506 0.247E 0.2436 0.239E 0.235E 0.231E
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0.45 IE 0.445E 0.440E 0.435E 0.429E 0.424E
02 02 02 02 02 02
0.390E 0.385E 0.379E 0.374E 0.369E 0.364E
02 02 02 02 02 02
0.351E 0.3466 0.340E 0.335E O.330e 0.325E
02 02 02 02 02 02
0.314E 0.3096 0.304E 0.2996 0.2946 0.289E
02 0 . 2 e 9 E 02 0 . 2 8 4 E 02 0 . 2 7 9 E 02 0 . 2 7 3 E 02 0.268E 02 0 . 2 6 3 E
02 02 02 02 02 02
0.264E 0.259E 0.254E 0.249E 0.2446 0.240E
02 02 02 02 02 02
0.2436 0.238E 0.234E 0.229E 0.224E 0.219E
02 02 02 02 02 02
0.226E 0.221E 0.217E 0.212E 0.207E 0.203E
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.419E 0.415E 0.410E 0.406E 0.403E 0.39qE
02 02 02 02 02 02
0.3596 0.354E 0.350E 0.346E 0.342E 0.339E
02 02 02 02 02 02
0.320E 0.315E 0.311E 0.307E 0.303E 0.300E
02 02 02 02 02 02
0.284E 0.279E 0.275E 0.271E 0.267E 0.2646
02 0 . 2 5 9 6 02 0 . 2 5 4 6 02 0 . 2 5 0 E 02 0 . 2 4 6 E 02 0 . 2 4 2 E 02 0 . 2 3 9 E
02 02 02 02 02 02
0.235E 0.231E 0.226E 0.223E 0.219E 0.2166
02 02 02 02 02 02
0.215E 0.210E 0.206E 0.203E 0.199E 0.196E
02 02 02 02 02 02
0.199E 0.195E 0.191E 0.187E 0.184E 0.181E
02 02 02 02 02 02
155.0 160,0 165.0 170.0 175.0 180.0
0.396E 0.394E 0.392E 0.391E 0.390E 0.390E
02 02 02 02 02 02
0.336E 0.334E 0.332E 0.330E 0.330E 0.329E
02 02 02 02 02 02
0.297E 0.294E 0.293E 0.291E 0.290E 0.2906
02 02 02 02 02 02
0.2616 0.2596 0.257E 0.256E 0.2556 0.255E
02 0 . 2 3 7 6 02 0 . 2 3 4 E 02 0 . 2 3 2 E 02 0 . 2 3 1 E 02 0.230e 02 0 . 2 3 0 E
02 02 02 02 02 02
0.213E 0.2116 0.2096 0.208E 0.2076 0.2076
02 02 02 02 02 02
0.194E 0.1926 0.1906 0.1896 0.188E 0.188E
02 02 02 02 02 02
0.179E 0.1776 0.1756 0.1746 0.173E 0.173E
02 02 02 02 02 02
ENERGY ( M E V ) CENTER-- U F - -MASS 0-SIGMA-OIMB/SR) a 0
^AA 3\2
A 4 A 5 A 6
22.000 0.968 0.077 -0.045 0.000 0.000 0,000 0,000
20.800 0.963 0.082 -0.045 0.000 0.000 0.000 0.000
ANGLE(D6GR6E)
INPUT
19,800 0,957 0,087 -0,044 0,000 0,000 0,000 0,000
DIFFERENTIAL
VALUES 17.900 0.946 0.094 -0.040 0.000 0.000 0.000 0.000
C R U S S - :5 6 C T i n N S
FUR
THE R E A C T I O N
(MB/SRI
T(U,N)He4
15.800 0.9i; 0.105 -0.023 0.000 0.003 0.000 0.000
16.700 0.93 1 0.100 -0.032 0.000 0.001 0.000 0.000 :I N
TH6
11 4 . 3 0 0 0.878 0.113 0.002 0.000 0.005 0.000 0.002
15.000 0.898 0.110 -0.013 0.000 0.004 0.000 0.001
LABORATURY
SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0,2526 0,2526 0,2626 0.251E 0,251E 0,250E 0,249E
02 02 02 02 02 02 02
0.239E 0.2396 0.2396 0.2396 0.238E 0.237E 0.236E
02 0 . 2 2 8 6 02 0 . 2 2 8 6 02 0 . 2 2 8 6 02 0 . 2 2 8 6 02 0 . 2 2 7 6 02 0 . 2 2 6 E 02 0 . 2 2 5 6
02 02 02 02 02 02 02
0.208E 0.208E 0.207E 0.2076 0.2066 0.205E 0.204E
02 0 . 1 9 5 E 02 0 . 1 9 5 E 02 0 . 1 9 5 6 02 0 . 1 9 4 6 02 0 . 1 9 3 6 02 0 . 1 9 2 6 02 0 . 1 9 0 E
02 02 02 02 02 02 02
0.1866 0.1866 0.1856 0.1846 0.1836 0.1826 0.1806
02 02 02 02 02 02 02
0.177E 0.177E 0.176E 0.175E 0.174E 0.172E 0.170E
02 02 02 02 02 02 02
0 .. 1 7 0 E 0 ,. 1 7 0 6 0 ,. 1 6 9 6 0 ,. 1 6 8 6 0 ,, 1 6 6 6 0 .. 1 6 4 6 0 .. 1 6 1 6
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0,248E 0,247E 0,245E 0.243E 0.240E 0,238E
02 02 02 02 02 02
0.235E 0.2336 0.2326 0.2306 0.227E 0.225E
02 02 02 02 02 02
0.224E 0.222E 0.221E 0.218E 0.216E 0.213E
02 02 02 02 02 02
0.2036 0.201E 0.1996 0.1976 0.1946 0.1926
02 0 . l e 9 E 02 0 . 1 8 7 E 02 0 . 1 8 5 6 02 0 . 1 8 2 E 02 0 . 1 8 0 E 02 0 . 1 7 7 E
02 02 02 02 02 02
0.1786 0.176E 0.173E 0.171E 0.168E 0.165E
02 02 02 02 02 02
0.1686 0.1666 0.1636 0.160E 0.1576 0.164E
02 02 02 02 02 02
0 .. 1 5 9 E 0 ., 1 5 6 6 0 ,. 1 5 3 E 0 ,. 1 5 0 6 0 ,. 1 4 7 6 0 ,, 1 4 4 6
02 02 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.235E 0.231E 0.2286 0.224E 0.2206 0.2166
02 02 02 02 02 02
0.222E 0.218E 0.215E 0.2116 0.207E 0.203E
02 02 02 02 02 02
0.210E 0.207E 0.203E 0.200E 0.196E 0.191E
02 02 02 02 02 02
0.1896 0.185E 0.182E 0.1786 0.1746 0.1706
02 0 . 1 7 4 E 02 0 . 1 7 0 E 02 0 . 1 6 7 6 02 0 . 1 6 3 E 02 0 . 1 6 0 E 02 0 . 1 5 6 6
02 02 02 02 02 02
0.162E O.ISSE 0.1556 0.151E 0.1486 0.1446
02 02 02 02 02 02
0.1516 0.1476 0.1446 0.1406 0.1376 0.1336
02 02 02 02 02 02
0 ,. 1 4 0 6 0 ,. 1 3 7 6 0 ,. 1 3 3 6 0 ,, 1 3 0 E 0 ,, 1 2 6 6 0 ., 1 2 3 6
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0.2116 0.2076 0.2026 0.1986 0.193E 0.189E
02 02 02 02 02 02
0.198E 0.1946 0.189E 0.185E 0.181E 0.177E
02 02 02 02 02 02
0.187E 0.1836 0.179E 0.174E 0.170E 0.1666
02 0 . 1 6 6 6 02 0.152E 02 0 . 1 6 2 6 02 0 . 1 4 8 6 02 0 . 1 5 8 E 02 0 . 1 4 4 6 02 0 . 1 5 5 6 02 0 . 1 4 1 6 02 0 . 1 5 1 6 02 0 . 1 3 7 5 02 0 . 1476 02 0 . 1 3 4 6
02 02 02 02 02 02
0 . 1 4 0 6 02 0 . 1 3 7 6 02 0 . 1 3 3 E 02 0 . 1 3 0 6 02 0 . 1 2 6 E 02 0 . 1236 02
0.1306 0.126E 0.123E 0.120E 0.1166 0.1146
02 02 02 02 02 02
0 ., 1 2 0 6 0 ,, 1 1 6 6 0 ., 1 1 3 6 0 ., 1 1 0 E 0 ,. 1 0 8 6 0 ,, 1 0 5 6
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.185E 0.181E 0.177E 0.174E 0.171E 0.1686
02 02 02 02 02 02
0.1736 0.1696 0.165E 0.1626 0.1596 0.1566
02 02 02 02 02 02
0.1626 0.1586 0.1556 0.1526 0.149E 0.147E
02 02 02 02 02 02
02 02 02 02 02 02
0.1206 0.117E 0.1156 0.112E O.UOE 0.109E
02 02 02 02 02 02
0. H I E 0.108E 0.106E 0.1046 0.1026 O.IOIE
02 02 02 02 02 02
0 ,, 1 0 2 6 0 ,, 1 0 0 6 0 .9876 0 ,, 9 7 0 6 0 ., 9 5 5 6 0 ,, 9 4 3 6
02 02 01 01 01 01
155.0 160.0 165.0 170.0 175.0 180,0
0.16S6 0.1636 0.162E 0.1616 0.1606 0,1606
02 02 02 02 02 02
0.1546 0,1526 0,1516 0,150E 0.149E 0,1496
02 0 . 1 4 4 6 02 0 . 1 4 3 6 02 0 . 1 4 1 E 02 0 . 1 4 0 6 02 0 . 1 4 0 6 02 0 . 1 3 9 6
02 0 . 1 0 7 6 02 0 . 1 0 6 6 02 0 . 1 0 5 E 02 0 . 1 0 4 E 02 0 . 1 0 4 E 02 0 . 1 0 4 6
02 02 02 02 02 02
0.9996 0.9896 0.981E 0.976E 0.9736 0.972E
01 01 01 01 01 01
0 ,. 9 3 3 6 0 .. 9 2 6 6 0 ,. 9 2 0 E 0 ,. 9 1 6 6 0 .. 9 1 4 6 0 .. 9 1 3 6
01 01 01 01 01 01
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
0.1436 0.1406 0.1376 0.1346 0.132E 0.1296
02 0 . 1 3 0 6 02 0 . 1 2 7 6 02 0 . 1 2 4 E 02 0 . 1 2 2 E 02 0 . 1 2 0 E 02 0 . 1 1 8 6
02 0 . 1 2 7 E 02 0 . 1 1 6 E 02 0 . 1 2 6 6 02 0 . 1 1 5 6 02 0 . 1 2 4 6 02 0 . 1 1 3 6 02 0 . 1 2 4 6 0 2 0 . 1 1 3 6 02 0 . 1 2 3 E 02 0 . 1 1 2 6 02 0 . 1 2 3 6 0 2 O . Z 1 2 6
610
NEUTRON PRODUCTION CROSS SECTIONS
T(4fi)4He. ENieRGYIMEV )
a{e lab), EJO lab): Recommended Values
0.500 INPUT VALUES FOR THE REACTION T(r),M)HE4 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ENERGY OF PARTICLE-3
ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 = 0.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
ENERGY(MEV)
17.590
IN THE LABHRATIIRY SYSTEM
15.779 15.577 15.555 15.445 15.315 15.179 15.037 14.891 14.741 14.590 14.437 14.285 14. 135 13.988 13.844 13.705 13.572 13.445
15.407 15.399 15.374 16.333 16.276 16.2 02 i o . 116 15.014 15.900 15.775 15.539 15.494 15.342
16.497 15.488 16.462 16.419 16.350 16.<;84 15.194 15.089 15.971 15.842 15.701 15.552 15.394
16.183 16.020 14.853 14.684 14.514 14.345
15.230 15.061 14.889 14.715 14.539 14.365
14.164 14.005 13.851 13.702 13.569 13.423
14.178 14.014 13.855 13.701 13.564 13.414
14.193 14.024 1 3 . 8 60 13.701 13.549 13.405
13.310 13.195 13.088 12.992 12.905 12.830 12.765 12.712 12.670 12.640 12.622 12.616
13.295 13.175 1 3 .06 7 12.967 12.878 12.800 12.733 12.678 12.635 12.504 12.585 12.579
13.282 13.159 13.046 12.943 12.852 12.771
13.270 13.143 13.027 12.921 12.827 12.744
12.836 12,786 12.747 12.719 12.702 12.697
13.326 13.214 13.112 13.018 12.935 12.862 12.799 12.748 12.707 12.678 12.561 12.555
12.702 12.646 12.601 12.670 12.550 12.544
12.674 12.515 12.570 12.537 12.517 12.511
1.000
1.100
1.200
14.094 13.965 13.839 13.716 13.599 13.487 13.382 13.284 13.193 13.111 13.037 12.972
13.362 13.259 13.164 13.078 13.000 12.933
13.343 13.236 13.137 13.047 12.957 12.896
12.917 12.871 12.835 12.809 12.794 12.789
12.875 12.827 12.789 12.763 12.746 12.741
0.900
0.950
14.882 14.754 14.624 14.492 14.359 14.226
IN MEV 0=
16.317 15.309 16.284 16.244 16.189 16.119 lo.u35 15.937 15.827 15.707 15.576 15.436 15.289 15.135 14.978 14.816 14.653 14.489 14.325
14.987 14.646 14.703 14.558 14.411 14.266 14.121 13.980 13.841 13.708 13.580 13.458
15.525 l5.'.i7 13.341 15.236 15.123 15.005
(MEVI
Q-VALUe
15.224 16.216 16.193 16.154 16.101 15.034 15.953 15.859 15.753 15.63 7 15.511 15.376 15.235 15.087 14.935 14.779 14.521 14.453 14.305 14.149 13.996 13.847 13.703 13.565 13.433
15.931 15.924 15.904 15.870 15.824 15.765 15.694 15.612 13.52U 15.418 15.307 15.189 15.065 14.935 14.801 14.664 14.525 14.385 14.246 14.108 13.972 13.840 13.711 13.589 13.472
15.828 15.821 15.802 15.770 15.726 15.670 15.603
Tl=1875.633 T2=2808.951 T3= 939.576 T4=3727.4ia
16.031 16.024 16.003 15.968 15.919 15.867 15.783 la.oVf 15.600 15.493 15.377 15.253 15.123
15.129 15.121 16.099 16.052 15.011 15.946 15.869
1.300
1.400
INPUT VALUES FDR THE REACTION T ( 0 , N ) H E 4 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ENERGY OF PARTICLE-3
ANGLE(DEGREE I
0, 5, 10 15, 20 25, 30 35.0 40.0 45.0 50.0 55.0 60.0 55.0 70.0 75.0 80.0 85.0 90.0
16.584 15.575 15.546 15.504 15.442 16.364 16.271 15.163 16.041 15.907 15.762 15.607 15.445
16.670 16.661 15.633 16.587 15.524 16.443 15.347 15.235 15.110 15.972 15.822 15.663 15.495
15.275 15.101 14.923 14.743 14.563 14.384
95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165,0 170.0 175.0 180.0
Tl=1875.633 T2=2808.951 T3= 9 3 9 . 5 7 5 74=3727.418 IMEV)
0-VALUE
IN THE LABORATORY SYSTEM
16.920 15.910 16.880 16.830 16.761 16.673 16.568 16.447 16.311 16.160 15.998 15.825 16.644 16.466 15.261 15.063 14.863 14.552 14.453
17.081 17.070 17.039 15.986 15,914 15.821 15.711 16.583 16.440 16.282 16.112 16.930 15.740 15.542 15.338 15,131 14.921 14.711 14.503
17.238 17.227 17.194 17.139 17.053 15.965 16.850 15.717 15.55 7 16.401 15.223 16.033 15.834
15.321 15.142 14.959 14.774 14.588 14.403
15.755 16,745 15.717 15.569 15.504 15.521 15.422 16.307 15.178 15.035 15.882 15.718 15.545 15.356 15.182 14.994 14.803 14.513 14.423
14.205 14.033 13.854 13.701 13.545 13.397
14.221 14.043 13.869 13.702 13.542 13.390
14.236 14.053 13.875 13.703 13.539 13.383
14.257 14.075 13.888 13.708 13.536 13.373
13.257 13.128 13.008 12.900 12.803 12.719 12.546 12.585 12.640 12.605 12.485 12.479
13.247 13.114 12.991 12.880 12.781 12.694
13.237 13.101 12.976 12.852 12.760 12.571 12.595 12.533 12.484 12.449 12.428 12.421
13.220 13.077 12.9 46 12.827 12.721 12.529 12.549 12.484 12.433 12.396 12.374 12.367
12.520 12.559 12.511 12.477 12.455 12.449
611
IN MEV 0=
15.627 15.414 15.197 14.979 14.760 14.643
17.392 17.380 17.346 17.288 17.209 17.108 16.987 16.847 16.591 15.518 15.332 1 5 . 134 15.925 15.711 1 5.48 9 15.263 16.035 14.808 14.583
17.543 17.531 17.495 17.436 17.352 17.247 17.121 16.975 15.812 16.633 16.439 16.233 16.017 15.793 15.553 15.329 15.093 14.857 14.622
14.298 14.097 13.902 13.714 13.534 13.354
14.329 14.120 13.917 13.721 13.535 13.358
14.360 14.143 13.932 13.730 13.536 13.353
14.392 14.157 13.949 13.739 13.539 13.350
13.205 13.055 12.920 12.795 12.585 12.590 12.507 12.439 12.385 12.348 12.325 12.318
13.192 13.038 12.897 12.758 12.554 12.554 12.469 12.398 12.343 12.304 12.280 12.272
13.181 13.022 12.875 12.743 12.625 12.621
13.173 13.008 12.867 12.720 12.598 12.491 12.400 12.325 12.2 57 12.225 1 2.2 00 12.191
12.433 12.360 12.304 12.263 12.238 12.230
Nuc(e(ir Data Tables, Vol. I I , No. 7, I 973
H. LISKIEN AND A. PAULSEN
T(4«)*He. ENERGYIMEV)
1.600
a{e lab), £„((? lab): Recommended Values 1.7C0
1.800
1.900
Z.OOO
2.100
2.200
2.300
CENTER-OP-MASS INPUT VALUES EUR THE REACTIUN T ( U , N ) H E 4 U-SIGMA-0(MR/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 6 ANGLE(DEGREE)
13.800 0.858 0.116 0.016 0.000 0.007 0.001 0.002
13.300 12.900 12.600 12.300 12.100 11.900 U.HOO 0.835 O.Sl* 0.793 0.771 0.749 0.730 0.707 0.120 0.122 0.124 0.127 0.129 0-130 9,-\li 0.029 0.042 0.054 0.067 0.080 0.091 0.104 0.001 0.002 0.004 0.005 0.007 0.009 0.012 0.008 0.009 O.OU 0.012 0.013 0.014 0.016 0.004 0.007 0.010 0.013 0.016 0.019 0.022 0.003 0.004 0.004 0.005 0.006 0.007 0.007 DIFFERENTIAL CRUSS-SECTIONS (MB/SR) IN THE LABURATURY SYSTEM
0,0 5,0 10,0 15,0 20t0 25,0 30.0
0.165E 0.164E 0.163E 0.162E U.160E 0.158E 0.155E
02 02 02 02 02 02 02
0.160E 0.159E 0.158E 0.156E a.l54E 0.151E 0.148E
02 02 02 02 02 02 02
0.156E 0.155E 0.154E O.lSlt 0.149E 0.145E 0.142E
02 02 02 02 02 02 02
0.153E 0.152E 0.150E 0.148E 0.145E 0.141E 0.137E
02 02 02 02 02 02 02
0.1506 0.149E 0.147E 0.144E 0.141E 0.137E 0.132E
02 02 02 02 02 02 02
0.14eE 0.147E 0.146E 0.142E 0.138E 0.133E 0.129E
02 02 02 02 02 02 02
0.146E 0.145E 0.143E 0.139E 0.135E 0.130E 0.125E
02 02 02 02 02 02 02
0.145E 0.145E 0.142E 0.138E 0.133E 0.128E 0.122E
02 02 02 02 02 02 02
35.0 40.0 45,0 50,0 55.0 60.0
0.152E 0.149E 0.146E 0.143E 0.139E 0.136E
02 02 02 02 02 02
0.145E 0.141E 0.138E 0.135E 0.131E 0.128E
02 02 02 02 02 02
0.138E 0.135E 0.131E O.ISSE 0.124E 0.121E
02 02 02 02 02 02
0.133E 0.129E 0.126E 0.122E 0.119E 0.115E
02 02 02 02 02 02
0.128E 0.124E 0.120E 0.117E 0.113E 0.109E
02 02 02 02 02 02
0.124E 0.120E 0.116E 0.U2E 0.108E 0.104E
02 02 02 02 02 02
0.120E 0.116E 0.112E 0.108E 0.104E O.IOOE
02 02 02 02 02 02
0.117E 0.112E 0.108E 0.104E O.IOOE 0.964E
02 02 02 02 02 01
65.0 70,0 75.0 80.0 85.0 90l0
0.132E 0.129E 0.125E 0.122E 0.118E 0,115E
02 02 02 02 02 02
0.124E 0,121E 0.n7£ 0.113E O.UOE 0.107E
02 02 02 02 02 02
0.H7E 0.H4E O.llOE 0.107E 0.103E 0,100E
02 02 02 02 02 02
O.lllE 0 . 108E 0.104E O.lOlE 0.978E 0.946E
02 02 02 02 01 01
0.106E 0.102E 0.988E 0.952E 0.919E 0.888E
02 02 01 01 01 01
O.IOIE 0.974E 0.937E 0.902E q.869E 0.838E
02 01 01 01 01 01
0.968E 0.930E 0.a93E 0.857E 0.e24E 0.795E
01 01 01 01 01 01
0.926E O.BSSE 0.851E 0.815E 0.783E 0.754E
01 01 01 01 01 01
95.0 100.0 105.0 110.0 115.0 120.0
0.112E 0.109E 0.106E 0.103E O.IOOE 0,985E
02 02 02 02 02 01
0.104E O.IOIE C.985E 0,960E 0.937E 0.916E
02 02 01 01 01 01
0.974E 0.947E 0.922E 0.899E 0.879E 0,861E
01 01 01 01 01 01
0.918E 0.e92E 0.868E 0.848E 0.830E 0.813E
01 01 01 01 01 01
0.860E 0.836E 0.814E 0.796E 0.780E 0.766E
01 01 01 01 01 01
0.812E 0.789E 0.769E 0.753E 0.739E 0.728E
01 01 01 01 01 01
0.769E 0.748E 0.730E 0.716E 0.704E 0.694E
01 01 01 01 01 01
0.729E 0.709E 0.693E 0.680E 0.670E 0.662E
01 01 01 01 01 01
125.0 130.0 135.0 140.0 145,0 150,0
0.964E 0.944E 0.927E 0.913E 0.900E 0,890E
01 01 01 01 01 01
0.898E 0.881E 0.fl66E 0.863E 0.842E 0,834E
01 01 01 01 01 01
0.844E 0.830E 0.817E 0.806E 0,797E 0,789E
01 01 01 01 01 01
165,0 160.0 165.0 170,0 175.0 180,0
0,883E 0.876E 0.872E 0.869E 0.867E 0.867E
01 01 01 01 Oi 01
0.827E 0.821E O.SieE 0.815E 0.814E 0.813E
01 01 01 01 01 01
0,783E 0.779E 0.775E 0.773E 0.772E 0,771E
01 01 01 01 01 01
0.746E 0.742E 0.739E 0.737E 0.735E 0.735E
01 01 01 01 01 01
0.709E 0.706E 0.703E 0.701E 0.700E 0.700E
01 01 01 01 01 01
0.680E 0.677E 0.674E 0.672E 0.671E 0.671E
01 01 01 01 01 01
0.653E 0.650E 0.648E 0.646E 0.6456 0.645E
01 01 01 01 01 01
0.629E 0.627E 0.624E 0.623E O.iZZi 0.622E
01 01 01 01 01 01
:NtKtYi«EV)
2.400
2.500
2.600
2.700
2.800
2.900
3.000
3.500
CENTER-OF-MASS INPUT VALUES FOR THE REACTION T { U , N ) H E 4 0-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 6
11.800 0,688 0,132 0.115 0.015 0.017 0.025 0.008
11.800 0,666 0.133 0.127 0.019 0.018 0.028 0.009
ANGLE(DEGRE6)
11.900 0.646 0.133 0.137 0,023 0,020 0.031 0.010
12.000 0.627 0.132 0.148 0.027 0.021 0.034 0.011
12.100 0.608 0.131 0.159 0.031 0.022 0.037 0.012
DIFFERENTIAL CROSS-SECTIONS (MB/SR)
12.200 0.589 0.130 0.169 0.034 0.024 0.040 0.014
12.300 0.571 0.130 0.180 0.037 0.025 0.042 0.015
13.800 0.490 0.126 0.223 0.051 0.031 0.057 0.022
IN THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.146E 0.145E 0.142E 0.138E 0,132E 0.127E 0.121E
02 02 02 02 02 02 02
0.147E 0.145E 0.142E 0.138E 0.132E 0.125E 0.119E
02 02 02 02 02 02 02
0.14eE 0.147E 0.144E 0.138E 0.132E 0.125E 0.118E
02 02 02 02 02 02 02
0.150E 0.149E 0.145E 0.139E 0.132E 0.125E 0.117E
02 02 02 02 02 02 02
0.152E 0.151E 0.146E 0.140E 0.132E 0.124E 0.115E
02 02 02 02 02 02 02
0.154E 0.152E 0.148E 0.141E 0.133E 0.124E 0.115E
02 02 02 02 02 02 02
0.156E 0.154E 0.149E 0.142E 0.133E 0.124E 0.114E
02 02 02 02 02 02 02
0.178E 0.175E 0.168E 0.157E 0.144E 0.131E 0.118E
02 02 02 02 02 02 02
35,0 40.0 45.0 50.0 55.0 60.0
0.115E O.llOE 0.105E O.IOIE 0.976E 0.937E
02 02 02 02 01 01
0,113E 0.107E 0.103E 0.986E 0.945E 0.905E
02 02 02 01 01 01
O.lllE 0.106E O.IOIE 0.966E 0.923E 0.8e2E
02 02 02 01 01 01
O.llOE 0.104E 0.993E 0.945E 0.902E 0.850E
02 02 01 01 01 01
0.109E 0.102E 0.974E 0.925E 0.880E 0.e37E
02 02 01 01 01 01
0.107E O.IOIE 0.953E 0.903E 0.858E 0.815E
02 02 01 01 01 01
0.106E 0.996E 0.936E 0.884E 0.8376 0.792E
02 01 01 01 01 01
0.107E 0.986E 0.912E 0.851E 0.797E 0.745E
02 01 01 01 01 01
65.0 70,0 75.0 80.0 85.0 90.0
0.89eE 0.859E 0,821E 0.786E 0.753E 0,726E
01 01 01 01 01 01
0.865E 0.825E 0,787E 0.752E 0.719E 0,692E
01 01 01 01 01 01
0.842E 0.eo2E 0.764E 0.728E 0.696E 0.669E
01 01 01 01 01 01
0.819E 0.778E 0.739E 0.703E 0.672E 0.645E
01 01 01 01 01 01
0.795E 0.754E 0.715E 0.678E 0.647E 0.622E
01 01 01 01 01 01
0.772E 0.730E 0.690E 0.654E 0.623E 0.598E
01 01 01 01 01 01
0.7496 0.7066 0.666E 0.6296 0.598E 0.5746
01 01 01 01 01 01
0.695E 0.645E 0.599E 0.559E 0.527E 0.505E
01 01 01 01 01 01
95.0 100.0 105.0 llp.O 115.0 120.0
0.701E 0.682E 0.668E 0.656E 0.648E 0.642E
01 01 01 01 01 01
0.669E 0.652E 0,539E 0.630E 0.623E 0.619E
01 01 01 01 01 01
0.647E 0.631E 0.619E 0.611E 0.605E 0.603E
01 01 01 01 01 01
0.625E 0.610E 0.600E 0.594E 0.591E 0.590E
01 01 01 01 01 01
0.602E 0.589E 0.581E 0.677E 0.576E 0.576E
01 01 01 01 01 01
0.580E 0.568E 0.562E 0.559E 0.560E 0.561E
01 01 01 01 01 01
0.5576 0.547E 0.5436 0.542E 0.544E 0.547E
01 01 01 01 01 01
0.493E 0.490E 0.494E 0.5O2E 0.513E 0,524£
01 01 01 01 01 01
125.0 130.0 135.0 140.0 145.0 150.0
0.637E 0.632E 0.629E 0.625E 0.621E 0.618E
01 01 01 01 01 01
0 . 6 1 5 E 01 0 . 6 0 1 E 01 0 . 5 8 9 E 01 0 . 5 7 6 E 01 0 . 5 6 3 E 01 0 . 5 5 0 E 01 0 . 5 3 4 E 0 . 6 1 2 E 01 0 . 5 9 9 E 01 " ' " " ' ~' " " " -' " ' ' -" " ' -" " 0.6096 -- - 0.606E 0.603E 0.6006
01 "•
155.0 160.0 165.0 270.0 175,0 180.0
0.616E 0.612E 0,610E 0.609E 0.608E 0,607E
01 01 01 01 01 01
0.697E 0.5956 0.5926 0.5916 0,5906 0,5906
01 01 01 01 01 01
Nuclear Data Tables, Vol. 11, No. 7, 1973
01 01 01 01 01 01
0.586E 0.5646 0.5826 0.580E 0.579E 0,579E
01 01 01 01 01 01
0.677E 0.575E 0.673E 0.571E 0.5706 0.570E
612
01 01 01 01 01 01
0.668E 0.566E 0.564E 0.562E 0.561E 0.561E
01 01 01 01 01 01
0.559E 0.557E 0.556E 0.555E 0.554E 0.554E
01 01 01 01 01 01
0.551E 0.549E 0.548E 0.547E 0.646E 0.646E
01 01 01 01 01 01
0.551E 0.551E 0.550E 0.549E 0.5496 0.549E
NEUTRON PRODUCTION CROSS SECTIONS
T(4/t)4He. ENERGY(MEV)
1.600
o{0 lab), £^{0 lab): Recommended Values 1.700
1.800
1.900
2.000
INPUT VALUES FDR THE REACTION REST ENERGY IIV MEV FUR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET T 2 = 2 8 0 8 . 9 6 1 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEOS 7 4 = 3 7 2 7 . 4 1 8
ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 36.0 40.0 45.0 50.0 55.0 60.0 55.0 70.0 75.0 80.0 85,0 90.0 95.0 100.0 105.0 110,0 115,0 120.0 125,0 130,0 136.0 140.0 145.0 150.0 155,0 150,0 165,0 170,0 175.0 180,0
ENERGY IMEV)
ENERGY OF PARTICLE-3
(MEV)
17.837 17.824 17.785 17.720 17.530 17.617 17.381 17.225 17.049 16,855 16,647 15.426 15.194 15.953 15,706 r5.455 15.202 14.950 14.700 14.454 14.215 13,983 13.760 13.547 13.346 13.156 12.984 12,824 12.679 12,550 12.437 12,341 12,262 12.201 12,156 12.130 12.121
17.980 17.967 17,926 17.859 17.767 17.649 17.509 17,347 17,165 15.966 16,749 15.521 15.281 16.032 15.777 15.518 15.258 14.998 14.740 14.487 14,240 14.001 13.772 13.663 13.347 13.153 12.974 12,810 12.561 12.529 12.413 12.315 12.234 12.171 12,125 12,098 12.089
18.122 18.108 18.066 17.997 17.901 17.780 17.634 17.467 17.279 17.073 16.850 16.614 16.357 16.111 15.848 15.581 15.313 15.045 14.780 14.519 14.266 14.020 13.784 13.660 13.348 13.150 12.966 12.798 12.645 12.510 12.391 12.291 12.208 12.143 12.097 12.069 12.059
18.262 18.247 IB.204 18.132 18.033 17.908 17.759 17.686 17.392 17.179 16.950 16.707 15.452 16.188 15.918 15.543 16.367 15.092 14.820 14.562 14.292 14.040 13.798 13.558 13.351 13.147 12.959 12.787 12.531 12.492 12.371 12.258 12.183 12.117 12.070 12.041 12.032
2.400
2,500
2,600
2.700
2.800
INPUT VALUES FOR THE REACTION REST ENERGY IN MEV FOR PROJECTILE T l = 1 8 7 5 . 5 3 3 TARGET T 2 = 2 8 0 8 . 9 5 1 PRODUCT T3= 9 3 9 . 6 7 6 RESIDUAL NUCLEUS
0.0 5.0 10.0 15.0 20.0 25,0 30.0 36.0 40.0 45.0 50.0 56.0 50,0 65.0 70.0 75.0 80.0 85.0 90.0 95,0 100,0 105.0 110.0 115.0 120,0 125.0 130.0 135.0 140.0 146.0 150.0 165,0 160.0 166.0 170.0 175.0 180.0
ENERGY OF PARTICLE-3
18.804 18,788 18,740 18.650 18.649 18.408 18.241 18.047 17,831 17.593 17.337 17.056 15.783 16.489 16.189 15.885 15,580 15.276 14.976 14,682 14,395 14.119 13,855 13.603 13,355 13.145 12.940 12,753 12.584 12.434 12.303 12,191 12.100 12.028 11.977 11.946 .11.936
18.937 16,920 16,870 16.788 18.674 18.530 16.358 18.160 17.938 17.694 17,432 17.155 15.864 16.564 16.257 15.946 15,634 15.323 15.015 14,715 14,423 14.141 13.871 13.614 13,373 13.147 12.938 12.748 12.575 12,422 12.289 12.175 12.082 12.009 11.957 11.925 11.915
19.068 19,051 19,000 18.915 18.799 18.661 16,475 18.272 18.044 17.795 17,527 17,242 15.945 16.638 16.324 15.005 15,687 15.369 15.056 14,749 14.450 14.152 13.867 13.626 13.379 13.149 12.937 12.743 12.567 12,412 12.276 12.160 12.066 11.992 11.939 11.907 11.896
2.300
Q-VALUE
IN HE« U=
17.590
18.399 18.385 18.340 18.256 18.164 18.036 17.881 17.703 17.504 17.285 17.049 16.799 16.537 15.255 15.987 15.705 15.422 15.139 14.859 14.585 14.318 14.050 13.812 13.575 13.354 13.145 12.953 12.777 12.618 12.476 12.352 12.247 12.150 12.093 12.044 12.015 12.005
lb.536 18.520 IS.475 18.399 18.294 16.161 18.003 17.819 17.614 17.389 17.147 16.889 15.620 16.341 16.056 15.767 15.476 15.185 14.899 14.518 14.344 14.080 13.826 13.585 13.358 13.146 12.949 12.768 12.605 12.461 12.335 12.227 12.139 12.070 12.020 11.991 11.981
18.671 18.655 18.608 18.530 18.422 18.286 18.123 17.934 17.724 17.492 17.243 16.979 16.703 15.417 16.124 15.828 15.530 15.233 14,939 14,651 14.371 14.101 13.841 13.595 13.363 13.146 12.945 12.761 12.595 12.447 12.318 12.209 12.119 12.048 11.998 11.958 11.958
2.900
3.000
3.500
TID,NIHE4 Q-VALUE
IN MEV U=
17.5
T4=3727.41B (MEV)
19.198 19.180 19.128 19.042 18.922 18.771 18.591 18.383 18.160 17.695 17.520 17.329 17.025 16.711 16,390 16.066 15.740 16.415 15,095 14.782 14.478 14.165 13.904 13.537 13.367 13.153 12.936 12.739 12.560 12.402 12.254 12.147 12.050 11.975 11.921 11.889 11.878
613
2.200
IN THE LABORATORY SYSTEM
17.691 17.679 17.641 17.578 17.492 17,383 17.252 17.101 15.931 15,744 16.543 15.330 16.105 15.873 16,634 15.T91 15.147 14.903 14.660 14.422 14,190 13,955 13,748 13.542 13.347 13.164 12,994 12,839 12.698 12,573 12.463 12,369 12,293 12,232 12,189 12,164 12,155
ANGLE(DEGREE)
2.100 TID,N)HEA
IN THE LABORATORY
19.327 19.309 19.255 19.157 19.045 18.890 18.705 18.493 18.254 17.994 17.713 17.416 17.105 16.784 15.457 16.125 15.792 15.461 15.135 14.815 14.506 14.207 13.921 13.650 13.394 13.156 12.936 12.735 12.554 12.393 12.253 12.134 12.036 11.959 11.905 11.872 11.851
19.465 19.435 19.381 19.291 19.156 19.008 18.819 18.602 18.366 18.092 17.805 17.502 17.184 15.857 16.522 16.184 15.845 15.508 15.175 14.850 14.534 14.229 13.939 13.662 13.403 13.161 12.937 12.733 12.549 12.385 12.243 12.122 12.022 11.945 11.889 11.856 11.845
SYSTEM
19.581 19.553 19.507 19.414 19.287 19.126 18.932 18.710 18.452 18.189 17.897 17.587 17.263 16.929 16.588 16.243 15.897 15.554 16.215 14.884 14.562 14.252 13.956 13.676 13.412 13.165 12.938 12.731 12.544 12.378 12.233 12.110 12.010 11.931 11.875 11.841 11.830
20.204 20.183 20.121 20.019 19.878 19.700 19.487 19.242 18.968 18.568 18.345 18.006 17.551 17.285 16.911 15.534 16.157 16.782 15.414 15.054 14.705 14.370 14.050 13.747 13.452 13.197 12.953 12.730 12.530 12.352 12.197 12.066 11.968 11.874 11.814 11.778 11.756
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(4/i)*He.
a(d lab), £„(0 lab): Recommended Values 4.500
ENERGY(MEV)
5.000
7.000
6.500
7.500
CENTER-OF-MASS INPUT VALUES FUR THE REACTION T(U,N)HE'4 U-SIGMA-0(MB/SR)
15.20C1 0.426 0.1231 0.25i 0 . 0 5 £1 0.037 0.071 0 . 0 2 ' :i O.OOC O.OOC1
> )
ANGLEIDEGREEI 0.0 5.0 10.0 15.0 20.0 25.0 30,0
)
18.20C1 0 . 3 6 ' ;} O.llS 0.264 0.064 0.051 0.103 0.044 0.000 O.OOC1
)
02 02 02 02 02 02 02
0.226E 0.2216 0.208E 0.189E 0.1676 0.145E 0.125E
02 02 02 02 02 02 02
0.244E 0.2366 0.223E 0.200E 0.174E 0.1486 0.126E
02 02 02 02 02 02 02
0.254E 0.247E 0.229E 0.202E 0.173E 0.144E 0.1206
02 0.2596 0 2 0.251E 0 2 0.2316 02 0.201E 0 2 0.168E 0 2 0.137E 02 0.1126
02 02 02 02 02 02 02
0.2596 0.250E 0.227E 0.194E 0.158E 0.126E O.IOIE
02 02 02 02 02 02 02
35.0 40.0 45.0 60.0 65.0 60.0
0.1076 0.967E 0.883E 0.8156 0.756E 0.699E
02 01 01 01 01 01
0.109E 0.978E 0.890E 0.821E 0.761E 0.701E
02 01 01 01 01 01
0.108E 0.9646 0.880E 0.8206 0.7666 0.7096
02 01 01 01 01 01
0.1Q3E 0.920E 0.8526 0.8076 0.7676 0.7176
0 2 0.9586 01 0.8606 0 1 0.811E 01 0.785E 0 1 0.767E 0 1 0.716E
01 01 01 01 01 01
0.858E 0.780E 0.755E 0.7506 0.7386 0.7066
01 01 01 01 01 01
65. 70, 75. 80. 85.
0.642E 0.565E 0.533E 0.488E 0.454E 0.434E
01 01 01 01 01 01
0.6386 0.5736 0.5116 0.4596 0.4216 0.4016
01 01 01 01 01 01
0.644E 0.575E 0.507E 0.4486 0.405E 0.383E
0 1 0.6646 01 0.6566 0 1 0 . 5 e i E 0 1 0.6836 0 1 0.509E 0 1 0.5086 0 1 0.445E 0 1 0.4406 0 1 0.399E 0 1 0.3906 0 1 0.373E 0 1 0 . 3 6 1 6
0 1 0.650E 0 1 0.578E 0 1 0.500E 0 1 0.429E 0 1 0.374E 0 1 0.3416
01 01 01 01 01 01
95.0 100.0 105.0 110.0 115.0 120.0 1?5. 130 135. 140 145. 150
0.426E 0.431E 0.443E 0.461E 0.481E 0.500E
01 01 01 01 01 01
0.3976 0.407E 0.4276 0.4536 0.4806 0.504E
01 01 01 01 01 01
0.3806 0.393E 0.4176 0.4476 0.478E 0.505E
0 1 0.368E 0 1 0.353E 0 1 0 1 0.381E 0 1 0.364E 0 1 0 1 0.406E 0 1 0.387E 0 1 0 1 0.436E 0 1 0.4176 0 1 0 1 0.467E 0 1 0.446E 0 1 0 1 0.495E 0 1 0.473E 01
0.33OE 0.338E 0.3596 0.386E 0.415E 0.439E
01 01 01 01 01 01
0.516E 0.529E 0.538E 0.5456 0.5496 0.551E
01 01 01 01 01 01
0.5256 0.542E 0.553E 0.5606 0.5646 0.5666
01 01 01 01 01 01
0.528E 0.544E 0.555E 0.561E 0.564E 0.565E
0 1 0.5166 0 1 0.492E 0 1 0.5316 0 1 0.5066 0 1 0.5406 01 0.513E 0 1 0 . 5 4 4 6 0 1 0.515E 0 1 0.5446 01 0.5156 0 1 0.5426 0 1 0.5136
0.4b9E 0.4716 0.478E 0.4826 0.482E 0.483E
01 01 01 01 01 01
0.552E 0.552E 0.553E 0.5536 0.5536 0.5536
01 01 01 01 01 01
0.5676 0.5686 0.5686 0.5686 0.5686 0.5686
01 0.5656 01 0.5646 01 0.5636 01 0.5626 0 1 0.5626 01 0.6626
01 0.4836 0 1 0.4846 0 1 0.4866 0 1 0.487E 0 1 0.4896 0 1 0.489E
01 01 01 01 01 01
155.0 160.0 165.0 170.0 175.0 180.0 ENERGY(MEV)
e.ooo
01 01 01 01 01 01
9.000
8.500
01 01 01 01 01 01
0 1 0.511E 01 0.6106 0 1 0.509E 01 0.509E 0 1 0.609E 01 0.5096
0.5396 0.537E 0.5356 0.5336 0.5326 0.5326
0.2616 0.2426 0.2176 0.1826 0.1456 0.112E 0.889E 0.7506 0.6966 0.6926 0.704E 0.704E 0.678E 0.6256 0.5546 0.4766 0.404E 0.348E 0.3126 0.299E 0.3046 0.323E 0.349E 0.377E 0.4016 0.4206 0.4336 0.441E 0 . 4 4 5E 0.448E 0.4506 0.4536 0.4566 0.460E 0.4646 0.466E 0.4676
0 2 0 .. 2 4 5 6 0 2 0 2 0 . .2356 0 2 0 2 0 . .2096 0 2 0 2 0 . .172E 0 2 0 2 0 .. 1 3 3 6 0 2 0 2 0 . .1006 0 2 0 1 0 .. 7 7 8 6 0 1 0 1 0 .. 6 5 9 6 0 1 0 . .6256 0 1 0 .. 6 4 2 6 0 1 0 , .6696 0 1 0 . .677E 0 1 0 . .655E
01 01 01 01 01 01
0 1 0 . .604E 0 1 0 ,. 5 3 2 6 0 1 0 . .4536 0 1 0 .. 3 8 1 6 0 1 0 . .3236 01 0 .2866
01 01 01 01 01 01
0 1 0 .. 2 7 1 6 0 1 0 .275E 0 1 0 .. 2 9 2 E 0 1 0 .3166 0 1 0 .3436 0 1 0 .3676
01 01 01 01 01 01
0 1 0 ..3876 0 1 01 0 .4006 0 1 0 1 0 .410E 0 1 0 1 0 .416E 0 1 0 1 0 .4216 0 1 01 0 .4266 0 1 01 0 .4326 0 1 0 1 0 .438E 0 1 0 1 0.. 4 4 4 E 0 1 0 1 0 .450E 0 1 0 1 0 .454E 0 1 0 1 0 .455E 0 1
10.000
9.500
C6NT6R--OF--MASS INPUT VALUES FOR THE REACTION T(1J,N1HE4
0-SIGMA-0(MB/SR)
ANGLE(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95 .0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175 .0 180.0
Nuclear Data Tables, Vol. 1 1, No. 7, 1973
16.900 0.280 0.080 0.184 0.013 0.124 0.183 0.10] 0.021 0.014
16.000 0.263 0.06! 0 . 1 7 :1 -0.010 0.13E i 0.194 0.124 0 . 0 3 :1 0.02C
16.400 0.271 0.072 0.17£ i 0.001 0.132 0.190 0.112 0.027 0.017
15.800 0.254 0.057 0 . 17C -0.01'; 0.14; 0.197 0 . 136 0.04C 1 0.023
0.358E 0.3736 0.383E 0.392E 0.399E 0.406E 0.4156 0.4246 0.433E 0.4416 0.4466 0.448E
16.700 0.246 0.04fi 0.167 -0.027 0.143 0.198 0.151 0.047 0 . 0 2 1r
)) ) )
)
DIFF6RENTIAL CROSS-:SECTIONS; 0.240E 0.230E 0.2016 0.163E 0.122E 0.897E 0.6796 0.5786 0.5676 0.6026 0.640E 0.655E 0.635E 0.583E 0.510E 0.430E 0.356E 0.298E 0.261E 0.2456 0.248E 0.264E 0.2886 0.3146 0.338E
)
)
(
0.198E 0.1956 0.185E 0.171E 0.154E 0.137E 0.121E
90.
)
)
)
18.OOC 18.90C1 17,400 18.70C 18.700 0.291 0.302 0.314 0.32Ei 0.343 0.087 0 . 0 94 0.101 0.107 0.111 0.192 0.202 0.214 0.23] 0.246 i 1 0.026 0.039 0.050 0.059 0.063 0.11
(MB/SRl 1IN THE LABORATORY SYSTEM
02 02 02 02 02 01 01
0.2356 0.224E 0.1946 0.1546 0.112E 0.798E 0.591E
02 0.2316 02 0.2196 02 0.1886 02 0.146E 02 0.1046 0 1 0.713E 0 1 0.519E
0 2 0.230E 0 2 0.230E 0 2 0.217E 02 0.216E 0 2 0.184E 0 2 0 . 1 8 1 6 02 0.140E 0 2 0.1356 0 2 0.9706 0 1 0.900E 0 1 0.638E 0 1 0.5676 0 1 0.454E 0 1 0 . 3 9 4 6
02 02 02 02 01 01 01
01 01 01 01 01 01
0.510E 0.518E 0.5686 0,6166 0.6346 0.6146
0 1 0.455E 0 1 0.4826 01 0.5456 0 1 0.600E 0 1 0.619E 01 0.5966
0 1 0.4086 01 0.4526 0 1 0.5286 0 1 0.587E 0 1 0.606E 0 1 0.679E
0 1 0.3676 01 0.4316 0 1 0.5196 01 0.5826 0 1 0.5986 01 0.5656
01 01 01 01 01 01
01 01 01 01 01 01
0.560E 0.4866 0.406E 0.333E 0.276E 0.2396
01 01 01 01 01 01
0.518E 0.440E 0.361E 0.291E 0,239E 0.207E
0 1 0.499E 0 1 0.4186 01 0.3396 0 1 0.272E 01 0.223E 0 1 0.195E
01 01 01 01 01 01
01 01 01 01 01 01
0.224E 0.2266 0.242E 0.2656 0.2916 0.315E
0 1 0.208E 0 1 0.1946 0 1 0.185E 01 0.2106 0 1 0.1986 0 1 0.191E 0 1 0.226E 0 1 0.2136 0 1 0.207E 0 1 0.248E 0 1 0.2365 0 1 0.229E 0 1 0.272E 0 1 0.2596 0 1 0.251E 0 1 0 . 2 9 5 6 0 1 0 . 2 8 IE 0 1 0 . 2 7 3 E
01 01 01 01 01 01
01 01 01 01 01 01 01 01 01 01 01 01
0.335E 0.3506 0.3626 0.372E 0.382E 0.392E 0.4036 0.4156 0.4266 0.4366 0.442E 0»444E
01 01 01 01 01 01 01 01 01 01 01 01
01 01 01 01 01 01 01 01 01 01 01 01
0.5396 0.463E 0.383E 0.3126 0.2576 0.2226
0.315E 0.3306 0.3436 0.355E 0.3676 0.380E 0.394E 0.4096 0.4236 0.435E 0.442E 0.445E
01 01 01 01 01 01
01 01 01 01 01 01 01 01 01 01 01 01
0.300E 0.316E 0.3306 0.344E 0.3586 0.373E 0.3906 0.4086 0.424E 0.437E 0.446E 0.449E
614
01 01 01 01 01 01 01 01 01 01 01 01
0.2916 0.3066 0.3206 0.335E 0.351E 0.369E 0.3896 0.4106 0.4306 0.4456 0.456E 0.4596
NEUTRON PRODUCTION CROSS SECTIONS
T(«tn)*He. ENERGYIBEV)
4.000
a{e lab), EJd lab): Recommended Values
4.500
5.000
5.500
6.000
6.500
7.000
7
INPUT VALUES FOR THE REACTION T(D,M)HE4 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIOUAL NUCLEUS
ANGLE(DEGREE)
0. 5, 10. 15, 20. 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65. 70. 75. 80, 85. 90, 96.0 100.0 106.0 110.0 115.0 120.0 126.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
ENERGY(MEV)
Tl=1875.633 T2=2e08.951 T3= 9 3 9 . 5 7 6 T4=3727.418
ENERGY OF PARTICLE-3
20.810 20.787 20.719 20.607 20.453 20.257 20.024 19.756 19.456 19.129 18.778 18.407 18.021 17.624 17.219 16.811 16.403 15.999 15.603 15.216 14.842 14.483 14.141 13.818 13.615 13.233 12.974 12.738 12.526 12.338 12.175 12.036 11.923 11.834 11.771 11.733 11.720
21.401 21.377 21.303 21.182 21.015 20.804 20.562 20.262 19.939 19.686 19.207 18.808 18.393 17.966 17.531 17.094 15.657 16.225 15.802 16.389 14.991 14.609 14.246 13.903 13.681 13.283 13.009 12.750 12.536 12.338 12.166 12.020 11.900 11.807 11.741 11.701 11.688
8.000
8.500
(MEVI
0-VALUE
IN MEV 0=
IN THE LABORATORY SYSTEM
21.981 21.956 21.876 21.745 21.565 21.339 21.069 20.759 20.412 20.034 19.629 19.202 18.759 18.303 17.840 17.374 16.909 15.450 16.000 15.663 15.141 14.737 14.354 13.992 13.663 13.340 13.052 12.790 12.555 12.347 12.165 12.014 11.889 11.792 11.722 11.580 11.667
22.552 22.523 22.439 22.300 22.109 21.867 21.578 21.247 20.878 20.476 20.046 19.591 19.120 18.635 18.144 17.661 17.169 15.574 16.199 15.738 15.294 14.859 14.465 14.085 13.730 13.402 13.100 12.825 12.581 12.364 12.176 12.015 11.885 11.785 11.713 11.659 11.666
23.114 23.084 22.995 22.847 2 2.644 22.387 2 2.081 21.730 21.338 20.912 20.456 19.976 19.475 18.965 18.447 17.926 17.408 16.897 16.398 16.914 15.447 16.002 14.579 14.182 13.811 13.468 13.154 12.858 12.613 12.387 12.192 12.026 11.891 11.786 11.711 11.565 11.651
9.000
9.600
10.000
23.570 23.638 23.544 23.387 23.172 22.901 22.577 22.205 21.793 21.342 20.861 20.365 19.830 19.292 18.745 18.199 17.555 17.120 16.597 16.090 15.502 15.137 14.595 14.282 13.895 13.539 13.212 12.915 12.560 12.416 12.214 12.042 11.902 11.794 11.715 11.569 11.654
24.220 24.186 24.087 23.922 23.595 23.409 23.068 22.578 22.243 21.769 21.263 20.731 20.180 19.615 19.044 18.471 17.902 17.342 16.796 15.256 16.768 15.274 14.816 14.386 13.983 13.513 13.274 12.967 12.692 12.460 12.241 12.064 11.919 11.807 11.727 11.679 11.653
24.754 24.729 24.624 24.451 24.213 23.913 23.656 23.145 22.688 22.192 21.552 21.106 20.627 19.937 19.339 18.741 18.147 17.564 16.994 16.444 15.916 16.412 14.935 14.489 14.074 13.590 13.340 13.022 12.739 12.489 12.273 12.090 11.941 11.825 11.743 11.593 11.677
INPUT VALUES FOR THE REACTION T ( D , N ) H e 4 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 66.0 60.0 56.0 70.0 75.0 80.0 85.0 90.0 95 100. 105 110. 115. 120. 125.0 130.0 135.0 140.0 145.0 150.0 166.0 150.0 156.0 170.0 175.0 180.0
ENERGY OF PARTlCLE-3
25.305 25.268 25.158 24.976 24.726 24.411 24.035 23.605 23.127 22.607 22.052 21.470 20.866 20.250 19.627 19.003 18.385 17.778 17.185 16.615 16.067 15.545 15.053 14.591 14.152 13.757 13.406 13.078 12.787 12.530 12.307 12.120 11.967 11.848 11.764 11.713 11.596
25.841 25.802 25.687 25.497 25.236 24.905 24.514 24.065 23.556 23.023 22.445 21.838 21.209 20.567 19.919 19.271 18.529 17.998 17.385 16.793 15.225 16.686 15.177 14.700 14.257 13.849 13.475 13.140 12.840 12.575 12.347 12.154 11.997 11.875 11.788 11.735 11.719
26.373 26.333 26.213 26.015 25.742 25.399 24.990 24.522 24.002 23.437 22.835 22.203 21.550 20.883 20.210 19.537 18.872 18.219 17.684 15.971 16.384 15.827 15.302 14.810 14.364 13.933 13.550 13.204 12.895 12.524 12.389 12.192 12.031 11.905 11.815 11.763 11.745
Tl=1875.633 T2=280B.951 T3= 9 3 9 . 5 7 6 74=3727.418 (MEV)
25.902 25.850 25.735 25.529 25.245 25.888 25.463 24.976 24.436 23.848 23.223 22.567 21.889 21.198 20.600 19.803 19.114 18.4 39 17.782 17.149 15.544 15.959 15.428 14.922 14.452 14.020 13.626 13.271 12.954 12.675 12.435 12.232 12.067 11.939 11.848 11.793 11.775
615
-VALUE
IN MEV 0=
17.590
I N THE LABORATORY SYSTEM
27.428 27.384 27.254 27.040 25.745 26.374 25.933 25.428 24.867 24.268 23.509 22.929 22.227 21.511 20.789 20.058 19.355 18.568 17.981 17.328 15.704 16.112 15.656 15.034 14.662 14.108 13.704 13.339 13.015 12.729 12.483 12.275 12.106 11.975 11.882 11.826 11.808
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
APPENDIX. Program for Calculation of Laboratory a's from cm. Values C C C C C C C C C C C C C C C C C C C C C C C C C C C
* THIS PROGRAM "EDIT" CALCULATES DIFFERENTIAL CROSS SECTIONS IN THE * LABORATORY SYSTEM FROM CENTER-OF-MASS INPUT DATA. * INPUT DATA NEEDED: * l.CARD: REACTION-NAMEf REST ENERGY IN MEV FOR PROJECTILE, TARGET, * PRODUCT AND RESIDUAL NUCLEUS, 0-VALUE, MARK, MODE * F0RMAT(5A4,5F10.3,2I5) * MARK=0, LABORATORY ENERGIES ARE NOT CALCULATED * MARK=1, LABORATORY ENERGIES ARE CALCULATED * MODE=0, INPUT VALUES ARE TOTAL CROSS SECTIONS AND * COEFFICIENTS NORMALIZED TO A0=1 * M0DE=1, INPUT VALUES ARE 0-DEGREE DIFFERENTIAL CROSS * SECTIONS AND COEFFICIENTS NORMALIZED TO SUM=1 * MODE=-l, END OF ALL CALCULATIONS * 2.CARD: INPUT ENERGY IN MEV, TOTAL CROSS SECTION IN MB OR 0-DEGREE * DIFFERENTIAL CROSS SECTION IN MB/SR, NUMBER OF LEGENDRE * COEFFICIENTS FOR THE ANGULAR DISTRIBUTION; * F0RMAT(5X,2F10.6,I5) « 3.CARD: INPUT ENERGY IN MEV, NORMALIZED COEFFICIENTS AO UP TO A5; * F0RMAT(5X,7F10.6) « IF THERE ARE MORE THAN 6 COEFFICIENTS, * 4.CARD: INPUT ENERGY IN MEV, NORMALIZED COEFFICIENTS A6 UP TO A H ; * F0RMAT(5X,7F10.6) * 5. : REPEAT CARD 2,3 (AND 4» FOR EVERY ENERGY TO BE TREATED; * 6.CARD: BLANK; * 7. : REPEAT CARD 1 TO 6 FOR EVERY REACTION TO BE TREATED; * CALCULATIONS ARE PERFORMED FOR EMISSION ANGLES BETWEEN 0 AND 180 * DEGREE IN STEPS OF 5 DEGREE. (LISKIEN DEC.72) DIMENSION TITLE(5),E(8),SIGMA(8),MAX(fi),A(8,12),ENERG(8,37) DIMENSION G02(8),W(8),SIG(8),B2(8),B3(8),Z(8),P(12)
800 F 0 R M A T { 5 A 4 , 5 F 1 0 , 3 , 2 I 5 ) 801 F 0 R M A T ( 5 X , 2 F 1 0 . 6 , I 5 ) 802 F 0 R M A T ( 5 X , 7 F 1 0 . 6 / 1 5 X , 6 F 1 0 . 6 ) 803 FORMATCl ENERGY(MEV) •,8F10.3) 804 FORMAT(IHO)
904 F0RMAT(20X,'REST ENERGY IN MEV FOR PROJECTILE Tl=«,F8.3,lOX, /'0-VALUE IN MEV 0=',F8.3/47X,'TARGET T2=',F8.3/46X,'PRODUCT T3=', /F8.3/37X,'RESIDUAL NUCLEUS T4=«,F8.3> 805 F0RMAT(30X,'CENTER-OF-MASS INPUT VALUES FOR THE REACTION ',5A4/) 905 FORMAT(22X,' INPUT VALUES FOR THE REACTION ',5A4/) 806F0RMAT(' SIGMA-T(MB) ',8F10.3) 906 FORMATC D-SIGMA-0(MB/SR)•,8F10.3 )
807 FORMAT(4X,'A " ' , 1 2 , 9 X , 8 F 1 0 . 3 ) 907 F 0 R M A T ( 5 X , ' A ' ,12,9X,8F10.3 ) 808 FORMAT(' ANGLE(DEGREE) ' , 1 3 X , ' D I F F E R E N T I A L CROSS-SECTIONS (MB/SR / ) IN THE LABORATORY SYSTEM' ) 908 FORMAT(' ANGLE(DEGREE) ' , 1 7 X , ' E N E R G Y OF PARTICLE-3 (MEV) IN THE /LABORATORY SYSTEM' ) 809 FORMAT(IH ) 810 F n R M A T ( F 8 . 1 , l l X , 8 E 1 0 . 3 ) 910 F 0 R M A T ( F 8 . 1 , 9 X , 8 F 1 0 . 3 ) 811 F0RMAT(' INPUT CARDS ARE IN DISORDER ' ) 812 FORMATC A-COEFFIClENTS INCORRECTLY NORMALIZED ' ) 813 FORMATC INPUT ENERGY FALLS IN DOUBLE-VALUED REGION ' ) 1000 R E A D ( 5 , 8 0 0 ) T I T L E , T 1 , T 2 , T 3 , T 4 , 0 , M A R K , M O D E IF(M0DE)999,1001,1001 1 0 0 1 NN=0 T12=Tl+T2 T34=T3+T4 T23=T2-T3 TF=-0/T2*(T12-0/2.) TB=-0/TZ3*(T12-T3-0/2) 1 IF(NN)999,2,1000 2 DO 3 1 = 1 , 8 DO 3 J = l , 1 2 A(I,J)=0. 3 CONTINUE DO 15 1 = 1 , 8 READ(5,801)E(I),SIGMA(I),MAX(I) IF(E( n ) 9 9 9 , 4 , 5 4 NN = I GO TO 16 5 IF(E(I)-TB)6,6,7 6 WRITE(6,813) GO TO 999 7 MAXI=MAX(I) READ(5,802)EB1,(A(I,J),J=1,MAXI) C CHECKING OF INPUT CARDS IF(E(n-EBl)8,9,8 8 WRITE(6,81l) GO TO 999 9 IF(MODE)999,10,11 10 I F ( A B S ( A ( I , 1 ) - 1 . ) - 0 . 0 0 0 1 ) 1 4 , 1 3 , 1 3 11 ASUM=0. 0 0 12 J=1,MAXI ASUM=ASUM+A(I,J) 12 CONTINUE IF(ABS(ASUM-1.)-0.0001)14,13,13 13 W R I T E ( 6 , 8 1 2 ) GO TO 999
Nuclear Data Tables, Vol. I I , No. 7, 1973
616
* « * « « * « * * * * « * « * « 5) * * * « * « « « * *
NEUTRON PRODUCTION CROSS SECTIONS
APPENDIX. Program for Calculation of Laboratory a's from cm. Values 14 U = 1 . - T F / E ( I ) Vl=l.+e(I)/(2.*Tl) V2 = l . + E ( I ) / n 2
Ul = S 0 R T ( V l / ( l . + E ( n * T 2 * U / ( 2 . * T 3 « T A ) ) ) U2=(l.-Q/T12)*(l.+E(I)*T2*U/(T3*T34))/V2 G02(I)=V2#*2/(1.+2.*E(I)*T2/T12**2) W( I )=SQRT I T l * T 3 / ( 7 2 * 7 - ^ * 0 ) ) * U 1 * U 2 IF(MARK)X14.15,114 114 V = l . - T B / E ( n B2(n=V2/Vl
B3(n = (l.-(1.-V2)«(l.+V*T23/(2.*T3)))/Vl Z(I)=T12*(T2-T3)*V/(T1*T3)
15 CONTINUE 16 I F ( N N - 1 ) 1 7 , 9 9 9 , 1 8 17 K=8 GO TO 19
18 K=NN-1
19 MAXIM=MAX(K) PRINTING OF HEADINGS AND INPUT VALUES FOR CROSS SECTION TABLES WRITE(6,803 H E ( I I , I = l , K ) WRITE(6,804) WRITE(6,805)TITLE IF(M0DE)999,22,20 20 W R I T E t 6 j 9 0 6 H S I G M A { n , I = l , K ) DO 21 11=1,MAXIM
JJ=II-1 WRITE(6,907)JJ,(A(KK,II1,KK=1,K» 21 CONTINUE GO TO 24 22 WRITE(6,806)(SIGMA(J),J=1,K) DO 23 11 = 1,MAXIM JJ=II-1 WRITE(6,807)JJ,(A(KK,II),KK=1,K) 23 CONTINUE 24 WRITE(6,804) WRITE(6,808) DO 33 L=l,37 IF((L-2)/6*6-L+2)27,25,25 25 IF(L-2)26,27,26 26 WRITE(6,809) FIXATION OF LABORATORY EMISSION ANGLE 27 THETA=(L-1)«5 RAD=THETA*0.017453 COSl=COS34,1,34 PRINTING OF HEADINGS AND INPUT VALUES FOR ENERGY TABLES 34 W R I T E ( 6 , 8 0 3 ) ( E ( I ) , I = 1 , K ) WRITE(6,804) WRITE(6,905)TITLE WRITE(6,904)T1,Q,T2,T3,T4 WRITE(6,804) WRITE(6,908)
35 36 37 38 999
DO 38 L=l,37 IF((L-2)/6*6-L+2)37,35,35 IF(L-2)36,37,36 WRITE(6,809) THETA=(L-1)*5 WRITE(6,810)THETA,(ENERG(I,L),I=1,K) CONTINUE 60 TO 1 CALL EXIT END
6 1 7
Nuclear Data Tables, Vol. 1 1 . No. 7. 1973
H. LISKIEN AND A. PAULSEN
REFERENCES FOR EXPERIMENTAL DATA AL50
D.L.ALLAN
AL56
W.D.ALLEN AND A.T.G.FERGUSON,
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R.C.ALLEN
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J.ALS-NIELSEN, CCDN-NFWSLETTER 6 (1967) H.V.ARGO, R.F.TASCHEK, H.M.AGNEW, A.HEMMENDINGER, AND W.T.LELAND, PHYS.REV. 87, 612 (1952)
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W.R.ARNOLD, J.A.PHILLIPS, G.A.SAWYER, PHYS.REV. 93, 483 (1954)
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(AND PRIVATE COMMUNICATION FROM J.D.SEAGRAVE) AND N.JARMIE,
PHYS.REV.
ARK.FYS. 2, 271
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E . J .STOVALL , JR. , AND
J.L.TUCK,
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I.BARTHOLDSON,
BA52
P.BAKER,JR.,
(1950)
BA55
R.aATCHELOR, R.AVES, AND T.H.R.SKYRME, REV.SCI.INSTR. 26, 1037
BA57A
E.M.BALABANOV, I.IA.BARIT, L.N.KATSAUROV, ATOMNAYA ENERGIYA SUPPL. 5, 37 (1957)
I.M.FRANK,
AND
I.V.SHTRANIKH,
BA57B
E.M.BALABANOV, I.IA.BARIT, L.N.KATSAUROV, ATOMNAYA ENERGIYA SUPPL. 5, 43 (1957)
I.M.FRANK,
AND
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AND A.WALTNER, PHYS.REV. 88, 1213
AND J.E.PERRY,JR.,
(1952)
PHYS.REV. 107, 1616
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S.J.BAME,JR.,
BA57D
S.J.BAME.JR., E.HADDAD, J.E.PERRY,JR., REV.SCI.INSTR. 28, 997 (1957)
(1957)
BE46
W.E.BENNETT, C.E.MANDEVILLE, AND H.T.RICHARDS, PHYS.REV. 69, 41R
BL48
J.M.BLAIR, G.FREIER, E.LAMPI, W.SLEATOR,JR., AND PHYS.REV. 74, 1599 (1948) AND BR 57
B056
D.L.BOOTH, G.PRESTON, AND P.F.D.SHAW,
B059
G.F.BOGDANOV, N.A.VLASOV, C.P.KALININ, B.V.RYBAKOV, V.A.SIDOROV, SOV.PHYS.-JETP 9, 440 (1959)
BR49
E.BRETSCHFR
BR51
J.E.BROLLFY,JR.,
J.L.FOWLER,
AND E.J.STOVALL,JR.,
BR57
J.E.BROLLEY,JR.,
T.M.PUTNAM,
AND L.ROSEN, PHYS.REV. 107 , B20
BR60
J.E.BRDLLFY.JR. AND J.L.FOWLER, FAST NEUTRON PHYSICS,VOL.I P.73 EDITED BY J.B.MARION AND J.L.FOWLFR (INTFRSCIENCF PUBLISHERS, INC.,NEW YORK, 1960)
RR64
n.n.BRILL, V.M.PANKRATOV, V.P.RUDAKOV, AND ATOMNAYA ENERGIYA 16, 141 (1964)
CH56
P.R.CHAGNON
C050
J.H.COON, PHYS.REV. 80, 488
AND R.K.SMITH, (1946)
J.H.WILLIAMS,
PROC.PHYS.SOC.(LONDON)A69,265(1956) L.N.SAMOILOV,
AND
AND A.P.FRENCH, PHYS.REV. 75, 1154 (1949) PHYS.REV. 82, 502(1951) (1957)
B.V.RYBAKOV,
AND G.f-.OWEN, PHYS.REV. 101 , 798
(1956)
(1950)
C052
J.P.CONNER,
C059
D.R.F.COCHRAN, R.K.SMITH, AND R.L.HENKEL, G063 (AND PRIVATE (fOMMUN ICATKIN FROM M.D .GOLDBERG)
T.W.BONNER, AND J.R.SMITH, PHYS.REV. 8ft, 468
CQ70
D.G.COSTELLO, S.J.FRIFSENHAHN,
CR56
L.CRANBERG,
(1952)
AND W.M.LOPEZ, NUCL.SCI.ENG. 39, 409(1970)
A.H.ARMSTRONG, AND R.L.HENKEL, PHYS.REV. 104, 1639 (1956)
DA57A
V.A.DAVIDENKO,
0A57B
V.A.DAVIDENKO, A.M.KUCHER, I.S.POGREBOV, ATOMNAYA ENERGIYA SUPPL. 5, 7 (1957)
I.S.POGREBOV,
AND A.I.SAUKOV, J.NUCL.ENERGY
2, 258
(1957)
DA58
W.W.DAEHNICK AND J.M.FOWLER,
DE63
W.DEUCHARS, J.L.PERKIN, AND R.BATCHELOR, NUCL.INSTR.METH. 23, 305
(1963)
EL53
E.A.ELIOT, D.ROAF, AND P.F.D.SHAW,
ER49
K.W.ERICKSON, J.L.FOWLER, AND E.J.STOVALL,JR., PHYS.REV. 76, 1141
F056
J.L.FOWLER
AMD
lU.F.TUTUROV,
PHYS.REV. Ill, 1309
AND J.E.BROLLEY,JR.,
(1958)
PROC.ROY.SOC.(LONDON) 216, 57 (1953)
FU57
J.C.FULLER, W.E.DANCE, AND D.C.RALPH, PHYS.REV. 108, 91
GA56
A.GALONSKY AND C.H.JOHNSON, PHYS.REV. 104, 421
GA57
A.S.GANEEV, A.M.GOVOROV, G.M.OSETINSK11, A.N.RAKIVNENKO, V.S.SIKSIN, ATOMNAYA ENERGIYA SUPPL. 5, 21 (1957) J.H.GIBBONS AND R.L.MACKLIN, PHYS.REV. 114, 571
G056
G.V.GORLOV, B.M.GOKHBERG, V.M.MOROZOV, AND V.A.SHIGIN, SOV.PHYS.TECH.PHYS. 1, 964 (1956)
I.V.SIZOV,
(1959)
G060A
M.D.GOLDBERG AND J.M. LE BLANC, PHYS.REV. 119, 1992
G060B
L.GONZALEZ, J.RAPAPORT, AND J.J.VAN
G061A
M.D.GOLDBERG AND J.M. LE BLANC, PHYS.REV. 122, 164
G061B
M.D.GOLDBERG, J.D.ANDERSON, J.P.STOERING, AND C.WONG, PHYS.REV. 122, 1510 (1961) (AND PRIVATE COMMUNICATION FROM M.D.GOLDBERG)
618
(1957)
(1956)
GI59
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
(1949)
REVS.MOD.PHYS. 28, 103 (1956)
(1960)
LOEF, PHYS.REV. 120, 1319 (1961)
(1960)
AND
NEUTRON PRODUCTION CROSS SECTIONS
REFERENCES FOR EXPERIMENTAL DATA Gn63 HE55 HU*9 JA50 JA56A JA56B KA59 Ke68 KN70 K055 K066 MA58 MA65 MC51 MC73A MI61 NA66 PA64 PA66 PA70 PF59 PF6B PR54 Rn57 SA51 SC72 SE59 Se60 SI68 SM57 ST52 ST56 ST60 TA49 TH66 TH69 TI54 VA57 VL55 V057 We52 WI53 WI60 WI61
M.O.GOLDBFRG, PROGRESS IN FAST NEUTRON PHYSICS, P.3 EDITED BY G.C.PHILLIPS, J.B.MARION, AND J.R.RISSER (UNIVERSITY OF CHICAGO PRESS, CHICAGO, 1963) A.HEMMENDINGER AND H.V.ARGO, PHYS.REV. 98, 70 (1955) G.T.HUNTER AND H.T.RICHARDS, PHYS.REV. 76, 1445 (1949) G.A.JARVIS, A.HEMMENDINGER, H.V.ARGO, AND R.F.TASCHEK, PHYS.REV. 79, 929 (1950) N.J&RMie AND J.0.SEAGRAVE, LA-2014 (1956) G.A.JARVIS, JA56A P.P.KANE, NUCL.PHYS. 10, 429 (1959) R.G.KERR AND J.D.ANDERSON, BULL.AM.PHYS.SOC. 13, 564 (196R) (AND PRIVATE COMMUNICATION FROM M.D.GOLDBERG) H.H.KNITTER (PRIVATE COMMUNICATION) A.T.KORITSKII, DISSERTATION (ACADEMY OF SCIENCES, USSR, 1955) A.P.KOBZEV, V . I .SALATSK 11 , AND S . A.TELEZHNIKOV , SOV.J.NUCL.PHYS. 3, 774 (1966) R.L.MACKLIN AND J.H.GIBBONS, PHYS.REV. 109, 105 (1958) R.L.MACKLIN AND J.H.GIBBONS, EANDC-50-S, VOL.I PAPER 13 (1965) K.G.MCNEILL AND G.M.KEYSER, PHYS.REV. 81, 602 (1951) D.K.MCDANIELS, M.DROSG, J.C.HOPKINS, AND J.D.SEAGRAVE (TO BE PUBLISHED) C.MILONE AND R.RICAMO, NUOVO CIM. 22, 116 (1961) V.NAGGIAR, L.LAFAYE, AND P.BREONCE, NUCL.INSTR.METH. 41, 77 (1966) A.PAULSEN AND H.LISKIEN, NUCL.PHYS. 56, 394 (1964) A.PAULSEN AND H.LISKIEN, PROC.CONF.ON NUCL.DATA FOR REACTORS, PARTS 1966, VOL.1 P.217 (IAEA, VIENNA, 1967) A.PAULSEN (PRIVATE COMMUNICATION) J,e,PERRY, E.HAnOAn, R.I.HRNKEL, G.A.JARVIS, AND R.K.SMITH, SF59 (AND PRIVATE COMMUNICATION FROM J ,1). SF AGRAVF ) A.PFFTKRMANS (PRIVATE COMMUNICATION) G.PRESTON, P.F.O.SHAW, AIMD S.A.YOUNG, PROC.ROY. SOC. ( LONDON ) A?26 , 206 ( 1954) L.ROSEN,JA56A A.R.SAYRES, K.W.JONES AND C.S.WU, PHYS.REV. 122, 1853 (1961) R.L.SCHULTE. M.COSACK. A.W.OBST, AND J.L.WFIL, NUCL.PHYS. A192, 609(1972) (AND PRIVATE COMMUNICATION FKOM J.L.WEiLl J.D.SEAGRAVE, PROC.CONF.ON NUCLEAR FORCES AND THE FEW NUCLEON PROBLEM, LONDON 1959, VOL.11 P.583 (PERGAMON PRESS, OXFORD, 1960) J.D.SEAGRAVE, L.CRANBERG, AND J.E.SIMMONS, PHYS.REV. 119, 1981 (1960) J.E.SIMMONS AND J.J.MALANIFY, BULL.AM.PHYS.SOC. 13, 564 (1968) (AND PRIVATE COMMUNICATION J.E.SIMMONS) R.K.SMITH AND J.E.PERRY,JR., BA57D, F056, JA56A T.F.STRATTON AND G.O.FREIER, PHYS.REV. 88, 261 (1952) L.STEWART, G.M.FRYE,JR., AND L.ROSEN, BULL.AM.PHYS.SOC. 1, 93 (1956) L.STEWART, J.E.BROLLEY,JR., ANO L.ROSEN, PHYS.REV. 119, 1649 (1960) R.F.TASCHEK, G.A.JARVIS, A.HEMMENDINGER, G.G.EVERHART, AND H.T.GITTINGS, PHYS.REV. 75, 1361 (1949) R.B.THEUS, W.I.MCGARRY, AND L.A.BEACH, NUCL.PHYS. 80, 273 (1966) S.T.THORNTON, NUCL.PHYS. A136, 25 (1969) U.TIMM, H.NEUERT, AND B.ELSNER, Z.PHYSIK 139, 425 (1954) A.K.VALTER AND A.P.KLlUCHAREV, BA57B N.A.VLASOV, S.P.KALININ, A.A.OGLOBLIN, L.N.SAMOILOV, V.A.SIDOROV, ANO V.I.CHUEV, SOV.PHYS.-JETP 1, 500 (1955) V.V.VOLKOV, P.E.VOROTNIKOV, E.A.KOLTYPIN, N.I.SIDOROV, AND G.B.IANKOV, ATOMNAYA ENERGIYA SUPPL. 5, 13 (1957) W.A.WENZEL ANO W.WHALING, PHYS.REV. 88, 1149 (1952) H.B.WILLARD, J.K.BAIR AND J.D.KINGTON, PHYS.REV. 90, 865 (1953) W.E.WILSON, D.B.FQSSAN, AND R.L.WALTER, BULL.AM.PHYS.SOC. 5, 410 (1960) (AND PRIVATE COMMUNICATION FROM M.D.GOLDBERG) W.E.WILSON, R.L.WALTER, AND O.B.FOSSAN, NUCL.PHYS. 27, 421 (1961) (AND PRIVATE COMMUNICATION FROM J.D.SEAGRAVE)
619
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
NEUTRON PRODUCTION CROSS SECTIONS AND ENERGIES FOR THE REACTIONS T{p,n)me,
D(4ii)3He, AND T(4n)*He
HORST LISKIEN and ARNO PAULSEN Joint Nuclear Research Center Central Bureau for Nuclear Measurements, Geel, Belgium Center-of-mass best values for the normalized Legendre coefficients and the 0° differential cross section as functions of input energy have been derived from various experimental results for the reactions T(jp,n)^He, Y>{d,nfHe, and T(cf,«)''He. This information has been used to calculate laboratory differential cross sections as functions of laboratory input energy and neutron emission angle which are given in tabular form with the corresponding neutron energy.
^
• U * /5^ i m T
U
A
J
•
n
T
Copyright © 1973 by Academic Press, Inc. All rights of reproduction in any form reserved.
569
Nuclear Date Tables, Vol. n . No. 7, 1973
H. LISKIEN AND A. PAULSEN
CONTENTS
INTRODUCTION Scope Procedure Conclusions References for Introduction
570
REACTION T{p,nfHe a (0° cm.), Legendre Coefficients (cm.), a (total): Recommended and Experimental Values
574
a (0 lab), E„ (0 lab): Recommended Values REACTION D(4«)3He a (0° cm.), Legendre Coefficients (cm.), a (total): Recommended and Experimental Values
586
a (0 lab), E„ (6 lab): Recommended Values REACTION T(4n)4He a (0° cm.), Legendre Coefficients (cm.), a (total): Recommended and Experimental Values
601
a (6 lab), E^ (0 lab): Recommended Values APPENDIX. Program for Calculation of Laboratory a's from cm. Values
616
REFERENCES FOR EXPERIMENTAL DATA
618 It was restricted to the proton or deuteron laboratory input energy range (from threshold) up to 10 MeV which is most important from the point of view of neutron production. Experimental results above 10 MeV were taken into account for determining the recommended curves near 10 MeV. The scope of this work does not include data about spurious neutrons from the break-up of the product nucleus (tertiary reactions) which appear at higher input energies. The same is true for all (p,n) or (d,n) reactions with the material of the target support. This review includes a tabulation of recommended neutron energies. For the calculation of these neutron energies and other kinematic parameters needed for the transformation between the laboratory (lab) and the center-of-mass (cm.) system the most recent nuclear mass tables'^ and relativistic formulas* were used. The following table presents the reaction g-values and compares thresholds with those for possible tertiary reactions.
INTRODUCTION There is an urgent need for an evaluation of data on the neutron source reactions T(^,«)^He, D{d,n)^lie, and T(4«)*He which are known as monoenergetic neutron sources (for a given neutron emission angle 0) and which play an important role in neutron metrology. The earlier reviews in this field^"^ are about ten years old and do not contain recommended results in numerical form. The present paper is a result of the completion and reevaluation of the authors' recent work*'^ with December 1972 as cutoff date. Scope This work presents recommendations based on a data compilation of differential and integrated (with respect to the neutron observation angle ^) cross sections.
Reaction
g-Value, MeV
Threshold, MeV
T(p,n)^He
-0.764
1.019 forew. 1.147 backw.
D{d,nfiie
Tid,n)me
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
Break-up Reaction
Threshold, MeV
T(p,np)D
8.35
-(-3.269
D(d,np)D
4.45
-1-17.590
T(d,npyT T(d,2nfiie
3.71 4.92
570
NEUTRON PRODUCTION CROSS SECTIONS
cosine serial expansion or as asymmetry or Legendre coefficients. In the cases where only differential cross sections have been given the data were least-squares fitted. The number of coefficients at a given energy was limited in such a way that the last coefficient was shown to be nonzero by the compilation. If the number of reported coefficients disagreed, a refitting procedure with the right number of coefficients was carried out as far as possible. The recommended curves were obtained by starting from smooth eye guides through the experimental Ai values. Then an iterative procedure was followed for renormalizing and resmoothening of these Ai curves. No attempt was made to fit the energy dependence of the Legendre coefficients to theoretical expressions from direct interaction theory because it is known that the considered data are at least partially in contradiction to the direct interaction mechanism.
Procedure The collected data were transformed, if necessary, into the T(p,nfne, D(d,nfne, and T(4n)*He centerof-mass systems, respectively. The compilation comprises, of course, experimental results which were obtained with exchange of target and projectile particles, or by observation of the product nucleus instead of the neutron. Experimental results obtained with thick targets were not taken into consideration. The validity of time reversal allows the calculation of cross sections from those of the inverse reaction by means of the reciprocity theorem. This principle is very strict and is not subject to any correction. Therefore data of this kind were considered. Only integrated cross sections of the reactions ^Hc{n,p)T and ^}ie(n,d)D had to be converted. This was done by means of the equations: «p.»(£p) = On,,(E„) -^
for mc(n,p)
data
with
0° Differential Cross Sections The compilation of 0° differential center-of-mass cross sections includes data which have been obtained by conversion by means of the recommended ^^ values and the expression
Ep = E„+ 1.019 MeV, and '^a,niEa) = ^nAiK) -r
for 3He(«,<^) data
with E^=. 1.499 £ „ - 6 . 5 3 8 MeV.
-(0°) = dui
Similar cross sections for reactions in which an involved neutron is replaced by a proton or vice versa [for example D(J,/?)T and Y>(d,nf\it or 3He(^,/>)*He and T(4n)*He] are predicted if nuclear forces are charge independent. However, the necessary corrections due to the influence of the Coulomb force are model dependent. Therefore such data have not been taken into account. For the parametrization of the differential centerof-mass cross sections we chose the form
^ -
Air Ac,
au)
2 A,p,(e)
The determination of the 0° differential centerof-mass cross section "best curve" following the eyeguide method was the next step. For the reaction T(d,nyKc the deuteron energy range from 0 to 300 keV forms an exceptional case. Within this range the reaction is isotropic in the centerof-mass system. This range contains also a dominating cross-section resonance with a peak value at 107 keV. Therefore the 0° differential center-of-mass crosssection data (which differ only by a factor of 477 from the integrated cross sections) were fitted to the BreitWigner-Eisenbud resonance formula
which implies the normalization
^(P:0)
do:^ ' ^
££2
= J:
3kl 4(£'o + ^^ + ^2- Ef + (r, -i- v^f'
In this formula index 1 indicates the scattering and index 2 the reaction channel. Two simplifications are made, namely that the entrance channel contains only j-waves and that the reaction radius a is identical for both entrance and exit channel. The widths are given by
i
This representation eliminates from the angular distributions systematic errors in the absolute cross-section scale. Relative Angular Distributions
'
Normalized Legendre coefficients have been calculated if the results were reported as coefficients of a
FHx^,7,) + G^ (x^,yi)
and 571
Nuclear Data Tables, Vol. U , No. 7, 1973
H. LISKIEN AND A. PAULSEN
r.
2-k.
Consequently there are four fitting parameters: the reaction radius a, the reduced widths yf and y|, which should not exceed the Wigner Umit 31i^/2n^a, and the resonance energy EQ. The solid line shown in the figure for the T(4n)*He 0° c m . cross section is the result of this fit. Special care was taken to match the eye-guide curve to this fit at 300 keV. The final parameters are compared below with those of earlier fits:
2 • Y2 ' ^ 2
where F and G are Coulomb functions for / = 0, rj is the charge parameter e^^^/fi^k^ (jx = reduced mass) and x^ = k^a and X2 = k2a. The level shifts are given by Ai = - - i {FF' + G G')
and
Aj =
r, 3 + 2x1
Ref.
yf(MeV . fm)
Yi(MeV • fm)
^o(MeV)
a(fm)
9 9 10 11 this evaluation
3.3 5.0 10.0 6.0 6.5
O.Il 0.12 0.28 0.12 0.15
-0.067 -0.126 -0.464 -0.144 -0.179
7 7 5 7 6
It seems that A2, which is nearly constant, is included in the value for E(, for the sets reported in Ref 9 and 10.
Conclusions Although "uncertainties" are often quoted in the published articles, they often are explained insufficiently or account only for a part of the error sources involved (for example uncertainties given for Legendre coefficients typically reflect only the consistency between data and the polynomial fit). Therefore the recommended curves do not account for the uncertainties quoted by the experimentalists. The best curves are of course subject to some arbitrariness as the authors have their own opinion about the reliability of the different measurements. Unfortunately in several publications the results are given only as plots which are difficult to read accurately. In these cases it was best to read the results by means of an elastometer. It is strongly recommended to publish all results in numerical form together with sufficient information about the uncertainty contribution of the different error sources.
Integrated Cross Sections The applied procedure fixes a "best curve" for the integrated cross section a according to the equation a = 4ITAQ [da/du (0°)]. An iterative smoothening procedure applied to 6?a/fi?w(0°) and a was allowed for. The comparison of the resulting integrated cross-section curve with experimental integrated cross sections directly reported as such in the literature was considered only as a cross-check. Differential Laboratory Cross Sections and Neutron Energies Finally recommended values of differential lab cross sections, a (6 lab) were calculated for practical use from the recommended center-of-mass Legendre coeflficients and the 0° cross sections. Neutron energies E„ (6 lab) are presented on the facing page. For the input energy, steps of 10 keV were chosen between 20 and 100 keV, of 50 keV between 0.1 and 1 MeV, of 100 keV between 1 and 3 MeV, and of 500 keV between 3 and 10 MeV. Steps of 5° were chosen for the emission angle. If laboratory data at intermediate energies are needed, it is recommended not to interpolate the tabulated laboratory values but instead the center-of-mass input data and to use the provided FORTRAN program (APPENDIX) to calculate the lab differential cross sections. The three dimensional plots^^ allow a quick survey of the lab differential cross sections.
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
The absence of reliable information on the uncertainties of the measured quantities, as mentioned in the paragraph above, implies the difficulty in stating accuracies for the evaluated quantities. The mean deviation between the experimental data (as far as they influenced the evaluation, see figures) and the recommended curve reflects the consistency of the data. However, if there are sufficient independent data (which can be confirmed for the largest part of these evaluations) this mean deviation can be considered also as a measure of the uncertainty of the recommended curve. Here are the results averaged over the considered energy range and for the Legendre coeflicients also averaged over all indices:
572
NEUTRON PRODUCTION CROSS SECTIONS
Reaction
very useful in these energy regions. The present evaluation indicates that the data for the reaction D{d,n)^iie can be considered as being satisfactory with respect to completeness and consistency. For the reaction T(d,«)*He the number of reported angular distributions is not satisfying. Here, especially at energies above 5 MeV, further investigations would be worthwhile. Finally, it should be mentioned that according to the reciprocity theorem for nuclear reactions (see Procedure) the presented evaluations can be converted easily to the corresponding data for the inverse reactions. For the reactions ^He(«,^)T and ^He(«,^)D, which are of practical interest for neutron detectors, this conversion was already carried out.^^
Legendre 0° c m . Integrated Coefficients, Cross Section, Cross Section, Abs. Dev. Rel. Dev. Rel. Dev.
T(/7,«)3He D(4«)3He
0.03 0.01
0.07 0.04
0.07 0.05
T(rf,«)*He
0.01^
0.03* 0.041-
0.07+
* below 300 keV only + above 300 keV For the reaction T(/7,n)^He there are no reliable experimental data about the angular distributions between foreward and backward threshold. Therefore the evaluation for this reaction was limited to the energy region between backward threshold and 10 MeV, but also between backward threshold and 2 MeV the Legendre coefficients are markedly more uncertain than at higher energies. Further experimental work will be
Acknowledgments The authors gratefully acknowledge the cooperation of M. D. Goldberg, J. E. Simmons, J. D. Seagrave, and J. L. Weil in sending unpublished material and proposing ameliorations.
References for Introduction 1. J. L. Fowler and J. E. Brolley, Jr., Rev. Mod. Phys. 28, 103 (1956)
7. A. H. Wapstra and N. B. Gove, Nucl. Data Tables 9, 265 (1971)
2. J. E. Brolley, Jr., and J. L. Fowler, Fast Neutron Physics (J. B. Marion and J. L. Fowler, ed.) Vol. I, p. 73, Interscience Publishers, Inc., New York (1960)
8. H. Horstmann and H. Liskien, "Relativistic Calculations of Kinematic Parameters for Nuclear Reactions," Report EUR 3668.e (1968)
3. M. D. Goldberg, Progress in Fast Neutron Physics (G. C. Phillips, J. B. Marion, and J. R. Risser, ed.) p. 3, University of Chicago Press, Chicago (1963)
9. H. V. Argo et al., Phys. Rev. 87, 612 (1952) 10. J. P. Conner, T. W. Bonner, and J. R. Smith, Phys. Rev. 88, 468 (1952)
4. H. Liskien and A. Paulsen, "An Evaluation for Cross Sections of the Reaction D(d,n)^He" Report EANDC(E)-143"L" (1971)
11. E. M. Balabanov et al., Atomnaya Energiya Suppl. 5, 43 (1957)
5. A. Paulsen and H. Liskien, "An Evaluation for Cross Sections of the Reaction T(d,nyHe," Report EANDC(E)-144"L" (1972)
12. G. Nastri and C. Cervini, "The Three-Dimensional Plotting Program TRICE," Report EUR 4484.e (1970)
6. H, Liskien and A. Paulsen, "An Evaluation for Cross Sections of the Reaction T(p,n)^He" Report EANDC(E)-152"L" (1972)
13. A. Paulsen and H. Liskien, Proc. Second IAEA Panel on Neutron Standard Reference Data, Vienna (1972) to be published
573
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
H. LISKIEN AND A. PAULSEN
Jip,n)me a(0° cm.), Legendre Coefficients (cm.), a(total) Recommended and Experimental Values a(e lab), E„{e lab) Recommended Values
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
5 7 4
NEUTRON PRODUCTION CROSS SECTIONS
T(p,n)^He. 0(0" cm.), Legendre Coefficients, a(total) Recommended and Experimental Values SIGMA-0 AO, A l , . . . SIGMA-T
(7(0° cm.) Legendre coefficients a(total)
Recommended Data ENERGY (MEV)
SIGMA-0 (MB/SR)
AO
Al
A2
A3
215. 246. 274. 302. 328. 354. 380. 406. 432.
1.200 1.300 1.400 1.500 1.600 1.700 1.800 1.900 2.000
16.2 17.6 19.1 20.7 22.3 24.0 25.8 27.7 30.0
1.056 1.112 1.142 1.161 1.170 1.174 1.172 1.166 1.146
-0.076 -0.220 -0.340 -0.435 -0.516 -0.580 -0.627 -0.660 -0.674
0.020 0.108 0.198 0.274 0.346 0.406 0.455 0.494 0.528
2.100 2.200 2.300 2.400 2.500 2.600 2.700 2,800 2.900 3.000
33.0 36.3 40.4 44.7 48.7 52.5 55.2 57.4 58.6 59.4
1.100 1.047 0.980 0.909 0.H56 O.BIO 0.783 0.764 0.752 0.745
-0.660 -0.631 -0.582 -0.533 -0.502 -0.477 -0.463 -0.455 -0.451 -0.450
0.563 0.591 0.613 0.639 0.664 0 . 6 90 0.708 0.724 0.740 0.753
-0.003 -0.007 -0.011 -0.015 -0.018 -0.023 -0.028 -0.033 -0.041 -0.048
3.500 4.000 4.500 5.000 5.500 6.000 6.500 7.000 7.500 8.000 8.500 9.000 9.500 10.000
58.1 50.9 42.2 35.3 29.4 24.8 21.1 18.4 16.4 15.2 14.5 14.0 14.1 14.4
0.738 0.753 0.784 0.827 0.888 0.963 1.039 1.104 1.153 1.167 1.146 1.107 1.050 0.984
-0.472 -0.520 -0.576 -0.635 -0.699 -0.768 -0.840 -0.901 -0.933 -0.900 -0.831 -0.751 -0.667 -0.560
0.832 0.910 0.990 1.069 1.148 1.228 1.301 1.367 1.361 1.273 1.159 1.036 0.920 0.796
-0.098 -0.167 - 0 . 2 54 -0.355 -0.478 -0.617 -0.760 -0.901 -0.979 -1.000 -0.987 -0.945 -0.879 -0.801
575
SIGMA-T (MB)
/44
456. 477. 497. 511. 524. 534. 543. 551. 554. 556. 0 .. 0 2 4 0 ,. 0 5 6 0 ., 0 9 4 0 ,. 1 4 1 0 .. 1 9 4 0 .. 2 6 0 0 ,. 3 3 1 0 .. 3 9 8 0 ,. 4 6 0 0 .. 5 1 3 0 ,. 5 5 3 0 ,. 5 7 6 0 ,. 5 8 1
539. 482. 416. 367. 328. 300. 275. 255. 238. 223. 209. 195. 186. 178.
Notleor Dato Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(p,n)^lie.
o
• AL56 OBASS * BOSS + C»70 o 6159 A G0«1B V JA56B • MASS 0 MC73A ® m « A • o
knb/sr)
)hL
° T(p.n
o
Ref. 60-
o(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values
'•i
/J?
SA61 SEGO srs6 VL56 WIS3 WI61
g«
0
•
^ 0
A
o
Jo-
1
oJ
jro
rf 0
^ \
mJr^v
V!^
020
3a
40
Ep [MeV|
5J0 SO 70 8.0 9.0100
2X)
•
Ep
3.0 io [MeVl
i.0
e.0 70
aoaoKto
•
Legendre Coefficients Experimental and Recommended Values
a(0° cm.)- Experimental and Recommended Values
T(p.n)'He
2.0
M Ep
lM*|
4X1
5.0
M
70 8iJ 9X) mO 0'
«•
30"
60*
90'
120'
150'
180'
a(9, Ep). Recommended Values
a(total). Experimental and Recommended Values
Solid line shows recommended values. Only experimental data which contributed to the recommended values are plotted. References are on page 618
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
576
NEUTRON PRODUCTION CROSS SECTIONS
T(p,«)3He. a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values EXPERIMENTAL 0 DEGREE C M .
EP(MeV) 1.150 1.160 1.170 1.174 1.179 1.180 1.190 1.195 1.203 1.208 1.220 1.220 1.227 1.232 1.237 1.237 1.248 1.250 1.250 1.260 1.261 1.266 1.280 1.301 1.307 1,330 1.330 1.343 1.350 1.350 1.356 1.370 1.380
l:t?8 1.410
1.420 1.420 1.430 1.454 1.467 1.470 1,470 1.490 1.500 1.520 1.550 1.550 1.550 1.560 1.569 1.580 1.583 1.590 1.600 1.613 1.620 1.620 1.620 1.640 1.688 1.690 1.700 1.704 1.750 1.760 1.770 1.800 1.800 1.804 1.810 1.812 1.820 1.828 1.840 1.920 1.920 1.923 1.958 1.960 1.966 1.970 1.997 2.000 2.000 2.020
SIGMA-0 14.7 13.1 12.9 15.5 15.5 12.7 11.3 16.2 16.5 16.3 13.5 14.1 18.9 17.0 16.9 16.0 16.8 14.9 15.0 12.1 18.0 17.8 14.9 17.5 18.9 17.2 16.2 18.0 16.9 15.7 18.4 16.3 17.6
11:^7
16.3 18.9 17.0 14.6 20.2 19,2 20.1 19.2 21.7 21.7 19.4 21.8 17.8 18.2 20.5 22.8 19.8 22.2 21.6 18.2 23.2 19.0 23.5 20.3 23.2 23.8 20.5 24.4 23.4 24.7 25.7 25.9 22.5 22.8 26.9 28.5 26.5 21.8 24.4 26.2 27.3 23.5 28.0 26.3 28.7 27.4 20.3 29.8 31.0 30.0 31.9
REF. MA65 AL56 WI53 MA65 MA65 WI53 JA56B GI59 MA65 MA65 WI53 BA55 GI59 MA65 MA65 GI59 GI59 WI53 AL56 JA56B MA65 MA65 WI53 GI59 MA65 AL56 WI53 GI59 WI53 BA55 GI59 C070 WI53 VL55 cn50 cnso WI63 BASS JA56B GI59 GI59 WIb3 C070 AL56 PE69 BA55 WI53 C050 C050 C050 GI59 C050 GI59 C070 C050 PE59 JA56B AL56 BA55 WI53 GI59 BA55 WI53 GI59 PE59 C070 WI53 C050 C050 GI59 GI59 GI59 BA55 GI59 WI53 WI53 JA56B PE59 GI59 WI53 GI59 SA61 GI59 WI53 AL56 C070
EP(MEV)
2.020 2.020 2.080 2.091 2.099 2.180 2.196 2.220 2.240 2.249 2.250 2.260 2.260 2.260 2.320 2.404 2.420 2.458 2.460 2.480 2.500 2.560 2.600 2.619 2,620 2.620 2.660 2.666 2.690 2.720 2.740 2.770 2.790 2.800 2.820 2.820 2.840 2,841 2.845 2.850 2.870 2.872 2.880 2.900 2.920 2.950 2.970 2.970 3.000 3.010 3,020 3,040 3.074 3.078 3.080 3.090 3.110 3.150 3.240 3,284 3.290 3.290 3.300 3.309 3,450 3.488 3.490 3.520 3.520 3.520 3.520 3.550 3.559 3.650 3.690 3.690 3.693 3.740 3.819 3.819 3.850 3.897 3.900 3,900 3.940
CROSS SECTION FOR THE REACTION T ( P , N » H e 3 SIGMA-0
31.5 30.2 32.4 29.6 30.0 35.7 36.4 32,9 32.1 38.4 35.1 37.7 32.4 33.1 40.4 46.2 43.8 46.0 42.1 45.1 45.6 44.7 48.2 55.8 42.3 45.8 48,2 52,4 49,1 49.7 50.0 50.5 51.1 50.4 50.4 54.5 50.5 61.2 62.9 51.9 49.7 56,3 50,8 51,0 51,5 52,1 52.6 52,0 52.2 52.5 51.6 53.1 64.4 57.9 53.7 53,5 52,3 52,7 52,0 57,9 50.7 52.5 51.0 62.8 49.2 56.6 49.9 34.0 38.4 42.2 42.5 48.1 60.7 47.1 45.5 56.5 54.1 45.6 57.3 55,6 44,6 51.2 43.6 44.7 44.3
577
REF. SE60 BA55 WI53 GI59 GI59 WI53 GI59 BA55 C050 PE59 JA56B WI53 C050 C050 WI53 GI59 WI53 PE59 JA56B WI53 VL55 JA56B WI53 GI59 C050 C050 JA56B PE59 WI53 WI53 WI53 WI53 WI53 WI53 WI53 AL56 WI53 GI59 GI59 WI53 JA56R PE59 WI53 WI53 WI53 WI53 MI53 JA56B WI53 W153 SE60 WI53 GI59 PE59 JA56B WI53 WI53 WI53 WI53 PE59 W153 JA56B VL55 GI59 WI53 PE59 JA56B C050 C050 C050 C050 WI53 GI59 WI53 JA56B SA61 PE59 WI53 GI59 GI59 WI53 PE59 VL55 JA56B WI53
EP(MEV) 4.000 4.020 4.070 4.079 4,100 4.101 4.160 4.200 4,250 4,300 4,359 4.370 4.400 4.500 4.520 4.600 4.619 4.630 4.700 4.720 4.840 4.920 .923 .940 .940 .000 .000 _.060 5.216 5.250 5.300 5,440 5,500 5,900 5,940 6,000 6.000 6.000 6.020 6.100 6.400 6.440 6.450 6.500 6.700 6.800 6.850 6,940 7.000 7.000 7.100 7.250 7.400 7.430 7.600 7.700 7.750 7.930 8.000 8.000 3.000 8.100 8.100 8.300 8.450 8.450 8.600 8.650 8.800 8.800 8.800 8.800 8.930 9.000 9.000 9.090 9.150 9.350 9,420 9,500 9,700 9.800 9.850 9.920 10.000
SIGMA-0
REF.
51.5 43.9 41.6 52.8 40.6 47.8 40.6 42.1 39.6 40.6 47.6 38.2 43.5 37.1 33.8 36.7 43.5 36.9 38.9 35.5 34.9 40.3 38.3 33.8 35.4 35.1 37.8 33.0 35.9 30.7 31.8 29.6 28.7 24.9 25.0 23.1 24.9 26.1 23.2 22.3 19.9 21.3 22.7 19.4 18.3 17.7 20.4 19.0 18.8 19.5 19.5 18.6 18.3 16.7 17.2 16.0 16.9 15,2 13.7 15,8 15,7 15,6 15,4 14.9 14.9 14.6 14.4 14.6 14.5 14.8 14.6 9.8 14.3 14.5 14.8 13.6 14.5 14.5 14.1 13.9 14.0 14.1 13.9 14.4 15.2
MC73A 0050 W153 GI59 JA56B PES? WI53 VL55 WI53 G061B GI59 WI53 PE59 WI53 SE60 VL5B GI59 WI53 PE59 WI53 WI53 GI59 GI59 WI53 WI61 PE59 MC73A WI53 GI59 PE59 VL55 WI61 PE59 VL55 WI61 8059 PE59 MC73A SA61 8059 VL55 WI61 B059 G061R VL55 VL55 8059 WI61 8059 MC73A 8059 8059 B059 WI61 8059 B059 8059 WI61 G061B 8059 MC73A B059 B059 B059 WI61 B059 MC73A B059 B059 G061B B059 ST56 WI61 B059 MC73A SA61 8059 B059 WI61 B059 B059 B059 B059 WI61 MC73A
Nuclear Data Tables, Vol. ) I , No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(p,n)^He. a(0° cm.), Legendre Coefficients, o(total) Recommended and Experimental Values NORMALIZED EXPERIMENTAL LEGENDRE COEFFICIENTS FOR THE REACTION
EP(MEV)
1.190 1.200 1.260 1.400 1.400 1.430 1.500 1.600 1.613 1.620 1.690 1.750 1.920 1.923 2.060 2.249 2.250 2.450 2.458 2.460 2.500 2.500 2.560 2.660 2.666 2.850 2.870 2.872 2.970 3.000 3.000 3.000 3.078 3.OHO 3.2S0 ^.i>bl.) 3.2H4 3.290 3.300 3.400 3.488 3.490 3.690 3.693 3.700 3.897 3.900 3.900 4.100 4.101 4.101 4.140 4.300 4.400 4.600 4.610 4.700 4.940 5.000 5.000 5.090 5.250 5.300 5.440 5.500 5.900 5.940 6.000 6.400 6.440 6.500 6.800 6.800 6.940 7.000 7.430 7.930 8.000 8.450 8.800 8.900 8.930 9.420 9.920 10,000
Nuclear Data Tables, Val. I I , No. 7, 1973
AO
0.919 1.065 1.064 1.074 1.349 1.110 1.163 1.109 1.192 1.136 1.154 1.217 1.138 1.196 1.064 1.002 0.951 0.822 0.875 0.840 0.957 0.845 0.847 0.768 0.802 0.771 0.749 0.761 0.736 0.758 0.791 0.760 0.728 0.719 0.756 0.R07 0.731 0.72H 0.R95 0.738 0.722 0.732 0.828 0.766 0.812 0.770 0.808 0.938 0.820 0.773 0.776 0.880 0.788 0.803 0.965 0.886 0.816 0.827 0.975 0.848 0.716 0.857 0.966 0.910 0.922 1.188 0.948 0.958 1.333 1.022 1.111 1.304 1.174 1.101 1.088 1.156 1.170 1.184 1.144 1.112 1.324 1.090 1.057 1.058 1.031
Al
0.112 -0.083 -0.074 -0.282 -0.694 -0.357 -0.509 -0.393 -0.511 -0.398 -0.588 -0.695 -0.592 -0.713 -0.542 -0.615 -0.519 -0.449 -0.536 -0.472 -0.351 -0.500 -0.499 -0.428 -0.488 -0.472 -0.395 -0.451 -0.424 -0.469 -0.476 -0.504 -0.437 -0.405 -0.497 -0.531 -0.452 -0.43H -0.454 -0.400 -0.459 -0.470 -0.565 -0.519 -0.538 -0.519 -0.540 -0.502 -0.561 -0.502 -0.543 -0.681 -0.568 -0.584 -0.594 -0.705 -0.609 -0.593 -0.883 -0.642 -0.455 -0.661 -0.619 -0.700 -0.731 -0.963 -0.733 -0.734 -1.141 -0.811 -0.990 -1.063 -0.942 -0.905 -0.874 -0.919 -0.953 -0.844 -0.830 -0.734 -1.103 -0.751 -0.644 -0.630 -0.559
A2
A3
-0.031 0.018 0.010 0.208 0.661 0.247 0.346 0.284 0.319 0.262 0.462 0.478 0.454 0.517 0.551 0.629 0.563 0.631 0.707 0.651 0.480 0.687 0.667 0.665 0.720 0.715 0.699 0.726 0.717 0.796 0.775 0.790 0.76? 0.724 0.H75 0.846 0.7HR 0.770 0.694 0.734 0.822 0.818 0.906 0.872 0.880 0.884 0.891 0.780 0.912 0.894 0.949 1.000 0.967 0.983 0.852 1.003 1.013 1.009 1.320 1.062 0.840 1.200 0.934 1.133 1.158 1.251 1.195 1.224 1.507 1.267 1.437 1.583 1.483 1.340 1.305 1.347 1.277 1.197 1.155 1.049 1.138 1.048 0.889 0.818 0.791
578
A4
-0.424
0.108
-0.090
0.062
-0.039 -0.016 0.005 -0.018 -0.046 -0.019 -0.071 -0.032 -0.015 -0.005 -0.034 -0.043 -0.053 -0.036 -0.029 -0.085 -0.090 -0.046 -0.053 -0.038 -0.084 -0.115 -0.067 -0.060 -0.163 -0.072 -0.085 -0.080 -0.145 -0.136 -0.140 -0.143 -0.141 -0.242 -0.190 -0.185 -0.219 -0.218 -0.245 -0.251 -0.267 -0.199 -0.303 -0.310 -0.570 -0.377 -0.114 -0.496 -0.413 -0.442 -0.488 -0.673 -0.583 -0.577 -1.035 -0.727 -0.824 -1.125 -0.995 -0.890 -0.848 -0.985 -1.020 -0.993 -0.988 -0.951 -0.786 -0.964 -0.856 -0.838 -0.837
-0.034 0.014 -0.015
0.029
-0.007 0.026 -0.024 0.017 -0.014 0.008 -0.018 0.026 0.019 0.020 0.037 0.019 0.058 0.049 0.044 0.015 0.083 0.067 0.158 0.109 0.013 0.100 0.132 0.099 0.139 0.197 0.173 0.129 0.336 0.249 0.266 0.301 0.280 0.354 0.329 0.401 0.526 0.456 0.519 0.524 0.427 0.577 0.554 0.592 0.574
T(P,N)HE3
REF.
JA56B G056 JA56B G056 VL55 JA56B PE59 G056 Pff^ JA56B WI53 PE59 JA56B PE59 WI53 PE59 JA56B WI53 PE59 JA56B VL55 PE68 JA56B JA56B PE59 WI53 JA56B PE59 JA56B KN70 PA66 PA70 PE59 JA56B PEb9 WI53 PE59 JA56R VL55 Gn61B PE59 JA56B JA56B PE59 WI53 PE59 JA56B VL55 JA56B PE59 PE59 WI53 G061B PE59 VL55 WI53 PE59 WI61 G061B PE59 WI53 PE59 VL55 WI61 PE59 VL55 WI61 MC73A VL55 WI61 G061B VL55 B059 WI61 MC73A WI61 WI61 G061B WI61 G061B B059 WI61 WI61 WI61 MC73A
NEUTRON PRODUCTION CROSS SECTIONS
T(p,n)^He. a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values EXPERIMENTAL TOTAL SIGMA-T EP(MEV) 51. 1.024 54. 1.024 57. 1.025 57. 1.025 59. 1.025 62. 1.026 63. 1.026 65. 1.027 69. li027 69. 1.028 82. 1.028 60. 1.028 73. 1.029 73. 1.029 77. 1.030 81. 1.031 81. 1.031 85. 1.033 86. 1.033 88. 1.034 95. 1.037 97. 1.037 98. 1.038 101. 1.040 103. 1.041 109. 1.044 109. 1.044 115. 1.047 127. 1.047 117. 1.050 123. 1.054 130. 1.057 119. 1.058 132. 1.061 136. 1.064 146. 1,066 140. 1.068 133. 1.069 149. 1.077 151. 1 .081 160. 1 .09X 161. l.0'J4 169. 1.09'> 155. 1.097 169. 1.104 171. 1.109 176. 1.118 178. 1.122 186. 1.133 186. 1.137 174. 1.137 160. 1.140 191. 1.145 190. 1.150 203. 1.174 204. 1.179 123. 1.190 215. 1.195 219. 1.203 217. 1.208 189. 1.220 254. 1.227 230. 1.232 229. 1.237 217. 1.237 229. 1.248 158. 1.260 246. 1.261 244. 1.266 245. 1.301 264. 1.307 253. 1.343 223. 1.350 261. 1.356 230. 1.370 295. 1.400 226. 1.410 234. 1.410 245. 1.420 210. 1.430 293. 1.454 279. 1.467 279. 1.470 317. 1.500 283. 1.520 260. 1.550 266. 1.550 301. 1.560 334. 1.569 290. 1.580 326. 1.583 317. 1.590 268. 1.600 347. 1.613 264. 1.620 298. 1.620 351. 1.688 302. 1.690 345. 1.704 378. 1.750 379. 1.760 331. 1.800 336. 1.800
CROSS SECTIONS FOR THE THE REACTION T(P,N)HE3 EPIME REF. SIGMA-T REF. GI59 396. 1.804 MA65 GI59 420. 1.810 MA65 GI59 390. 1.812 MA65 BA55 321. 1.820 MA65 GI59 359. 1.828 MA65 JA56B 342. 1.920 MA65 PE59 421. 1.923 MA65 382. GI59 1.958 MA65 397. GI59 1.966 MA65 294. SA61 1.970 MA65 429. GI59 1.997 GI59 456. C070 2.020 GI59 450. SE60 2.020 MA65 431. BA55 2.020 MA65 410. GI59 2.091 MA65 414. GI59 2.099 MA65 480. GI59 2.196 MA6 5 427. BA55 2.220 MA6 5 411. C050 2.240 MA65 483. PE59 2.249 MA65 417. JA56B 2.250 MA6 5 410. C050 2.260 MA65 419. C050 2.260 GI59 527. GI59 2.404 MA65 506. PE59 2.458 MA65 447. JA568 2.460 MA65 553. VL55 2.500 MA65 477. JA56B 2.560 MA65 564. GI59 2.619 GI59 428. C050 2.620 MA65 463. Cn50 2.620 MA65 462. JA56B 2.660 MA65 528. PE59 2.666 GI59 584. GI59 2.841 MA65 600. GI59 2.845 MA65 470. JA56B 2.870 GI59 538. PF59 2.872 MA65 479. JA56B 2.970 Gl^iq 483. SF60 3.020 MA65 602. GI59 MAft'v 3.074 529. PF59 3.07H Ma65 481. JA56B 3.OHO MA6S 532. PF59 3.284 Glbq 495. JA56B 3.290 GI59 580. VL55 3.300 MA65 585. GI59 3.309 MA65 491. G061B 3.400 MA65 513. PF59 3.488 MA65 471. JA56B 3.490 MA65 315. Cn50 3.520 MA65 356. C050 3.520 GI69 391. C050 3.520 BA55 394. C050 3.520 GI69 564. GI59 3.559 MA65 468. JA56B 3.690 MA65 528. SA61 3.690 MA65 521. PE59 3.693 JA56B 538. GI59 3.819 GI59 523. GI59 3.819 MA65 495. PE59 3.897 MA65 512. VL55 3.900 eA55 439. JA56B 3.900 GI59 415. C050 4.020 MA6 5 503. GI59 4.079 MA65 419. JA56B 4.100 GI59 465. PE59 4.101 GI59 465. PE59 4.101 JA56B 408. G061B 4.300 MA65 464. GI59 4.359 MA65 439. PE59 4.400 GI59 333. 4.520 MA65 SE60 445. 4.600 GI59 VL55 434. GI59 4.619 BA55 399. 4.700 GI59 PE59 415. C070 GI5g 4.920 395. VL55 GI59 4.923 372. WI61 4.940 C050 374. 5.000 C050 PE59 345. 5.000 BA55 G061B 385. 5.216 JA56B GI59 331. 5.250 GI59 PE59 380. 5.300 GI59 VL55 335. 5.440 C070 WI61 332. PE59 5.500 PE59 350. VL55 5.900 BA55 298. WI61 5.940 C050 282. SA61 6.020 C050 300. VL55 6.400 C060 271. WI61 6.440 GI59 278. G061B 6.500 C060 260. VL55 6.800 GI59 305. B059 6.800 C070 254. W161 6.940 C050 240. WI61 7.430 PE59 233. WI61 7.930 JA56B 219. G061B 8.000 BA55 213. W161 8.450 GI59 200. G061B 241. 8.800 BA55 B059 201. 8.900 GI69 WI61 187. 8.930 PE59 SA61 191. 9.090 C070 MI61 194. 9.420 C050 WI61 9.920 C050
579
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
H. LISKIEN AND A. PAULSEN
a(e lab), Eje lab): Recommended Values
T(p,nfHe. ENERGY(WEVI
1.300
1.200
U-SIGMA-0(MB/SR) A 0 A 1 A 2
) )
16.20C 1.056 -0.07a 0.020
IT.60C 1.112 -0.220
o.lot
) > i
VALUEi;
I N P U I"
19.IOC1 1.14;1 -0.34C 0.19£1
20.70C 1.161 -0.435 0.274
)
DIFFERENTIAL
ANGLE(l)EGREei
)
FOR
)
C R U S S - S F C T I O N !;
)
1.700
) ) ) IN
-o.bac1
1.60C
1 . 5 0C
1.400
C E N T E R - • U F - •MASS
THE R E A C T I O N 22.30C 1.17C -0.516 0.34f
(MB/SR)
1.80C
T(P,N)HE3
24.00C1 1.174
1 .900
25.80C1 1.172 - 0 . 5 2 1r 0.45;
0.406
THE
)
LABORATtlRY
27.700 1.165 -0.550 0.494
)
SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.561E 0.559E 0.553E 0.544E 0.530E 0.514E 0.494E
02 02 02 02 02 02 02
0.520E 0.518e 0.511E 0.499E 0.485E 0.468E 0.449E
0 2 0 . 5 1 4 E 02 02 0 . 5 1 1 6 02 02 0 . 5 0 2 E 02 02 0 . 4 8 9 6 02 02 0 . 4 7 I E 02 02 0 . 4 5 2 E 02 02 0 . 4 3 1 E 02
0.523E 0.520E 0.5096 0.4936 0.4736 0.4516 0.42«e
02 02 02 02 02 02 02
0.539E 0.5356 0.523E 0.604E 0.480E 0.454E 0.428E
02 02 02 02 02 02 02
0.6606 0.565E 0.642E 0.520E 0.493E 0.464E 0.4356
02 02 02 02 02 02 02
0.685E 0.581E 0.565E 0.641E 0.5116 0.4786 0.446E
02 02 02 02 02 02 02
0.6156 0.6106 0.6926 0.566E 0.632E 0.495E 0.4596
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.471E 0.4466 0.416E 0.384E 0.3506 0.313E
02 02 02 02 02 02
0.4296 0.409E 0.388E 0.367E 0.344E 0.321E
02 02 02 02 02 02
0.411E 0.392E 0.374E 0.357E 0.341E 0.325E
0.406E 0.3fi6E 0.369E 0.355E 0.3426 0.3306
02 02 02 02 02 02
0.404E 0.3836 0.356E 0.352E 0.342E 0.334E
02 02 02 02 02 02
0.4076 0.384E 0.365E 0.363E 0.3446 0.3396
02 02 02 02 02 02
0.415E 0.390E 0.370E 0.357E 0.349E 0.346E
02 02 02 02 02 02
0.425F 0.3986 0.375E 0.362E 0.3546 0.3526
02 02 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.275E 0.235E 0.195E 0.157E 0.123E 0.931E
02 02 02 02 02 01
0.295E 0.2696 0.241E 0.213E 0.185E 0.1586
02 0 . 3 0 7 E 02 0 . 2 8 9 E 02 0 . 2 5 9 E 02 0 . 2 4 7 E 02 0 . 2 2 5 E 02 0 . 2 O 2 E
§1 000 ... 323 091 518 EEE
02 02 0 . 2 7 5 6 02 0 . 2 5 7 6 02 0 . 2 3 7 6
0 2 0 . 3 2 5E 0 2 0 . 3 3 4 E 02 0 . 3 1 8 E 02 0 . 3 3 0 E 02 0 . 3 0 8 E 02 0 . 3 2 5 E 02 0 . 2 9 7 E 02 0 . 3 1 7 E 02 0 . 2 8 3 E 02 0 . 3 0 7 E 0 2 0 . 2 5 7 6 02 0 . 2 9 4 F
02 02 02 02 02 02
0.343E 0.342E 0.340E 0.3366 0.329E 0.3196
02 02 02 02 02 02
0.352E 0.353E 0.3546 0.353E 0.3496 0.3436
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0 . 5 89E 0 1 0.503E 01 0.367E 01 0 . 2 7 0 6 01 0.2016 01 0.154E 01
0.134E 0.113E 0.948E 0.793E 0.666E 0.562E
02 02 01 01 01 01
0.180E 0.159E 0.140E 0.1236 0.1086 0.951E
02 0 . 2 1 8 E 02 0 . 1 9 8 6 02 0 . 1 7 9 6 02 0.1526 02 0 . 1 4 5 6 01 0.1316
02 02 02 02 02 02
0.2506 0.2326 0.214E 0.197E 0.181E 0.1556
02 02 02 02 02 02
0.2806 0.264E 0.247F 0.230E 0.214E 0.199E
02 02 02 02 02 02
0.307E 0.293E 0.278E 0.2526 0.246E 0.230E
02 02 02 02 02 02
0.3336 0.3216 0.3076 0.2916 0.276E 0.260E
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.120E 0.9656 0.792E 0.6666 0.573E 0.504E
01 0.4796 00 0.413E 00 0 . 3 6 0 6 00 0 . 3 1 8 6 00 0.285E 00 0.259E
01 0.8416 01 0.748E 01 0 . 6 7 1 E 01 0 . 6 0 8 E 01 0.5566 01 0.5146
01 0 . U 8 6 01 0 . 1 0 7 6 01 0.984E 01 0.905E 01 0.839E 01 0.7846
02 0.152E 0! 0.1406 01 0.129E 01 0.120E 01 0.112E 01 0.105E
02 02 02 02 02 02
0.184E 0.1716 0.160E 0.150E 0.1416 0.1346
02 02 02 02 02 02
0.216E 0.2026 0.1906 0.179E 0.1706 0.1526
02 02 02 02 02 02
0.245E 0.2326 0.219E 0.207E 0.197E 0.1896
02 02 02 02 02 02
155.0 160.0 165.0 170.0 175.0 180.0
0.452E 0.4156 0.3886 0.3706 0.360E 0.3566
00 00 00 00 00 00
0.481E 0.455E 0.436E 0.4236 0.4156 0.412E
01 0 . 7 4 0 6 01 Q.706E 01 0.680E 01 0.6626 01 0 . 6 5 1 6 01 0.5486
01 O.IOOE 01 0.957E 01 0 . 9 3 6 6 01 0.914E 01 0 . 9 0 1 6 01 0.8956
02 0 . 1 2 8 E 01 0 . 1 2 3 6 01 0 . 1 1 9 E 01 0.117E 01 0 . 1 1 5 E 01 0.1166
02 02 02 02 02 02
0.155E 0.150E 0.145E 0.1436 0.1416 0.140E
02 02 02 02 02 02
0.1826 0.175E 0.171E 0.168E 0.166E 0.155E
02 02 02 02 02 02
ENERGY(MEV)
0.239E 0.224E 0.212E 0.206E 0.200E 0.199E
01 01 01 01 01 01
2.200
2.100
2.000
C E N T E R -•OF- -MASS U-SIGMA-0(MR/SR) A 0 A 1 A 2 A 3
DIFFERENTIAL
ANGLE(DEGREE)
C R O S S - ;S E C T I O N S
0.6556 0.648E 0.6296 0.5996 0.5616 0.5206 0.4786
02 02 02 02 02 02 02
0.709E 0.702E 0.679E 0.6446 0.601E 0.5526 0.504E
02 02 02 02 02 02 02
0.770E 0.7516 0.7356 0.6956 0.6456 0.5906 0.5336
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.4406 0.4096 0.3856 0.3696 0.3606 0.3586
02 02 02 02 02 02
0.459E 0.421E 0.392E 0.3736 0.3636 0.360E
02 02 02 02 02 02
0.4816 0.435E 0.400fc 0.3766 0.353E 0.359E
65.0 70.0 75.0 80.0 85.0 90.0
0 . 3 6 0E 0.3646 0.3676 0.3696 0.3686 0.3646
02 02 02 02 02 02
0.3626 0.368E 0.374E 0.380E 0.3e2E 0.381E
02 02 02 02 02 02
0.351E 0.358E 0.3776 0.3856 0.3916 0.3946
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0.3576 0.3476 0.334E 0.3206 0.3056 0.290E
02 02 02 02 02 02
0.377E 0.3706 0.3596 0.3476 0.333E 0.3186
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.2756 0.261E 0.2486 0.2366 0.2256 0.216E
02 02 02 02 02 02
0.304E 0.290E 0.276E 0.264E 0.254E 0.2446
155.0 160.0 165.0
0.209E 0.2036 0.198E 0.1946 0.1926 0.1926
02 02 02 02 u2 02
0.2356 0.2306 0.2256 0.2216 U.2I9E 0.218E
Iru.U
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
FOR
40.400 0.980 -0.582 0.513 -0.01]L
0.0 5.0 10.0 15.0 20.0 25.0 30.0
175.0 180.0
VALU6S
2.500
2.400
2.300
I N P U l'
36.300 1.047 -0.531 0.591 -O.OOT
33.000 1.100 -0.660 0.563 -0.003
30.000 1.146 -0.674 0.528 0.000
02 02 02 02 02 02
THE
REACTIUIM
44.700
) )
o.9o;
-0.533 0.63^ -0.015 (MB/SR>
iIN
)
48.70C 0.856 -0.502 0.654 - O . O I E1 •r H E
2.700
2.600
TIP,NIHE3 55.200 0.783 -0.453 0.708 -0.028
52.500 0.810 - 0 . 4 7 " ir 0.690 -0.02 3
LABORATORY
SYSTEM
02 0.9286 02 0 . 9 1 6 E 02 0 . 8 8 2 E 02 0.828E 02 0 . 7 6 0 6 02 0 . 5 8 3 6 02 0.605E
02 02 02 02 02 02 02
O.IOOE 0.989E 0.9606 0.e89£ 0.812E 0.7256 0.6356
03 02 02 02 02 02 02
0.107E 0.105E O.IOIE 0.947E 0.861E 0.7646 0.654E
03 03 03 02 02 02 02
0.112E 0.1106 0.105E 0.9876 0.8956 0.7926 0.6856
03 03 03 02 02 02 02
02 0 . 5 0 8 6 02 0 . 4 5 3 E 02 0 . 4 1 0 6 02 0 . 3 8 0 6 02 0 . 3 6 2 6 02 0 . 3 5 5 6
02 0 . 5 3 0 E 02 0 . 4 5 5 6 02 0.412E 02 0 . 3 7 4 E 02 0.351E 02 0 . 3 4 1 E
02 02 02 02 02 02
0.550E 0.4756 0.4136 0.368E 0.340E 0.328E
02 02 02 02 02 02
0.568E 0.482E 0.412E 0.360E 0.327E 0.312E
02 02 02 02 02 02
0.5816 0.489E 0.413E 0.3556 0.3196 0.3016
02 02 02 02 02 02
0.357E 0.3646 0.3756 0.3856 0.3966 0.402E
02 0 . 3 4 2 E 02 0.351E 02 0.364E 02 0 . 3 7 8 E 02 0.3926 02 0.4026
02 02 02 02 02 02
0.328E 0.3386 0.3646 0.372E 0.389E 0.404E
02 02 02 02 02 02
0.311E 0.3226 0.3406 0.3626 0.383E 0.403E
02 02 02 02 02 02
0.3006 0.311E 0.3306 0.3546 0.3796 0.4016
02 02 02 02 02 02
0.3936 0.3886 0.3806 0.369E 0.357E 0.344E
02 0 . 4 0 4 E 02 0 . 4 0 9 6 02 0 . 4 0 3 6 0 2 0 . 4 1 1 6 02 0 . 3 9 8 E 02 0 . 4 1 0 6 02 0 . 3 8 9 E 02 0 . 4 0 5 6 02 0 . 3 7 9 6 02 0 . 3 9 6 E 02 0 . 3 6 7 6 02 0 . 3 8 6 E
02 02 02 02 02 02
0.4156 0.4216 0.4236 0.4216 0.4156 0.407E
02 02 02 02 02 02
0.418E 0.428E 0.434E 0.435E 0.432E 0.426E
02 02 02 02 02 02
0.4206 0.4346 0.4426 0.445E 0.445E 0.4416
02 02 02 02 02 02
02 02 02 02 02 02
0.3306 0.3166 0.3036 0.2806 0.2706
02 0 . 3 5 4 6 02 0 . 3 4 1 E 02 0 . 3 2 8 E 02 0.316E 02 0 . 3 0 5 6 02 0 . 2 9 5 6
02 0.375E 02 0 . 3 6 3 E 02 0 . 3 5 1 E 02 0 . 3 4 0 6 02 0.3296 02 0 . 3 2 0 6
02 02 02 02 02 02
0.397E 0.3856 0.375E 0.364E 0.3546 0.344E
02 02 02 02 02 02
0.418E 0.408E 0.398E 0.388E 0.378E 0.369E
02 02 02 02 02 02
0.4356 0.426E 0.417E 0.4076 0.3986 0.3896
02 02 02 02 02 02
02 02 02 02 02 U2
0.2526 0.2556 0.2506 0.2466 0.244E 0.^4:>c
02 02 02 02 02 02
02 02 02 02 02 02
02 02 02 02 02 02
0.335E 0.3296 0.324E 0.320E 0.318E 0.3176
02 02 02 02 02 02
0.351E 0.354E 0.349E 0.346E 0.343E 0.342E
02 02 02 02 02 02
0.3816 0.3756 0.3696 0.356E 0.3536 0.3526
02 02 02 02 02 02
0.29ie
0.847E 0 . 8 37 E 0.8076 0.7516 0.703E 0.6376 0.5706
0.287E 0.2816 0.2756 0.2716 0.269E U.268E
580
0.3U6 0.3056 0.2996 0.2956 0.2936 0.2926
NEUTRON PRODUCTION CROSS SECTIONS
T0>,«)3He. ENERGY(MEV)
1.200
aid lab), EJO lab): Recommended Values 1.300
1.400
1.500
1.600
1.700
INPUT VALUES FOR THE REACTION T ( P , N ) H E 3 REST ENERGY IN MEV FOR PRUJECTILE TARGET PRODUCT RESIDUAL NUCLEUS
Tl= 938.282 T2=2808.951 T3= 9 3 9 , 5 7 6 T4=2808.421
ENERGY OF PARTICLE-3 (MEV)
ANGLE(DEGREe)
0.463 0.420 0.379 0.341 0.307 0.275
0.996 0.992 0.981 0.962 0.937 0.905 0.867 0.825 0.780 0.732 0.682 0.631 0.58 1 0.532 0.485 0.440 0.399 0.360 0.325
1.099 1.095 1 .083 1.063 1.036 1.001 0.962 0.917 0.868 0.816 0.763 0.708 0.654 0.601 0.550 0.501 0.456 0.413 0.375
0.200 0.179 0.159 0.143 0.129 0.117
0.247 0.221 0.199 0.180 0.163 0.149
0.293 0.265 0.240 0.217 0.198 0.181
0.340 0.308 0.280 0.256 0.233 0.214
0.136 0.126 0.117 0.109 0.103 0.098
0.167 0.155 0.144 0.135 0.128 0.121 0.116 0.112 0.109 0.107 0.106 0.106
0.198 0.184 0.172 0.162 0.153 0.146
0.050 0.048 0.047 0.046 0.045 0.045
0.106 0.098 0.090 0.084 0.079 0.075 0.071 0.069 0.067 0.065 0.064 0.064
2.300
2.400
2.300
0.32 3 0.288 0.256 0.226 0.199 0.175
0.108 0.094 O.OBl 0.071 0.062 0.055
0.154 0.136 0.120 0.107 0.095 0.085
0.024 0.021 0.019 0.017 0.016 0.015
0.049 0.045 0.040 0.037 0.034 0.032
0.077 0.070 0.065 0.060 0.056 0.053
0.014 0.013 0.013 0.012 0.012 0.012
0.031 0.029 0.028 0.028 0.027 0.027
2.200
0.351 0.349 0.342 0.331 0.316 0.297 0.275
0.466 0.463 0.456 0.443 0.426 0.406 0.381
0.575 0.573 0.564 0.561 0.532 0.509 0.482
0.683 0.680 0.670 0.655 0.635 0.610 0.5B0
35.0 AO.O 45.0 50.0 55.0 60.0
0.251 0.226 0.199 0.172 0.146 0.121
0.354 0.325 0.295 0.265 0.234 0.205
0.462 0.420 0.386 0.352 0.317 0.283
0.547 0.512 0.474 0.436 0.397 0.359
65.0 70.0 75.0 80.0 85.0 90.0
0.099 0.078 0.061 0.046 0.035 0.026
0.177 0.152 0.129 0.108 0.091 0.075
0.251 0.221 0.193 0.168 0.145 0.125
95.0 100.0 105.0 110.0 115.0 120.0
0.019 0.014 0.011 0.008 0.006 0.005
0.063 0.053 0.044 0.037 0.032 0.028
125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
0.004 0.003 0.003 0.003 0.002 0.002 0.002 0.002 0.002 0.001 0.001 0.001
2.000
-0.764
I N THE LABORATORY SYSTEM 0.788 0.785 0.775 0.759 0.737 0.709 0.677 0.641 0.602 0.561 0.519 0.476 0.434 0.393 0.354 0.318 0.284 0.253 0.225
0.0 5.0 10.0 15.0 20.0 25.0 30.0
ENERGY(MEV)
0-VALUE I N MEV 0=
0.893 0.889 0.878 0.861 0.837 0.807 0.773 0.734 0.691 0.647 0.601 0.554 0.508
0.093 0.090 0.088 0.086 0.08 5 0.084
0.140 0.135 0.132 0.129 0.128 0.128
2.700
INPUT VALUES FUR THE REACTION T ( P , N ) H E 3 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
Tl= 938.282 T2=2808.951 T3= 9 3 9 . 5 7 6 74=2808.421
ENERGY OF PARTICLE-3 (MEV)
0-VALUE
IN MEV 41=
-0.764
I N THE LABORATORY SYSTEM
1.406 1.401 1.387 1.363 1.330 1.290 1.242 1.188 1.130 1.068 1.003 0.937 0.871
1.508 1.503 1.487 1.462 1.428 1.385 1.335 1.278 1.217 1.151 1.083 1.013 0.943
1.609 1.604 1.588 1.562 1.525 1.481 1.428 1.368 1.303 1.234 1.162 1.089 1.015
1.7U 1.705 1.688 1.661 1.623 1.576 1.520
1.B12 1.806 1.788 1.760 1.720 1.671 1.613
1.913 1.907 1.888 1.858 1.817 1.766 1.705
1.008 0.955 0.900 0.843 0.785 0.727
1.304 1.300 1.286 1.263 1.232 1.194 1.149 1.098 1.043 0.984 0.923 0.861 0.799
1.458 1.390 1.317 1.242 1.164 1.087
1.547 1.476 1.400 1.321 1.240 1.159
1.637 1.562 1.4B3 1.400 1.315 1.230
0.670 0.615 0.562 0.513 0.467 0.425
0.738 0.679 0.623 0.570 0.520 0.474
0.806 0.744 0.683 0.626 0.573 0.524
0.875 0.808 0.744 0.683 0.627 0.574
0.943 0.872 0.804 0.740 0.680 0.624
1.011 0.936 0.865 0.797 0.733 0.674
1.078 I . 000 0.925 0.853 0.786 0.724
1.146 1.054 0.985 0.910 0.839 0.773
0.386 0.351 0.321 0.293 0.269 0.248
0.433 0.395 0.361 0.331 0.305 0.282
0.479 0.439 0.402 0.370 0.341 0.315
0.526 0.482 0.443 0.408 0.377 0.349
0.573 0.526 0.484 0.446 0.413 0.383
0.619 0.570 0.525 0.485 0.449 0.418
0.666 0.614 0.566 0.523 0.485 0.452
0.713 0.657 0.607 0.562 0.522 0.486
0.230 0.214 0.200 0.188 0.179 0.171 0.164 0.159 0.155 0.152 0.150 0.150
0.261 0.244 0.229 0.216 0.205 0.196 0.188 0.182 0.178 0.175 0.173 0.172
0.293 0.274 0.257 0.243 0.231 0.221 0.213 0.206 0.202 0.198 0.196 0.195
0.325 0.304 0.286 0.271 0.258 0.247 0.238 0.231 0.225 0.221 0.219 0.218
0.357 0.335 0.315 0.299 0.284 0.273 0.263 0.255 0.249 0.245 0.243 0.24<:
0.390 0.366 0.345 0.327 0.311 0.298
0.422 0.396 0.374 0.355 0.338 0.325
0.455 0.427 0.403 0.383 0.365 0.351
0.288 0.280 0.273 0.26 9 0.266 u.^65
0.313 0.304 0.297 0.293 U.2vu U.2B9
0.339 0.329 0.322 0.317 U.314 0.313
1.202 1.198 1.185 1.163 1.134 1.098 1.055
581
Nuclear Data Tables, Vol. H , No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(/>,ii)3He. ENERGY(MEV)
2.800
a(6 lab), £^^(6 lab): Recommended Values 3.0UU
2.90U
3.500
4.000
4.500
5.500
5.000
CENTER--OF--MASS INPUT VALUES FOR THE REACTION T ( P , N ) H E 3 o-iIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 ANGLEIDEGREE)
58.600 0.75; -0.451 0.740 - 0 . 0 4 1I 0.000
57.400 0.764 -0.455 0.724 -0.033 0.000
)
59.400 0.745 -0.450 0.753 -0.048 0.000
5 0 . 9 00 0.753 -0.520 0.910 -0.167 0.024
58.100 0.738 -0.472 0.832 -0.098 0.000
29.400 0.888 -0.699 1.148 -0.478 0.141
35.300 0.827 -0.635 1.069 -0.355 0.094
42.200 0.784 -0.576 0.990 -0.254 0.056
DIFFERENTIAL CROSS-:SECTIONS (MB/SRI 1; N IrH£ LABORATORY SYSTEM
0.0 5.0 lO.O 15.0 20.0 25.0 30.0
0.115E 0.114E 0.109E O.IOIE 0.923E 0.815E 0.702E
03 03 03 03 02 02 02
0.117E 0.115E O.lllE 0.103E 0.937E 0.827E 0.711E
03 03 03 03 02 02 02
0.118E 0.116E O.lllE 0.104E 0.946E 0.835E 0.718E
03 03 03 03 02 02 02
0.113E 0.112E 0.107E O.IOOE 0.918E 0.814E 0.703E
03 03 03 03 02 02 02
0.981E 0.9686 0.9316 0.872E 0.796E 0.708E 0.613E
02 02 02 02 02 02 02
0.805E 0.794E 0.765E 0.718E 0.658E 0.5886 0.514E
02 02 02 02 02 02 02
0.668E 0.6606 0.6366 0.599E 0.5526 0.497E 0.4406
02 02 02 02 02 02 02
0.553E 0.546E 0.528E 0.5006 0.454E 0.424E 0.381E
02 02 02 02 02 02 02
35.0 'fO.O 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 UO.O 115.0 120.0 125.0 130.0 135.0 I'tO.O 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
0.593E 0.495E 0.414E 0.353E 0.313E 0.293E 0.290E 0.301E 0.322E 0.34BE 0.375E 0.400E 0.422E 0.439E 0.450E 0.456E 0.457E 0.455E
02 02 02 02 02 02 02 02 02 02 02 02
0.599E 0.498E 0.413E 0.349E 0 . 3 0 6E 0.284E 0.280E 0.291E 0.312E 0.339E 0.368E 0.395E
02 02 02 02 02 02 02 02 02 02 02 02
02 02 02 02 02 02 02 02 02 02 02 02
0.591E 0.487E 0.397E 0.324E 0.272E 0.2416
02 02 02 02 02 02
0.519E 0.430E 0 . 3 5 IE 0.2866 0.238E 0.207E
0.338E 0.297E 0.257E 0.2216 0.189E 0.162E
02 02 02 02 02 02
0.193E 0.1946 0.2086 0.2326 0.2626 0.2956
02 02 02 02 02 02
0.3826 0.3276 0.276E 0.232E 0.195E 0.166E 0.148E 0.140E 0.142E 0.153E 0.171E 0.195E
02 02 02 02 02 02
02 02 02 02 02 02
0.4406 0.369E 0.3066 0.2526 0.210E 0.180E 0.164E 0.1606 0.1686 0.185E 0.2096 0.2376
02 02 02 02 02 02
0.230E 0.236E 0.256E 0.285E 0.3196 0.3536
02 02 02 02 02 02 02 02 02 02 02 02
02 02 02 02 02 02
0.142E 0.130E 0.1266 0.1316 0.144E 0.163E
02 02 02 02 02 02
02 02 02 02 02 02
0.420E 0.439E 0.452E 0.46ie 0.464E 0.464E
02 02 02 02 02 02
0.604E 0.501E 0.413E 0.347E 0.301E 0.278E 0.273E 0.283E 0.304E 0.332E 0.362E 0.391E 0.417E 0.439E 0.454E 0.465E 0.470E 0.471E
02 02 02 02 02 02
0.3866 0.416E 0.440E 0.459E 0.4726 0.480E
02 02 02 02 02 02
0.3296 0.3606 0.388E 0.4126 0.430E 0.445E
02 02 02 02 02 02
0.2686 0.2986 0.327E 0.353E 0.374E 0.3926
02 02 02 02 02 02
0.222E 0.251E 0.279E 0.306E 0.329E 0.349E
02 02 02 02 02 02
0.186E 0.212E 0.239E 0.265E 0.290E 0.311E
02 02 02 02 02 02
0.450E 0.443E 0.434E 0.425E 0.416E 0.408E
02 02 02 02 02 02
0.4606 0.454E 0.447E 0.438E 0.430E 0.422E
02 02 02 02 02 02
0.469E 0.464E 0.457E 0.449E 0.442E 0.434E
02 02 02 02 02 02
0.4846 0.485E 0.483E 0.479E 0.474E 0.469E
02 02 02 02 02 02
0.4546 0.461E 0.464E 0.465E 0.464E 0.462E
02 02 02 02 02 02
0.406E 0.416E 0.423E 0.428E 0.431E 0.432E
02 02 02 02 02 02
0.3666 0.3796 0.3896 0.3976 0.4026 0.4056
02 02 02 02 02 02
0.330E 0.345E 0.358E 0.3676 0.374E 0.380E
02 02 02 02 02 02
0.400E 0.394E 0.389E 0.385E 0.382E 0.382e
02 02 02 02 02 02
0.415E 0.408E 0.403E 0.400E 0.397E 0.397E
02 02 02 02 02 02
0.427E 0.421E 0.416E 0.413E 0.410E 0.410E
02 02 02 02 02 02
0.4646 0.460E 0.4566 0.4536 0.451E 0.451E
02 02 02 02 02 02
0.460E 0.458E 0.4566 0.4546 0.4536 0.4526
02 02 02 02 02 02
0.4326 0.4326 0.431E 0.4316 0.430E 0.430E
02 02 02 02 02 02
0.4086 0.409E 0.410E 0.410E 0.4106 0.4106
02 02 02 02 02 02
0.383E 0.386E 0.388E 0.389E 0.389E 0.3906
02 02 02 02 02 02
ENERGY(MEV)
6 . 0 0 01
6 . 5 0 01
7.5O01
7.OO01
8.00C f
8.5O01
9 . 0 0 01
9.500
CENTER-•OF--MASS INPUT VALUES, FOR THE REACTION T(P,N1HE3 0-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4
24.80C 1 0 . 9 6 31 -0.768 1.228 1 -0.617 0.194
ANGLE(DEGREE)
14.100 15.20C 1 14.500 14.00C 1 16.40C 1 1.050 1.167 1.146 1.107 1.152 I -0.667 - 0 . 9 0C1 -0.831 -0.751 - 0 . 9 3 2I 0.920 1.036 1.273 1 1.15' t 1.361 -0.879 -0.945 -l.OOC -0.987 - 0 . 9 7 Si 0.576 0.553 0.460 0 . 5 1 3I 0 . 3 9 61 DIFFERENTIAL CROSS-SECTIONS. (MB/SR) IN THE LABORATORY SYSTEM 21.IOC 1 1.039 - 0 . 8 4 C1 1.301 -0.760 0.26C1
18.40C 1 1.104 -0.901 1.367 -0.901 0.331
)
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.464E 0.459E 0.445E 0.424E 0.398E 0.368E 0.338E
02 02 02 02 02 02 02
0.393E 0.389E 0.378E 0.361E 0.341E 0.320E 0.298E
02 02 02 02 02 02 02
0.342E 0.338E 0.329E 0.315E 0.299E 0.283E 0.267E
02 02 02 02 02 02 02
0.304E 0.300E 0,2916 0.27,8 6 0.254E 0.250E 0.2386
02 02 02 02 02 02 02
0.2816 0.277E 0.267E 0.254E 0.239E 0.226E 0.217E
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.307E 0.276E 0.246E 0.216E 0.188E 0.162E
02 02 02 02 02 02
0.277E 0.255E 0.233E 0.210E 0.186E 0.162E
02 02 02 02 02 02
0.253E 0.238E 0.222E 0.204E 0.183E 0.161E
02 02 02 02 02 02
0.229E 0.220E 0.210E 0.197E 0.181E 0.162E
02 02 02 02 02 02
0.211E 0.207E 0.202E 0.194E 0.182E 0.166E
65.0 70.0 75.0 80.0 85.0 90.0
0.141E 0.126E 0.117E 0.117E 0.125E 0.139E
02 02 02 02 02 02
0.141E 0.123E O.lllE 0.107E O.llOE 0.121E
02 02 02 02 02 02
02 02 02 01 01 01
0.159E 0.183E 0.209E 0.235E 0.259E 0.282E
02 02 02 02 02 02
0.138E 0.159E 0.183E 0.208E 0.232E 0.255E
02 02 02 02 02 02
02 02 02 01 01 02 02 02 02 02 02 02
0.142E 0.123E 0.107E 0.975E 0.944E 0.985E
95.0 100.0 105.0 IIO.O 115.0 120.0
0.139E 0.120E 0.106E 0.989E 0.989E 0.106E 0.120E 0.139E 0.162E 0.186E 0.210E 0.234E
0.109E 0.125E 0.145E 0.167E 0.190E 0.2126
02 02 02 02 02 02
0.1486 0.1286 0.1126 0.9966 0.9326 0.936E O.IOOE 0.113E 0.1306 0.149 6 0.170E 0.1906
02 02 02 02 02 02 02 02 02 01 01 01 02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.302E 0.319E 0.333E 0.344E 0.353E 0 . 3 5 9E
02 02 02 02 02 02
0.276E 0.294E 0,309E 0.322E 0.332E 0.340E
02 02 02 02 02 02
0.255E 0.274E 0.290E 0.304E 0.315E 0.324E
02 02 02 02 02 02
0.2336 0.251E 0.267E 0.2816 0.292E 0.302E
02 02 02 02 02 02
0.2106 0.2286 0.243E 0.257E 0.268E 0.277E
02 02 02 02 02 02
155.0 160.0 165.0 170.0 175.0 180.0
0.364E 0.368E 0.370E 0.372E 0.373E 0.373E
02 02 02 02 02 02
0.346E 0.350E 0.353E 0.355E 0,357E 0.357E
02 02 02 02 02 02
0.330E 0.336E 0.339E 0.342E 0.343E 0.3446
02 02 02 02 02 02
0.3096 0.314E 0.3186 0.3216 0.3226 0.3236
02 02 02 02 02 02
0.285E 0.290E 0.2946 0.297E 0.2996 0.299E
02 02 02 02 02 02
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
582
0.2676 0.263E 0.252E 0.2376 0.2216 0.2086 0.2006 0.196E 0.1946 0.1936 0.1906 0.1816 0.1686 0.151E 0.132E 0.114E O.IOOE 0.911E 0.883E 0.9196 O.lOlE 0.115E 0.132E 0.151E 0.170E
02 02 02 02 02 02 02
0.188E 0.2056 0.2216 0.2346 0.245E 0.254E 0.2626 0.268E 0.272E 0.275E 0.276E 0.277E
02 02 02 02 01 01 01 02 02 02 02 02
0.257E 0.253E 0.241E 0.224E 0.206E 0.1926 0.183E 0.180E 0.1816 0.183E 0.183E 0.178E 0.168E 0.152E 0.1346 0.1166 O.IOOE 0.8896 0.8356 0.842E 0.908E 0.102E 0.116E 0.133E 0.151E
02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 01 01 01 01 02 02 02 02
02 02 02 02 02 02
0.168E 0.184E 0.199E 0.212E 0.223E 0.232E
02 02 02 02 02 02
02 02 02 02 02 02
0.239E 0.245E 0.249E 0.252E 0.254E 0.254E
02 02 02 02 02 02
02 02 02 02 02 02
0.2596 0.2546 0.240E O.220E 0.200E 0.184E 0.1736 0.1706 0.172E 0.176E 0.179E 0.176E 0.168E 0.1546 0.137E 0.H8E O.IOIE 0.885E 0.8096 0.7956 0.8396 0.932E 0.106E 0.1216 0.138E 0.1546 0.170E 0.ie4E 0.197E 0.207E 0.217E 0.224E 0.230E 0.234E 0.2376 0.2396 0.2396
02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02 01 01 01 01 01 02 02 02 02 02 02 02 02 02 02 02 02 02 02 02
NEUTRON PRODUCTION CROSS SECTIONS
T(p,n)3He. ENERGYlMEVI
2.800
a(8 lab), Efl(O lab): Recommended Values 2.900
4.000 4.500 3.000 3.500 INPUT VALUES FOR THE REACTION TIP,NIHE3
REST ENERGY IN MEV FOR PRUJECTI LE Tl~ 938.282 TARGET T2~2808.951 PRUDUCT T3= 939.576 RESIDUAL NUCLEUS T4=2808.421
5.000
5.5 0 0
Q-VALUE IN MEV (,)=
-0.764
0.0 5.0 10.0 15.0 20.0 25.0 30.0
2.015 2.008 1.989 1.<)58 1.915 1.861 1.798
35.0 40.0 45.0 50.0 55.0 60.0
1.727 1.649 1.566 1.479 1.391 1.302
ENERGY OF PAR TI CL E-3 (MEV) IN THE LABORATORY SYSTEM 3.724 3.222 2.720 2.217 4.225 3.213 3.713 2.210 2.712 4.213 2.18<) 3.184 3.681 2.687 4.177 2.647 2.155 4.118 ~:~~~ ~:m 2.592 2.108 4.037 3.466 2.995 2.050 2.523 3.936 3.359 2.901 1.982 2.442 3.817 3.239 2.795 1.816 2.351 1.905 3.682 2.679 3.107 1.735 2.250 1.821 3.534 2.966 2.555 1.648 2.143 3.376 1.731 2.818 2.425 1.558 2.032 1.637 3.211 2.666 1.917 2.292 3.041 1.466 1.541 2.158 2.513 1.802 2.869 1.373 1.445
65.0 70.0 75.0 80.0 85.0 90.0
1.214 1.128 1.045 0.966 0.892 0.823
1.105 1.023 0.945 0.873
l:m
1.349 1.256 1.166 1.080 0.999 0.923
1.687 1.575 1.466 1.362 1.264 1.172
2.024 1.893 1.166 1.644 1.529 1.421
2.361 2.211 2.066 1.926 1.794 1.670
2.697 2.529 2.365 2.208 f·059 .919
2.6 6 5 2.490 2.324 2.1 68
95.0 100.0 105.0 110.0 fl5.0 20.0
0.759 0.701 0.648 0.601 0.558 0.521
0.806 0.145 0.690 0.640 0.595 0.555
0.853 0.789 0.731 0.678 0.631 0.590
1.087 1.008 0.931 0.872 0.814 0.762
1.321 1. 228 1.143 1.067 0.998 0.936
1.554 1.448 1.350 1.261 1.181 1.11 0
1.188 1.667 1.557 1.456 1.365 1.284
2.022 1.887 1.7 6 3 1. 651 1.54<) 1.458
125.0 130.0 135.0 140.0 145.0 150.0
0.487 0.458 0.433 0.411 0.393 0.377
0.520 0.489 0.463 0.439 0.420 0.403
0.553 0.520 0.492 0.468 0.447 0.430
0.717 0.676 0.641 0.611 0.585 0.563
0.881 0.833 0.791 0.754 0.723 0.696
1.046 0.990 0.941 0.898 0.861 0.831
1.211 1.147 1.091 1.042 1.000 0.965
1.376 1.304 1.241 1.186 1.139 1.100
155.0 160.0 165.0 170.0 175.0 180.0
0.364 0.354 0.346 0.341 0.338 0.337
0.390 0.378 0.371 0.365 0.362 0.360
0.416 0.404 0.395 0.389 0.386 0.384
0.545 0.530 0.519 0.511 0.507 0.505
0.675 0.657 0.644 0.634 0.629 0.627
0.805 0.785 0.769 0.758 0.752 0.749
0.936 0.912 0.895 0.882 0.874 0.672
1.067 1.040 1.020 1.006 0.998 0.995
6.000
6.500
8.500 7.500 6.000 7.000 INPUT VALUES FOR THE REACTION TlP,NIHE3
9.000
9.500
ANGLE (DEGREE)
ENERGY lMEV I
2.116 2.109 2.089 2.056 2.012 1.956 1.890
REST ENERGY IN MEV FOR PROJECT I LE TARGET PRODUCT RESIOUAL NUCLEUS ANGLE l DEGREE)
ENERGY OF PAR TICL 6.230 6.213 6.162 6.077 5.962 5.816 5.648
Tl= 938.282 T2=2808.951 73= 939.576 T4=2808.421
4.726 4.712 4.673
~:gn
4.406 4.274
4.125 3.962 3.186 3.603 3.414 3.224
~:gU
Q-VALUE IN MEV
E-3 I MEV I IN THE LA80RATORY SYST EM 6.730 7.231 7. 731 8.230 6.208 7.709 6.712 7.211 7.647 8.142 6.657 7.152 7.544 8.032 6.566 7.055 6.923 7.403 7.683 6.442 7.226 7.695 6.267 6.757 7.018 7.474 6.105 6.561
Q~
-0.764
0.0 5.0 10.0 15.0 20.0 25.0 30.0
5.229 5.214 5.171 5.099 5.001 4.878 4.733
5.730 5.714 5.666 5.586 5.482 5.348 5.191
35.0 40.0 45.0 50.0 55.0 (,0.0
4.570 4.390 4.198 3.996 3.789 3.579
5.012 4.817 4.607 4.388 4.162 3.934
5.455 5.244 5.017 4.780 4.536 4.288
5.897 5.670 5.427 5.172 4.909 4.643
6.340 6.097 5.836 5.563 5.282 4.997
6.782 6.523 6.246 5.955 5.655 5.352
7.224 6.949 6.655 6.346 6.028 5.70(,
7.666 7.376 7.064 6.736 6.401 6.060
65.0 70.0 75.0 80.0 85.0 90.0
3.370 3.164 2.964 2.772 2.589 2.416
3.706 3.481 3.263 3.053 2.853 2.665
4.042 3.799 3.562 3.335 3.118 2.914
4.377 4.116 3.861 3.616 3.382 3.162
4.713 4.433 4.160 3.897 3.647 3.411
5.049 4.750 4.459 4.178 3.911 3.659
5.384 5.0(,7 4.757 4.459 4.176 3.907
5.719 5.383 5.056 4.741 4.440 4.15b
95.0 100.0 105.0 110.0 115.0 120.0
2.256 2.107 1.970 1.846 1.733 1.632
2.489 2.326 2.177 2.041 1.917 1.806
2.723 2.546 2.384 2.235 2.101 1.980
2.956 2.76b 2.590 2.430 2.285 2.154
3.190 2.985 2.797 2.625 2.469 2.329
3.423 3.205 3.003 2.819 2.653 2.503
3.657 3.424 3.210 3.014 2.837 2.677
3.890 3.643 3.416 3.209 3.020 2.851
125.0 130.0 135.0 140.0 145.0 150 .0
1.542 1.462 1.392 1.331 1.279 1.235
1.707 1.620 1.543 1.476 1.418 1.370
1.873 1.777 1.693 1.620 1.558 1.505
2.038 1.935 1.844 1.765 1.697 1.640
2.203 2.092 1.995 1.910 1.837 1.775
2.369 2.250 2.145 2.054 1.976 1.910
2.534 2.407 2.296 2.199 2.115 2.045
2.699
155.0 160.0 l65.0 70.0 175.0 180.0
1.198 1.169 1.147 1.131 1.121 1.118
1.330 1.297 1.273 1.255 1.245 1.241
1.461 1.426 1.399 1.380 1.368 1.365
1.592 1.554 1.525 1.504 1.4"12 1.488
1.724 1.682 1. 651 1.629 1. 615 1.611
1.855 1.811 1.777 1.753 1.739 1.734
1.986 1.939 1.903 1.878 1.862 1.857
2.117 2.067 2.029 2.002 1.986 1.981
583
8.730 8.707 8.636 8.521 8.362 6.164 7.931
~.565
.446 2.343 2.255 2.180
Nudeor Data Tables, Vol. 1 L No.7, 1973
H. LISKIEN AND A. PAULSEN
a(B lab), En(B lab): Recommended Values ENERGY IMEV 1
10.000
U-SIGMA-OIMB/SRI A 0
~ ~
A 3 A 4
CENTER-Of-MASS INPUT VALUES fUR THE REACTION TIP,N1HE3 14.400 0.984 -0.560 0.796 -0.801 0.581
ANGLE (DEGREE I
0.264E 0.25BE O.243E 0.221E 0.19BE o .180E 0.lb8E
02 02 02 02 02 02 02
35.0 40.0 45.0
0.165E 0.167E 0.173E O.l77E 0.176E 0.lb9E 0.157E 0.139E o .120E 0.102E o .878E 0.783E 0.747E 0.769E 0.842E 0.955E 0.109E o .124E
02 02 02 02 02 02 02 02 02 02 01 01 01 01 01 01 02 02
50.0
55.0 60.0 65.0
70.0
75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0
160.0 165.0 170.0 175.0 180.0
Noeloar Data Tablo., Val. 11, No.7, 1973
DIfFERENTIAL CRUSS-SECTIUNS 1MB/SRI IN THE LABURATURY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
o .139E
02 0.154E 02 0.lS1E 02 O.l'llE 02 0.200E 02
0.16 BE 02
0.20SE 02 02 02 02 02 02
o .213E 0.21SE 0.221E 0.223E 0.223E
584
NEUTRON PRODUCTION CROSS SECTIONS
a«() lab), En«(j lab): Recommended Values ENERGY (MEV 1
10.000
INPUT VALUES FUR THE REACTIUN TlP,NIHE3 REST ENERGY IN MEV FOR PRUJECTILE T1~ 938.282 Q-VALUE IN MEV Q= TARGET T2~28D8. 951 PRUUUCT T3~ 939.516 RESIDUAL NUCLEUS T4~28D8.421 ANGL E(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0
ENERGY OF PARTICLE-3 lMEV) IN THE LABORATORY SYSTEM 9.230 9.206 90131 9.010 8.843 8.634 8.388
35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0
80108 7.802 7.413 70129 6.774 6.414 6.055 5.700 5.354
95.0 100 .0 L05.0 110.0
4.123 3.863 3.623 3.403 3.204 3.025
125.0 130.0 135.0 140.0 145.0 150.0
2.864
155.0 160.0 165.0
2.249 2.196 2.155 2.127 2.109 2.104
Hfi:8
ng:8
180.0
-0.764
5.021
4.704 4.404
2.722
2.597 2.488 2.394 2.315
585
Nuclear Dalo Table.s, Vol. 1I, No.7, 1973
H. LISKIEN AND A. PAULSEN
0'(0 c.m.), Legendre Coefficients (c.m.), a(total) Recommended and Experimental Values 0
a(O lab), En(B lab) Recommended Values
Nu"l.o, Data Tobl••, Vol. 11, No.7, 1973
586
NEUTRON PRODUCTION CROSS SECTIONS
D(~n)3He.
0(0 0 c.m.),
Legendre Coefficients, o(total) Recommended and Experimental Values SIGMA-O
AD, AI, ...
SIGMA-T
c.rn.) Legendre coefficients o(total) 0(0
0
Recommended Data AO
A2
A4
A6
A8
AlO
SIGMA-T
ENE RG Y (MEV)
SIGMA-O
0.020 0.030 0.040 0.050
0.025 0.125 0.31 0.52
0.819 0.785 0.758 0.737
0.181 0.215 0.241 0.261
0.001 0.002
0.060 0.070 0.080 0.090 0.100
0.78 1.06 1.35 1.66 2.00
0.719 0.705 0.692 0.681 0.671
0.279 0.292 0.304 0.314 0.323
0.002 0.003 0.004 0.005 0.006
7.0 9.4 11.7 14.2 16.9
0.150 0.200 0.250 0.300 0.350 0.400 0.450 0.500
3.33 4.6 5.9 7.1 8.3 9.4 10.4 11.4 12.4 13.4 14.3 15.1 15.8 16.5
0.356 0.379 0.395 0.408 0.418 0.426 0.433 0.437 0.440 0.443 0.444 0.445 0.446 0.445 0.444 0.443 0.441 0.43'J
0.011 0.016 0.022 0.028 0.035 0.042 0.049 0.057
0.550 0.600 0.650 0.700 0.750 0.800 0.R50 0.900 0.Q50 1.000 1.100 1.200 1.300 1.400 1.500 1.600 1.700 1.800 1.900 2.000
0.3 HI 0.370 0.360 0.351 0.342 0.334 0.326 0.318
0.434 0.478 0.422 0.'t16 0.410 0.404 0.398 0.392 0.387 0.382
0.158 0.174 0.189 0.203 0.216 0.228 0.240 0.251 0.260 0.270
0.001 0.003 0.005 0.008 0.011 0.014 0.017 0.020 0.023 0.027 0.030
26.5 35.0 43.0 50.0 57.0 63.0 67.7 72.5 77 .0 81.3 A5.2 88.2 90.5 92.7 94.9 96.9 98.3 99.A
20.0 21.0 21. ':I
0.633 0.605 0.583 0.564 0.547 0.532 0.518 0.506 0.494 0.483 0.474 0.465 0.456 0.447 Cl.439 0.432 0.4"5 0.418 0.40')
101.8 103.7 104.9 105.5 105.9 105.9 105.8 105.7 105.5 105.3
0.311 0.304 0.298 0.293 0.287 0.282 0.217 0.272 0.268 0.262
0.377 0.372 0.367 0.362 0.357 0.353 0.349 0.345 0.341 0.337
0.279 0.287 0.294 0.301 0.308 0.314 0.320 0.326 0.331 0.337
0.033 0.037 0.041 0.044 0.048 0.051 0.054 0.057 0.060 0.064
105.2 105.0 104.8 104.5 104.3 104.0 103.8 103.5 103.2 102.9
0.240 0.221 0.206 0.192 0.182 0.174 0.168 0.163 0.159 0.156 0.153 0.150 0.148 0.147
0.322 0.308 0.295 0.284 0.274 0.265 0.257 0.250 0.244 0.239 0.234 0.230 0.227 0.224
0.356 0.367 0.372 0.374 0.374 0.373 0.370 0.366 0.362 0.358 0.354 0.350 0.346 0.342
0.082 0.098 0.112 0.125 0.137 0.148 0.159 0.169 0.178 0.187 0.195 0.202 0.209
2.100 2.200 2.300 2.400 2.500 2.600 2.700 2.800 2.900 3.000 3.500 4.000 4.500 5.000 5.500 6.000 6.500 7.000 7.500 8.000 8.500 9.000 9.500 10.000
(MB/SR)
17. II
17.A 18.4 19.0 22. "r
23.4 24.0 24.6 25.2 25.8 26.4
26.9 27.5 28.0 28.4 28.9 29.3 29.8 30.3 30.7 31.2 33.5 35.7 37.8 40.0 41.5 42.9 43.8 44.6 45.2 45.7 46.1 46.4 46.5 46.5
0.3'13
0.066 0.074 0.082 0.090 0.098 0.10A 0.117 0.125 (l.134 0.147
587
1MB)
0.26 1.23 2.95 4.8
o .1l5
0.004 0.012 0.020 0.027 0.032 0.037 0.042 0.046 0.049 0.052 0.055 0.056 O. e-58
0.002 0.003 0.005 0.006 0.008 0.009 0.010 0.011 O.Oll 0.012 0.013 0.014 0.014
101.0 99.2 97.7 96.4 95.1 93.9 92.7 91.5 90.5 89.5 88.6 87.7 86.8 86.0
Nuclear Dato TabI8.s~ Vol. 11 1 No.7 I 1973
H. LISKIEN AND A. PAULSEN
0'(0 0 c.m.), Legendre Coefficients, Recommended and Experimental Values
a (total)
D(~n)3He.
f--~ef,-
50
D(d.ln)3~
~.
.....
• III
~(o')
CR56 9' .oA'58 IX EL53
f
GAfi7
~o
(mb/srl
c.m.
+ PRS4
~
o
ROS? 5C12
• SMS7 • 5T56
• THIl9 v ~~
30
legendre C"lMftlcl-nts Ai
not'tn
Ai
.I
•e fo+C51 G060A
/
20
!!.!!.
o
0.01
0.02
0,05
0,1
I
Ed
D.5
1.0
• IWIl M!II8 MUll
AI
o • )(
e
0'
[mb] 100
• THtO
• '9'
" "
0.2
2.0
5,0
TH611 vos,
O'01==I==~+5~~~:t=::I=~~
1Q.0
0.01 0.02
005
0.1
0.2
[MeV] -
~.f.
Ed
0.5
1.0
2.0
5.D
100
[Me'/l - -
Legendre Coefficients Experimental and Recommended Values
J
D(b.n)3~e
,A~5'
Intotgro led Cro.s Se(:tlon d
f1L4!S BOIS! BR!57 GA'57 G060A 1ilJ.45
----t00 PR54 st12 MC51
I
• THEIS
80
.,
/P ~
."q,
\•
Po
/
80
20
o
• $<:72
0.4
0
•
.-.• II
0'(0 c.m.). Experimental and Recommended Values
120 f--....
)::( EL53 ' o FU51 o CW7
• ooeo.
V 0.2
·""'"
0.6
V
....,., V
" "
0.8
• BW
oJ
10
D(d,n) He
•
,;.....
0056 -BRS7
+<0>9
~(O') 40
1.0
I'
O'C,I!l, CrQSS 5e-c1lon
All.. ...• BUB
om
../ 0.02
lJ
0.05
I
I
.
I !'
0.1
0.2
0.5
1.0
Eel [MeV]--.
2.0
5.0
10.0 0"
a(total). Experimental and Recommended Values
3()&
60'
90'
120'
ISO'
ISG'
O'((), E p )' Recommended Values
Solid line shows recommended values. Only experimental data which contributed to the recommended values are plotted. References are on page 618
Nudeor Data Tobl... Vol. 11, No.7, 1973
588
NEUTRON PRODUCTION CROSS SECTIONS
D(~n)3He.
0(0 0 c.m.),
Legendre Coefficients, o(total) Recommended and Experimental Values
EXPERIMENTAL O-DEGREE C.M. CROSS SECTIDNS FOR THE REACTION DlD,NlHE3 EDIMEVl O.013DO 0.01521 0.01789 0.01900 0.02161 0.02200 0.02500 0:02705 0.03000 0.03300 0.03346 0.03600 0.04000 0.04285 0.0460 0.0522 0.0530 0.0600 0.0670 0.0730 0.0800 0.0869 0.093 0.100 0.107 0.110 0.113 0.120 0.130 0.140 0.156 0.160 n.162 0.195 o.2n'i o.;>o{, (). ;>l ()
().;> ',0 (). ii" 0
SIGMA-O
AR54 EL53 EL53 AR54 EL53 AR54 AR54 EL53 AR54 AR54 EL53 AR54 AR54 EL53 AR54 B056 AR54 AR54 AR54 AR54 AR54 8056 AR54 AR54 AR54 AR54 AR54 MC51 GA57 MC51 PR54 MC51 GII?7 GI\'i7 GI\">7 PR',4 Gil '>7
(" 1
r;I\',7 (;11',7 (;11',7
0 .. ?&.,I.)
r,.ft 'I.A 6.1
I
fl ...~
().i'('o
() • i'f)
().i'70
(). ill? (). :3;> ~J
0.330 0.362 0.365 0.380 0.400 0.405 0.425 0.447 0.466 0.470 0.400 0.490 0.500 0.500 0.510 0.554 0.595 0.600 0.660 0.668 0.675 0.700 0.700 0.750 0.760 0.770 0.791 0.825 0.850 0.884 0.925 0.960 0.960 0.980 0.990 0.990 1.000 1.150 1.340 1.430 1.550 1.750 1.750 1.850 1.960 1.960
REF.
0.003 0.008 0.018 0.020 0.039 0.037 0.062 0.090 0.118 0.160 0.175 0.21 0.28 0.35 0.40 0.50 0.58 0.77 0.98 1.18 1.41 1.38 1.81 2.06 2.28 2.34 2.41 2.5 2.8 3.6 3.7 3.6 ::1.6 4.R 4.R 'i.n 'i.o
6.7 h., R.? 7.A R.4
H.A
9.3 6.7 10.5 10.6 10.3 10.8 11.5 10.9 7.8 11.4 8.9 11.5 12.1 12.1 11.0 14.8 14.4 11.9 14.3 11.3 13.5 16.1 16.0 16.3 13 .3 18.1 17 .3 18.6 17 .5 7.7 18.9 16.6 16.1 18.4 19.8 17 .3 23.0 23.5 25.0 19.8 27.4 26.0 25.1
ED(MEVl 2.000 2.010 2.150 2.150 2.300 2.450 2.490 2.510 2.540 2.600 2.800 2.830 3.020 3.020 3.020 3.070 3.110 3.150 3.350 3.400 3.400 3.500 3.520 3.600 3.750 3.850 4.000 4.100 4.150 4.500 4.550 4.600 4.620 4.630 4.750 4.790 'i.OOO 5.000 'i.OOO 5.130 '5.130 'i.250 5.300 5.3 AO 5 .390 5.500 5.500 5.500 5.550 5.630 5.800 5.800 5.800 5.920 6.000 6.200 6.250 6.310 6.320 6.380 6.500 6.830 6.900 7.000 7.200 7.250 7.250 7.440 7.500 7.500 7.650 7.750 7.890 8.000 8.150 8.250 8.320 B.400 8.400 8.500 8.500 8.750 8.800 8.880 8.940 9.000 9.420 9.870 9.920 10.000
Mr.'" ClI',,, PRI}/,.
(;11"7 (;11',7 GA"7 PR'>4 GA57 GA'j7 CH% GAS7 GA57 GA57 PR54 GA57 GA57 HU49 V057 CH56 GA57 GA57 GA57 CH56 GA57 GA57 CH56 V057 HU49 CH56 GA57 GA57 GA57 CH56 GA57 GA57 GA57 BL48 SA61 GA57 R057 HU49 V057 5T56 HU49 BL48 ST 51'> 5M57 HU49 5T56 BL48 SC72
589
SIGMA-O
REF.
27.4 26.5 25.9 20.8 28.0 31.1 28.7 28.4 21.3 29.2 30.5 21.4 32.5 32.2 29.8 32.3 21.4 31.5 32.4 33.2 21.2 34.2 34.6 34.8 34.4 35.5 36.0 36.2 35.7 37.6 33.7 38.2 37.6 35.5 39.'5 38.4 40.5 37.1 39.A 37.0 39.1 37.4 41.9 3A.3 42.A 38.6 41.6 43.0 31.2 38.5 42.4 42.7 44.1 42.6 40.7 43.4 44.5 40.4 44.8 44.4 40.2 44.8 46.4 42.2 44.6 45.4 41.5 46.0 46.5 42.8 46.4 43.• 1 45.9 44.4 45.5 44.2 46.2 46.0 43.2 48.0 44.5 50.5 47.7 45.9 48.2 43.4 48.2 46.7 46.4 43.1
SM57 R057 ST56 HU49 SM57 ST56 BL48 SC72 HU49 SM57 S,.,57 HU49 R057 BL48 SC72 5"'57 HU49 5T56 S,.,57 G060A HU49 SC72 BL48 5,.,57 ST56 S,.,57 scn S,.,57 5T56 SC72 5T56 5T56 5M57 5M57 FlR64 WI60
sen
SM57 TH69 SM57 5M57 5"'57 G060A 5M57 WI60 S,.,57 SC72 BR64 SA61 SM57 SC72 TH69 BR57 WI60 5,.,57
5en
BR64 CR56 C059 WI60 5,.,57 C059 WI60 5,.,57 G060A C059 5,.,57 WI60 BR64 SM57 C059 S,.,57 WI60 5,.,57 BR57 5M57 C059 WI60 OA58 G060A SM57 BR64 C059 WI60 C059 TH69 WI60 C059 WI60 TH69
Nuclear Dolo Table., Val. 11, No.7. 1973
H. LISKIEN AND A. PAULSEN
D(d,n)3He.
Legendre Coefficients, Recommended and Experimental Values 0(0 0 c.m.),
a(total)
NORMALIZED EXPERIMENTAL LEGENDRE COEFFICIENTS FOR THE REACTION OfO,NIHE3 EDCMEVI 0.01425 0.01521 0.01689 0.01789 0.01950 0.02139 0.02161 0.02595 0.02690 0.02705 0.03050 0.03200 O. 03346 0.03506 0.04048 0.04285 0.0451 0.0522 0.0610 0.0710 0.08b9 0.0930 0.09b6 0.1000 0.1220 0.1475 0.1560 0.1940 0.2000 0.2060 0.24B3 0.2500 0.2670 0.2700 0.2985 0.3000 0.3300 0.34!l7 0.3b2 0.303 0.400 0.400 0.447 0.46b 0.490 0.500 o.~oo
o.~nn
0 • .,.,4 !l.bOO 0.600 0.600 0.600 0.6bB 0.675 0.700 0.100 0.100 0.150 0.191 0.800 0.825 0.BB4 0.900 0.960 0.980 0.990 1.000 1.340 1.430 1.600 1.750 1.960 1.960 2.150 2.490 2.510 2.540 2. B30 3.020 3.020 3.110 3.400 3.500 3.520 4.000 4.500 5.000 5.000 5.000 5.100 5.500 5.800 5.BOO 5.BOO 5.BOO 6.000 6.200 6.310 7.000 7.600 B.OOO 8.150 8.400 9.000 9.000 9.600 10.000 10.000
Nuclear Dala Table., Val. 11, No.7. 1973
AD 0.778 0.824 0.796 0.790 0.889 0.806 0.810 0.793 0.784 0.761 0.793 0.795 0.775 0.787 0.772 0.753 0.746 0.736 0.702 0.703 0.679 0.684 0.664 0.750 0.642 0.615 0.636 0.587 0.b40 0.583 0.565 0.640 0.575 0.549 0.540 0.590 0.552 0.535 0.522 0.540 0.542 0.539 0.514 0.472 0.740 0.497 0.';47 0.0;10 0.441\ 0.5U 0.500 0.472 0.533 0.492 0.470 0.710 0.464 0.480 0.457 0.411 0.450 0.440 0.447 0.450 0.453 0.424 0.670 0.421 0.640 0.373 0.338 0.610 0.314 0.322 0.570 0.282 0.291 0.550 0.530 0.259 0.269 0.520 0.510 0.234 0.241 0.226 0.207 0.194 0.183 0.195 0.188 0.184 0.179 0.178 0.185 0.178 0.180 0.175 0.172 0.161 0.166 0.154 0.161 0.152 0.139 0.155 0.158 0.142 0.138
A2 0.222 0.176 0.204 0.210 0.111 0.194 0.190 0.207 0.21b 0.239 0.207 0.205 0.225 0.213 0.228 0.247 0.248 0.264 0.298 0.296 0.321 0.31b 0.324 0.250 0.341 0.365 0.373 0.379 0.350 0.394 0.402 0.349 0.429 0.427 0.407 0.380 0.42b 0.413 0."37 0."20 0.42fl 0.357 0.4"0 0.450 0.250 0.4;'>0
O.4Jt~
0.""0 0.444 0.463 0.440 0.413 0.365 0.4~ 0.4 4 0.2b~ 0.42 0.440 0.475 0.457 0.440 0.431 0.45B 0.450 0.400 0.411 0.270 0.425 0.290 0.426 0.405 0.280 0.379 0.387 0.290 0.353 0.364 0.290 0.280 0.343 0.342 0.280 0.270 0.311 0.332 0.308 0.288 0.276 0.24 0.2B 0.274 0.274 0.260 0.270 0.279 0.272 0.263 0.258 0.232 0.240 0.242 0.238 0.239 0.250 0.230 0.231 0.203 0.224 0.229
6
A6
A4
A8
AID
0.006 0.001 0.012 0.017 0.020 -0.009 0.034 0.010 0.023 0.033 0.011 -0.00" 0.02" 0.053 0.030 0.022 0.052 0.041 0.040 0.030 0.104 0.0"1> 0.07R 0.010 Il.OH3 -a.oot; 0.070 n.I08 n.Ol4 0.060 0.115 0.102 0.053 0.076 0.030 0.113 O.OBO 0.Ob8 0.072 0.110 0.129 0.095 0.100 0.147 0,105 0.060 0.148 0.070 0.201 0.257 0.100 0.267 0.262 0.130 0.303 0.306 0.150 O.lBO 0.338 0.335 O.lBO 0.200 0.35B 0.356 0.372 0.374 0.374 0.34B 0.377 0.356 0.377 0.374 0.368 0.379 0.37B 0.3Bl 0.379 0.376 0.360 0.352 0.355 0.361 0.359 0.345 0.355 0.343 0.342 0.341
590
0.010 0.040 0.029 0.010 0.062 0.039 0.010 0.010 0.060 0.054 0.020 0.020 0.085 0.071 0.088 0.111 0.131 0.162 0.126 0.150 0.139 0.146 0.134 0.132 0.144 0.136 0.151 0.180 0.173 0.181 0.186 0.183 0.172 0.20B a .19B 0.201 0.213 0.205
0.012 0.006 0.020 0.025 0.036 0.022 0.006 0.026 0.032 0.025 0.016 0.02B 0.035 0.037 0.030 0.049 0.048 0.047 0.036 0.034 0.056 0.048 0.081 0.066 0.066
0.026 0.026 0.009 0.025 0.009 0.005 0.010 0.017 0.011 0.020 0.014 0.033 0.022 0.013 0.014 0.013 0.021
REF. EL53 EL53 El53 EL53 TH66 EL53 EL53 EL53 TH66 EL53 EL53 TH66 EL53 ELS3 EL53 EL53 7H66 8056 PR54 THb6 B056 KA59 TH6b FU57 TH66 TH66 PR54 THbb FU57 PR54 THb6 CH56 GA57 PR54 THb6 FU57 GA57 TH66 PR54 FU57 ~H56 Ob08 GA57 PRS4 HU49 VOS7 (H56 FU'>7 GA'>7 CH56 FU'>7 MI61 G06011 GA57 CH56 HU49 V057 FU57 CH56 GA57 FU57 CH56 GA57 FU57 8l4B GA51 HU49 V057 HU49 Bl48 Mlb1 HU49 8148 scn HU49 BL48 SC72 HU4'l HU49 Bl4B SC 72 HU49 HU49 SC72 8l4B SC72 scn THb9 G060A SC72 SM51 scn TH69 SM57 BR57 S(n
KE6B Se72 CR56 KE68 G060A KE68 BR57 OA5R KE68 TH69 G060A TH69 KE68
NEUTRON PRODUCTION CROSS SECTIONS
D{d,n)^He. a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values EXPERIMENTAL TOTAL CROSS SECTIONS FOR THE REACTION D ( D , N ) H E 3
ED(MEV) 0.013 0.019 0.022 0.025 0.030 0,033 0.036 0.040 0.046 0.052 0.053 0,060 0.06 7 0.073 0.0 HO 0.0H7
0.0 93 O.IOO 0.10 7 0. 110 0.113 0.120 0.130 0. 140 0.156 0.160 0.162 0.195 0.205 0.206 0.210 0.250 0.250 0.255 0.260 0.267 0.270 0.275 0.325 0.330 0.362 0.365 0.380 0.400 0.405 0.425 0.447 0.466 0.470 0.480 0.490 0.500
SIGMA-T 0.033 0.200 0.367 0.592 l.OB 1.46 1.88 2.43 3.42 4.64 4.78 6,25 7.86 9.30 10.90 11.85 13,6 15.? 16.6 17.0 17.4 19.0 23.0 26.0 29,0 26.0 28.0 37.0 36.0 38.3 38.0 38,0 25.0 46,0 44.0 45.0 51.0 47.0 57.0 54.0 60.0 60.0 63.0 45.0 70.0 70.0 67,0 73.3 74.0 70.0 51.0 58,0
REF.
ED(MEV)
AR54 AR54 AR54 AR54 AR54 AR54 AR54 AR54 AR54 8056 AR54 AR54 AR54 AR54 AR54 RnS6 ARb4 AR^>4 AR54 AR54 ARb4 MCbl GA57 MC51 PR54 MC51 GA57 GA57 GA57 PR54 GA5T MC51 CH56 GA57 GA57 GA57 PR54 GA57 GA57 GA57 PR54 GA57 GA57 CH56 GA57 GA57 GA57 PR54 GA57 GA57 HU49 CH56
0.510 0.554 0.595 0.600 0,660 0.668 0.675 0.700 0.750 0.760 0,770 0,791 0,825 0,850 0,884 0,925 0.960 0.980 0.990 1.340 1.430 1.750 1.960 1.960 2.150 2.490 2.510 2.540 2.830 3.020 3,020 3,110 3,400 3,500 3,520 3,690 4.000 4.500 5.000 5.000 5.000 5.500 5,550 5,800 5,800 5.800 6,200 7,600 8.150 9,000 9,600 10,000
591
SIGMA-T
REF.
72.0 76.0 74.0 67.0 88.0 83.0 72.0 72.0 82.0 92.0 91.0 89.0 74.0 100.0 94.0 100.0 41.0 98.0 97.0 107.0 104.0 107.0 105.0 104.3 106.0 102.0 104.6 105.0 102.0 103.0 103.8 101.0 96.0 101.4 102.0 106,0 99,8 98,6 94,6 97,3 96,1 94,9 71,0 93,0 93,7 94,1 93,4 96,5 88,0 83.2 93.7 82.6
GA57 GA57 GA57 CH56 GA57 GA57 CH56 HU49 CH56 GA57 GA57 GA57 CH56 GA57 GA57 GA57 SA61 GA57 HU49 HU49 BL48 HU49 BL48 SC72 HU49 BL48 SC72 HU49 HU49 BL48 SC72 HU49 HU49 SC72 BL48 HU49 SC72 SC72 G060A SC72 TH69 SC72 SA61 BR57 SC72 TH69 SC72 G060A BR57 TH69 G060A TH69
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973
H. LISKIEN AND A. PAULSEN
D(4n)^He. ENERGY(MEV1
0.020
a(0 lab), E^iO lab): Recommended Values 0.040
0.030
0.050
0.050
0.070
0.090
0.080
CENTER--OF--MASS INPUT VALUES FDR THE REACTION 0 ( D , N ) H 6 3 U-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4
0.025 0.819 0.000 0.181 0.000 0.000
0.310 0.758 0.000 0.241 0.000 0.001
0.125 0.785 0.000 0.215 0.000 0,000
ANGLE(DEGREE)
0.780 0.719 0.000 0.279 0.000 0.002
0.520 0.737 0.000 0 . 2 6 1L 0.000 0.002
DIFFERENTIAL CROSS- S6CTIt)NS
IN •rHE LABORATORY SYSTEM
(MB/SR)
01 01 01 01 01 01 01
0.189E 01 0.188E 01 0.185E 01 0 . 1 8 I E 01 0.175E 01 0 . 1 5 8 E 01 0.150E 01
00 00 00 00 00 00
0 . 6 8 9 E 00 0 . 6 5 6 E 00 0 . 5 3 0 E 00 0 . 6 1 1 E 00 0 . 5 9 9 6 00 0 . 5 9 4 E 00
0.123E 0.1156 0.109E 0.103E 0.955E 0.9076 0.855E 0.812E 0.7786 0.753E 0.738E 0.7316
01 01 01 01 00 00 00 00 00 00 00 00
0.151E 01 0.142E 01 0.133E 01 0 . 1 2 5 E 01 0.115E 01 0 . 1 0 9 6 01 0.102E 01 0.974E 00 0 . 9 3 1 E 00 0 . 9 0 0 6 00 0 . 8 8 1 E 00 0 . 8 7 4 6 00
0.4536 0.4596 0.459E 0.4826 0.4986 0.5156
00 00 00 00 00 00
0.596E 00 0 . 7 3 4 6 0 . 5 0 4 E 00 0 . 7 4 5 6 0 . 5 1 7 E 00 0 . 7 6 3 6 0.536E 00 0.788E 0 . 6 5 9 E 00 0 . 8 1 8 E 0 . 5 8 5 E 00 0 . 8 5 2 E
00 00 00 00 00 00
0.878E 0.892E 0.915E 0.9476 0.985E 0.1026
00 00 00 00 00 01
00 00 00 00 00 00
0.5366 0.5576 0.5786 0.5996 0.6196 0.5386
00 00 00 00 00 00
0 . 7 1 3 E 00 0 . 8 8 9 6 0 . 7 4 2 E 00 0 . 9 2 8 6 0 . 7 7 2 E 00 0 . 9 6 7 6 0 . 8 0 2 6 00 O.IOOE 0 . 8 3 0 6 00 0 . 1 0 4 E 0 . 8 5 5 6 00 0 . 1 0 7 E
00 00 00 01 01 01
0.1076 0.1126 0.117B 0.122E 0.125E 0.131E
01 01 01 01 01 01
00 00 00 00 00 00
0.655E 0.569E 0.680E 0.689E 0.694E 0.595 6
00 00 00 00 00 00
0.879E 0.899E 0.9156 0.927E 0.934E 0.9376
O.llOE 0.113E 0.1156 0.1176 0.1186 0.1186
01 01 01 01 01 01
0.1346 0.1386 0.140E 0.142E 0.143E 0.144E
01 01 01 01 01 01
0 . 2 6 6 E -- 0 1 0 . 2 6 5 E --01 0 . 2 6 3 E -- 0 1 0.26OE--01 0 . 2 5 6 E --01 0 . 2 5 1 E --01 0 . 2 4 5 E -- 0 1
0 . 1 3 4 E 00 0 , 3 3 8 6 0 . 1 3 4 E 00 0 . 3 3 7 6 0 . 1 3 3 E 00 0 . 3 3 4 6 0 . 1 3 1 E 00 0 . 3 2 8 6 0 . 1 2 8 E 00 0 . 3 2 1 6 0 . 1 2 5 6 00 0 . 3 1 2 6 0 . 1 2 2 6 00 0 . 3 0 1 E
35.0 *0.0 45.0 50.0 55.0 60.0
0 . 2 3 8 8 --01 0 . 2 3 1 E -- 0 1 0 . 2 2 4 E -- 0 1 0 . 2 1 7 E -- 0 1 0 . 2 1 0 E -- 0 1 0 . 2 0 3 E -- 0 1
0 . 1 1 8 6 00 0 . 1 1 3 6 00 0 , 1 0 9 6 00 0 , 1 0 5 E 00 O.IOIE 00 0 . 9 7 2 6 -- 0 1
0 . 2 9 0 E 00 0 . 4 8 3 6 0 . 2 7 8 6 00 0 . 4 5 1 6 0 . 2 6 5 6 00 0 . 4 3 8 E 0 . 2 5 4 6 00 0 . 4 1 6 6 0 . 2 4 2 E 00 0 . 3 9 5 6 0 . 2 3 1 6 00 0 . 3 7 6 6
00 00 00 00 00 00
0.721E 0.6856 0.6496 0.5136 0.579E 0.548E
00 00 00 00 00 00
0.975E 0.924E 0.872E 0.821E 0.772E 0.728E
65.0 70.0 75.0 80.0 85.0 90.0
0 . 1 9 7 6 --01 0 . 1 9 2 E -- 0 1 O.ISBE-- 0 1 0 . 1 8 5 E --01 0 . 1 8 3 E --01 0 . 1 8 2 E --01
0 . 9 3 7 6 --01 0 . 9 0 8 E --01 0 . 8 8 3 6 --01 0 . 8 6 5 6 --01 0 . 8 5 2 6 --01 0 . 8 4 6 6 --01
0.222E 0.214E 0.207E 0.202E 0.199E 0.197E
00 00 00 00 00 00
0.3596 0.3446 0.3326 0.3246 0.3186 0.3156
00 00 00 00 00 00
0.521E 0.497E 0.479E 0.4556 0.4566 0.4526
95.0 100.0 105.0 110.0 115.0 120.0
0 . 1 8 1 E -- 0 1 0 . 1 8 2 E -- 0 1 0 . 1 8 4 E -- 0 1 0 . 1 8 7 E -- 0 1 0 . 1 9 0 E -- 0 1 0 . 1 9 4 E -- 0 1
0 . 8 4 6 E -- 0 1 0 . 8 5 2 6 --01 0 . 8 6 3 E -- 0 1 0 . 8 7 9 6 --01 0 . 8 9 9 6 --01 0 . 9 2 1 6 --01
0.1976 0.1996 0.2026 0.2076 0.2126 0.2186
00 00 00 00 00 00
0.315E 0.319E 0.3256 0.333E 0.3436 0.354E
00 00 00 00 00 00
125.0 130.0 135.0 140.0 145.0 150.0
0 . 1 9 8 E '- 0 1 0 . 2 0 3 E -- 0 1 0 . 2 0 7 E -- 0 1 0 . 2 1 2 E -- 0 1 0 . 2 1 6 E '- 0 1 0 . 2 2 1 E -- 0 1
0 . 9 4 7 6 -- 0 1 0 . 9 7 3 E -- 0 1 O.IOOE 00 0 . 1 0 2 6 00 0 . 1 0 5 E 00 0 . 1 0 7 6 00
0.225E 0.2336 0.2406 0.2486 0.2556 0.2526
00 00 00 00 00 00
0.3576 0.380E 0.394E 0.407E 0.420E 0.431E
155.0 160.0 155.0 170.0 175.0 180.0
0 . 2 2 4 E -- 0 1 0.228E -01 0 . 2 3 0 E -- 0 1 0 . 2 3 2 E '- 0 1 0 . 2 3 3 E -- 0 1 0.234E -01
0.1106 O.lllE 0.U3E 0.114E 0.115E 0.115E
00 00 00 00 00 00
0.2676 0.273E 0.277E 0.280E 0.2826 0.282E
00 00 00 00 00 00
0.4426 0.4516 0.4596 0.454E 0.457E 0.468E
ENERGY(MEV)
0.1001
0.2001
0.1501
0.5736 0.5716 0.565E 0.555E 0.541E 0.524E 0.504E
1.550 0.581 0.000 0.314 0.000 0.005
00 0 . 8 6 8 E 00 0 . 1 1 9 E 0 1 0 . 1 5 2 6 00 0 . 8 6 5 E 00 0 . 1 1 8 E 0 1 0 . 1 5 2 E 00 0 . 1 1 5 E 0 1 0 . 1 4 9 6 on 00.. 88 35 74 EE 00 0 . 1 1 4 E 01 0 . 1 4 6 E 00 00 0 . 8 1 5 E 00 O . l l l E 0 1 0 . 1 4 2 E 00 0 . 7 8 7 E 00 0 . 1 0 7 E 0 1 0 . 1 3 5 6 00 0 . 7 5 5 E 00 0 . 1 0 2 E 0 1 0 . I 3 O E
0.0 5,0 10.0 15.0 20.0 25.0 30.0
00 00 00 00 00 00 00
1.350 0.692 0.000 0.304 0.000 0.004
1.050 0.705 0.000 0.292 0.000 0.003
0.2501
0 . 3 0 C1
00 00 00 00 00 00
00 00 00 00 00 00
O . 3 5 01
0.450
0.400
CENTER-•OF-•MASS INPUT VALUES, FUR TH6 R6ACTI0N D ( D . N ) H 6 3 D-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4
2.0001 0.671 O.OOC1 0.323 O.OOC1
0.006
ANGLE(DEGREE)
5.900 0.583 0.0001 0.395 0.0001 0.022
4 . 6 0 C1 0.605 O.OOC1 0 . 3 7 91 O.OOC1
3 . 3 3 C1 0.633 0.0001 0 . 3 5 61 O.OOC1 0,011
o.oie
DIFF6R6NTIAL
7.1O01 0.55'if O.OOC1 0 . 4 0 81 O.OOC1 0 . 0 2 61
C R 0 S S - S 6 C T I 0 N S. (MB/SR)
8.300 0.547 O.OOC 0.418 0.000 0.035
)
9 . 4 0 C1 0.532 O.OOC1 0 . 4 2 61 O.OOC1 0.042
10.400 0.518 0.000 0.433 0.000 0.049
IN THE LABORATORY SYSTE^1
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.229E 0.228E 0.2246 0.219E 0.212E 0.203E 0.193E
01 01 01 01 01 01 01
0.3936 0.3906 0.3646 0.3736 0.3586 0.3406 0.3206
01 01 01 01 01 01 01
0.55Ae 0.5526 0.5416 0.524E 0.500E 0.4736 0.4426
01 01 01 01 01 01 01
0.7286 0.7236 0.7076 0.6826 0.6486 0.509 6 0.5656
01 01 01 01 01 01 01
0.8926 0.8856 0.8646 0.8316 0.7856 0.7346 0.6776
01 01 01 01 01 01 01
0.1066 0.105E 0.1026 0.981E 0.925E 0.8596 0.7876
02 02 02 01 01 01 01
0.1216 0.1206 0.1176 0.1126 0.1056 0.9736 0.8856
02 02 02 02 02 01 01
0 . 1 3 5 E 02 0 . 1 3 5 E 02 0 . 1 3 1 6 02 0 . 1 2 5 E 02 0 . 1 1 7 E 02 0 . 1 0 7 E 02 0.974E 01
35.0 40.0 45.0 50.0 55.0 60.0
0.182E 0.170E 0.159E 0.148E 0.138E 0.129E
01 01 01 01 01 01
0.2996 0.2776 0.256E 0.2356 0.2166 0.2006
01 01 01 01 01 01
0.4096 0.3756 0.3436 0.3126 0.2846 0.260E
01 01 01 01 01 01
0.5196 0.4736 0.4286 0.3866 0.349E 0.316E
01 01 01 01 01 01
0.6176 0.558E 0.502E 0.449 E 0.4036 0.3636
01 01 01 01 01 01
0.7136 0.640E 0.571E 0.508E 0.4536 0.4066
01 01 01 01 01 01
0.7976 0.7116 0.530E 0.557E 0.494E 0.441E
65.0 70.0 75.0 80.0 85.0 90.0
01 01 01 01 01 01
0.1856 0.173E 0.1546 0.158E 0.1546 0.1536
01 01 01 01 01 01
0 . 2 3 9 6 01 0 . 2 8 9 6 0 . 2 2 2 6 01 0 . 2 5 8 6 0.2096 01 0.2526 0.2016 01 0.2416 0 . 1 9 6 6 01 0 . 2 3 5 6 0 . 1 9 5 6 01 0 . 2 3 4 6
01 01 01 01 01 01
0.3306 0.3046 0.2856 0.273E 0.2576 0.2666
01 01 01 01 01 01
0.3686 0.3386 0.3176 0.303E 0.2966 0.295E
01 01 01 01 01 01
0.398E 0.365E 0.342E 0.3276 0.320E 0.320E
0.871E 01 0 . 7 7 1 E 01 0.679E 01 0.597E 01 0 . 5 2 5 6 01 0 . 4 6 8 E 01 0 . 4 2 2 E 01 0.387E 01 0.352E 01 0.346E 01 0 . 3 3 9 6 01 0.339E 01
95.0 100.0 105.0 110.0 115.0 120.0
0.121E 0.114E 0.109E 0.105E 0.1036 0.102E 0.103E 0.1046 0.1076 O.lllE 0.116E 0.121E
01 01 01 01 01 01 01 01 01 01 01 01
01 01 01 01 01 01
0.1546 0.1586 0.163E 0.1706 0.179E 0.188E
01 01 01 01 01 01
0.1976 0.2026 0.2106 0.2206 0.2326 0.2456
01 01 01 01 01 01
0.237E 0.244E 0.2556 0.258E 0.2846 0.301E
01 01 01 01 01 01
0.2706 0.2796 0.2926 0.308E 0.327E 0.348E
01 01 01 01 01 01
0.3016 0.3116 0.3256 0.3456 0.3576 0.3926
01 01 01 01 01 01
0.3256 0.3386 0.355E 0.3766 0.401E 0.4296
01 01 01 01 01 01
0.3456 0.359E 0.3776 0.401E 0.428E 0.4596
01 01 01 01 01 01
125.0 130.0 135.0 140.0 145.0 150.0
0.127E 0.133E 0.139E 0.145E 0.151E 0.1566
01 01 01 01 01 01
0.198E 0.209E 0.219E 0.230E 0.240E 0.249E
01 01 01 01 01 01
0.260E 0.275E 0.290E 0.3066 0.3196 0.332E
01 01 01 01 01 01
0.3206 0.3406 0.3596 0.3786 0.397E 0.4146
01 01 01 01 01 01
0 . 3 7 IE 0.3956 0.4196 0.4426 0.4646 0.4856
01 01 01 01 01 01
0.4196 0.447E 0.4746 0.5026 0.5286 0.5526
01 01 01 01 01 01
0.4596 0.4916 0.522E 0.5546 0.5836 0,6116
01 01 01 01 01 01
0.493E 0.527E 0.5536 0.5976 0.631E 0.551E
01 01 01 01 01 01
155.0 160.0 165.0 170.0 175.0 180.0
0.151E 0.165E 0.1686 0.170E 0.1726 0.1726
01 01 01 01 01 01
0.257E 0.2546 0.2706 0.2746 0.2766 0.277E
01 01 01 01 01 01
0.3446 0.3546 0.3626 0.3586 0.3716 0.3726
01 01 01 01 01 01
0.4296 0.4426 0.4526 0.4596 0.4546 0.466E
01 01 01 01 01 01
0.5036 0.518E 0.531E 0.540E 0.5466 0.5486
01 01 01 01 01 01
0.574E 0.5926 0.507E 0.618E 0.625E 0.6276
01 01 01 01 01 01
0.5356 0,5576 0,5746 0,685E 0.594E 0,6966
01 01 01 01 01 01
0.5896 0.7126 0.7316 0.7456 0.7536 0.756E
01 01 01 01 01 01
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
592
NEUTRON PRODUCTION CROSS SECTIONS
D(4/i)3He.
aid lab), EJfi lab): Recommended Values 0.030
ENERGY(MEV)
REST ENERGY I N MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET T 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6
o.oyo
0.080
O.O'hO 0.050 0.060 0.070 INPUT VALUES FOR THE REACTION DID,N)H63 0-VALUE
IN MEV U=
3.269
RESIDUAL NUCLEUS T't=2808.42l
ENERGY OF PARTICLE-3 IHEV) IN THE LABORATORY SYSTEM
ANGLE(DEGREE*
0.0 S.O 10.0 15.0 20, 25. 30, 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165-.0 170.0 175.0 180.0 ENERGY(MEV)
2.673 2.659 2.643 2.626 2.607 2.588
2.751 2.750 2.746 2.741 2.733 2.723 2.711 2.697 2.681 2.663 2.645 2.624 2.603
2.778 2.777 2.773 2.76 7 2 . 7 58 2.747 2.734 2.719 2.702 2.683 2.662 2.640 2.617
2.804 2.802 2.798 2.792 2.78 2 2.770 2.756 2.740 2.721 2.701 2.679 2.655 2.631
2.828 2.827 2.822 2.815 2.805 2.793 2.777 2.760 2.740 2.718 2.695 2.670 2.643
2.568 2.547 2.526 2.504 2.482 2.461
2.581 2.558 2.535 2.511 2.487 2.463
2.59 3 2.568 2.543 2.517 2.491 2.466
2.605 2.578 2.551 2.523 2.496 2.468
2.616 2.588 2.559 2.529 2.500 2.471
2.439 2.420 2,401 2,383 2,366 2,350
2.439 2.418 2.397 2.377 2.358 2.340
2.440 2.416 2.394 2.372 2,351 2.331
2.440 2.415 2.391 2.36 7 2.344 2.323
2.441 2.414 2.388 2.363 2.339 2.316
2.442 2.413 2.386 2.359 2.334 2.309
2.348 2.335 2.324 2.313 2.303 2,295
2.334 2.320 2,306 2.294 2.283 2.273
2.288 2.282 2.277 2.274 2.272 2,271
2.265 2.258 2.253 2.249 2.247 2.246
2.322 2.306 2.291 2.278 2.265 2.255 2.246 2.238 2.232 2.228 2.225 2.225
2.312 2.294 2.278 2.263 2.250 2.238 2.229 2.220 2.214 2.209 2.207 2.206
2.303 2.284 2.266 2.250 2.236 2.224 2.213 2.204 2.197 2.192 2.189 2.189
2.294 2.274 2.255 2.239 2.224 2.210 2,199 2.190 2.182 2.177 2.174 2.173
2.286 2.265 2.246 2.228 2.212 2.198 2.186 2.176 2.168 2.163 2.160 2.159
0.300
0.350
2.538 2.522 2.506 2.489 2.473 2.456
2.691 2.690 2.687 2.682 2.676 2.668 2.658 2.647 2,634 2.620 2.605 2.589 2.572 2.554 2.535 2.516 2.497 2.478 2.458
2.440 2.426 2.413 2.400 2.388 2.376
2.439 2.423 2.406 2.391 2.376 2.361
2.365 2.354 2.345 2.336 2.328 2.321 2.315 2.310 2.306 2.304 2.302 2.301
2.615 2.615 2.613 2.610 2.605 2.600 2.593
2.656 2.655 2.653 2.649 2.643 2.636 2.628
2.585 2.576 2.567 2.556 2.545 2.533
2.618 2.608 2.596 2.582 2.569 2.554
2.520 2.507 2.494 2.481 2.467 2.453
0.100
0.150
0.200
2.722 2.721 2.718 2.713 2.706 2.696 2.686
0.250
0.400
0
INPUT VALUES FOR THE REACTION 0 ( D . N ) H E 3 REST ENERGY I N MEV FOR PROJECTILE TARGET PRUDUCT RESIDUAL NUCLEUS ANGLE(DEGREE)
ENERGY OF PARTICLE-3
Tl=1875.633 72=1875.633 T3= 9 3 9 . 5 7 6 T4=2808 . 4 2 1 (MEV)
Q-VALUE IN MEV 0=
IN THE LABORATORY SYSTEM
0.0 5.0 10,0 15,0 20.0 25.0 30,0 35,0 40,0 45,0 50,0 55.0 50.0 65.0 70.0 75.0 80.0 85.0 90.0
2.851 2.850 2,845 2,838 2,827 2,814 2,798
2,957 2,955 2,950 2,940 2,927 2,910 2,889
3,051 3 k 049 3.042 3,031 3,015 2,995 2,971
3.138 3.135 3.127 3.114 3.096 3.073 3.046
3.219 3.216 3.207 3.193 3.172 3.147 3.116
3.295 3.293 3.283 3.267 3.245 3.217 3.183
3.370 3.367 3.356 3.339 3.314 3.284 3.247
3.442 3.438 3.427 3.408 3.381 3.348 3.309
2,779 2,758 2,735 2.710 2,683 2,656 2.626 2.596 2,566 2,535 2,504 2,473
2,866 2,840 2,811 2,779 2,745 2,711
2,943 2,912 2,878 2,841 2.802 2.761
3.014 2.979 2.940 2.698 2.854 2.807
3.081 3.041 2.998 2.951 2.902 2 . 8 50
3.144 3.101 3.053 3.002 2.948 2.89 2
3.205 3.158 3.105 3.051 2.992 2.931
3.253 3.213 3.157 3.098 3.035 2.970
2,675 2,638 2,600 2,552 2,523 2,485
2.719 2.675 2.631 2,586 2,542 2,498
2.759 2.710 2.660 2.610 2.560 2.510
2.797 2.743 2.687 2.632 2.577 2.523
2.833 2.774 2.714 2.554 2.594 2.535
2.868 2.804 2.740 2.575 2.611 2.548
2.902 2.834 2.755 2.695 2.527 2,560
95.0 100.0 105.0 IIO.O 115.0 120.0
2,442 2,413 2,383 2,355 2,329 2,303
2,448 2,411 2,375 2,342 2,309 2,278
2,455 2,412 2,372 2,332 2,295 2,260
2.452 2.415 2.359 2.325 2.284 2.245
2.470 2.418 2.358 2.321 2.275 2.233
2.478 2.422 2.358 2.317 2.269 2.223
2.486 2.427 2.369 2.315 2.253 2.215
2,495 2.432 2.371 2,313 2.259 2.207
125.0 130,0 135,0 140,0 145,0 150,0
2,279 2,257 2,236 2,218 2,201 2.186 2.174 2.164 2.156 2.150 2.146 2.145
2,250 2,223 2,198 2,175 2,156 2.138
2,227 2,196 2,168 2,143 2,120 2.100
2.209 2 . 175 2.144 2 . 116 2.091 2.059
2.193 2.157 2.123 2.093 2.055 2.043
2.180 2.141 2.105 2.073 2.045 2.020
2.169 2.128 2.090 2.056 2.026 1.999
2.150 2.115 2,075 2.040 2.009 1.981
2.123 2. I l l 2.10 2 2.095 2.091 2.089
2,084 2,070 2,059 2,051 2,047 2,045
2.051 2.035 2.024 2.015 2.010 2.009
2.023 2.007 1.994 1.985 1.979 1.977
1.999 1.981 1.968 1.958 1.952 1.950
1.977 1.959 1.945 1.934 1.928 1.925
1.958 1.939 1.924 1.913 1.907 1.905
155,0 160.0 165.0 170.0 175.0 180.0
593
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
a(0 lab), £^(0 lab): Recommended Values
D(d,nfHe. ENERGYIMEV)
0.500
0.550
0.600
0.650
0.7C0
0.750
O.SOO
0.850
CENTER-UF-MASS INPUT VALUES FUR THE REACTION DIU,IM|HE3 0-SIGMA-0IM6/SR) A 0 A 1 A 2 A 3 A 4
ll.AOO 0.506 0.000 0.437 0.000 0.057
12.400 0.494 0.000 0.440 0.000 0.066
ANGLE(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0
13.400 0.483 0.000 0.443 0.000 0.074
14.300 0.474 0.000 0.444 0.000 0.082
15.100 0.465 0.000 0.445 0.000 0.090
DIFFERENTIAL CROSS-SECTIONS IMB/SRl
15.800 0.456 0.000 0.446 0.000 0.098
16.500 0.447 0.000 0.445 0.000 0.108
17.200 0.439 0.000 0.444 0.000 0.117
IN THE LABORATORY SYSTEM
0.151E 0.1506 0.145E 0.138E 0.128E 0.117E 0.105E
02 02 02 02 02 02 02
0.1676 0.166E 0.159E 0.151E 0.140E 0.127E 0.114E
02 02 02 02 02 02 02
0.182E 0.180E 0.1746 0.164E 0.151E 0.137E 0.122E
02 02 02 02 02 02 02
0.197E 0.194E 0.187E 0.176E 0.162E 0.146E 0.129E
02 02 02 02 02 02 02
0.210E 0.207E 0.1996 0.187E 0.171E 0.153E 0.135E
02 02 02 02 02 02 02
0.222E 0.219E 0.210E 0.196E 0.179E 0.160E 0.1406
02 02 02 02 02 02 02
0.234E 0.230E 0.221E 0.206E 0.187E 0.166E 0.144E
02 02 02 02 02 02 02
0.246E 0.242E 0.232E 0.215E 0.195E 0.172E 0.148E
02 02 02 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.4466 0.409E 0.383E 0.367E 0.359E 0.3596
01 01 01 01 01 01
0.4686 0.430E 0.403E 0.386E 0.3786 0.3786
01 01 01 01 01 01
0.489E 0.449E 0.4226 0.405E 0.396E 0.396E
01 01 01 01 01 01
0.508E 0.468E 0.440E 0.4236 0.414E 0.413E
01 01 01 01 01 01
0.522E 0.482E 0.454E 0.437E 0.427E 0.4266
01 01 01 01 01 01
0.367E 0.3806 0.4006 0.425E 0.455E 0.488E
01 01 01 01 01 01
0.386E 0.400E 0.420E 0.447E 0.478E 0.514E
01 01 01 01 01 01
0.404E 0.418E 0.4406 0.467E 0.501E 0.539E
01 01 01 01 01 01
0.420E 0.435E 0.457E 0.4856 0.5206 0.5616
01 01 01 01 01 01
0.4336 0.447E 0.469E 0.498E 0.534E 0.577E
01 01 01 01 01 01
01 01 01 01 01 01 01 01 01 01 01 01
0,.541E 0.,503E 0,.476E 0,.459E 0 .,448E 0..4456
95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0
0,.4506 0..4626 0..483E 0..5136 0..550E 0,.5956
01 01 01 01 01 01 01 01 01 01 01 01
0.5526 0.515E 0.489E 0.4716 0.4606 0.4556 0.4596 0.4706 0.490E 0.5196 0.5586 0.604E
01 01 01 01 01 01 01 01 01 01 01 01
0.524E 0.562E 0.6016 0.639E 0.6766 0.710E
01 01 01 01 01 01
0.553E 0.595E 0.637E 0.679E 0.719E 0.756E
01 01 01 01 01 01
0.582E 0.626E 0.672E 0.717E 0.761E 0.801E
0.605E 0.653E 0.7016 0.750E 0.796E 0.840E
01 01 01 01 01 01
0.623E 0.673E 0.725E 0.776E 0.825E 0.871E
01 01 01 01 01 01
01 01 01 01 01 01
0 .6466 0 .7006 0,.757E 0 .814E 0..868E 0 .920E
01 01 01 01 01 01
0.656E 0.713E 0.772E 0.832E 0.8896 0.9436
01 01 01 01 01 01
155.0 160.0 165.0 170.0 175.0 180.0
0.740E 0.7666 0.787E 0.802E 0.8126 0.815E
01 01 01 01 01 01
0.7e9E 0.818E 0.8416 0.8586 0.868E 0.872E
01 01 01 01 01 01
0.838E 0.869E 0.894E 0.9126 0.9236 0.927E
01 01 01 01 01 01 01 01 01 01 01 01
0.8796 0.9126 0.939E 0.959E 0.971E 0.9756
01 01 01 01 01 01
0.913E 0.948E 0.9776 0.9976 0.1016 O.IOIE
01 01 01 01 02 02
0.531E 0.4926 0.4646 0.4466 0.437E 0.435E 0.441E 0.4556 0.477E 0.506E 0.5446 0.587E 0.636E 0.688E 0.742E 0.796E 0.848E 0.8966 0.940E 0.977E O.IOOE 0.102E 0.1046 0.104E
01 01 02 02 02 02
0,.965E 0..lOOE 0,.103E 0,. 106E 0 .107E 0..107E
01 02 02 02 02 02
0.991E 0.1036 0.1066 0.109E 0.1106 O.lllE
01 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
ENERGY(MEV)
0.900
0.950
1.000
1.100
1.200
1.300
1.400
1.500
CENTER-OF-MASS INPOT VALUES FOR THE REACTION DIU,N)HE3 D-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 6
17.800 0.43; 0.000 0.443 0.000 0.125 0.000 0.000
»
ANGLE(DEGREE 1
19.000 0.416 1 0.000 0.439 0.000 0.142 0.000 0.001
18.400 0.425 0.000 0.441 0.000 0.134 0.000 0.000
20.000 0.405 0.000 0.434 0.000 0.158 0.000 0.003
21.000 0.393 0.000 0.428 0.000 0.174 0.000 0.005
21.900 0.381 0.000 0.42; 0.000 0.189 0.000 0.008
23.400 0.360 0.000 0.410 0.000 0.216 0.000 0.014
22.700 0.370 0.000 0.416 0.000 0.203 0.000 0.011
DIFFERENTIAL CROSS-:SECTIONS (MB/SR) 1[N THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.257E 0.2536 0.2416 0.2236 0.2016 0.177E 0.152E
02 02 02 02 02 02 02
0.267E 0.2636 0.2516 0.2326 0.208E 0.181E 0.155E
02 02 02 02 02 02 02
0.278E 0.274E 0.260E 0.2406 0.214E 0.186E 0.158E
02 02 02 02 02 02 02
0.297E 0.2926 0.276E 0.2536 0.2246 0.193E 0.162E
02 02 02 02 02 02 02
0.316E 0.310E 0.293E 0.266E 0.234E 0,199E 0,165E
02 02 02 02 02 02 02
0.334E 0.327E 0.307E 0.2786 0.2416 0.2036 0.1676
02 02 02 02 02 02 02
0.3516 0.343E 0.321E 0.2886 0.248 6 0.2076 0.1686
02 02 02 02 02 02 02
0.365E 0.357E 0.333E 0.296E 0.2536 0.2096 0.1686
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.129E 0.1086 0.9176 0.784E 0.6846 0.612E
02 02 01 01 01 01
0.131E 0.1096 0.923E 0.7886 0.6896 0.6196
02 02 01 01 01 01
02 02 01 01 01 01
0.134E O.lllE 0.9296 0.7936 0.699E 0.635E
02 02 01 01 01 01
0.1346 0.1086 0.901E 0.778E 0.7026 0.6586
02 02 01 01 01 01
0.1336 0.106E 0.8846 0.7676 0.699E 0.662E
02 02 01 01 01 01
01 01 01 01 01 01
0.570E 0.536E 0.511E 0.493E 0.4806 0.472E
01 01 01 01 01 01
01 01 01 01 01 01
0.593E 0.5626 0.539E 0.519E 0.502E 0.4906
0.6086 0.5816 0.5596 0.5376 0.518E 0.502E
01 01 01 01 01 01
0.1356 0.1106 0.915E 0.786E 0.7036 0.6526 0.6206 0.5966 0.673E 0.5516 0.5286 0.5086
02 02 01 01 01 01
0.5616 0.525E 0.500E 0.481E 0.4696 0.464E
02 02 01 01 01 01 01 01 01 01 01 01
0.135E O.lllE 0.926E 0.7926 0.7036 0,6466
65.0 70.0 75.0 80.0 85.0 90.0
0.132E O.UOE 0.9296 0.7936 0.6956 0.626E 0.579E 0.546E 0.5226 0.5036 0.488E 0.480E
01 01 01 01 01 01
0.6306 0.609E 0.586E 0.562E 0.536E 0.5136
01 01 01 01 01 01
0.639E 0.620E 0.5986 0.5716 0.5436 0.516E
01 01 01 01 01 01
95.0 100.0 105.0 110.0 115.0 120.0
0.4656 0.475E 0.4956 0.5246 0.5636 0.6106
01 01 01 01 01 01
0.472E 0.480E 0.499E 0.527E 0.566E 0.614E
01 01 01 01 01 01
0.478E 0.485E 0.5026 0.5306 0.5706 0.618E
01 01 01 01 01 01
0.485E 0.489E 0.504E 0.531E 0.569E 0.619E
01 01 01 01 01 01
0.492E 0.492E 0.504E 0.5306 0.5686 0.6196
01 01 01 01 01 01
0.4956 0.492E 0.5016 0.6246 0.5626 0.613E
01 01 01 01 01 01
0.496E 0.4896 0.495E 0.5176 0.554E 0.605E
01 01 01 01 01 01
0.495E 0.4846 0.4886 0.5086 0.5446 0.5966
01 01 01 01 01 01
125.0 130.0 135.0 140.0 145.0 150.0
0.664E 0.7236 0.7846 0.8466 0.905E 0.9616
01 01 01 01 01 01
0.670E 0.730E 0.794E 0.6586 0.920E 0.9786
01 01 01 01 01 01
0.6756 0.7386 0.8036 0.870E 0.934E 0.994E
01 01 01 01 01 01
0.678E 0.743E 0.812E 0.883E 0.951E O.lOlE
01 01 01 01 01 02
0.679E 0.7486 0.8206 0.895E 0.967E 0.1036
01 01 01 01 01 02
01 01 01 01 01 02
0.669E 0.743E 0.e22E 0.903E 0.983E 0.105E
01 01 01 01 01 02
0.6616 0.7366 0.818E 0.902E 0.9866 0.1066
01 01 01 01 01 02
155.0 160.0 165.0 170.0 175.0 180.0
0.1016 0.1056 0.1086 O.lllE 0.1126 0.113E
02 02 02 02 02 02
0.1036 0.1076 O.lllE 0.113E 0.1156 0.1156
02 02 02 02 02 02
0.1046 0.1096 0.1136 0.1166 0.117E 0.118E
02 02 02 02 02 02
0.107E 0.1126 0.1166 0.119E 0.1216 0.1216
02 02 02 02 02 02
0.1096 0.1156 0.119E 0.122E 0.124E 0.125E
02 02 02 02 02 02
0.676E 0.747E 0.8236 0.901E 0.977E 0.105E O.lllE 0.1176 0.1216 0.1256 0.1276 0.127E
02 02 02 02 02 02
0.112E 0.1186 0.1236 0.1276 0.1296 0.1306
02 02 02 02 02 02
0.1136 0.1196 0.1246 0.1286 0.1306 0.1316
02 02 02 02 02 02
Nucleor Data Tables, VoL 1 1 , No. 7, 1973
5 9 4
NEUTRON PRODUCTION CROSS SECTIONS
D(4n)^He. ENERGY(MEV)
0.500
a(0 lab), E„(e lab): Recommended Values
0.550
0.600
0.650
0.700
0.750
0.800
0
INPUT VALUES FOR THE REACTION n l D , N ) H E 3 REST ENERGY I N MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET T 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS T * = 2 a 0 8 . * 2 l ENERGY OF PARTICLE-3
ANGLE(OEGREE)
Q-VALUE
IN MEV g=
(MEVI IN THE LABORATORY SYSTEll
0.0 5.0 10.0 15.0 20.0 25.0 30.0
3.511 3.507 3.495 3.475 3.447 3.411 3.369
3.579 3.575 3.562 3.540 3.610 3.472 3.427
3.645 3.641 3.627 3.604 3.572 3.532 3.485
3.710 3.705 3.591 3.666 3.633 3.691 3.641
3.774 3.769 3.753 3.728 3.593 3.649 3.596
3.837 3.831 3.815 3.788 3.752 3.705 3.650
3.899 3.893 3.876 3.848 3.810 3.751 3.703
3.960 3.954 3.935 3.907 3.867 3.816 3.756
35.0 'tO.O '^5.0 50.0 55.0 60.0
3.320 3.266 3.207 3.143 3.076 3.007
3.430 3.369 3.303 3.232 3.167 3.079
3.483 3.419 3.349 3.274 3.196 3.114
3.535 3.468 3.395 3.316 3.234 3.148
3.687 3.510 3.527 3.438 3.345 3,248
2.935 2.862 2.789 2.716 2.643 2.572
2.999 2.918 2.837 2.756 2.676 2.597
3.030 2.945 2.860 2.775 2.592 2.610
3.061 2.972 2.883 2.794 2.707 2.522
3.587 3.515 3.439 3.357 3.271 3.182 3.09 1 2.998 2.905 2.814 2.723 2.635
3.537 3.564 3.484 3.398 3.308 3.215
65.0 70.0 75.0 80.0 85.0 90.0
3.376 3.318 3.255 3,188 3.117 3.043 2.957 2.890 2.813 2.736 2.660 2.685
3.120 3.024 2.928 2.832 2.739 2.547
3.150 3 . 0 50 2.950 2.851 2.754 2.660
95.0 100.0 105.0 110.0 115.0 120.0
2.503 2.437 2.373 2.312 2.255 2.201
2.612 2.442 2.375 2.312 2.252 2.196
2.522 2.448 2.378 2.312 2.250 2.191
2.631 2.455 2.382 2.313 2.248 2.188
2.540 2.451 2.386 2.314 2.247 2.185
2.650 2.458 2.389 2.315 2.246 2.182
2.559 2.474 2.394 2.318 2.246 2.180
2.569 2.481 2.398 2.320 2.245 2.178
125.0 130.0 135.0 140.0 145.0 150.0
2.151 2.106 2.064 2.027 1.993 1.965 1.940 1.921 1.905 1.894 1.887 1.885
2.144 2.096 2.053 2.014 1.980 1.950 1.925 1.904 1.888 1.877 1.870 1.867
2.137 2.088 2.043 2.003 1.967 1.936 1.910 1.889 1.873 1.861 1.854 1.851
2.132 2.081 2.034 1.993 1.955 1.924 1.897 1.875 1.858 1.846 1.839 1.836
2.127 2.074 2.025 1.983 1.945 1.913
2.119 2.063 2.012 1.957 1.927 1.893
2.115 2.058 2.006 1.960 1.919 1.884
1.885 1.8 63 1.845 1.833 1.825 1.823
2.122 2.068 2.019 1.975 1.936 1.902 1.874 1.851 1.833 1.820 1.812 1.810
1.864 1.840 1.822 1.809 1.801 1.798
1.8 54 1.830 1.811 1.798 1.790 1.'787
0.900
0.950
1.000
1.100
1.200
1.300
1.400
1.500
155.0 160.0 165.0 170.0 175.0 180.0
ENERGYIMEV)
INPUT VALUES FOR THE REACTION D ( 0 , N ) H E 3
ANGLE(DEGREE)
REST ENERGY I N MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 Q-VALUE IN MEV Q= TARGET 7 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS 7 4 = 2 8 0 8 . 4 2 1 ENERGY OF PARTICLe-3 (MEV) I N THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
4.020 4.014 3.995 3.965 3.923 3.871 3.808
35.0 40.0 45.0 50.0 55.0 60.0
3.736 3.556 3.570 3.478 3.381 3.280
65.0 70.0 75.0 80.0 85.0 90.0
3.178 3.075 2.972 2.869 2.769 2.572
95.0 100.0 105.0 110.0 115.0 120.0
2.578 2.488 2.402 2.322 2.245 2.176
125.0 130.0 135.0 140.0 145.0 150.0
2.112 2.053 2.000 1.953 1.911 1.875 1.845 1.820 1.801 1.788 1.779 1.777
155.0 160.0 165.0 170.0 175.0 180.0
4.079 4.073 4.054 4.022 3.979 3.924 3.859 3.785 3.702 3.612 3.517 3.416 3.313 3.207 3.100 2.993 2.888 2.785 2.584 2.588 2.495 2.407 2.324 2.247 2.175 2.109 2.049 1.995 1.947 1.904 1.868 1.837 1.812 1.792 1.778 1.770 1.767
4.138 4.132 4.112 4.079 4.034 3.978 3.910 3.833 3.747 3.555 3.555 3.452 3.345 3.235 3.125 3.015 2.906 2.800 2.597 2.597 2.502 2.412 2.327 2.248 2.175 2.107 2.046 1.991 1.941 1.898 1.861 1.829 1.803 1.784 1.759 1.761 1.758
4.255 4.248 4.226 4.191 4.143 4.083 4.011 3.928 3.837 3.738 3.632 3.521 3.407 3.291 3.174 3.058 2.943 2.831 2.722 2.517 2.517 2.423 2.334 2.251 2.174 2.104 2.040 1.982 1.931 1.885 1.848 1.815 1.789 1.768 1.763 1.745 1.742
595
4.359 4.362 4.339 4.302 4.250 4.186 4.109 4.022 3.924 3.819 3.707 3.590 3.469 3.347 3.223 3.100 2.979 2.861 2.747 2.537 2.532 2.433 2.341 2.254 2.175 2.102 2.035 1.976 1.923 1.876 1.836 1.803 1.775 1.754 1.739 1.730 1.727
4.482 4.474 4.450 4.410 4.355 4.288 4.205 4.114 4.011 3.900 3.781 3.658 3.530 3.401 3.271 3.142 3.015 2.891 2.772 2.557 2.548 2.445 2.348 2.259 2.176 2.100 2.032 1.970 1.916 1.86 8 1.827 1.792 1.76 4 1.742 1.727 1.718 1.715
4.593 4.585 4.560 4.518 4.460 4.388 4.302 4.205 4.095 3.979 3.854 3.724 3.591 3.455 3.319 3.184 3.051 2.921 2.797 2.577 2.554 2.457 2.357 2.264 2.178 2.100 2.029 1.955 1.910 1.850 1.818 1.783 1.754 1.732 1.716 1.706 1.703
3.2
4.703 4.595 4.668 4.524 4.563 4.487 4.397 4.294 4.180 4.057 3.927 3.790 3.550 3.508 3.366 3.225 3.086 2.951 2.821 2.697 2.580 2.469 2.366 2.259 2.181 2.101 2.028 1.962 1.905 1.854 1.811 1.775 1.745 1.722 1.706 1.696 1.593
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
D(4n)3He. ENERGYIMEV)
1.600
0(6 lab), £„(0 lab): Recommended Values 1.700
1.800
1.900
2.000
2.100
CENTER-•OF-•MASS INPUT VALU6S, FOR THE REACTION l ) ( U , N ) H E 3 D-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 6
2 4 . 5 0 C1 0.342 O.OOCi 0 . 3 9 61 O.OOC 0 . 2 4 C1 O.OOC1 0 . 0 2 C1
24.000 0.351 0.000 0.404 0.000 0.22E1 0.000 0.017
)
25.20C 0.33«t O.OOC1 0.392 0.000 0.25) 0.000 0 . 0 2 31
2 6 . 4 0 C1 0.3181 O.OOC1 0.382 O.OOCi 0.270 O.OOC1 0.030
2 5 . 8 0 C1 0.326 O.OOC1 0.387 O.OOC1 0.260 O.OOC1 0.027
)
DIFFERENTIAL CRUSS-!;6CTIUN!i (MB/SR)
ANGLE(DEGREE) 0 . 3 7 9 6 02 0 . 3 7 0 6 02 0 . 3 4 3 E 02 0 . 3 0 4 E 02 0 . 2 5 7 6 02 0 . 2 1 0 6 02 0 . 1 6 7 6 02
55.0 70.0 75.0 80.0 85.0 90.0
0.54BE 0 1 0 . 6 5 5 6 01 0 . 5 6 6 6 01 0 . 5 7 3 E 01 0 . 5 8 1 E 01 0 . 5 8 8 E 0.530E 01 0 . 6 4 0 E 01 0 . 6 5 2 6 01 0.659E 01 0.558E 01 0.575E 0 . 5 0 8 E 01 0 . 6 1 8 6 0 1 0 . 5 2 9 6 0 1 0 . 5 3 5 E 01 0 . 6 4 3 E 01 0 . 5 4 9 E 0 . 5 8 0 6 0 1 0 . 5 8 7 6 01 0 . 5 9 5 6 0 1 0 . 6 0 0 E 01 0 . 6 0 5 E 01 0 . 5 0 9 E 0 . 5 4 8 6 0 1 0 . 5 5 2 6 01 0 . 5 5 7 E 01 0 . 5 5 9 6 01 0 . 5 6 1 E 01 0 . 5 6 2 6 0.517E 01 0.517E 01 0 . 5 1 8 E 01 0 . 5 1 7 6 01 0.515E 01 0 . 5 1 3 6
95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0 ENERGY(MEV)
0.1316 0.1046 0.8566 0.7556 0.5976 0 . 6 6 66
02 02 01 01 01 01
0.1296 0.102E 0.8466 0.744E 0.593E 0.570E
02 02 01 01 01 01
02 02 02 02 02 02 02
)> ) )
IN THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0
0 . 3 9 2 E 02 0 . 4 0 5 E 02 0 . 4 1 9 6 0 . 3 8 2 E 02 0 . 3 9 5 6 02 0 . 4 0 7 6 0 . 3 5 3 E 02 0 . 3 6 4 E 02 0 . 3 7 4 6 0 . 3 1 1 6 02 0 . 3 1 8 E 0 2 0 . 3 2 5 6 0 . 2 5 1 E 02 0 . 2 5 5 E 02 0 . 2 6 8 6 0 . 2 1 1 6 02 0 . 2 1 2 6 0 2 0 . 2 1 2 6 0 . 1 6 5 6 02 0 . 1 5 4 E 02 0 . 1 5 3 6
28.000 0.298 0.000 0.367 0.000 0.294 0.000 0.041
2 7 . 5 0 C1 0.30A O.OOC 0.372 O.OOC 0 . 2 8 1f O.OOC 0.031
26.900 0.311 0.000 0.377 0.000 0.27'= 1 0.000 0 . 0 3 31
0 . 4 3 3 E 0 2 0 . 4 4 4 6 02 0 . 4 5 8 E 02 0 . 4 2 0 E 0 2 0 . 4 3 1 E 0 2 0 . 4 4 4 E 02 0 . 3 8 4 E 02 0 . 3 9 3 6 0 2 0 . 4 0 3 E 0 2 0 . 3 3 2 E 02 0 . 3 3 7 6 02 0 . 3 4 4 E 02 0 . 2 7 2 E 0 2 0 . 2 7 4 6 02 0 . 2 7 7 E 02 0 , 2 1 2 £ 02 0 . 2 1 2 E 02 0 . 2 1 2 6 02 0 . 1 6 1 6 0 2 0 . 1 5 9 6 02 0 . 1 5 7 6 0 2
0 . 1 2 5 E 02 0.124E 02 0.122E 0.9996 01 0.977E 01 0.951E 0 . 8 2 B 6 01 0.813E 01 0.793E 0 . 7 3 5 6 0 1 0 . 7 2 8 6 01 0 . 7 1 7 E 0.693E 01 0.592E 01 0.6906 0 . 5 7 6 E 0 1 0 . 5 8 0 E 01 0 . 6 8 4 E
02 01 01 01 01 01
0.470E 0.454E 0.4116 0.349E 0.2796 0.211E 0.1556
02 02 02 02 02 02 02
0 . 1 1 9 6 02 0 . 1 1 5 6 0 . 9 2 5 6 01 0 . 9 0 4 6 0 . 7 7 5 6 01 0 . 7 6 0 6 0.7O7E 01 0 . 7 0 2 E 0.6a8E 01 0 . 6 9 0 E 0 . 5 8 8 6 01 0 . 6 9 5 6
02 01 01 01 01 01
0.114E 0.8826 0.748E 0.697E 0.5926 0.7016
02 01 01 01 01 01
01 01 01 01 01 01
0.5966 0.6846 0.6556 0.5146 0.564E 0.512E
01 01 01 01 01 01
0.704E 0.5926 0.662E 0.618E 0.555E 0.511E
01 01 01 01 01 01
0.4926 0.4786 0.4796 0.4976 0.5336 0.5B56
01 01 01 01 01 01
0 . 4 8 8 6 01 0 . 4 8 5 E 01 0 . 4 8 2 6 01 0.477E 01 0 . 4 7 1 6 0 . 4 7 1 6 01 0 . 4 5 5 E 01 0 . 4 5 9 6 01 0 . 4 5 0 E 01 0 . 4 4 2 E 0 . 4 6 9 6 01 0 . 4 5 0 E 01 0.452E 01 0 . 4 4 1 E 01 0.431E 0.4B5E 01 0 . 4 7 5 6 01 0 . 4 6 5 E 01 0 . 4 5 3 E 01 0 . 4 4 1 E 0 . 5 2 0 E 01 0 . 5 0 9 6 01 0 . 4 9 9 E 01 0 . 4 8 7 6 01 0 . 4 7 4 E 0 . 5 7 2 6 01 0 . 5 5 2 6 01 0 . 5 5 2 E 01 0 . 5 4 0 6 01 0 . 5 2 9 E
01 01 01 01 01 01
0 . 4 6 7 6 01 0 . 4 5 3 E 0 . 4 3 5 6 01 0 . 4 2 9 E 0 . 4 2 2 6 01 0 . 4 1 4 E 0 . 4 3 2 6 01 0 . 4 2 2 E 0 . 4 6 4 6 01 0 . 4 5 4 6 0 . 5 1 9 6 01 0 . 5 0 9 6
01 01 01 01 01 01
0.6516 0.72BE 0.812E 0.8996 0.9856 0.1066
01 01 01 01 01 02
0 . 6 4 0 6 01 0 . 5 3 0 E 0 . 7 1 9 6 01 0 . 7 1 1 E 0.805E 01 0.800E 0.895E 01 0 . 8 9 2 E 0 . 9 8 4 E 01 0 . 9 8 4 E 0 . 1 0 6 6 02 0 . 1 0 7 E
0 . 5 2 1 6 01 0 . 5 1 2 6 01 0 . 5 0 1 E 0 . 7 0 4 6 01 0.596E 01 Q.688E 0 . 7 9 5 6 01 0 . 7 9 0 6 01 0 . 7 8 3 E 0 . 8 9 0 6 01 0 . 6 8 8 6 01 0.883E 0 . 9 8 4 6 01 0 . 9 8 4 6 01 0 . 9 a 2 E 0 . 1 0 7 6 02 0 . 1 0 7 E 02 0 . 1 0 7 6 0 . 1 1 5 6 02 0 . 1 1 5 6 02 0 . 1 1 5 E 0 . 1 2 2 E 02 0 . 1 2 3 6 0 2 0 . 1 2 3 E 0 . 1 2 8 6 02 0 . 1 2 9 6 02 0 . 1 2 9 E 0 . 1 3 2 6 02 0 . 1 3 3 E 02 0 . 1 3 3 E 0 . 1 3 4 6 02 0 . 1 3 5 E 02 0 . 1 3 5 E 0 . 1 3 5 E 02 0 . 1 3 5 6 02 0 . 1 3 7 E
01 01 01 01 01 02
0.5936 0.6816 0.7796 0.8816 0.9836 0.107E 0.115E 0.1246 0.1306 0.1346 0.137E 0.138E
01 01 01 01 01 02
0.5846 0.673E 0.773E 0.8786 0.981E 0.1086
01 01 01 01 01 02
02 02 02 02 02 02
0 . 1 1 6 E 02 0 . 1 2 4 6 02 0.130E 02 0 . 1 3 5 E 02 0 . 1 3 8 6 02 0 . 1 3 8 6 02
0 . 1 1 4 6 02 0 . 1 1 4 6 02 0 . 1 2 0 6 0 2 0 . 1 2 1 6 02 0 . 1 2 5 6 02 0.126E 02 0 . 1 2 9 6 02 0 . 1 3 0 E 02 0 . 1 3 1 6 02 0 . 1 3 2 E 02 0 . 1 3 2 E 0 2 0 . 1 3 3 6 02 2.400
2.500
01 01 01 01 01 02
0 . 1 1 5 E 02 0 . 1 2 1 E 02 0 . 1 2 7 E 02 0 . 1 3 1 6 02 0 . 1 3 3 6 02 0 . 1 3 4 6 02 2.600
2.700
2.800
02 02 02 02 02 02
2.900
3.000
3.500
CENTER-OF-MASS INPUT VALUES FOR THE REACTION U ( U , N I H E 3 D-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 5
28.400 0.293 0.000 0.362 0.000 0.301 0.000 0.044
28.900 0.287 0.000 0.357 0.000 0.308 0.000 0.048
ANGLE(DEGREE)
29.300 0.282 0.000 0.353 0.000 0.314 0.000 0.051
29.800 0.277 0.000 0.349 0.000 0.320 0.000 0.054
DIFFERENTIAL CROSS-SECTIONS
30.300 0.272 0.000 0.345 0.000 0.325 0.000 0.057 (MB/SR)
30.700 0.258 0.000 0.341 0.000 0.331 0.000 0.050
31.200 0.262 0.000 0.337 0.000 0.337 0.000 0.054
33.500 0.240 0.000 0.322 0.000 0.355 0.000 0.082
I N THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.480E 02 0 . 4 9 2 E 0 . 4 5 4 E 02 0 . 4 7 5 E 0.419E 02 0.427E 0 . 3 5 3 E 02 0 . 3 5 8 6 0 . 2 8 0 6 02 0 . 2 8 2 E 0 . 2 1 0 6 02 0 . 2 0 9 6 0.153E 02 0.150E
02 02 02 02 02 02 02
0 . 5 0 2 E 02 0 . 5 1 4 E 02 0 . 5 2 5 E 02 0 . 5 3 5 E 0 . 4 8 4 E 02 0 . 4 9 5 E 02 0 . 5 0 5 E 02 0 . 5 1 5 E 0 . 4 3 4 E 02 0 . 4 4 3 6 02 0 . 4 5 1 E 02 0.45BE 0 . 3 6 2 E 02 0 . 3 6 8 6 02 0 . 3 7 3 E 02 0 . 3 7 7 6 0 . 2 8 3 6 02 0 . 2 8 5 6 02 0 . 2 8 5 E 02 0 . 2 8 7 6 0 . 2 0 8 6 02 0 . 2 0 7 E 02 0 . 2 0 7 E 02 0 . 2 0 5 F 0 . 1 4 8 6 0 2 0 . 1 4 5 6 02 0 . 1 4 3 6 02 0 . 1 4 1 E
35.0 40.0 45.0 50.0 65.0 60.0
O.lllE 0.861E 0.7346 0.6936 0.5956 0.708E
0.108E 0.837E 0.7206 0.688E 0.6976 0.714E
02 01 01 01 01 01
0 . 1 0 5 E 02 0 . 1 0 3 E 0 . 8 1 5 6 01 ~ 0.707E 01 0 . 5 8 4 6 01 0 . 5 9 9 6 01 0.719E 01
55.0 70.0 75.0 80.0 85.0 90.0
0.713E 01 0.720E 0.700E 01 0.707E 0.669E 01 0.6746 0 . 6 2 3 6 01 0.625E 0.557E 01 0.5586 0.510E 01 0.508E
01 01 01 01 01 01
0.727E 0.7136 0.679E 0.528E 0.5676 0.505E
, . . . . „ _ _. _. .. .. 0 . 7 2 1 6 01 0 . 7 2 8 6 01 0 . 7 3 6 E 01 0 . 7 3 8 E 0 . 5 8 5 6 01 0 . 6 9 1 6 0 1 0 . 6 9 5 6 01 0 . 5 9 7 E 0 . 5 3 1 6 01 0 . 6 3 5 E 01 0 . 5 3 8 E 01 0 . 5 3 7 E 0 . 5 6 8 6 01 0 . 5 6 9 6 01 0 . 5 7 0 E 01 0 . 5 5 7 E 0.503E 01 0.501E 01 0 . 4 9 9 6 01 0 . 4 9 4 E
01 01 01 01 01
__ 0.747E 0.699E 0.533E 0.555E 0.475E
_. 01 01 01 01 01
95.0 100.0 105.0 110.0 115.0 120.0
0 . 4 5 9 6 01 0 . 4 5 4 6 0.423E 01 0.415E 0 . 4 0 5 E 01 0 . 3 9 5 E 0.4126 01 0.4026 0.444E 01 0.433E 0.499E 01 0.488E
01 01 01 01 01 01
0 . 4 4 9 6 01 0.445E 01 0.440E 01 0.436E 01 0 . 4 2 8 6 0 . 4 0 8 E 0 1 0 . 4 0 1 E 01 0 . 3 9 4 E 01 0 . 3 8 8 6 01 0 . 3 7 7 6 0 . 3 8 7 6 0 1 0 . 3 7 9 6 01 0 . 3 7 0 6 01 0 . 3 5 2 6 01 0 . 3 5 1 6 0 . 3 9 2 6 0 1 0 . 3 8 3 E 01 0 . 3 7 3 6 01 0 . 3 5 4 6 01 0 . 3 5 2 6 0 . 4 2 3 E 01 0 . 4 1 3 6 01 0 . 4 0 4 6 01 0.395E 01 0.3B3E 0 . 4 7 9 E 01 0 . 4 7 0 E 01 0 . 4 5 2 6 01 0 . 4 5 4 E 01 0 . 4 4 2 E
01 01 01 01 01 01
0.4016 0.342E 0.3096 0.3076 0.339E 0.402E
01 01 01 01 01 01
125.0 130.0 135.'0 140.0 145.0 150.0
0.575E 01 0.555E 0.556E 01 0.558E 0 . 7 5 7 E 01 0 . 7 6 1 E 0.873E 01 0 . 8 6 9 E 0.9786 01 0.9766 0 . 1 0 7 6 02 0 . 1 0 7 6
01 01 01 01 01 02
0 . 5 5 5 6 0 1 0 . 5 4 9 6 01 0 . 5 4 2 6 01 0 . 5 3 5 E 0 . 5 5 1 6 01 0 . 5 4 5 6 01 0 . 5 4 0 6 01 0 . 5 3 5 6 0 . 7 5 5 6 0 1 0 . 7 5 2 6 01 0 . 7 4 9 E 01 0 . 7 4 5 6 0 . 8 5 5 E 0 1 0 . 8 6 4 6 01 0 . 8 6 3 6 01 0 . 8 5 0 6 0 . 9 7 4 6 0 1 0 . 9 7 5 6 01 0 . 9 7 5 E 01 0 . 9 7 4 E 0 . 1 0 7 E 0 2 0 . 1 0 7 6 02 0 . 1 0 8 6 02 0 . 1 0 8 6
0.525E 0.625E 0.7396 0.8576 0.9736 0.1086
01 01 01 01 01 02
0.491E 0.501E 0.723E 0.8506 0.974E 0.109E
01 01 01 01 01 02
155.0 160.0 155.0 170.0 175.0 180.0
0.1166 0.1246 0.130E 0.135E 0.138E 0 . 1 39E
02 02 02 02 02 02
0,1176 0.1246 0.1316 0.136E 0.1386 0.1396
0 . 1 1 7 E 0 2 0 . 1 1 7 6 02 0 . 1 1 8 6 0 . 1 2 5 6 02 0 . 1 2 5 6 02 0 . 1 2 6 6 0 . 1 3 2 6 02 0 . 1 3 2 6 02 0 . 1 3 3 E 0 . 1 3 7 E 0 2 0 . 1 3 7 6 02 0 . 1 3 8 6 0 . 1 4 0 E 02 0 . 1 4 0 6 02 0 . 1 4 1 6 0 . 1 4 1 E 02 0 . 1 4 1 6 02 0 . 1 4 2 6
02 02 02 02 02 02
0.1196 0.128E 0.135E 0.140E 0.143E 0.145E
02 02 02 02 02 02
NuclMr Data Tables, VoL 11, No. 7, 1973
02 01 01 01 01 01
02 02 02 02 02 02
0.117E 0.124E 0.13IE 0.1356 0.1386 0.139E
01 01 01 01 01 01
02 02 02 02 02 02
0 .. 1 1 7 6 0 ,, 1 2 5 6 0.. 1 3 1 6 0 ., 1 3 5 6 0 ,. 1 3 9 6 0 .. 1 4 0 6
596
02 02 02 02 02 02 02
0 . 5 4 8 E 02 0 . 5 0 4 E 0 . 5 2 6 E 02 0 . 5 7 7 E 0 . 4 6 5 E 02 0 . 5 0 4 E 0 . 3 8 1 E 02 0.401E 0 . 2 8 8 E 02 0 . 2 9 2 E 0 . 2 0 3 E 02 0 . 1 9 5 E 0 . 1 3 8 E 02 0 . 1 2 5 E
02 02 02 02 02 02 02
02 "•
02 02 02 02 02 02
01 01 01 01 01 02
NEUTRON PRODUCTION CROSS SECTIONS
a(e lab), E„(e lab): Recommended Values
D(d,n)^He. ENERGY(MEVI
1.600
1.700
1.800
1.900
2.000
2.100
2.200
2.300
INPUT VALUES FOR THE REACTUIN D I 0 , N ) H E 3 REST ENERGY I N MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS
ANGLE(OeGREE)
ENERGY OF PARTICLE-3
Tl=ie75.633 T2=1875.633 T3= 9 3 9 . 5 7 6 T't=2808.421
IMEVI
Q-VALUE
3.269
I N THE LABORATORY SYSTEM 5.449 5.437 5.401 5.342 5.261 5.159 5.038 4.901 4.750 4.587 4.415 4.236 4.053
5.553 5.540 5.503 5.442 5.358 5.252 5.128 4.986 4,829 4.651 4.483 4.298 4.109
3.859 3.68 5 3.504 3.328 3.158 2.995 2.841 2.696 2.561 2.435 2.320 2.214
3'Si2
3 . 7 30 3.544 3.362 3.188 3.020 2.862 2.713 2.574 2,446 2.328 2.220
1.743 1.710 1.684 1.566 1.656 1.652
2.119 2.033 1.957 1.890 1.831 1.782 1.740 1.706 1.581 1.652 1.651 1.648
2,123 2.036 1.958 1,890 1.830 1,780 1,738 1.704 1,677 1,559 1,647 1 ,544
2.900
3.000
3.500
0.0 5.0 10.0 15.0 20.0 25.0 30.0
4.813 4.803 4.775 4.729 4.665 4.586 4.491
4.921 4.911 4.681 4.833 4.766 4.683 4.584
5.028 5.017 4.987 4.936 4.867 4.779 4.676
5.134 5.123 5.091 5.039 4.966 4.875 4.768
5.240 5.228 5.195 5.140 5.065 4.970 4.858
5.346 5.333 5.298 5.241 5.163 5.056 4.949
35.0 'tO.O 45.0 50.0 55.0 60,0
4.383 4.264 4.134 3,998 3.855 3.709
4.471 4.346 4.211 4.068 3.920 3.767
4.558 4.428 4.287 4.139 3,984 3,825
4.645 4.509 4.363 4,208 4.047 3.883
4.731 4.590 4.438 4.278 4.111 3.940
4.816 4.670 4.513 4.346 4.173 3.99 7
65.0 70.0 75.0 80.0 85.0 90.0
3.560 3.412 3.265 3.121 2.981 2.846
3.613 3.458 3.305 3.156 3.010 2.871
3.665 3.504 3.346 3.190 3,040 2,896
3.716 3.550 3.386 3.225 3.070 2.921
3.767 3.595 3.425 3.260 3.099 2.946
3.818 3.540 3.46 5 3.294 3.129 2.971
95.0 100.0 105.0 110.0 115.0 120.0
2.717 2.595 2.481 2.374 2.275 2.184
2.738 2.612 2.493 2.383 2.282 2.188
2,758 2,628 2,506 2,393 2,288 2.193
2.779 2.645 2.520 2.403 2.296 2.197
2.800 2.662 2.533 2.414 2.303 2.203
2.820 2.679 2.547 2.424 2.311 2.208
125.0 130.0 135.0 140.0 145.0 150.0
2.101 2,027 1,960 1,900 1,849 1,804
2.103 2.026 1.958 1.897 1.844 1.799
2.105 2,027 1.956 1,894 1,840 1.794
2.108 2.028 1.956 1.892 1.637 1.790
2.111 2.029 1.956 1.891 1.835 1.787
2.115 2.031 1.956 1.890 1.833 1.784
155.0 160.0 165.0 170.0 175.0 180.0
1,767 1,737 1,714 1.697 1.687 1.684
1.761 1.730 1.706 1.689 1.679 1.676
1,755 1,724 1,700 1,683 1.672 1.669
1.751 1.719 1.694 1.676 1.666 1.663
1.747 1.714 1.689 1.671 1.660 1.657
2.400
2.500
2.600
2.700
2.800
ENERGY(MEV)
IN «FV 0=
INPUT VALUES FOR THE REACTION D(D,N)HE3 REST ENERGY I N MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0
i9«o
55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0
lop.o
105.0 110.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
71=1875.633 T2=1875.633 T3= 9 3 9 . 5 7 6 74=2808.421
ENERGY OF PARTICLE-3 (MEV) 5.556 5.643 5,605 5,541 5.454 5.345 5,216 5.069 4.907 4.733 4,549 4,359 4.164
5.759 5.746 5.706 5,640 5.550 5.438 5.304
3.968 3.773 3.582 3.395 3.216 3.044
4,018 3.818 3,621 3,429 3,245 3,069
2,882 2,730 2.588 2.457 2.336 2.226 2.127 2.038 1.959 1.890 1.830 1.778 1.736 1.701 1.674 1.655 1.644 1.640
0-VALUE
IN MEV 0=
3.269
I N THE LABORATORY SYSTEM
5.861 5.848 5.806 5.739 5.646 5.530 5.392 5.236 5.064 4.879 4.683 4.481 4.275
5.953 5.949 5.907 5 . 8 37 5.741 5,622 5.480
6.065 6.050 6.007 5.935 5.836 5.713 5.567
6.166 6.151 5.106 6.032 5.931 5.804 5.654
6.267 6.252 6.206 5.130 6.025 5.895 5.741
5.758 6.750 6.598 5.512 5,493 6.345 6.171
5.319 5.142 4.951 4.750 4.542 4.330
5.402 5.219 5.023 4.817 4.503 4.385
5.484 5.295 5.095 4.883 4.663 4.440
5.566 5.373 5.166 4.949 4.724 4.495
5.972 5.755 5.521 5,275 5,022 4.765
4.U7 3.906 3.698 3.497 3.303 3.119
4.167 3.950 3.737 3.531 3.333 3.144
4.216 3.993 3.776 3.554 3.362 3.169
4.265 4.037 3.814 3.598 3.391 3.194
4.508 4.253 4.005 3.755 3.536 3.319
2,903 2,747 2,602 2.468 2.345 2.233
4.068 3.862 3.660 3.463 3.274 3.094 2.924 2.765 2,616 2.480 2.354 2.240
2.945 2.782 2.631 2.491 2.363 2.247
2.966 2.800 2.645 2.503 2.373 2.255
2.987 2.818 2.650 2.515 2.383 2.262
3.009 2.835 2.675 2.527 2.392 2.270
3.115 2.925 2.750 2.590 2.444 2.312
2.132 2.042 1.961 1.891 1.830 1.777
2.137 2.045 1.964 1.892 1.830 1.777
2.143 2.049 1.966 1.893 1.830 1.777
2.148 2.053 1.959 1.895 1.831 1.777
2.154 2.058 1.972 1.897 1.833 1.777
2.160 2.062 1.975 1.900 1.834 1.778
2.194 2.088 1.996 1.915 1.845 1.786
1.734 1.699 1.672 1 .653 1.541 1.638
1.733 1.697 1.570 1.651 1.639 1.635
1.732 1.596 1.668 1.549 1.637 1.633
1.732 1.695 1.667 1.547 1.535 1.632
1.732 1.695 1.655 1.646 1.634 1.63 0
1.732 1.694 1.566 1.645 1.533 1.629
1.737 1.697 1.667 1.646 1.533 1.629
5,153 4,986 4.806 4.617 4.420 4.220
597
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
D(4n)^He.
0(6 lab), £„(6l lab): Recommended Values 5.500
4.600
ENERGY(MEV)
6.500
CENTER-OF-MASS INPUT VALUES FOR THE REACTIUN U ( U , N I H E 3 U-SIGMA-0(MB/SR) A 0 A I A 2 A 3 A 4 A 5 A 6 A 7 A 8 A 9 AlO
37.800 0.206 0.000 0.295 0.000 0.372 0.000 0.112 0.000 0.012 0.000 0.003
35.700 0.221 0.000 0.308 0.000 0.367 0.000 0.098 0.000 0.004 0.000 0.002
65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155, 160, '65, .70, 175, ENERGY IMEV)
0.658E 0.625E 0.537E 0.416E 0.292E 0.186E 0.113E 0.722E 0.574E 0.585E 0.661E 0.734E 0.775E 0.777E 0.748E 0.6966 0.625E 0.542E 0.454E 0.372E 0.308E 0.272E 0.270E 0.303E 0.370E 0.464E 0.5796 0.707E 0.840E 0.970E 0.109E 0.120E 0.129E 0.137E 0.143E 0.1466 0.1476
02 02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02 02
0.7106 0.6716 0.567E 0.4276 0.289E 0.177E 0.102E 0.6476 0.533E 0.571E 0.662E 0.744E 0.7876 0.788E 0.7556 0.6966 0.6176 0.5276 0.4336
7646 7186 596E 4376 285E 167E 933t 580E 497E 558E 662E 01 0 749E 01 0, 7926
01 01 01 -• 01 01 01
0.348E 0.283E 0.2476 0.245E 0.279E 0.347E
0.4436 0.5606 0.6926 0.829E 0.965E 0.1096 0.1216 0.1316 0.1396 0.1456 0.1486 0.150E
02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01
0.805E 0.7536 0.616E 0.441fc 0.2776 0.156E 0.844E 0.530E 0.478 6 0.557E 0.668E 0.7556 0.7956 0.7896 0.7476 0.6796 0.592E 0.4946 0.3956
0.7906 0.7536 0.6896 0.605E 0.510E 0.4126 0.324E 307E 0.2596 2426 0.2236 207E 0.223E 01 0, 206E 0.2586 01 0, 240E 0.327E 308E
0.843E 0.785E 0.633E 0.443E 0.270E 0.146E 0.770E
01 01 01 01 Ql 01 01 01 01 01 01 01 01 01 01 01 01 01
0.4906 0.4686 0.565E 0.683E 0.767E 0.7996 0.7866 0.741E 0.672E 0.584E 0.4856 0.3856 0. 2966 0 . 2296 0. 193E 0. 192E 0. 2256 0 . 293E
01 01 01 01 01 02
0. 390E 0. 511E 0 . 648 6 0. 7956 0 . 943E 0. 108E 0 121E 0 132E 0 141E 0 148E 0 152E 0 1546
4056 5256 6626 80 6E 952E 109E 121E 1326 1416 148 E 1526 1536
01 0.425E 0.544E 0.679E 0.8216 0.9636 02 0.1096 0 0.1226 0 0.1326 0 0.1416 0 0.147E 0 0.1516 0 0.1536
02 02 02 02 02 02
IN THE LAB(JRATURY SYSTEM
02 02 02 02 02 02 01" 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01
0.871E 0.808E 0.6446 0.4416 0.261E 0.137E 0.705E 0.466E 0.4736 0.5826 0.698E 0.774E 0.7966 0.777E 0.728E 0.660E 0.5746 0.477E 0.378E 0, 290E 0. 2236 0, 186E 0. 182E 0, 213E 0. 278E 374E .4936 631E ,778E .927E ,107E
02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 -_ 01 01 01 01 01 01 01 01 01
,1206 1316 ,1406 1476 ,1516 1526
02 02 02 02 02 02
01
01 01 01 01 02
0.897E 0.828E 0.6536 0.4386 0.2526 0.1286 0.653E 0.4546 0.4866 0.6016 0.7136 0.7786 0.7926 0.7666 0.716E 0.648E 0.5656 0.4716 0.374E 0.2876 0.2206 0.1816 0.1756 0.2046 0.266E 0.359E 0.478E 0.6166 0.763E 0.913E 0.105E 0.1186 0.130E 0.1396 0.1466 0.150E 0.1516
02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02
0.,9186 0.,8456 0,,6596 ,4346 243E 1206 6106 4486 ,5016 ,6226 ,7286 ,7826 ,7856 0,.753E 0,.7026 0,.5376 0 .5576 0 .466E 0 .3726 0 .2866 0 .2186 0 .1786 0 .1596 0 .1956 0 .2556 0 .3476 0 .4556 .6026 .749 6 0 .8996 .1046 0 .1176 .1286 .1376 .1446 .1486 ,1506
9.500
8.500
8.000
02 02 02 02 02 02 01
45.200 0.159 0.000 0.244 0.000 0.362 0.000 0.178 0.000 0.046 0.000 0.011
4 4 . 6 00 0.163 0.000 0.250 0.000 0.366 0.000 0.169 0.000 0.042 0.000 0.010
43.800 0.168 0.000 0.257 0.000 0.370 0.000 0.159 0.000 0.037 0.000 0.009
0.174 0.000 0.265 0.000 0.373 0.000 0.148 0.000 0.032 0.000 0.008
0.182 0.000 0.274 0.000 0.374 0.000 0.137 0.000 0.027 0.000 0.006
DIFFERENTIAL CRUSS-SECT IONS (MB/SR)
ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0
0.192 0.000 0.284 0.000 0.374 0.000 0.125 0.000 0.020 0.000 0.005
CENTER-OF-MASS INPUT VALUES FOR THE REACTION 0 ( U , N ) H 6 3 0-SlGMA-0(MB/SR) A 0 A 3 A 4 A 5 A 6 A 7 A 8 A 9 AlO
4 6 . 100 0 . 153 0 . 000 0 . 234 0 000 0 . 354 0 . 000 0 . 195 0 000 0 052 000 0 012 0
45.700 0.156 0,000 0.239 0.000 0.358 0.000 0.187 0.000 0.049 0.000 0.011
DIFFERENTIAL CROSS-SECTIONS
ANGLE(DEGREE)
0.937E 0.860E 0.665E 0.431E 0.235E 0.113E 0.574E
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0
0.741E 0.689E 0.627E 0.552E 0.465E 0.374E
95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155, 160, 165, 170. 175, 180.
0.2886 0.2206 0.1776 0.1656 0.1876 0.2456 0.3366 0.4546 0.5916 0.738E 0.888E 0.1036 0.1156 0.1276 0.135E 0.1436 0.147E 0.1486
Nuclear Data Tables, Vol, 11, No. 7, 1973
46.500 0.148 0.000 0.227 0.000 0.346 0.000 0.209 0.000 0.056 0.000 0.014
46.400 0.150 0.000 0.230 0.000 0.350 0.000 0.202 0.000 0.055 0.000 0.013
02 02 02 02 02 02 01
0.450E 0.525E 0.649E 0.745E 0.7B5E 0 . 7 7 7 E 01
01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02 02
0.9536 0.8726 0.6686 0.4266 0.2276 0.1066 0.5416 0.451E 0.544E 0.6716 0.7586 0.7866 0.7686 0.7266 0.6756 0.617E 0.547E 0.464E 0.374E 0.2896 0.2196 0.1746 0.1596 0.1806 0.2366 0.3256 0.4426 0.578E 0.7266 0.8756 O.IOIE 114E 125E 1346 1416 1456
,9666 02 ,6826 02 ,6706 02 ,4216 02 " • 219E 02 .9966 01 .5136 01 ,4526 01 .5596 01 ,6866 01 " ,76^6 01 ,7816 01 ,7536 01 ,7076 01 ,6586 01 .6056 01 .5396 01 .4606 0 1 .37 26 01
0.975E 0.888E 0.670E 0.4166 0.2126 0.9436 0.4916 0.4566 0.5796 0.7076 0.7766 0.7776 0,7366 0.685E 0.6396 0,593E 0.535E 0.460E 0.3746
.2886 .217E .1706 01 ,1546 .1726 .2276 .3156 .4316 .5576 ,7136 .8616 01 .1006 02 ,1136 02 .124E 02 .1336 02 .1396 02 .1436 02 . 144E 02
0.1686 0.1496 0.1666 0.2196 0.3076 0.4226 0.5576 0.7026 0.8496 0.9896 0.1116 0.122E 0.1316 0.1376 0.1416 0.1426
§:i?li
598
46.500 0.147 0.000 0.224 0.000 0.342 0.000 0.215 0.000 0.058 0.000 0.014 (MB/SR)
02 02 02 02 02 01 01 01 01 01 01 01 01
IN THE LABORATORY SYSTEM
01 01 01 01 01 01 01 01 01 01 01 01
0,,9826 0. 8936 0,.6696 0, 4106 0,.2056 0.,8996 0.,4796 .4726 ,606E .730E 785E .7756 7255 6726 .5286 5866 .5336 4626 3786
02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01 01 01
0,,2946 0. 2206 0,,1696 0 . 1486 0,,1626 0. 2146
01 01 01 01 01 01 02 02 02 02 02 02
0. 3006 0,.4156 0. 5496 - .6926 0 ,8376 0 ,9756 0,.1096 0. 1206 0.,1296 0. 1356 0.,139E 0. 1406
01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02
02 02 02 02 02 02 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02 02
NEUTRON PRODUCTION CROSS SECTIONS
D(d,nfne. ENERGY(MEV)
4.000
a{fi lab), EJfi lab): Recommended Values 4.500
5.000
5.500
6.000
6.500
7.000
7.500
INPUT VALUES FUR THE REACTION D(D,N1HE3 REST ENERGY IN MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET T 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS T 4 = 2 8 0 8 . 4 2 1
ANGLE(DEGREE)
ENERGY OF PARTICLE-3
0.0 5.0 10.0 15.0 20.0 25.0 30.0
7.263 7.243 7.184 7.088 6.955 6.789 6.593
35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0
6.372 6.128 5.868 5.595 5.313 5.028
95.0 100.0 105.0 110.0 115.0 120.0
3.218 3.013 2.824 2.652 2.495 2,355
125.0 130.0 135.0 140.0 145.0 150.0
2.229 2.117 2.019 1.934 1.860 1.798 1.747 1.705 1.674 1.651 1.638 1.633
155.0 160.0 165.0 170.0 175.0 IBO.O
ENERGY(MEVI
4.744 4.463 4.190 3.927 3.676 3.440
8.000
9.690 9.660 9.570 9.422 9.220 8.968 8.671
3.541 3.290 3.062 2.854 2.668 2.501
9.209 9.181 9.097 8.960 8.771 8.536 8.260 7.947 7.605 7.241 6.860 6.470 6.076 5.686 5.304 4.935 4.582 4.249 3.938 3.649 3.384 3.142 2.924 2.728 2.553
2.354 2.223 2.110 2.011 1.927 1.856 1.798 1.751 1.716 1.690 1.675 1.670
2.398 2.262 2.144 2.041 1.954 1.880 1.820 1.771 1.734 1.708 1.693 1.688
8.241 8.217 8.146 8.029 7.868 7.668 7.431 7.164 6.871 6.558 6.231 5.895 5.556
8.726 8.700 8.62 3 8.495 8.321 8.103 7.847 7.557 7 . 2 39 6.900 6.546 6.183 5.817
4.981 4.675 4.378 4.092 3.820 3.564 3.326 3.105 2.902 2.718 2.561 2.402 2.268 2.150 2.047 1.957 1.880 1.816
6.218 4.886 4.564 4.256 3.963 3.689
5.452 5.095 4.750 4.419 4.106 3.813
3.433 3.197 2.982 2.786 2.609 2.451 2.310 2.186 2.077 1.983 1.902 1.834
1.761 1.718 1.686 1.661 1.647 1.643
1.778 1.733 1.699 1.674 1.660 1.655
9.000
9.500
REST ENERGY IN MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET 7 2 = 1 8 7 5 . 6 3 3 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS 7 4 = 2 8 0 8 . 4 2 1 ENERGY OF PARTICLE-3
(MEV)
11.125 11.088 10.980 10.802 10.658 10.254 9.897 9.494 9.054 8.586 8.099 7.602 7.103
11.601 11.563 11.448 11.259 11.002 10.681 10.304 9.879 9.415 8.921 8.408 7.884 7.358
12.077 12.036 11.915 11.717 11.445 11.107 10.710
12.551 12.509 12.382 12.173 11.888 11.533 11.116
10.263 9.775 9.256 8,716 8.165 7.614
10.646 10.134 9.589 9.023 8.446 7.868
6.609 6.129 5.667 5.228 4,816 4.433
7.069 6.540 6.032 5.661 5.100 4.682
7.299 6.745 6.214 5.712 5.241 4.806
95.0 100.0 105.0 110.0 115.0 120.0
4.080 3.759 3.468 3.207 2.975 2.769
6.840 6.334 5.849 5.389 4.958 4.567 4.189 3.864 3.651 3,280 3.038 2.825
4.298 3.949 3.634 3,353 3,102 2,881
4.407 4.044 3.718 3.426 3.166 2.938
13.026 12.981 12.847 12.629 12.33 0 11.958 11.521 11.029 10.492 9.922 9.330 8.727 8.123 7.528 6.950 6.396 5.873 5.383 4.931 4.516 4.140 3.801 3.499 3.231 2.995
125.0 130.0 135.0 140.0 145.0 150.0 165.0 160.0 165.0 170.0 175.0 180.0
2.587 2.429 2.292 2.174 2.074 1.990
2.637 2.473 2.331 2.210 2.106 2.020 1.949 1.89 3 1.860 1.819 1.801 1.795
2,687 2,518 2,371 2,246 2,140 2,051
2.737 2.563 2.412 2.283 2.174 2.082
2.788 2.608 2.453 2.320 2.208 2.114
1,978 1,920 1,876 1,845 1,826 1.820
2.007 1.948 1.902 1.870 1.851 1.845
2.037 1.976 1.930 1.897 1.877 1.871
599
8.336 7.970 7.579 7.172 6.755 6.336
10.169 10.137 10.041 9.883 9.667 9.398 9.081 8.724 8.333 7.917 7.483 7.039 6.593
5.919 5.512 5.119 4.746 4.392 4.062
6.151 5.719 5.303 4.907 4.534 4.187
10.648 1Q.613 10.5U 10.343 10.113 9.827 9.490 9.111 8.696 8 . 2 54 7.793 7.323 6.850 6.382 5.926 5.487 5.069 4.677 4.3U
3.757 3.47 8 3.224 2.994 2.789 2.606
3.866 3.572 3.306 3.066 2.851 2.660
3.974 3.667 3.388 3.137 2.913 2.715
2.446 2.303 2.179 2.073 1.982 1.906
2.492 2.344 2.216 2.106 2.012 1.933 1.868 1.816 1.777 1.749 1.733 1.727
2.540 2.387 2.254 2.140 2.043 1.961 1.8 94 1.841 1.800 1 .772 1.754 1.749
1.843 1.793 1.756 1.726 1.712 1.707
0(0,N>He3 Q-VALUE
IN MEV g=
IN THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0
1.921 1.866 1.824 1.795 1.777 1.772
3.269
10.000
INPUT VALUES FUR THE REACTION
ANGLE(DEGREE)
IN MEV 0=
(MEV I IN THE LABORATORY SYSTEM
7.7^4 7.732 7.667 7.560 7.413 7.230 7.014 6.769 6.501 6.214 5.914 5.605 5.293
8.500
O-VALUE
Nucleor Data Tables, VoL 1 1, No. 7, 1973
NEUTRON PRODUCTION CROSS SECTIONS
T(d,n)me a(0° cm.), Legendre Coefficients (cm.), a(total) Recommended and Experimental Values aie lab), E„(e lab) Recommended Values
6 0 1
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(d',n)*He.
a(0° cm.), Legendre Coefficients, a(totaI) Recommended and Experimental Values SIGMA-0 AO, Al, . . . SIGMA-T
a(0° cm.) Legendre coefficients o(total)
Recommended Data ENERGY (MEV)
SIGMA-0 (MB/SR)
AO
Al
A2
A4
A3
A5
A6
A7
A8
SIGMA-T (MB)
0.020 0.030 0.040 0.050
4.3 19.6 52.9 106.0
1.000 1.000 1.000 1.000
54. 246. 665. 1332.
0.060 0.070 0.080 0.090 0.100
175. 250. 315. 367. 3 94. 317. 199. 133. 95.2 77.5 63.5 53.0 45.5
1.000 1.000 1.000 1.000 1.000 l.QOO 1.000 1.000 1.000 1.000 0.999 0.998 0.997
2199. 3142. 3958. 4612. 4951.
0.550 0.600 0.650 0.700 0.750 0.800 0.8
39.4 35.5 31.9 29.4 27.0 25.0 23.4 22.0
1.100 1.200 1.300 1.400 1.500 1.600 1.700 1.800 1.900 2.000
17.9 16.7 16.8 15.0 14.3 13.8 13.3 12.9 12.6 12.3
2.100 2.200 2.300 2.400 2.500 2.600 2.700 2.800 2.900 3.000 3.500 4.000 4.500 5.000 5.500 6.000 6.500 7.000 7.500 8.000 8.500 9.000 9.500 10.000
0.150 0.200 0.250 0.300 0.350 0.400 0.450 0.500
0.004 0.013 0.021
-0.003 -O.OU -0.018
3984. 2501. 1671. 1196. 974. 797. 665. 570.
0.030 0.038 0.046 0.053 0.060 0.067 0.072 0.077 0.082 0.087
-0.025 -0.031 -0.035 -0.039 -0.043 -0.045 -0.045 -0.045 -0.045 -0.044
493. 443. 396. 364. 334. 307. 286. 268. 252. 238.
0.094 0.100 0.105 0.110 0.113 0.116 0.120 0.122 0.124 0.127
-0.040 -0.03? -0.023 -0.013 0.002 0.016 0.029 0.042 0.054 0.067
12.1 11.9 11.8 11.8 11.8 11.9 12.0 12.1 12.2 12.3
0.995 0.993 0.989 0.986 0.983 0.978 0.973 0.968 0.963 0.957 0.946 0.931 0.915 0.898 0.878 0.85 8 0.835 0.814 0.793 0.771 0.749 0.730 0.707 0.688 0.666 0.646 0.627 0.608 0.589 0.571
0 . 129 0.13C 0.132 0.132 0.133 0.133 0.132 0.131 0.130 0.130
13.8 15.2 17.0 18.2 18.7 18.9 18.7 18.0 17.4 16.9 16.4 16.0 15.8 15.7
0.490 0.426 0.384 0.359 0.343 0.328 0.314 0.302 0.291 0.280 0.271 0.263 0.254 0.246
0.126 0.123 0.119 0.115 0.111 0.107 0.101 0.094 0.087 0.080 0.072 0.065 0.057 0.048
IV.I
Nuclear Dota Tables, Vol. 1 1 , No. 7, 1973
0.080 0.091 0.104 0.115 0.127 0.137 0.148 0.159 0.169 0.180
0 ,, 0 0 0 0.000 0 ,, 0 0 0 0 ., 0 0 0 0.000 0 ,, 0 0 1 0, . 0 0 2 0, , 0 0 4 0, . 0 0 5 0, . 0 0 7 0, , 0 0 9 0.. 0 1 2 0 ., 0 1 5 0 ,, 0 1 9 0, , 0 2 3 0, , 0 2 7 0 ,, 0 3 1 0 ., 0 3 4 0, , 0 3 7
0, , 0 0 1 0, , 0 0 3 0 ,. 0 0 4 0.005 0 .• 0 0 7 0 ,, 0 0 8 0,. 0 0 9 0, , 0 1 1 0,. 0 1 2 0 .013 0,, 0 1 4 0 .016 0, , 0 1 7 0,. 0 1 8 0, , 0 2 0 0.. 0 2 1 0, , 0 2 2 0,. 0 2 4 0, , 0 2 5
0 ,, 0 0 0 0 ,, 0 0 0 0, , 0 0 1 0 ,, 0 0 4 0,. 0 0 7 0, , 0 1 0 0, . 0 1 3 0,. 0 1 6 0, , 0 1 9 0 .022 0 ., 0 2 5 0, , 0 2 8 0 ,, 0 3 1 0,. 0 3 4 0, , 0 3 7 0,. 0 4 0 0, , 0 4 2
0 ,. 0 0 1 0 ,, 0 0 2 0 ,, 0 0 2 0 ,, 0 0 3 0, , 0 0 4 0 ,. 0 0 4 0, , 0 0 5 0, . 0 0 6 0 ,. 0 0 7 0.. 0 0 7 0 ,, 0 0 8 0, , 0 0 9 0 ,, 0 1 0 0,. 0 1 1 0, . 0 1 2 0, , 0 1 4 0, . 0 1 5
0.223 0.256 0.268 0.264 0.248 0.231 0.214 0.202 0.192 0.184 0.17fi 0.173 0.170 0.167
0, , 0 5 1 0, , 0 5 8 0 ., 0 6 2 0, , 0 6 4 0, , 0 6 3 0, . 0 5 9 0 ., 0 5 0 0, . 0 3 9 0, , 0 2 6 0,. 0 1 3 0.001 - 0 ,.010 - 0 .,019 - 0 ,.027
0,, 0 3 1 0,. 0 3 7 0, , 0 4 3 0,. 0 5 1 0, , 0 6 0 0 .073 0 ,, 0 8 9 0,. 1 0 2 0, , 1 1 4 0 .124 0 ., 1 3 2 0 .138 0 ,, 1 4 2 0,. 1 4 3
0, , 0 5 7 0,. 0 7 1 0 ,, 0 8 7 0,. 1 0 3 0 ., 1 2 0 0,. 1 3 4 0 ,, 1 4 9 0, . 1 6 2 0 ,, 1 7 3 0,. 1 8 3 0 ,, 1 9 0 0,, 1 9 4 0 ,. 1 9 7 0, , 1 9 8
0, . 0 2 2 0, , 0 2 9 0 ., 0 3 7 0, , 0 4 4 0 ,, 0 5 2 0., 0 6 1 0 ., 0 7 1 0 ., 0 8 0 0 ,, 0 9 0 0,. 1 0 1 0 ,, 1 1 2 0 .. 1 2 4 0 ,, 1 3 6 0, , 1 5 1
6 0 2
213. 195. 182. 169. 158. 149. 140. 132. 126. 119. 114. 109. 105. 102. 98.6 96.5 94.7 92.1 90.1 88.5
0,. 0 0 2 0, , 0 0 4 0,. 0 0 7 0.011 0,. 0 1 6 0, , 0 2 1 0,. 0 2 7 0, , 0 3 3 0^. 0 4 0 0.047
0,. 0 0 1 0 ,, 0 0 3 0, . 0 0 5 0 ., 0 0 8 0,. 0 1 1 0 ,, 0 1 4 0,. 0 1 7 0 ,, 0 2 0 0 ,, 0 2 3 0 ,, 0 2 7
85.0 81.2 81.8 81.9 80.8 77.9 73.9 68.5 63.8 59.5 56.0 53.0 50.4 48.4
NEUTRON PRODUCTION CROSS SECTIONS
T(rf,n)4He.
a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values
0* cm. O-oss Section
o ARS2 a BAS7 6 • BA57C
^ 0')
+ C052 V 0AS6 & G061A <>HES5
sS*""' eoJ\
0 5I6a @ 5TS2 * STK
[mb/srj cm.
\
To
) Q
;i
o^ ^ • o
OM
a05
OK)
0.15 Ed 1M(«)
0.20
025
0 0.3
030
0.4
06
06 to
•
a(0° cm.). Experimental and Recommended Values
rf^v
2.0 Ed iMeV)
40
'
6.0
S)
&0 10.0
a(0° cm.). Experimental and Recommended Values 1
T(d.n)'He
Ref. 1200- °
o a •
AR52 eA57B BA57C GA56 G061 A HES5
— —
Imb) 1000-
1
8000
\« = .
2.0
3.0
40
5.0 60 Ed iMeV)
70
6.0
9.0
00.3
10.0
•
Legendre Coefficients. Experimental and Recommended Values
04
0.6
0.8 1.0
2.0 Ed iMeVl
4.0
6.0
60 10.0
a(total). Experimental and Recommended Values
Solid line shows recommended values. Only experimental data which contributed to the recommended values are plotted. References are on page 618 603
Nuclear Data Tables, Vol. 1 1 , IMo. 7 , 1973
H. LISKIEN AND A. PAULSEN
T(4ii)*He. a(0° cm.), Legendre CoefHcients, a(total) Recommended and Experimental Values
EXPERIMENTAL 0 DEGREE C M . CROSS SECTION FOR THE REACTION T(D,N)HEA
ED(MEV)
SIGMA-0
REF.
ED(MEV)
SIGMA-0
REF,
0.0103 0.0154 0.0207 0.0220 0.0250 0.0250 0.0258 0.0300 0.0310 0.0330 0.0345 0.0360 0.0363 0.0400 0.0400 0.0415 0.0425 0.0460 0.0467 0.0481 0.0485 0.0500 0.0500 0.0520 0.0520 0.0525 0.0530 0.0533 0.0537 0.0554 0.0571 0.0580 0.0600 0.0600 0.0623 0.0625 0.0640 0.0670 0.0671 0.0675 0.0693 0.0693 0.0700 0.0700 0.0725 0.0728 0.0730 0.0733 0.0760 0.0762 0.0767 0.0780 0.0793 0.0800 0.0800 0.0820 0.0825 0.0827 0,0833 0.0867 0.0867 0.0893 0.0900
0.13 1.35 4.91 6.84 11.5 3.0 12.5 22.1 23.3 31.4 34.8 41.3 40.1 57.5 23.0 59.3 40.0 88.3 84.5 111.0 93.9 50. 68. 127. 118. 88. 129. 140. 131. 141. 141. 176. 173. 97. 183. 142. 208. 224. 245. 224. 247. 238. 160. 220. 200. 260. 267. 274. 292. 279. 284. 284. 334. 303. 313. 240. 263. 329. 330. 338. 359. 364. 325.
cn52 cn52 cn52 AR54 AR54 0A57A C052 AR54 cn52 AR54 C052 AR54 cn52 AR54 0A57A cn52 DA57A AR54 Cn52 BA57B C052 DA57A DA57A BA57R Cn52 DA57A AR54 AR52 BA57B cn52 cn52 AR5? AR54 DA57A cn52 DA57A AR52 AR54 BA57B C052 AR52 C052 DA57A DA57A DA57A C052 AR54 BA57B AR52 C052 Kn66 C052 BA57B K066 AR54 DA57A DA57A AR52 C052 Kn66 BA57B AR52 DA57A
0.0900 0.0903 0.0913 0.0925 0.0930 0.0931 0.0933 0.0937 0.0954 0.0960 0.0971 0.1000 0.1000 0.1000 0.1000 0.1011 0.1025 0.1027 0.1040 0.1060 0.1062 0.1067 0.1070 0.1090 0.1093 0.1100 0.1100 0.1100 0.1100 0.1110 0.1130 0.1130 0.1133 0.1141 0.1150 0.1150 0.1153 0.1160 0.1200 0.1200 0.1200 0.1200 0.1200 0.1211 0.1225 0.1227 0.1250 0.1250 0.1250 0.1260 0.1267 0.1293 0.1297 0.1321 0.1325 0.1332 0.1333 0.1340 0.1350 0.1360 0.1360 0.1400
290. 351. 390. 330. 377. 380. 366. 3 84. 406. 3 84. 391. 335. 390. 392. 375. 414. 390. 3 90. 404. 415. 406. 404. 394. 406. 392. 404. 394. 382. 395. 405. 393. 402. 401. 409. 403. 401. 399. 3 90. 374. 375. 403. 3 98. 389. 381. 388. 382. 385. 400. 395. 379. 373. 367. 374. 340. 360. 351. 357. 363. 390. 360. 350. 339.
DA57A C052 BA57B DA57A AR54 BA57B K066 C052 BA57B AR52 C052 DA57A AR54 K066 DA57A BA57B DA57A AR52 C052 BA57B BA57R K066 AR54 C052 AR52 K066 AR54 DA57A DA57A cn52 AR54 BA57B K066 BA57B 0A57A C052 BA57B AR52 AR54 DA57A DA57A DA57A K066 BA57B DA57A AR52 C052 DA57A DA57A BA57B K066 AR52 BA57B BA57B DA57A BA57B K066 cn52 DA57A Cn52 AR52 Kn66
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
604
NEUTRON PRODUCTION CROSS SECTIONS
T(
a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values
EXPERIMENTAL 0 DEGREE C M . CROSS SECTION FOR THE REACTION (CONTINUED)
T(D,N)HE4
ED(MEV)
SIGMA-0
REF.
ED(MEV)
SIGMA-0
REF.
0.1400 0.1412 0.1427 0.1430 0.1458 0.1460 0.1467 0.1493 0.1500 0.1500 0.1525 0.1530 0.1532 0.1533 0.1560 0.1600 0.1620 0.1627 0.1659 0.1667 0,1670 0.1700 0.1700 0.1725 0.1730 0.1733 0.1760 0.1773 0.1800 0.1825 0.1830 0.1859 0.1867 0.1893 0.1933 0 . 193 6 0.2000 0.2000 0.2027 0.2050 0.2062 0.2067 0.2133 0.2151 0.2160 0.2200 0.2250 0.2265 0.2267 0.2270 0.2293 0.2333 0.2350 0.2400 0.2427 0.2467 0.2510 0.2513 0.2533 0.2548 0.2560 0.2600 0.2600
383. 307. 334. 339. 316. 329. 321. 316. 360. 350. 315. 309. 271. 305. 300. 288. 276. 282. 264. 272. 272. 308. 303. 278. 260. 256. 247. 239. 240. 255. 245. 209. 224. 221. 209. 198. 195. 242. 202. 198. 182. 182, 171. 174. 180. 162. 200. 158. 153. 167. 162. 146. 152. 139. 147. 134. 142. 133. 128. 134. 133. 123. 134.
DA57A BA57R AR52 C052 BA57B C052 K066 AR52 DA57A DA57A DA57A C052 BA57B K066 Cn52 K066 C052 AR52 8A57B Kn66 C052 0A57A DA57A DA57A C052 K066 AR52 BA57B K066 DA57A Cn52 BA57B K066 AR52 K066 BA57B K066 DA57A AR52 C052 BA57B K066 K066 BA57B AR52 K066 DA57A BA57B K066 Cn52 AR52 K066 BA57B K066 AR52 K066 C052 AR52 K066 BA57B AR52 K066 BA57B
0.2667 0.2675 0.2693 0.2733 0.2760 0.2800 0.2880 0.2933 0.2957 0.3020 0.3067 0.3098 0.3200 0.3290 0.3333 0.3348 0,3467 0.3570 0.3600 0.3733 0.3830 0.3854 0.3867 0.4000 0.4020 0.4133 0.4267 0.4400 0.4480 0.4533 0.4602 0.4667 0.4800 0.4810 0.4822 0.4933 0,4960 0.5067 0.5200 0.5330 0.5333 0.5350 0.5467 0 . 5 5 70 0.5600 0.5733 0.5867 0.6000 0.6070 0.6108 0.6133 0.6267 0.6300 0.6400 0.6530 0.6533 0.6667 0.6890 0.6933 0.7045 0.7200 0.7333
118. 120, 119. 113. 118. 108. 109.
K066 BA57B AR52 K066 cn52 K066 BA57B K066 BA57B C052 K066 BA57B K066 C052 K066 BA57B K066 C052 Kn66 Kn66 AR52 BA57B K066 K066 C052 K066 K066 K066 C052 K066 BA57B Kn66 K066 C052 BA57B K066 cn52 K066 K066 C052 K066 BA57R K066 BA57B K066 K066 K066 K066 C052 BA57B K066 K066 BA57B K066 AR52 K066 K066 C052 K066 BA57B K066 K066
605
99.
101. 98.9 92.9 97.0 86.8 87.5 81.7 92.0 77.7 76.6 73.6 70.1 61.3 68.0 66.9 63.6 65.5 60.5 57.5 54.8 54.6 52.3 60.0 50.0 47.8 50.5 53.0 45.8 48.6 44.0 42.4 43,2 40,9 47,0 39,6 46,0 38,4 37,3 36,0 35.1 34.8 41.0 34.2 33.3 38.0 32.4 30.6 31.7 30.9 27.8 29.5 34.0 28.5 27.9
Nucleor Data Tables, Vol. 1 1 , No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(d,n)*He.
a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values
EXPERIMENTAL 0 DEGREE C M . CROSS SECTION FOR THE REACTION T(D»N)HEA (CONTINUED)
ED(MEV)
SIGMA-0
0.7336 0.7500 0.7600 0.7740 0.7867 0.8000 0.8000 0.8267 0.8400 0.8640 0.8667 0.9000 0.9000 0.9333 0.9570 0.9667 1.0000 1.0000 1.0000 1.0000 1.0300 1.0333 1.0550 1.0667 1.100 1.150 1.156 1.200 1.250 1.263 1.267 1.300 1,300 1.300 1.330 1.374 1.400 1.400 1.489 1.500 1.500 1.600 1 .608 1.700 1.732 1.750 1.750 1.820 1.930 2.000 2.050 2.160 2.170 2.210 2.250 2.250 2.310 2.420 2.500 2.560 2.690 2.750 2.800
29.0 29.8 26.9 23.0 25.9 25.5 24.4 24.6 24.0 20.3 23.1 23.1 22.1 21.1 18.7 20.2 19.5 19.8 20.3 24.4 20.1 18.7 17.3 18.3 17.7 17.4 15.1 17.9 16.8 13.6 15.9 17.8 14.9 15.9 16.8 13.0 15.4 15.0 12.8 14.4 14.4 14.2 11.8 13.7 11.3 13.1 12.6 13.0 13.2 12.1 12.9 12.0 11.1 13.1 11.9 11.8 12.3 11.5 12,2 11.5 11.6 12.6 12.3
Nuclear Data Tables, Vol. 1 1 , No. 7, 1 973
RFF.
ED(MEV)
BA57B BA57C Kn66 C052 K066 K066 AR52 K066 K066 C052 Kn66 BA.57C Kn66 K066 Cn52 K066 Kn66 AL58 BA57C HE55 GA56 K066 Cn52 Kn66 Kn66 BA57C Cn52 GA56 BA57C C052 AL5R GA56 BA57C BA57C GA56 C052 GA56 BA57C CG52 GA56 BA57C GA5A C052 GA56 Cn52 BA57C BA57C GA56 GA56 BA57C GA56 GA56 GA56 ST52 BA57C BA57C GA56 GA56 BA57C GA56 GA56 BA57C GA56
2.950 3.000 3.060 3.130 3.230 3.250 3.250 3.320 3.400 3.500 3.500 3.600 3.700 3,750 3,800 3.900 3.980 4.000 4.000 4.090 4.170 4.250 4.250 4.250 4.320 4.380 4.480 4.500 4.570 4.670 4.750 4,800 4,890 5.000 5.000 5.250 5.250 5.500 5.600 5.750 6.000 6.000 6.100 6.250 6.250 6.400 6.500 6.750 6.800 7.000 7.000 7.000 7.250 7.900 8.000 8.400 8,500 9.000 9.100 9.500 9.900 0.000
606
SIGMA-0 11.7 13.1 13.1 12.3 12.8 13.3 13.5 12.7 12.5 12.6 14.3 13.7 14.5 15.1 14.0 14.2 15.0 14.5 15.7 15.2 16.0 16.4 16.8 16.6 18.2 16.7 16.3 17.3 17.6 17.5 17.5 16.4 17.8 17.5 18.5 18.5 18.1 19.0 17.0 18.8 19.1 18.6 17.8 19,0 18,7 18,8 18,7 18,2 16,9 18,2 18,6 17,9 18,2 17,2 16,5 16,4 15,0 16,5 18,0 16,8 15,0 15,9
RFF, GA56 BA57C GA56 GA56 GA56 BA57C BA57C GA56 GA5A GA56 BA57C GA56 GA56 PA57C GA56 GA56 GA56 BR64 BA57C GA56 GA56 GA56 BA57C BA57C GA56 GA56 GA56 BA57C GA56 GA56 BA57C GA56 GA56 GA56 BA57C BA57C BA57C BA57C BR64 BA57C BA57C BA57C ST60 BA57C BA57C Gn61A BA57C BA57C BR64 BA57C BA57C SI68 BA57C BR64 SI68 ST60 Gn61A SI68 BR64 BR64 ST60 SI68
NEUTRON PRODUCTION CROSS SECTIONS
T(4n)*He. a(0° cm.), Legendre Coefficients, a(total) Recommended and Experimental Values NORMALIZED EXPERIMENTAL LEGENDRE COEFFICIENTS FOR THE REACTION TID.NJHE'i
ED(MEV) 0.023 0.050 0.083 0.117 0.133 0.253 0.380 0.500 0.653 0.750 0.800 1.000 1.000 1.000 1.250 1.500 1.530 1.750 2.210 2.500 3.000 3.000 3.050 3.500 3.970 4.000 4.500 5.000 6.000 6.200 7.000 7.900 9.100
AO 1.000 1.000 1.000 1.000 1.000 1.000 1.000 0.983 1.007 0.988 0.885 0.946 0.959 0.921 0.922 0.B85 0.916 0.833 0.714 0.662 0.578 0.568 0.554 0.492 0.412 0.427 0.390 0.360 0.326 0.319 0.301 0.289 0.261
Al
0.034 0.033 0.055 0.108 0.090 0.073 0.125 0.105 0.113 0.070 0.123 0.130
o.iie
0.129 0.148 0.128 0.111 0.121 0.119 0.112 0.117 0.121 0.115 0.102 0.065 0.062
A2
-0.017 -0.040 -0.043 0.007 -0.036 -0.032 -0.046 -0.027 0.002 0.014 0.044 0.132 0.113 0.165 0.159 0.200 0.220 0.276 0.252 0.274 0,264 0.222 0.225 0.182 0.201 0.173
REF.
0.005 0.038 0.040 0.068 0.024 0.052 0.067 0.053 0.060 0.067 0.059 0.049 0.041 0.013 0.017
0.019 0.028 0.028 -0.019 0.041 0.034 0.026 0.046 0.042 0.046 0.072 0.069 0.110 0.124 0.139
0.032 0.043 0.063 0.029 0.062 0.055 0.071 0.087 0.103 0.135 0.149 0.180 0.178 0.196
0.009 0.017 0.013 0.024 0.029 0.043 0.032 0.035 0.043 0.065 0.065 0.084 0.094 0.127
0.005
0 004
0.019 0.034
0, 017 0 025
BR49 BR49 ALSO AL50 AL50 AR52 AR52 BA57C AR52 BA57C AR52 BA57C PA64 HE55 BA57C BA57C GA56 BA57C GA56 BA57C BA57C PA64 GA56 BA57C GA56 BA57C BA57C BA57C BA57C G061A BA57C G061A G061A
T(d,n)'He EXPERIMENTAL TOTAL CROSS SECTION FOR THE REACTION T(0,N>HE4 (ABOVE 300 KEV OEUTERON ENERGvT ED(MEV)
SIGMA-T
REF.
0.3098 0.3348 0.3800 0.3854 0.4602 0.4822 0.5000 0.5350 0.5570 0.6108 0.6300 0.6530 0.7045 0.7336 0.750 0.800 1.000 1.000 1.250 1.500 1.530 1.750 2.210 2.500 3.000 3.050 3.500 3.970 4.000 4.500 4. 980 5.000 5.790 6.000 6.200 7.000 7.900 9.100
1220. 1160. 770. 850. 750. 670. 644. 590. 570. 510. 470. 380. 420. 360. 369. 300. 245. 280. 191. 159. 165. 135. 108. 99,9 93.6 85,0 88.4 84.0 85,0 85 " 88 82 90 76 73 69 63 53
BA57B BA57B AR52 BA57B BA57B BA57B BA57C BA57B BA57B BA57B BA57B AR52 BA57B BA57B BA57C AR52 BA57C HE55 BA57C BA57C GA56 BA57C GA56 BA57C BA57C GA56 BA57C GA56 BA57C BA57C GA56 BA57C GA56 BA57C G061A BA57C G061A Gn61A
a(6, Ep). Recommended Values
607
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
H. USKIEN AND A. PAULSEN
0(6 lab), £^{6 lab): Recommended Values
T(d,nYHe. ENERGYIMEV)
0.020
0.030
0.040
0.050
0.060
0.070
0.080
0.090
CENTER-OF-MASS INPUT VALUES FUR THE REACTION T ( U , N ) H E 4 t)-SIGMA-0(MB/SR) A 0
4.300 1.000
ANGLE(UEGREE)
19.600 1.000
52.900 1.000
106.000 1.000
175.000 1.000
DIFFERENTIAL CROSS-SECTIONS (MB/SR)
250.000 1.000
315.000 1.000
367.000 1.000
IN THE LARORATURV SYSTEM
2'° 5.0 10.0 15.0 20-0 25.0 30.0
5'tl?i O'M'i 0.439| 9,'?|2i O'^lll 0'?38| 0.438E
2i 0} 01 0} 01 01 01
0'201f 9-201E 0.201E O'^Olf 0.200E 0.200E 0.200b
02 02 02 0? 02 02 02
0.545E 0.545E 0.545E 0.544E 0.544E 0.543E 0.543E
02 02 02 02 02 02 02
0.109E 0.109E 0.109E 0.109E 0.109E 0.109E 0.109E
03 03 03 03 03 03 03
0.181E 0.181E 0.181E 0.181E 0.181E O.iaOE 0.180E
03 03 03 03 03 03 03
0.260E 0.260E 0.260E 0.269E 0.259E 0.259E 0.258E
03 03 03 03 03 03 03
0.328E 0.328E 0.328E 0.328E 0.327E 0.327r 0.326E
03 03 03 03 03 03 03
0.3R4E 0.3R3E 0.383F 0.383E 0.3H2E 0.392E 0.381E
03 03 03 03 03 03 03
35.0 ?P'0 *5.0 ^§•0 55.0 60.0
0.437| 0«?37| 0.436E 2'?lll 0.435E 0.434E
01 01 01 2J 01 01
0.200E 0.199E 0.199E 0'}99e 0.19eE 0.198E
02 02 02 02 02 02
0.542E 0.541E 0.540E 0.539E 0.538E 0.537E
02 02 02 OZ 02 02
0.108E 0.108E 0.108E 0.108E 0.108E 0.107E
03 03 03 03 03 03
0.180E 0.180E 0.179E 0.179E 0.178E 0.178E
03 03 03 03 03 03
0.25eE 0.257E 0.257E 0.256E 0.255E 0.255E
03 03 03 03 03 03
0.326E 0.325E 0.324E 0.323E 0.322E 0.321E
03 03 03 03 03 03
0.380E 0.379E 0.378E 0.377E 0.376E 0.375E
03 03 03 03 03 03
65.0 19'0 J5.0 |0.0 85.0 90.0
0.433E 0.433| 0'*l?i 0.431E 0'*30E 0.429E
01 01 01 01 01 01
0.198E 0.197E 0.197E 0.196E 0.196E 0.195E
02 02 02 02 02 02
0.535E 0,534E 0.533E 0.531E 0.530| 0.528E
02 02 02 02 02 02
0.107E 0.107E 0.106E 0.106E 0.106E 0.105E
03 03 03 03 03 03
0.177E 0.177E 0.176E 0.176E 0.175E 0.174E
03 03 03 03 03 03
0.254E 0.253E 0.252E 0.251E 0.25OE 0.249E
03 03 03 03 03 03
0.320E 0.319E 0.318E 0.317E 0.316F 0.314E
03 03 03 03 03 03
0.374E 0.372E 0.371E 0.369E 0.36eE 0.366E
03 03 03 03 03 03
95.0 100.0 105.0 110.0 115.0 120.0
0'*??i 0.428| 0.427| S'S??i 0.426| 0.425E
01 01 01 8,1 01 01
0.195E 0.195E 0.194E 0.194E 0.193E 0.193E
OZ 02 02 02 02 02
0.527E 0.526E 0.524E 0.523E 0.b22E 0.520E
02 02 02 02 02 02
0.105E 0.105E 0.105E 0.104E 0.104E 0.104E
03 03 03 03 03 03
0.174E 0.173E 0.173E 0.172E 0.172E U.171E
03 03 03 03 03 03
0.249E 0.248E 0.247E 0.246E 0.245E 0.244E
03 03 03 03 03 03
0.313E 0.312E 0.311E 0.31QE 0.309E 0.3086
03 03 03 03 03 03
0.365E 0.363E 0.362E 0.361E 0.3591 0.358E
03 03 03 03 03 03
125.0 130.0 135.0 IJO.O 1*5.0 150.0
0.424E 0.424E 0.423E 0.422E 0.422| 0.421E
01 01 01 01 01 01
0.193E 0.192E 0.192E 0.192E 0.191E 0.191E
02 02 02 02 OZ 02
0.519E 0.518E 0.517E 0.516E 0.515E 0.515E
02 02 02 02 02 02
0.103E 0.103E 0.103E 0.103E 0.103E 0.102E
03 03 03 03 03 03
0.171E 0.170E 0.170E 0.170E 0.169E 0.169E
03 03 03 03 03 03
0.244E 0.243E 0.242E 0.242E 0.241F 0.241E
03 03 03 03 03 03
0.307E 0.306E 0.305E 0.304E 0.303E 0.303E
03 03 03 03 03 03
0.357E 0.356E 0.355E 0.354E 0.353E 0.352E
03 03 03 03 03 03
155.0 1*0.0 1^5.0 170.0 \l%'° 180.0
0.421E 0.421E 0'?21| 0'?|0e 5'??9i 0.420E
01 01 01 01 21 01
0.191E 0.191E 0.191E 0.190E 0.190E 0.190E
02 02 02 02 02 02
0.514E 0.513E 0.513E 0.513E 0.513E 0.512E
02 02 02 02 02 02
0.102E 0.102E 0.102E 0.102E 0.102E 0.102E
03 03 03 03 03 03
0.169E 0.168E 0.16e£ 0.168E 0.168E 0.1686
03 03 03 03 03 03
0.240E 0.240E 0.240E 0.240E 0.240E 0.239E
03 03 03 03 03 03
0.302E 0.302E O.loil 0.301E 0.301E 0.3016
03 03 03 03 03 03
0.351E 0.3516 0 350E 0.350E 0.350E 013501
03 03 03 03 03 03
6N6RGY(MEV)
0.100
0.150
0.200
0.250
0.300
0.350
0.400
0.450
CENTER-OF-MASS INPUT VALUES FOR THE REACTION TID,N1HE4 D-SIGMA-0(MB/SR) A 0 A 1 A 2
394,000 1.000 0.000 0.000
317.000 1.000 0.000 0.000
ANGLE(OEGREE)
199.000 1.000 0.000 0.000
133.000 1.000 0.000 0.000
95.200 1.000 0.000 0.000
DIFFERENTIAL CRUSS-SECTIUNS (MB/SRl
77.500 1.000 0.000 0.000
63.600 0.999 0.004 -0.003
53.000 0.9S8 0.013 -O.Oll
IN THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.413E 0.413E 0.412E 0.412E 0.412E 0.411E 0.410E
03 03 03 03 03 03 03
0.336E 0.335E 0.335E 0.335E 0.334E 0.334E 0.333E
03 03 03 03 03 03 03
0.212E 0.212E 0.212E 0.212E 0.211E 0.211E 0.210E
03 03 03 03 03 03 03
0.143E 0.143E 0.143E 0.142E 0.142E 0.142E 0.141E
03 03 03 03 03 03 03
0.103E 0.103E Q.103E 0.103E 0.102E 0.102E Q.102E
03 03 03 03 03 03 03
0.846E 0.846E 0.B45E 0.843E 0.841E 0.839E 0.836E
02 02 02 02 02 02 02
0.697E 0.697E 0.696E 0.695E 0.693E 0.691E 0.689E
02 02 02 02 02 02 02
0.585E 0.5S5E 0.584E 0.b83E 0.582E O.SBIE 0.579E
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0.409E 0.408E 0.407E 0.406E 0.404E 0.403E
03 03 03 03 03 03
0.332E 0.331E 0.330E 0.329E 0.327E 0.326E
03 03 03 03 03 03
0.210E 0.209E 0.208E 0.207E 0.206E 0.205E
03 03 03 03 03 03
0.141E 0.140E 0.1406 0.139E 0.138E 0.138E
03 03 03 03 03 03
O.IOIE O.lOlE O.IOOE O.IOOE 0.997E 0.991E
03 03 03 03 02 02
0.e32E 0.829E 0.824E 0.820E 0.814E 0.809E
02 02 02 02 02 02
0.686E 0.683E 0.579E 0.675E 0.670E 0.666E
02 02 02 02 02 02
0.676F 0.574E 0.571E 0.567E 0.664E 0.5606
02 02 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.401E 0.400E 0.398E 0.397E 0.395E 0.393E
03 03 03 03 03 03
0.324E 0.323E 0.321E 0.320E 0.318E 0.3166
03 03 03 03 03 03
0.204E 0.203E Q.202E 0.201E 0.200E 0.198E
03 03 03 03 03 03
0.137E 0.136E 0.135E 0.134E 0.133E 0.132E
03 03 03 03 03 03
0.985E 0.978E 0.971E 0.965E 0.958E 0.951E
02 02 02 02 02 02
0.B04E 0.798E 0.792E 0.7b6E 0.780E 0.774E
02 02 02 02 02 02
0.661E 0.656E 0.650E 0.645E 0.639E 0.634E
02 02 02 02 02 02
0.555E 0.551E 0.5466 0.541E 0.5366 0.530E
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0.392E 0.390E 0.388E 0.387E 0.385E 0.384E
03 03 03 03 03 03
0.315E 0.313E 0.312E 0.310E 0.309E 0.307E
03 03 03 03 03 03
0.197E 0.196E 0.195E 0.194E 0.193E 0.192E
03 03 03 03 03 03
0.132E 0.131E 0.130E 0.129E 0.1286 0.127E
03 03 03 03 03 03
0.944E 0.937E 0.930E 0.924E 0.9186 0.912E
02 02 02 02 02 02
0.768E 0,762E 0.7566 0.750E 0.745E 0.739E
02 02 02 02 02 02
0.628E 0.623E 0.617E 0.612E D.607E 0.602E
02 02 02 02 02 02
0.525E 0.5196 0.514E 0.5096 0.5036 0.4986
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.383E 0.381E 0.380E 0.379E 0.378E 0.377E
03 03 03 03 03 03
0.306E 0.304E 0.303E 0.302E 0.301E 0.300E
03 03 03 03 03 03
0.191E 0.190E 0.189E 0.188E 0.188E 0.187E
03 03 03 03 03 03
0.127E 0.126E 0.125E 0.125E 0.124E 0.124E
03 03 03 03 03 03
0.906E 0.901E 0.896E 0.891E 0.887E 0.884E
02 02 02 02 02 02
0.734E 0.730E 0.726E 0.7226 0.718E 0.715E
02 02 02 02 02 02
0.597E 0.593E 0.589E 0.5856 0.5&2E 0.579E
02 02 02 02 02 02
0.493E 0.489F 0.4B4E 0.4806 0.4776 0.4746
02 02 02 02 02 02
155.0 160.0 165.0 170.0 175.0 160.0
0.376E 0.376E 0.375E 0.375E 0.375E 0.375E
03 03 03 03 03 03
0.300E 0.2996 0.299E 0.298E 0.298E 0.298E
03 03 03 03 03 03
0.186E 0.186E 0.186E 0.1856 0.185E 0.185E
03 03 03 03 03 03
0.123E 0.123E 0.123E 0.123E 0.1236 0.123E
03 03 03 03 03 03
0.881E 0.878E 0.8766 0.875E 0.874E 0.874E
02 02 02 02 02 02
0.712E 0.710E 0.709E 0.707E 0.707E 0.7066
02 02 02 02 02 02
0.576E 0.574E 0.573E 0.571E 0.671E 0.5706
02 02 02 02 02 02
0.4716 0.469E 0.467E 0.466E 0.4656 0.465E
02 02 02 02 02 02
Nuclear Data Tables, Vol. 11, No. 7, 1973
608
NEUTRON PRODUCTION CROSS SECTIONS
0(6 lab), E„(e lab): Recommended Values
T(d,n)*He. ENERGY(MEV)
0.020
0.030
0.040
0.050
0.050
0.070
0.080
INPUT VALUES FOR THE REACTION T { 0 , N ) H E 4 REST ENERGY IN MEV FUR PRUJECTILE
Tl=1875.633
TARGET T2=2808.951
0-VALUE IN HEV «=
17.590
PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEUS 7 4 = 3 7 2 7 . 4 1 8 ENERGY nF PARTICLE-3
ANGLE(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 IIO.O 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
14.341 14.340 14.336 14.331 14.322 14.312 14.300 14.285 14.269 14.251 14.231 14.210 14.188 14.164 14.140 14.114 14.089 14.063 14.036 14.010 13.984 13.958 13.934 13.910 13.886 13.865 13.844 13.825 13.807 13.792 13.778 13.766 13.756 13.748 13.743 13.739 13.738
14.414 14.413 14.409 14.402 14.392 14.379 14.364 14.346 14.326 14.304 14.280 14.254 14.226 14.197 14.167 14.136 14.104 14.072 14.040 14.008 13.976 13.945 13.915 13.885 13.857 13.830 13.805 13.782 13.760 13.741 13.724 13.710 13.698 13.688 13.682 13.677 13.676
ENERGY (MEV)
0.100
0.150
(MEV)
IN THE LABORATORY SYSTEM
14.477 14.476 14.471 14.462 14.451 14.436 14.418 14.398 14.375 14.349 14.321 14.291 14.259 14.226 14.191 14.155 14.118 14.081 14.044 14.007 13.970 13.934 13.899 13.865 13.833 13.802 13.773 13.745 13.721 13.699 13.680 13.663 13.649 13.639 13.631 13.625 13.624
14.533 14.531 14.52 6 14.516 14.504 14.487 14.467 14.444 14.418 14.389 14.358 14.324 14.289 14.251 14.212 14.172 14.131 14.090 14.048 14.007 13.966 13.925 13.886 13.848 13.812 13.777 13.745 13.715 13.688 13.563 13.541 13.623 13.607 13.595 13.587 13.581 13.580
14.584 14.582 14.576 14.566 14.552 14.534 14.512 14.487 14.458 14.425 14.392 14.355 14.316 14.275 14.232 14.188 14.143 14.098 14.052 14.007 13.962 13.918 13.875 13.833 13.793 13.756 13.720 13.688 13.658 13.631 13.607 13.587 13.570 13.557 13.547 13.542 13.540
14.532 14.630 14.623 14.612 14.597 14.577 14.554 14.525 14.495 14.461 14.424 14.384 14.341 14.297 14.251 14.203 14.155 14.105 14.056 14.007 13.959 13.911 1 3 . 86 5 13.820 13.777 13.736 13.698 13.653 13.631 13.60 2 13.576 13.554 13.536 13.522 13.511 13.505 13.503
14.677 14.674 14.667 14.655 14.639 14.616 14.593 14.563 14.530 14.493 14.453 14,411 14,365 14.317 14.268 14.217 14.155 14.113 14.050 14.008 13.956 13.905 13.856 13.808 13.762 13.718 13.678 13.640 13.506 13.575 13.547 13.524 13.505 13.489 13.479 13.472 13.470
14.719 14.716 14.709 14.596 14.679 14.656 14.630 14.598 14.563 14.524 14.482 14.436 14.388 14.337 14.285 14.231 14.176 14.120 14.054 14.008 13.953 13.899 13.847 13.796 13.748 13.702 13.559 13.619 13.582 13.550 13.521 13.496 13.476 13.459 13.448 13.441 13.439
0.200
0.250
0.300
0.350
0.400
0.450
INPUT VALUES FOR THE REACTION T ( D , N ) H E 4
ANGLE(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 IIO.O 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
REST ENERGY IN MEV FOR PROJECTILE T l = 1 8 7 5 . 6 3 3 0-VALUE I d MEV 0= TARGET T 2 - 2 8 0 8 . 9 5 1 PRODUCT T3= 9 3 9 . 5 7 5 RESIDUAL NUCLEUS 7 4 = 3 7 2 7 . 4 1 8 ENERGY OF PARTICLE-3 (MEV) IN THE LARORATORY SYSTEM
14.759 14.757 14.749 14.735 14.717 14.693 14.665 14.632 14.594 14.553 14.508 14.460 14.409 14.355 14.300 14.243 14.185 14.126 14.067 14.009 13.951 13.894 13.839 13.785 13.734 13.686 13.641 13.599 13.560 13.526 13.496 13.470 13.448 13.431 13.419 13.412 13.410
14.940 14.936 14.926 14.910 14.887 14.858 14.823 14.782 14.736 14.585 14.629 14.570 14.507 14.441 14.373 14.303 14.232 14.160 14.067 14.015 13.944 13.875 13.807 13.742 13.680 13.521 13.566 13.515 13.458 13.427 13.390 13.358 13.332 13.312 13.297 13.288 13.285
15.096 15 . 09 3 15.081 15.062 15.035 15.001 14.960 14.912 14.859 14.800 14.735 14.655 14.593 14.517 14.436 14.357 14.274 14.191 14.107 14.024 13.942 13.862 13.784 13.709 13.538 13.570 13.507 13.448 13.394 13.345 13.304 13.258 13.238 13.215 13.198 13.188 13.184
15.238 15.234 15.221 15.199 15.169 15.130 15.084 15.031 14.971 14.904 14.832 14.754 14.672 14.586 14.498 14.407 14.314 14.221 14.127 14.034 13.943 13.853 13.765 13.683 13.603 13.527 13.457 13.391 13.332 13.279 13.232 13.191 13.158 13.132 13.113 13.102 13.098
609
17.590
15.369 16.364 15.350 16.325 15.293 15.250 15.200 15.141 16.074 15.001 14.921 14.83 6 14.745 14.651 14.554 14.454 14.352 14.250 14.147
15.492 15.487 16.471 16.445 15.409 16.353 16.308 15.244 16.171 16.092 16.00 5 14.913 14.815 14.713 14.507 14.499 14.389 14.278 14.167
15.609 15.503 16.586 15.558 16.519 15.470 16.410 16.342 16.254 16.178 16.085 14.986 14.881 14.771 14.658 14.542 14.424 14.305 14.187
15.720 15.714 15.696 15.666 16.625 15.572 15.509 16.435 15.352 16.261 15.152 15.056 14.944 14.828 14.707 14.584 14.459 14.333 14.207
14.045 13.945 13.847 13.752 13.560 13.573
14.057 13.949 13.843 13.740 13.542 13.548
14.059 13.953 13.840 13.731 13.525 13.525
14.082 13.959 13.839 13.723 13.612 13.505
13.491 13.414 13.343 13.278 13.219 13.158 13.124 13.088 13.060 13.040 13.027 13.023
13.459 13.376 13.299 13.2 30 13.157 13.112 13.065 13.026 12.996 12.974 12.950 12.956
13.431 13.342 13.261 13.186 13.120 13.061 13.011 12.970 12.937 12.914 12.900 12.895
13.405 13.312 13.226 13.147 13.077 13.015 12.952 12.918 12.884 12.859 12.845 12.840
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
a(d lab), £^(6 lab): Recommended Values
Tid,n)*He. ENERGY(MEV1
0.50C1
0.55C
)
0.60C
C E N T E R - • U F - •MASS U-SIGMA-0(Me/SR) A 0 A 1 A 2
3 9.400 0.99; 0.030
45.500 0.997 0.021 -O.Olfi
0.6bC
-o.oae
)
V A L U E ;; 31.900 0.989 0.046 -0.035
35.500 0.993 0.038 - 0 . 0 3 !L
DIFFERENTIAL
ANGLe(DEGR£e]
)
INPUT
C R O S S - S E C T I O N S;
0.75C
0.700 FUR
THE R E A C T I U l M
1IN T H E
0.80C
)
0.850
23.400 0.973 0.072 -0.045
25.000 0.978 0.067 -0.045
27.000 0 . 9 8 ;i 0.06 0 -0.043
29.400 0.986 0.053 -0.039 (MB/SRI
)
T(U,NlHe4
LABORATURY
SYSTeM
0.0 5.0 10.0 15.0 20.0 2i>.0 30.0
0.505E 0.505E 0.504E 0.503E 0.503E 0.501E 0.300t
02 02 02 02 02 02 02
0.439E 0.4396 0.4396 0.438E 0.4376 0.4366 0.435E
02 02 02 02 02 02 U2
0.397E 0.397E 0.397E 0.397E 0.396E 0.395E 0.394E
02 02 02 02 02 02 02
0.3596 0.359E 0.358E 0.358E 0.3576 0.357E 0.366E
02 0 . 3 3 2 E 02 0 . 3 3 2 6 02 0 . 3 3 2 E 02 0 . 3 3 1 E 02 0 . 3 3 1 E 02 0 . 3 3 0 E 02 0 . 3 2 9 E
02 02 02 02 02 02 02
0.306E 0.3066 0.3066 0.3056 0.3056 0.304E 0.304E
02 02 02 02 02 02 02
0.2S4E 0.2846 0.2846 0.2846 0.2836 0.2836 0.2826
02 02 02 02 02 02 02
0.267E 0.267E 0.267E 0.2676 0.266E 0.2656 0.2656
02 02 02 02 02 02 02
35.0 40.0 'tS.O 50.0 55.0 60.0
0.498E 0.496E 0.493E 0.490E 0.487E 0.484E
02 02 02 02 02 02
0.434E 0.4326 0.430E 0.427E 0.424E 0.421E
02 02 02 02 02 02
0.393E 0.391E 0.389E 0.387E 0.384E 0.381E
02 02 02 02 02 02
0.354E 0.3536 0.3516 0.3496 0.3466 0.3436
02 0 . 3 2 8 6 02 0 . 3 2 7 E 02 0 . 3 2 5 E 02 0 . 3 2 3 6 02 0 . 3 2 0 6 02 0 . 3 1 7 E
02 02 02 02 02 02
U.3U2E 0.301E 0.299E 0.297E 0.2956 0.292E
U2 02 02 02 02 02
0.2bl6 0.27v6 0.278E 0.276E 0.2736 0.2716
02 0 . 2 6 3 6 1)2 0 . 2 6 2 t 02 0 . 2 6 0 6 02 0 . 2 5 8 E 02 0 . 2 5 6 E 02 0 . 2 5 3 6
02 o2 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.480E 0.475E 0.471E 0.466E 0.461E 0.456E
02 0 . 4 1 7 E 02 0 . 4 1 4 E 02 0 . 4 0 9 E 02 0.405E 02 0.400E 02 0 . 3 9 5 E
02 0 . 3 7 8 E 02 0.374E 02 0 . 3 7 0 E 02 0.366E 02 0 . 3 6 1 E 02 0 . 3 5 6 6
02 0 . 3 4 0 6 02 0 . 3 3 7 6 02 0 . 3 3 3 6 02 0.328E 02 0 . 3 2 4 6 02 0 . 3 1 9 6
02 0 . 3 1 4 E 02 0 . 3 1 1 E 02 0 . 3 0 7 E 02 0.303E 02 0 . 2 9 8 E 02 0 . 2 9 3 E
02 0 . 2 8 9 6 02 0 . 2 8 6 6 02 0 . 2 8 2 6 02 0 . 2 7 8 6 02 0 . 2 7 4 E 02 0 . 2 6 9 E
02 02 02 02 02 02
0.2686 0.2646 0.261E 0.2576 0.2526 0.2486
02 02 02 02 02 02
0.2506 0.247E 0.2436 0.239E 0.235E 0.231E
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0.45 IE 0.445E 0.440E 0.435E 0.429E 0.424E
02 02 02 02 02 02
0.390E 0.385E 0.379E 0.374E 0.369E 0.364E
02 02 02 02 02 02
0.351E 0.3466 0.340E 0.335E O.330e 0.325E
02 02 02 02 02 02
0.314E 0.3096 0.304E 0.2996 0.2946 0.289E
02 0 . 2 e 9 E 02 0 . 2 8 4 E 02 0 . 2 7 9 E 02 0 . 2 7 3 E 02 0.268E 02 0 . 2 6 3 E
02 02 02 02 02 02
0.264E 0.259E 0.254E 0.249E 0.2446 0.240E
02 02 02 02 02 02
0.2436 0.238E 0.234E 0.229E 0.224E 0.219E
02 02 02 02 02 02
0.226E 0.221E 0.217E 0.212E 0.207E 0.203E
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.419E 0.415E 0.410E 0.406E 0.403E 0.39qE
02 02 02 02 02 02
0.3596 0.354E 0.350E 0.346E 0.342E 0.339E
02 02 02 02 02 02
0.320E 0.315E 0.311E 0.307E 0.303E 0.300E
02 02 02 02 02 02
0.284E 0.279E 0.275E 0.271E 0.267E 0.2646
02 0 . 2 5 9 6 02 0 . 2 5 4 6 02 0 . 2 5 0 E 02 0 . 2 4 6 E 02 0 . 2 4 2 E 02 0 . 2 3 9 E
02 02 02 02 02 02
0.235E 0.231E 0.226E 0.223E 0.219E 0.2166
02 02 02 02 02 02
0.215E 0.210E 0.206E 0.203E 0.199E 0.196E
02 02 02 02 02 02
0.199E 0.195E 0.191E 0.187E 0.184E 0.181E
02 02 02 02 02 02
155.0 160,0 165.0 170.0 175.0 180.0
0.396E 0.394E 0.392E 0.391E 0.390E 0.390E
02 02 02 02 02 02
0.336E 0.334E 0.332E 0.330E 0.330E 0.329E
02 02 02 02 02 02
0.297E 0.294E 0.293E 0.291E 0.290E 0.2906
02 02 02 02 02 02
0.2616 0.2596 0.257E 0.256E 0.2556 0.255E
02 0 . 2 3 7 6 02 0 . 2 3 4 E 02 0 . 2 3 2 E 02 0 . 2 3 1 E 02 0.230e 02 0 . 2 3 0 E
02 02 02 02 02 02
0.213E 0.2116 0.2096 0.208E 0.2076 0.2076
02 02 02 02 02 02
0.194E 0.1926 0.1906 0.1896 0.188E 0.188E
02 02 02 02 02 02
0.179E 0.1776 0.1756 0.1746 0.173E 0.173E
02 02 02 02 02 02
ENERGY ( M E V ) CENTER-- U F - -MASS 0-SIGMA-OIMB/SR) a 0
^AA 3\2
A 4 A 5 A 6
22.000 0.968 0.077 -0.045 0.000 0.000 0,000 0,000
20.800 0.963 0.082 -0.045 0.000 0.000 0.000 0.000
ANGLE(D6GR6E)
INPUT
19,800 0,957 0,087 -0,044 0,000 0,000 0,000 0,000
DIFFERENTIAL
VALUES 17.900 0.946 0.094 -0.040 0.000 0.000 0.000 0.000
C R U S S - :5 6 C T i n N S
FUR
THE R E A C T I O N
(MB/SRI
T(U,N)He4
15.800 0.9i; 0.105 -0.023 0.000 0.003 0.000 0.000
16.700 0.93 1 0.100 -0.032 0.000 0.001 0.000 0.000 :I N
TH6
11 4 . 3 0 0 0.878 0.113 0.002 0.000 0.005 0.000 0.002
15.000 0.898 0.110 -0.013 0.000 0.004 0.000 0.001
LABORATURY
SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0,2526 0,2526 0,2626 0.251E 0,251E 0,250E 0,249E
02 02 02 02 02 02 02
0.239E 0.2396 0.2396 0.2396 0.238E 0.237E 0.236E
02 0 . 2 2 8 6 02 0 . 2 2 8 6 02 0 . 2 2 8 6 02 0 . 2 2 8 6 02 0 . 2 2 7 6 02 0 . 2 2 6 E 02 0 . 2 2 5 6
02 02 02 02 02 02 02
0.208E 0.208E 0.207E 0.2076 0.2066 0.205E 0.204E
02 0 . 1 9 5 E 02 0 . 1 9 5 E 02 0 . 1 9 5 6 02 0 . 1 9 4 6 02 0 . 1 9 3 6 02 0 . 1 9 2 6 02 0 . 1 9 0 E
02 02 02 02 02 02 02
0.1866 0.1866 0.1856 0.1846 0.1836 0.1826 0.1806
02 02 02 02 02 02 02
0.177E 0.177E 0.176E 0.175E 0.174E 0.172E 0.170E
02 02 02 02 02 02 02
0 .. 1 7 0 E 0 ,. 1 7 0 6 0 ,. 1 6 9 6 0 ,. 1 6 8 6 0 ,, 1 6 6 6 0 .. 1 6 4 6 0 .. 1 6 1 6
02 02 02 02 02 02 02
35.0 40.0 45.0 50.0 55.0 60.0
0,248E 0,247E 0,245E 0.243E 0.240E 0,238E
02 02 02 02 02 02
0.235E 0.2336 0.2326 0.2306 0.227E 0.225E
02 02 02 02 02 02
0.224E 0.222E 0.221E 0.218E 0.216E 0.213E
02 02 02 02 02 02
0.2036 0.201E 0.1996 0.1976 0.1946 0.1926
02 0 . l e 9 E 02 0 . 1 8 7 E 02 0 . 1 8 5 6 02 0 . 1 8 2 E 02 0 . 1 8 0 E 02 0 . 1 7 7 E
02 02 02 02 02 02
0.1786 0.176E 0.173E 0.171E 0.168E 0.165E
02 02 02 02 02 02
0.1686 0.1666 0.1636 0.160E 0.1576 0.164E
02 02 02 02 02 02
0 .. 1 5 9 E 0 ., 1 5 6 6 0 ,. 1 5 3 E 0 ,. 1 5 0 6 0 ,. 1 4 7 6 0 ,, 1 4 4 6
02 02 02 02 02 02
65.0 70.0 75.0 80.0 85.0 90.0
0.235E 0.231E 0.2286 0.224E 0.2206 0.2166
02 02 02 02 02 02
0.222E 0.218E 0.215E 0.2116 0.207E 0.203E
02 02 02 02 02 02
0.210E 0.207E 0.203E 0.200E 0.196E 0.191E
02 02 02 02 02 02
0.1896 0.185E 0.182E 0.1786 0.1746 0.1706
02 0 . 1 7 4 E 02 0 . 1 7 0 E 02 0 . 1 6 7 6 02 0 . 1 6 3 E 02 0 . 1 6 0 E 02 0 . 1 5 6 6
02 02 02 02 02 02
0.162E O.ISSE 0.1556 0.151E 0.1486 0.1446
02 02 02 02 02 02
0.1516 0.1476 0.1446 0.1406 0.1376 0.1336
02 02 02 02 02 02
0 ,. 1 4 0 6 0 ,. 1 3 7 6 0 ,. 1 3 3 6 0 ,, 1 3 0 E 0 ,, 1 2 6 6 0 ., 1 2 3 6
02 02 02 02 02 02
95.0 100.0 105.0 110.0 115.0 120.0
0.2116 0.2076 0.2026 0.1986 0.193E 0.189E
02 02 02 02 02 02
0.198E 0.1946 0.189E 0.185E 0.181E 0.177E
02 02 02 02 02 02
0.187E 0.1836 0.179E 0.174E 0.170E 0.1666
02 0 . 1 6 6 6 02 0.152E 02 0 . 1 6 2 6 02 0 . 1 4 8 6 02 0 . 1 5 8 E 02 0 . 1 4 4 6 02 0 . 1 5 5 6 02 0 . 1 4 1 6 02 0 . 1 5 1 6 02 0 . 1 3 7 5 02 0 . 1476 02 0 . 1 3 4 6
02 02 02 02 02 02
0 . 1 4 0 6 02 0 . 1 3 7 6 02 0 . 1 3 3 E 02 0 . 1 3 0 6 02 0 . 1 2 6 E 02 0 . 1236 02
0.1306 0.126E 0.123E 0.120E 0.1166 0.1146
02 02 02 02 02 02
0 ., 1 2 0 6 0 ,, 1 1 6 6 0 ., 1 1 3 6 0 ., 1 1 0 E 0 ,. 1 0 8 6 0 ,, 1 0 5 6
02 02 02 02 02 02
125.0 130.0 135.0 140.0 145.0 150.0
0.185E 0.181E 0.177E 0.174E 0.171E 0.1686
02 02 02 02 02 02
0.1736 0.1696 0.165E 0.1626 0.1596 0.1566
02 02 02 02 02 02
0.1626 0.1586 0.1556 0.1526 0.149E 0.147E
02 02 02 02 02 02
02 02 02 02 02 02
0.1206 0.117E 0.1156 0.112E O.UOE 0.109E
02 02 02 02 02 02
0. H I E 0.108E 0.106E 0.1046 0.1026 O.IOIE
02 02 02 02 02 02
0 ,, 1 0 2 6 0 ,, 1 0 0 6 0 .9876 0 ,, 9 7 0 6 0 ., 9 5 5 6 0 ,, 9 4 3 6
02 02 01 01 01 01
155.0 160.0 165.0 170.0 175.0 180,0
0.16S6 0.1636 0.162E 0.1616 0.1606 0,1606
02 02 02 02 02 02
0.1546 0,1526 0,1516 0,150E 0.149E 0,1496
02 0 . 1 4 4 6 02 0 . 1 4 3 6 02 0 . 1 4 1 E 02 0 . 1 4 0 6 02 0 . 1 4 0 6 02 0 . 1 3 9 6
02 0 . 1 0 7 6 02 0 . 1 0 6 6 02 0 . 1 0 5 E 02 0 . 1 0 4 E 02 0 . 1 0 4 E 02 0 . 1 0 4 6
02 02 02 02 02 02
0.9996 0.9896 0.981E 0.976E 0.9736 0.972E
01 01 01 01 01 01
0 ,. 9 3 3 6 0 .. 9 2 6 6 0 ,. 9 2 0 E 0 ,. 9 1 6 6 0 .. 9 1 4 6 0 .. 9 1 3 6
01 01 01 01 01 01
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
0.1436 0.1406 0.1376 0.1346 0.132E 0.1296
02 0 . 1 3 0 6 02 0 . 1 2 7 6 02 0 . 1 2 4 E 02 0 . 1 2 2 E 02 0 . 1 2 0 E 02 0 . 1 1 8 6
02 0 . 1 2 7 E 02 0 . 1 1 6 E 02 0 . 1 2 6 6 02 0 . 1 1 5 6 02 0 . 1 2 4 6 02 0 . 1 1 3 6 02 0 . 1 2 4 6 0 2 0 . 1 1 3 6 02 0 . 1 2 3 E 02 0 . 1 1 2 6 02 0 . 1 2 3 6 0 2 O . Z 1 2 6
610
NEUTRON PRODUCTION CROSS SECTIONS
T(4fi)4He. ENieRGYIMEV )
a{e lab), EJO lab): Recommended Values
0.500 INPUT VALUES FOR THE REACTION T(r),M)HE4 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ENERGY OF PARTICLE-3
ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 = 0.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
ENERGY(MEV)
17.590
IN THE LABHRATIIRY SYSTEM
15.779 15.577 15.555 15.445 15.315 15.179 15.037 14.891 14.741 14.590 14.437 14.285 14. 135 13.988 13.844 13.705 13.572 13.445
15.407 15.399 15.374 16.333 16.276 16.2 02 i o . 116 15.014 15.900 15.775 15.539 15.494 15.342
16.497 15.488 16.462 16.419 16.350 16.<;84 15.194 15.089 15.971 15.842 15.701 15.552 15.394
16.183 16.020 14.853 14.684 14.514 14.345
15.230 15.061 14.889 14.715 14.539 14.365
14.164 14.005 13.851 13.702 13.569 13.423
14.178 14.014 13.855 13.701 13.564 13.414
14.193 14.024 1 3 . 8 60 13.701 13.549 13.405
13.310 13.195 13.088 12.992 12.905 12.830 12.765 12.712 12.670 12.640 12.622 12.616
13.295 13.175 1 3 .06 7 12.967 12.878 12.800 12.733 12.678 12.635 12.504 12.585 12.579
13.282 13.159 13.046 12.943 12.852 12.771
13.270 13.143 13.027 12.921 12.827 12.744
12.836 12,786 12.747 12.719 12.702 12.697
13.326 13.214 13.112 13.018 12.935 12.862 12.799 12.748 12.707 12.678 12.561 12.555
12.702 12.646 12.601 12.670 12.550 12.544
12.674 12.515 12.570 12.537 12.517 12.511
1.000
1.100
1.200
14.094 13.965 13.839 13.716 13.599 13.487 13.382 13.284 13.193 13.111 13.037 12.972
13.362 13.259 13.164 13.078 13.000 12.933
13.343 13.236 13.137 13.047 12.957 12.896
12.917 12.871 12.835 12.809 12.794 12.789
12.875 12.827 12.789 12.763 12.746 12.741
0.900
0.950
14.882 14.754 14.624 14.492 14.359 14.226
IN MEV 0=
16.317 15.309 16.284 16.244 16.189 16.119 lo.u35 15.937 15.827 15.707 15.576 15.436 15.289 15.135 14.978 14.816 14.653 14.489 14.325
14.987 14.646 14.703 14.558 14.411 14.266 14.121 13.980 13.841 13.708 13.580 13.458
15.525 l5.'.i7 13.341 15.236 15.123 15.005
(MEVI
Q-VALUe
15.224 16.216 16.193 16.154 16.101 15.034 15.953 15.859 15.753 15.63 7 15.511 15.376 15.235 15.087 14.935 14.779 14.521 14.453 14.305 14.149 13.996 13.847 13.703 13.565 13.433
15.931 15.924 15.904 15.870 15.824 15.765 15.694 15.612 13.52U 15.418 15.307 15.189 15.065 14.935 14.801 14.664 14.525 14.385 14.246 14.108 13.972 13.840 13.711 13.589 13.472
15.828 15.821 15.802 15.770 15.726 15.670 15.603
Tl=1875.633 T2=2808.951 T3= 939.576 T4=3727.4ia
16.031 16.024 16.003 15.968 15.919 15.867 15.783 la.oVf 15.600 15.493 15.377 15.253 15.123
15.129 15.121 16.099 16.052 15.011 15.946 15.869
1.300
1.400
INPUT VALUES FDR THE REACTION T ( 0 , N ) H E 4 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ENERGY OF PARTICLE-3
ANGLE(DEGREE I
0, 5, 10 15, 20 25, 30 35.0 40.0 45.0 50.0 55.0 60.0 55.0 70.0 75.0 80.0 85.0 90.0
16.584 15.575 15.546 15.504 15.442 16.364 16.271 15.163 16.041 15.907 15.762 15.607 15.445
16.670 16.661 15.633 16.587 15.524 16.443 15.347 15.235 15.110 15.972 15.822 15.663 15.495
15.275 15.101 14.923 14.743 14.563 14.384
95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165,0 170.0 175.0 180.0
Tl=1875.633 T2=2808.951 T3= 9 3 9 . 5 7 5 74=3727.418 IMEV)
0-VALUE
IN THE LABORATORY SYSTEM
16.920 15.910 16.880 16.830 16.761 16.673 16.568 16.447 16.311 16.160 15.998 15.825 16.644 16.466 15.261 15.063 14.863 14.552 14.453
17.081 17.070 17.039 15.986 15,914 15.821 15.711 16.583 16.440 16.282 16.112 16.930 15.740 15.542 15.338 15,131 14.921 14.711 14.503
17.238 17.227 17.194 17.139 17.053 15.965 16.850 15.717 15.55 7 16.401 15.223 16.033 15.834
15.321 15.142 14.959 14.774 14.588 14.403
15.755 16,745 15.717 15.569 15.504 15.521 15.422 16.307 15.178 15.035 15.882 15.718 15.545 15.356 15.182 14.994 14.803 14.513 14.423
14.205 14.033 13.854 13.701 13.545 13.397
14.221 14.043 13.869 13.702 13.542 13.390
14.236 14.053 13.875 13.703 13.539 13.383
14.257 14.075 13.888 13.708 13.536 13.373
13.257 13.128 13.008 12.900 12.803 12.719 12.546 12.585 12.640 12.605 12.485 12.479
13.247 13.114 12.991 12.880 12.781 12.694
13.237 13.101 12.976 12.852 12.760 12.571 12.595 12.533 12.484 12.449 12.428 12.421
13.220 13.077 12.9 46 12.827 12.721 12.529 12.549 12.484 12.433 12.396 12.374 12.367
12.520 12.559 12.511 12.477 12.455 12.449
611
IN MEV 0=
15.627 15.414 15.197 14.979 14.760 14.643
17.392 17.380 17.346 17.288 17.209 17.108 16.987 16.847 16.591 15.518 15.332 1 5 . 134 15.925 15.711 1 5.48 9 15.263 16.035 14.808 14.583
17.543 17.531 17.495 17.436 17.352 17.247 17.121 16.975 15.812 16.633 16.439 16.233 16.017 15.793 15.553 15.329 15.093 14.857 14.622
14.298 14.097 13.902 13.714 13.534 13.354
14.329 14.120 13.917 13.721 13.535 13.358
14.360 14.143 13.932 13.730 13.536 13.353
14.392 14.157 13.949 13.739 13.539 13.350
13.205 13.055 12.920 12.795 12.585 12.590 12.507 12.439 12.385 12.348 12.325 12.318
13.192 13.038 12.897 12.758 12.554 12.554 12.469 12.398 12.343 12.304 12.280 12.272
13.181 13.022 12.875 12.743 12.625 12.621
13.173 13.008 12.867 12.720 12.598 12.491 12.400 12.325 12.2 57 12.225 1 2.2 00 12.191
12.433 12.360 12.304 12.263 12.238 12.230
Nuc(e(ir Data Tables, Vol. I I , No. 7, I 973
H. LISKIEN AND A. PAULSEN
T(4«)*He. ENERGYIMEV)
1.600
a{e lab), £„((? lab): Recommended Values 1.7C0
1.800
1.900
Z.OOO
2.100
2.200
2.300
CENTER-OP-MASS INPUT VALUES EUR THE REACTIUN T ( U , N ) H E 4 U-SIGMA-0(MR/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 6 ANGLE(DEGREE)
13.800 0.858 0.116 0.016 0.000 0.007 0.001 0.002
13.300 12.900 12.600 12.300 12.100 11.900 U.HOO 0.835 O.Sl* 0.793 0.771 0.749 0.730 0.707 0.120 0.122 0.124 0.127 0.129 0-130 9,-\li 0.029 0.042 0.054 0.067 0.080 0.091 0.104 0.001 0.002 0.004 0.005 0.007 0.009 0.012 0.008 0.009 O.OU 0.012 0.013 0.014 0.016 0.004 0.007 0.010 0.013 0.016 0.019 0.022 0.003 0.004 0.004 0.005 0.006 0.007 0.007 DIFFERENTIAL CRUSS-SECTIONS (MB/SR) IN THE LABURATURY SYSTEM
0,0 5,0 10,0 15,0 20t0 25,0 30.0
0.165E 0.164E 0.163E 0.162E U.160E 0.158E 0.155E
02 02 02 02 02 02 02
0.160E 0.159E 0.158E 0.156E a.l54E 0.151E 0.148E
02 02 02 02 02 02 02
0.156E 0.155E 0.154E O.lSlt 0.149E 0.145E 0.142E
02 02 02 02 02 02 02
0.153E 0.152E 0.150E 0.148E 0.145E 0.141E 0.137E
02 02 02 02 02 02 02
0.1506 0.149E 0.147E 0.144E 0.141E 0.137E 0.132E
02 02 02 02 02 02 02
0.14eE 0.147E 0.146E 0.142E 0.138E 0.133E 0.129E
02 02 02 02 02 02 02
0.146E 0.145E 0.143E 0.139E 0.135E 0.130E 0.125E
02 02 02 02 02 02 02
0.145E 0.145E 0.142E 0.138E 0.133E 0.128E 0.122E
02 02 02 02 02 02 02
35.0 40.0 45,0 50,0 55.0 60.0
0.152E 0.149E 0.146E 0.143E 0.139E 0.136E
02 02 02 02 02 02
0.145E 0.141E 0.138E 0.135E 0.131E 0.128E
02 02 02 02 02 02
0.138E 0.135E 0.131E O.ISSE 0.124E 0.121E
02 02 02 02 02 02
0.133E 0.129E 0.126E 0.122E 0.119E 0.115E
02 02 02 02 02 02
0.128E 0.124E 0.120E 0.117E 0.113E 0.109E
02 02 02 02 02 02
0.124E 0.120E 0.116E 0.U2E 0.108E 0.104E
02 02 02 02 02 02
0.120E 0.116E 0.112E 0.108E 0.104E O.IOOE
02 02 02 02 02 02
0.117E 0.112E 0.108E 0.104E O.IOOE 0.964E
02 02 02 02 02 01
65.0 70,0 75.0 80.0 85.0 90l0
0.132E 0.129E 0.125E 0.122E 0.118E 0,115E
02 02 02 02 02 02
0.124E 0,121E 0.n7£ 0.113E O.UOE 0.107E
02 02 02 02 02 02
0.H7E 0.H4E O.llOE 0.107E 0.103E 0,100E
02 02 02 02 02 02
O.lllE 0 . 108E 0.104E O.lOlE 0.978E 0.946E
02 02 02 02 01 01
0.106E 0.102E 0.988E 0.952E 0.919E 0.888E
02 02 01 01 01 01
O.IOIE 0.974E 0.937E 0.902E q.869E 0.838E
02 01 01 01 01 01
0.968E 0.930E 0.a93E 0.857E 0.e24E 0.795E
01 01 01 01 01 01
0.926E O.BSSE 0.851E 0.815E 0.783E 0.754E
01 01 01 01 01 01
95.0 100.0 105.0 110.0 115.0 120.0
0.112E 0.109E 0.106E 0.103E O.IOOE 0,985E
02 02 02 02 02 01
0.104E O.IOIE C.985E 0,960E 0.937E 0.916E
02 02 01 01 01 01
0.974E 0.947E 0.922E 0.899E 0.879E 0,861E
01 01 01 01 01 01
0.918E 0.e92E 0.868E 0.848E 0.830E 0.813E
01 01 01 01 01 01
0.860E 0.836E 0.814E 0.796E 0.780E 0.766E
01 01 01 01 01 01
0.812E 0.789E 0.769E 0.753E 0.739E 0.728E
01 01 01 01 01 01
0.769E 0.748E 0.730E 0.716E 0.704E 0.694E
01 01 01 01 01 01
0.729E 0.709E 0.693E 0.680E 0.670E 0.662E
01 01 01 01 01 01
125.0 130.0 135.0 140.0 145,0 150,0
0.964E 0.944E 0.927E 0.913E 0.900E 0,890E
01 01 01 01 01 01
0.898E 0.881E 0.fl66E 0.863E 0.842E 0,834E
01 01 01 01 01 01
0.844E 0.830E 0.817E 0.806E 0,797E 0,789E
01 01 01 01 01 01
165,0 160.0 165.0 170,0 175.0 180,0
0,883E 0.876E 0.872E 0.869E 0.867E 0.867E
01 01 01 01 Oi 01
0.827E 0.821E O.SieE 0.815E 0.814E 0.813E
01 01 01 01 01 01
0,783E 0.779E 0.775E 0.773E 0.772E 0,771E
01 01 01 01 01 01
0.746E 0.742E 0.739E 0.737E 0.735E 0.735E
01 01 01 01 01 01
0.709E 0.706E 0.703E 0.701E 0.700E 0.700E
01 01 01 01 01 01
0.680E 0.677E 0.674E 0.672E 0.671E 0.671E
01 01 01 01 01 01
0.653E 0.650E 0.648E 0.646E 0.6456 0.645E
01 01 01 01 01 01
0.629E 0.627E 0.624E 0.623E O.iZZi 0.622E
01 01 01 01 01 01
:NtKtYi«EV)
2.400
2.500
2.600
2.700
2.800
2.900
3.000
3.500
CENTER-OF-MASS INPUT VALUES FOR THE REACTION T { U , N ) H E 4 0-SIGMA-0(MB/SR) A 0 A 1 A 2 A 3 A 4 A 5 A 6
11.800 0,688 0,132 0.115 0.015 0.017 0.025 0.008
11.800 0,666 0.133 0.127 0.019 0.018 0.028 0.009
ANGLE(DEGRE6)
11.900 0.646 0.133 0.137 0,023 0,020 0.031 0.010
12.000 0.627 0.132 0.148 0.027 0.021 0.034 0.011
12.100 0.608 0.131 0.159 0.031 0.022 0.037 0.012
DIFFERENTIAL CROSS-SECTIONS (MB/SR)
12.200 0.589 0.130 0.169 0.034 0.024 0.040 0.014
12.300 0.571 0.130 0.180 0.037 0.025 0.042 0.015
13.800 0.490 0.126 0.223 0.051 0.031 0.057 0.022
IN THE LABORATORY SYSTEM
0.0 5.0 10.0 15.0 20.0 25.0 30.0
0.146E 0.145E 0.142E 0.138E 0,132E 0.127E 0.121E
02 02 02 02 02 02 02
0.147E 0.145E 0.142E 0.138E 0.132E 0.125E 0.119E
02 02 02 02 02 02 02
0.14eE 0.147E 0.144E 0.138E 0.132E 0.125E 0.118E
02 02 02 02 02 02 02
0.150E 0.149E 0.145E 0.139E 0.132E 0.125E 0.117E
02 02 02 02 02 02 02
0.152E 0.151E 0.146E 0.140E 0.132E 0.124E 0.115E
02 02 02 02 02 02 02
0.154E 0.152E 0.148E 0.141E 0.133E 0.124E 0.115E
02 02 02 02 02 02 02
0.156E 0.154E 0.149E 0.142E 0.133E 0.124E 0.114E
02 02 02 02 02 02 02
0.178E 0.175E 0.168E 0.157E 0.144E 0.131E 0.118E
02 02 02 02 02 02 02
35,0 40.0 45.0 50.0 55.0 60.0
0.115E O.llOE 0.105E O.IOIE 0.976E 0.937E
02 02 02 02 01 01
0,113E 0.107E 0.103E 0.986E 0.945E 0.905E
02 02 02 01 01 01
O.lllE 0.106E O.IOIE 0.966E 0.923E 0.8e2E
02 02 02 01 01 01
O.llOE 0.104E 0.993E 0.945E 0.902E 0.850E
02 02 01 01 01 01
0.109E 0.102E 0.974E 0.925E 0.880E 0.e37E
02 02 01 01 01 01
0.107E O.IOIE 0.953E 0.903E 0.858E 0.815E
02 02 01 01 01 01
0.106E 0.996E 0.936E 0.884E 0.8376 0.792E
02 01 01 01 01 01
0.107E 0.986E 0.912E 0.851E 0.797E 0.745E
02 01 01 01 01 01
65.0 70,0 75.0 80.0 85.0 90.0
0.89eE 0.859E 0,821E 0.786E 0.753E 0,726E
01 01 01 01 01 01
0.865E 0.825E 0,787E 0.752E 0.719E 0,692E
01 01 01 01 01 01
0.842E 0.eo2E 0.764E 0.728E 0.696E 0.669E
01 01 01 01 01 01
0.819E 0.778E 0.739E 0.703E 0.672E 0.645E
01 01 01 01 01 01
0.795E 0.754E 0.715E 0.678E 0.647E 0.622E
01 01 01 01 01 01
0.772E 0.730E 0.690E 0.654E 0.623E 0.598E
01 01 01 01 01 01
0.7496 0.7066 0.666E 0.6296 0.598E 0.5746
01 01 01 01 01 01
0.695E 0.645E 0.599E 0.559E 0.527E 0.505E
01 01 01 01 01 01
95.0 100.0 105.0 llp.O 115.0 120.0
0.701E 0.682E 0.668E 0.656E 0.648E 0.642E
01 01 01 01 01 01
0.669E 0.652E 0,539E 0.630E 0.623E 0.619E
01 01 01 01 01 01
0.647E 0.631E 0.619E 0.611E 0.605E 0.603E
01 01 01 01 01 01
0.625E 0.610E 0.600E 0.594E 0.591E 0.590E
01 01 01 01 01 01
0.602E 0.589E 0.581E 0.677E 0.576E 0.576E
01 01 01 01 01 01
0.580E 0.568E 0.562E 0.559E 0.560E 0.561E
01 01 01 01 01 01
0.5576 0.547E 0.5436 0.542E 0.544E 0.547E
01 01 01 01 01 01
0.493E 0.490E 0.494E 0.5O2E 0.513E 0,524£
01 01 01 01 01 01
125.0 130.0 135.0 140.0 145.0 150.0
0.637E 0.632E 0.629E 0.625E 0.621E 0.618E
01 01 01 01 01 01
0 . 6 1 5 E 01 0 . 6 0 1 E 01 0 . 5 8 9 E 01 0 . 5 7 6 E 01 0 . 5 6 3 E 01 0 . 5 5 0 E 01 0 . 5 3 4 E 0 . 6 1 2 E 01 0 . 5 9 9 E 01 " ' " " ' ~' " " " -' " ' ' -" " ' -" " 0.6096 -- - 0.606E 0.603E 0.6006
01 "•
155.0 160.0 165.0 270.0 175,0 180.0
0.616E 0.612E 0,610E 0.609E 0.608E 0,607E
01 01 01 01 01 01
0.697E 0.5956 0.5926 0.5916 0,5906 0,5906
01 01 01 01 01 01
Nuclear Data Tables, Vol. 11, No. 7, 1973
01 01 01 01 01 01
0.586E 0.5646 0.5826 0.580E 0.579E 0,579E
01 01 01 01 01 01
0.677E 0.575E 0.673E 0.571E 0.5706 0.570E
612
01 01 01 01 01 01
0.668E 0.566E 0.564E 0.562E 0.561E 0.561E
01 01 01 01 01 01
0.559E 0.557E 0.556E 0.555E 0.554E 0.554E
01 01 01 01 01 01
0.551E 0.549E 0.548E 0.547E 0.646E 0.646E
01 01 01 01 01 01
0.551E 0.551E 0.550E 0.549E 0.5496 0.549E
NEUTRON PRODUCTION CROSS SECTIONS
T(4/t)4He. ENERGY(MEV)
1.600
o{0 lab), £^{0 lab): Recommended Values 1.700
1.800
1.900
2.000
INPUT VALUES FDR THE REACTION REST ENERGY IIV MEV FUR PROJECTILE T l = 1 8 7 5 . 6 3 3 TARGET T 2 = 2 8 0 8 . 9 6 1 PRODUCT T3= 9 3 9 . 5 7 6 RESIDUAL NUCLEOS 7 4 = 3 7 2 7 . 4 1 8
ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 36.0 40.0 45.0 50.0 55.0 60.0 55.0 70.0 75.0 80.0 85,0 90.0 95.0 100.0 105.0 110,0 115,0 120.0 125,0 130,0 136.0 140.0 145.0 150.0 155,0 150,0 165,0 170,0 175.0 180,0
ENERGY IMEV)
ENERGY OF PARTICLE-3
(MEV)
17.837 17.824 17.785 17.720 17.530 17.617 17.381 17.225 17.049 16,855 16,647 15.426 15.194 15.953 15,706 r5.455 15.202 14.950 14.700 14.454 14.215 13,983 13.760 13.547 13.346 13.156 12.984 12,824 12.679 12,550 12.437 12,341 12,262 12.201 12,156 12.130 12.121
17.980 17.967 17,926 17.859 17.767 17.649 17.509 17,347 17,165 15.966 16,749 15.521 15.281 16.032 15.777 15.518 15.258 14.998 14.740 14.487 14,240 14.001 13.772 13.663 13.347 13.153 12.974 12,810 12.561 12.529 12.413 12.315 12.234 12.171 12,125 12,098 12.089
18.122 18.108 18.066 17.997 17.901 17.780 17.634 17.467 17.279 17.073 16.850 16.614 16.357 16.111 15.848 15.581 15.313 15.045 14.780 14.519 14.266 14.020 13.784 13.660 13.348 13.150 12.966 12.798 12.645 12.510 12.391 12.291 12.208 12.143 12.097 12.069 12.059
18.262 18.247 IB.204 18.132 18.033 17.908 17.759 17.686 17.392 17.179 16.950 16.707 15.452 16.188 15.918 15.543 16.367 15.092 14.820 14.562 14.292 14.040 13.798 13.558 13.351 13.147 12.959 12.787 12.531 12.492 12.371 12.258 12.183 12.117 12.070 12.041 12.032
2.400
2,500
2,600
2.700
2.800
INPUT VALUES FOR THE REACTION REST ENERGY IN MEV FOR PROJECTILE T l = 1 8 7 5 . 5 3 3 TARGET T 2 = 2 8 0 8 . 9 5 1 PRODUCT T3= 9 3 9 . 6 7 6 RESIDUAL NUCLEUS
0.0 5.0 10.0 15.0 20.0 25,0 30.0 36.0 40.0 45.0 50.0 56.0 50,0 65.0 70.0 75.0 80.0 85.0 90.0 95,0 100,0 105.0 110.0 115.0 120,0 125.0 130.0 135.0 140.0 146.0 150.0 165,0 160.0 166.0 170.0 175.0 180.0
ENERGY OF PARTICLE-3
18.804 18,788 18,740 18.650 18.649 18.408 18.241 18.047 17,831 17.593 17.337 17.056 15.783 16.489 16.189 15.885 15,580 15.276 14.976 14,682 14,395 14.119 13,855 13.603 13,355 13.145 12.940 12,753 12.584 12.434 12.303 12,191 12.100 12.028 11.977 11.946 .11.936
18.937 16,920 16,870 16.788 18.674 18.530 16.358 18.160 17.938 17.694 17,432 17.155 15.864 16.564 16.257 15.946 15,634 15.323 15.015 14,715 14,423 14.141 13.871 13.614 13,373 13.147 12.938 12.748 12.575 12,422 12.289 12.175 12.082 12.009 11.957 11.925 11.915
19.068 19,051 19,000 18.915 18.799 18.661 16,475 18.272 18.044 17.795 17,527 17,242 15.945 16.638 16.324 15.005 15,687 15.369 15.056 14,749 14.450 14.152 13.867 13.626 13.379 13.149 12.937 12.743 12.567 12,412 12.276 12.160 12.066 11.992 11.939 11.907 11.896
2.300
Q-VALUE
IN HE« U=
17.590
18.399 18.385 18.340 18.256 18.164 18.036 17.881 17.703 17.504 17.285 17.049 16.799 16.537 15.255 15.987 15.705 15.422 15.139 14.859 14.585 14.318 14.050 13.812 13.575 13.354 13.145 12.953 12.777 12.618 12.476 12.352 12.247 12.150 12.093 12.044 12.015 12.005
lb.536 18.520 IS.475 18.399 18.294 16.161 18.003 17.819 17.614 17.389 17.147 16.889 15.620 16.341 16.056 15.767 15.476 15.185 14.899 14.518 14.344 14.080 13.826 13.585 13.358 13.146 12.949 12.768 12.605 12.461 12.335 12.227 12.139 12.070 12.020 11.991 11.981
18.671 18.655 18.608 18.530 18.422 18.286 18.123 17.934 17.724 17.492 17.243 16.979 16.703 15.417 16.124 15.828 15.530 15.233 14,939 14,651 14.371 14.101 13.841 13.595 13.363 13.146 12.945 12.761 12.595 12.447 12.318 12.209 12.119 12.048 11.998 11.958 11.958
2.900
3.000
3.500
TID,NIHE4 Q-VALUE
IN MEV U=
17.5
T4=3727.41B (MEV)
19.198 19.180 19.128 19.042 18.922 18.771 18.591 18.383 18.160 17.695 17.520 17.329 17.025 16.711 16,390 16.066 15.740 16.415 15,095 14.782 14.478 14.165 13.904 13.537 13.367 13.153 12.936 12.739 12.560 12.402 12.254 12.147 12.050 11.975 11.921 11.889 11.878
613
2.200
IN THE LABORATORY SYSTEM
17.691 17.679 17.641 17.578 17.492 17,383 17.252 17.101 15.931 15,744 16.543 15.330 16.105 15.873 16,634 15.T91 15.147 14.903 14.660 14.422 14,190 13,955 13,748 13.542 13.347 13.164 12,994 12,839 12.698 12,573 12.463 12,369 12,293 12,232 12,189 12,164 12,155
ANGLE(DEGREE)
2.100 TID,N)HEA
IN THE LABORATORY
19.327 19.309 19.255 19.157 19.045 18.890 18.705 18.493 18.254 17.994 17.713 17.416 17.105 16.784 15.457 16.125 15.792 15.461 15.135 14.815 14.506 14.207 13.921 13.650 13.394 13.156 12.936 12.735 12.554 12.393 12.253 12.134 12.036 11.959 11.905 11.872 11.851
19.465 19.435 19.381 19.291 19.156 19.008 18.819 18.602 18.366 18.092 17.805 17.502 17.184 15.857 16.522 16.184 15.845 15.508 15.175 14.850 14.534 14.229 13.939 13.662 13.403 13.161 12.937 12.733 12.549 12.385 12.243 12.122 12.022 11.945 11.889 11.856 11.845
SYSTEM
19.581 19.553 19.507 19.414 19.287 19.126 18.932 18.710 18.452 18.189 17.897 17.587 17.263 16.929 16.588 16.243 15.897 15.554 16.215 14.884 14.562 14.252 13.956 13.676 13.412 13.165 12.938 12.731 12.544 12.378 12.233 12.110 12.010 11.931 11.875 11.841 11.830
20.204 20.183 20.121 20.019 19.878 19.700 19.487 19.242 18.968 18.568 18.345 18.006 17.551 17.285 16.911 15.534 16.157 16.782 15.414 15.054 14.705 14.370 14.050 13.747 13.452 13.197 12.953 12.730 12.530 12.352 12.197 12.066 11.968 11.874 11.814 11.778 11.756
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
T(4/i)*He.
a(d lab), £„(0 lab): Recommended Values 4.500
ENERGY(MEV)
5.000
7.000
6.500
7.500
CENTER-OF-MASS INPUT VALUES FUR THE REACTION T(U,N)HE'4 U-SIGMA-0(MB/SR)
15.20C1 0.426 0.1231 0.25i 0 . 0 5 £1 0.037 0.071 0 . 0 2 ' :i O.OOC O.OOC1
> )
ANGLEIDEGREEI 0.0 5.0 10.0 15.0 20.0 25.0 30,0
)
18.20C1 0 . 3 6 ' ;} O.llS 0.264 0.064 0.051 0.103 0.044 0.000 O.OOC1
)
02 02 02 02 02 02 02
0.226E 0.2216 0.208E 0.189E 0.1676 0.145E 0.125E
02 02 02 02 02 02 02
0.244E 0.2366 0.223E 0.200E 0.174E 0.1486 0.126E
02 02 02 02 02 02 02
0.254E 0.247E 0.229E 0.202E 0.173E 0.144E 0.1206
02 0.2596 0 2 0.251E 0 2 0.2316 02 0.201E 0 2 0.168E 0 2 0.137E 02 0.1126
02 02 02 02 02 02 02
0.2596 0.250E 0.227E 0.194E 0.158E 0.126E O.IOIE
02 02 02 02 02 02 02
35.0 40.0 45.0 60.0 65.0 60.0
0.1076 0.967E 0.883E 0.8156 0.756E 0.699E
02 01 01 01 01 01
0.109E 0.978E 0.890E 0.821E 0.761E 0.701E
02 01 01 01 01 01
0.108E 0.9646 0.880E 0.8206 0.7666 0.7096
02 01 01 01 01 01
0.1Q3E 0.920E 0.8526 0.8076 0.7676 0.7176
0 2 0.9586 01 0.8606 0 1 0.811E 01 0.785E 0 1 0.767E 0 1 0.716E
01 01 01 01 01 01
0.858E 0.780E 0.755E 0.7506 0.7386 0.7066
01 01 01 01 01 01
65. 70, 75. 80. 85.
0.642E 0.565E 0.533E 0.488E 0.454E 0.434E
01 01 01 01 01 01
0.6386 0.5736 0.5116 0.4596 0.4216 0.4016
01 01 01 01 01 01
0.644E 0.575E 0.507E 0.4486 0.405E 0.383E
0 1 0.6646 01 0.6566 0 1 0 . 5 e i E 0 1 0.6836 0 1 0.509E 0 1 0.5086 0 1 0.445E 0 1 0.4406 0 1 0.399E 0 1 0.3906 0 1 0.373E 0 1 0 . 3 6 1 6
0 1 0.650E 0 1 0.578E 0 1 0.500E 0 1 0.429E 0 1 0.374E 0 1 0.3416
01 01 01 01 01 01
95.0 100.0 105.0 110.0 115.0 120.0 1?5. 130 135. 140 145. 150
0.426E 0.431E 0.443E 0.461E 0.481E 0.500E
01 01 01 01 01 01
0.3976 0.407E 0.4276 0.4536 0.4806 0.504E
01 01 01 01 01 01
0.3806 0.393E 0.4176 0.4476 0.478E 0.505E
0 1 0.368E 0 1 0.353E 0 1 0 1 0.381E 0 1 0.364E 0 1 0 1 0.406E 0 1 0.387E 0 1 0 1 0.436E 0 1 0.4176 0 1 0 1 0.467E 0 1 0.446E 0 1 0 1 0.495E 0 1 0.473E 01
0.33OE 0.338E 0.3596 0.386E 0.415E 0.439E
01 01 01 01 01 01
0.516E 0.529E 0.538E 0.5456 0.5496 0.551E
01 01 01 01 01 01
0.5256 0.542E 0.553E 0.5606 0.5646 0.5666
01 01 01 01 01 01
0.528E 0.544E 0.555E 0.561E 0.564E 0.565E
0 1 0.5166 0 1 0.492E 0 1 0.5316 0 1 0.5066 0 1 0.5406 01 0.513E 0 1 0 . 5 4 4 6 0 1 0.515E 0 1 0.5446 01 0.5156 0 1 0.5426 0 1 0.5136
0.4b9E 0.4716 0.478E 0.4826 0.482E 0.483E
01 01 01 01 01 01
0.552E 0.552E 0.553E 0.5536 0.5536 0.5536
01 01 01 01 01 01
0.5676 0.5686 0.5686 0.5686 0.5686 0.5686
01 0.5656 01 0.5646 01 0.5636 01 0.5626 0 1 0.5626 01 0.6626
01 0.4836 0 1 0.4846 0 1 0.4866 0 1 0.487E 0 1 0.4896 0 1 0.489E
01 01 01 01 01 01
155.0 160.0 165.0 170.0 175.0 180.0 ENERGY(MEV)
e.ooo
01 01 01 01 01 01
9.000
8.500
01 01 01 01 01 01
0 1 0.511E 01 0.6106 0 1 0.509E 01 0.509E 0 1 0.609E 01 0.5096
0.5396 0.537E 0.5356 0.5336 0.5326 0.5326
0.2616 0.2426 0.2176 0.1826 0.1456 0.112E 0.889E 0.7506 0.6966 0.6926 0.704E 0.704E 0.678E 0.6256 0.5546 0.4766 0.404E 0.348E 0.3126 0.299E 0.3046 0.323E 0.349E 0.377E 0.4016 0.4206 0.4336 0.441E 0 . 4 4 5E 0.448E 0.4506 0.4536 0.4566 0.460E 0.4646 0.466E 0.4676
0 2 0 .. 2 4 5 6 0 2 0 2 0 . .2356 0 2 0 2 0 . .2096 0 2 0 2 0 . .172E 0 2 0 2 0 .. 1 3 3 6 0 2 0 2 0 . .1006 0 2 0 1 0 .. 7 7 8 6 0 1 0 1 0 .. 6 5 9 6 0 1 0 . .6256 0 1 0 .. 6 4 2 6 0 1 0 , .6696 0 1 0 . .677E 0 1 0 . .655E
01 01 01 01 01 01
0 1 0 . .604E 0 1 0 ,. 5 3 2 6 0 1 0 . .4536 0 1 0 .. 3 8 1 6 0 1 0 . .3236 01 0 .2866
01 01 01 01 01 01
0 1 0 .. 2 7 1 6 0 1 0 .275E 0 1 0 .. 2 9 2 E 0 1 0 .3166 0 1 0 .3436 0 1 0 .3676
01 01 01 01 01 01
0 1 0 ..3876 0 1 01 0 .4006 0 1 0 1 0 .410E 0 1 0 1 0 .416E 0 1 0 1 0 .4216 0 1 01 0 .4266 0 1 01 0 .4326 0 1 0 1 0 .438E 0 1 0 1 0.. 4 4 4 E 0 1 0 1 0 .450E 0 1 0 1 0 .454E 0 1 0 1 0 .455E 0 1
10.000
9.500
C6NT6R--OF--MASS INPUT VALUES FOR THE REACTION T(1J,N1HE4
0-SIGMA-0(MB/SR)
ANGLE(DEGREE) 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95 .0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175 .0 180.0
Nuclear Data Tables, Vol. 1 1, No. 7, 1973
16.900 0.280 0.080 0.184 0.013 0.124 0.183 0.10] 0.021 0.014
16.000 0.263 0.06! 0 . 1 7 :1 -0.010 0.13E i 0.194 0.124 0 . 0 3 :1 0.02C
16.400 0.271 0.072 0.17£ i 0.001 0.132 0.190 0.112 0.027 0.017
15.800 0.254 0.057 0 . 17C -0.01'; 0.14; 0.197 0 . 136 0.04C 1 0.023
0.358E 0.3736 0.383E 0.392E 0.399E 0.406E 0.4156 0.4246 0.433E 0.4416 0.4466 0.448E
16.700 0.246 0.04fi 0.167 -0.027 0.143 0.198 0.151 0.047 0 . 0 2 1r
)) ) )
)
DIFF6RENTIAL CROSS-:SECTIONS; 0.240E 0.230E 0.2016 0.163E 0.122E 0.897E 0.6796 0.5786 0.5676 0.6026 0.640E 0.655E 0.635E 0.583E 0.510E 0.430E 0.356E 0.298E 0.261E 0.2456 0.248E 0.264E 0.2886 0.3146 0.338E
)
)
(
0.198E 0.1956 0.185E 0.171E 0.154E 0.137E 0.121E
90.
)
)
)
18.OOC 18.90C1 17,400 18.70C 18.700 0.291 0.302 0.314 0.32Ei 0.343 0.087 0 . 0 94 0.101 0.107 0.111 0.192 0.202 0.214 0.23] 0.246 i 1 0.026 0.039 0.050 0.059 0.063 0.11
(MB/SRl 1IN THE LABORATORY SYSTEM
02 02 02 02 02 01 01
0.2356 0.224E 0.1946 0.1546 0.112E 0.798E 0.591E
02 0.2316 02 0.2196 02 0.1886 02 0.146E 02 0.1046 0 1 0.713E 0 1 0.519E
0 2 0.230E 0 2 0.230E 0 2 0.217E 02 0.216E 0 2 0.184E 0 2 0 . 1 8 1 6 02 0.140E 0 2 0.1356 0 2 0.9706 0 1 0.900E 0 1 0.638E 0 1 0.5676 0 1 0.454E 0 1 0 . 3 9 4 6
02 02 02 02 01 01 01
01 01 01 01 01 01
0.510E 0.518E 0.5686 0,6166 0.6346 0.6146
0 1 0.455E 0 1 0.4826 01 0.5456 0 1 0.600E 0 1 0.619E 01 0.5966
0 1 0.4086 01 0.4526 0 1 0.5286 0 1 0.587E 0 1 0.606E 0 1 0.679E
0 1 0.3676 01 0.4316 0 1 0.5196 01 0.5826 0 1 0.5986 01 0.5656
01 01 01 01 01 01
01 01 01 01 01 01
0.560E 0.4866 0.406E 0.333E 0.276E 0.2396
01 01 01 01 01 01
0.518E 0.440E 0.361E 0.291E 0,239E 0.207E
0 1 0.499E 0 1 0.4186 01 0.3396 0 1 0.272E 01 0.223E 0 1 0.195E
01 01 01 01 01 01
01 01 01 01 01 01
0.224E 0.2266 0.242E 0.2656 0.2916 0.315E
0 1 0.208E 0 1 0.1946 0 1 0.185E 01 0.2106 0 1 0.1986 0 1 0.191E 0 1 0.226E 0 1 0.2136 0 1 0.207E 0 1 0.248E 0 1 0.2365 0 1 0.229E 0 1 0.272E 0 1 0.2596 0 1 0.251E 0 1 0 . 2 9 5 6 0 1 0 . 2 8 IE 0 1 0 . 2 7 3 E
01 01 01 01 01 01
01 01 01 01 01 01 01 01 01 01 01 01
0.335E 0.3506 0.3626 0.372E 0.382E 0.392E 0.4036 0.4156 0.4266 0.4366 0.442E 0»444E
01 01 01 01 01 01 01 01 01 01 01 01
01 01 01 01 01 01 01 01 01 01 01 01
0.5396 0.463E 0.383E 0.3126 0.2576 0.2226
0.315E 0.3306 0.3436 0.355E 0.3676 0.380E 0.394E 0.4096 0.4236 0.435E 0.442E 0.445E
01 01 01 01 01 01
01 01 01 01 01 01 01 01 01 01 01 01
0.300E 0.316E 0.3306 0.344E 0.3586 0.373E 0.3906 0.4086 0.424E 0.437E 0.446E 0.449E
614
01 01 01 01 01 01 01 01 01 01 01 01
0.2916 0.3066 0.3206 0.335E 0.351E 0.369E 0.3896 0.4106 0.4306 0.4456 0.456E 0.4596
NEUTRON PRODUCTION CROSS SECTIONS
T(«tn)*He. ENERGYIBEV)
4.000
a{e lab), EJd lab): Recommended Values
4.500
5.000
5.500
6.000
6.500
7.000
7
INPUT VALUES FOR THE REACTION T(D,M)HE4 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIOUAL NUCLEUS
ANGLE(DEGREE)
0. 5, 10. 15, 20. 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65. 70. 75. 80, 85. 90, 96.0 100.0 106.0 110.0 115.0 120.0 126.0 130.0 135.0 140.0 145.0 150.0 155.0 160.0 165.0 170.0 175.0 180.0
ENERGY(MEV)
Tl=1875.633 T2=2e08.951 T3= 9 3 9 . 5 7 6 T4=3727.418
ENERGY OF PARTICLE-3
20.810 20.787 20.719 20.607 20.453 20.257 20.024 19.756 19.456 19.129 18.778 18.407 18.021 17.624 17.219 16.811 16.403 15.999 15.603 15.216 14.842 14.483 14.141 13.818 13.615 13.233 12.974 12.738 12.526 12.338 12.175 12.036 11.923 11.834 11.771 11.733 11.720
21.401 21.377 21.303 21.182 21.015 20.804 20.562 20.262 19.939 19.686 19.207 18.808 18.393 17.966 17.531 17.094 15.657 16.225 15.802 16.389 14.991 14.609 14.246 13.903 13.681 13.283 13.009 12.750 12.536 12.338 12.166 12.020 11.900 11.807 11.741 11.701 11.688
8.000
8.500
(MEVI
0-VALUE
IN MEV 0=
IN THE LABORATORY SYSTEM
21.981 21.956 21.876 21.745 21.565 21.339 21.069 20.759 20.412 20.034 19.629 19.202 18.759 18.303 17.840 17.374 16.909 15.450 16.000 15.663 15.141 14.737 14.354 13.992 13.663 13.340 13.052 12.790 12.555 12.347 12.165 12.014 11.889 11.792 11.722 11.580 11.667
22.552 22.523 22.439 22.300 22.109 21.867 21.578 21.247 20.878 20.476 20.046 19.591 19.120 18.635 18.144 17.661 17.169 15.574 16.199 15.738 15.294 14.859 14.465 14.085 13.730 13.402 13.100 12.825 12.581 12.364 12.176 12.015 11.885 11.785 11.713 11.659 11.666
23.114 23.084 22.995 22.847 2 2.644 22.387 2 2.081 21.730 21.338 20.912 20.456 19.976 19.475 18.965 18.447 17.926 17.408 16.897 16.398 16.914 15.447 16.002 14.579 14.182 13.811 13.468 13.154 12.858 12.613 12.387 12.192 12.026 11.891 11.786 11.711 11.565 11.651
9.000
9.600
10.000
23.570 23.638 23.544 23.387 23.172 22.901 22.577 22.205 21.793 21.342 20.861 20.365 19.830 19.292 18.745 18.199 17.555 17.120 16.597 16.090 15.502 15.137 14.595 14.282 13.895 13.539 13.212 12.915 12.560 12.416 12.214 12.042 11.902 11.794 11.715 11.569 11.654
24.220 24.186 24.087 23.922 23.595 23.409 23.068 22.578 22.243 21.769 21.263 20.731 20.180 19.615 19.044 18.471 17.902 17.342 16.796 15.256 16.768 15.274 14.816 14.386 13.983 13.513 13.274 12.967 12.692 12.460 12.241 12.064 11.919 11.807 11.727 11.679 11.653
24.754 24.729 24.624 24.451 24.213 23.913 23.656 23.145 22.688 22.192 21.552 21.106 20.627 19.937 19.339 18.741 18.147 17.564 16.994 16.444 15.916 16.412 14.935 14.489 14.074 13.590 13.340 13.022 12.739 12.489 12.273 12.090 11.941 11.825 11.743 11.593 11.677
INPUT VALUES FOR THE REACTION T ( D , N ) H e 4 REST ENERGY IN MEV FOR PROJECTILE TARGET PRODUCT RESIDUAL NUCLEUS ANGLE(DEGREE)
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 66.0 60.0 56.0 70.0 75.0 80.0 85.0 90.0 95 100. 105 110. 115. 120. 125.0 130.0 135.0 140.0 145.0 150.0 166.0 150.0 156.0 170.0 175.0 180.0
ENERGY OF PARTlCLE-3
25.305 25.268 25.158 24.976 24.726 24.411 24.035 23.605 23.127 22.607 22.052 21.470 20.866 20.250 19.627 19.003 18.385 17.778 17.185 16.615 16.067 15.545 15.053 14.591 14.152 13.757 13.406 13.078 12.787 12.530 12.307 12.120 11.967 11.848 11.764 11.713 11.596
25.841 25.802 25.687 25.497 25.236 24.905 24.514 24.065 23.556 23.023 22.445 21.838 21.209 20.567 19.919 19.271 18.529 17.998 17.385 16.793 15.225 16.686 15.177 14.700 14.257 13.849 13.475 13.140 12.840 12.575 12.347 12.154 11.997 11.875 11.788 11.735 11.719
26.373 26.333 26.213 26.015 25.742 25.399 24.990 24.522 24.002 23.437 22.835 22.203 21.550 20.883 20.210 19.537 18.872 18.219 17.684 15.971 16.384 15.827 15.302 14.810 14.364 13.933 13.550 13.204 12.895 12.524 12.389 12.192 12.031 11.905 11.815 11.763 11.745
Tl=1875.633 T2=280B.951 T3= 9 3 9 . 5 7 6 74=3727.418 (MEV)
25.902 25.850 25.735 25.529 25.245 25.888 25.463 24.976 24.436 23.848 23.223 22.567 21.889 21.198 20.600 19.803 19.114 18.4 39 17.782 17.149 15.544 15.959 15.428 14.922 14.452 14.020 13.626 13.271 12.954 12.675 12.435 12.232 12.067 11.939 11.848 11.793 11.775
615
-VALUE
IN MEV 0=
17.590
I N THE LABORATORY SYSTEM
27.428 27.384 27.254 27.040 25.745 26.374 25.933 25.428 24.867 24.268 23.509 22.929 22.227 21.511 20.789 20.058 19.355 18.568 17.981 17.328 15.704 16.112 15.656 15.034 14.662 14.108 13.704 13.339 13.015 12.729 12.483 12.275 12.106 11.975 11.882 11.826 11.808
Nuclear Data Tables, Vol. 11, No. 7, 1973
H. LISKIEN AND A. PAULSEN
APPENDIX. Program for Calculation of Laboratory a's from cm. Values C C C C C C C C C C C C C C C C C C C C C C C C C C C
* THIS PROGRAM "EDIT" CALCULATES DIFFERENTIAL CROSS SECTIONS IN THE * LABORATORY SYSTEM FROM CENTER-OF-MASS INPUT DATA. * INPUT DATA NEEDED: * l.CARD: REACTION-NAMEf REST ENERGY IN MEV FOR PROJECTILE, TARGET, * PRODUCT AND RESIDUAL NUCLEUS, 0-VALUE, MARK, MODE * F0RMAT(5A4,5F10.3,2I5) * MARK=0, LABORATORY ENERGIES ARE NOT CALCULATED * MARK=1, LABORATORY ENERGIES ARE CALCULATED * MODE=0, INPUT VALUES ARE TOTAL CROSS SECTIONS AND * COEFFICIENTS NORMALIZED TO A0=1 * M0DE=1, INPUT VALUES ARE 0-DEGREE DIFFERENTIAL CROSS * SECTIONS AND COEFFICIENTS NORMALIZED TO SUM=1 * MODE=-l, END OF ALL CALCULATIONS * 2.CARD: INPUT ENERGY IN MEV, TOTAL CROSS SECTION IN MB OR 0-DEGREE * DIFFERENTIAL CROSS SECTION IN MB/SR, NUMBER OF LEGENDRE * COEFFICIENTS FOR THE ANGULAR DISTRIBUTION; * F0RMAT(5X,2F10.6,I5) « 3.CARD: INPUT ENERGY IN MEV, NORMALIZED COEFFICIENTS AO UP TO A5; * F0RMAT(5X,7F10.6) « IF THERE ARE MORE THAN 6 COEFFICIENTS, * 4.CARD: INPUT ENERGY IN MEV, NORMALIZED COEFFICIENTS A6 UP TO A H ; * F0RMAT(5X,7F10.6) * 5. : REPEAT CARD 2,3 (AND 4» FOR EVERY ENERGY TO BE TREATED; * 6.CARD: BLANK; * 7. : REPEAT CARD 1 TO 6 FOR EVERY REACTION TO BE TREATED; * CALCULATIONS ARE PERFORMED FOR EMISSION ANGLES BETWEEN 0 AND 180 * DEGREE IN STEPS OF 5 DEGREE. (LISKIEN DEC.72) DIMENSION TITLE(5),E(8),SIGMA(8),MAX(fi),A(8,12),ENERG(8,37) DIMENSION G02(8),W(8),SIG(8),B2(8),B3(8),Z(8),P(12)
800 F 0 R M A T { 5 A 4 , 5 F 1 0 , 3 , 2 I 5 ) 801 F 0 R M A T ( 5 X , 2 F 1 0 . 6 , I 5 ) 802 F 0 R M A T ( 5 X , 7 F 1 0 . 6 / 1 5 X , 6 F 1 0 . 6 ) 803 FORMATCl ENERGY(MEV) •,8F10.3) 804 FORMAT(IHO)
904 F0RMAT(20X,'REST ENERGY IN MEV FOR PROJECTILE Tl=«,F8.3,lOX, /'0-VALUE IN MEV 0=',F8.3/47X,'TARGET T2=',F8.3/46X,'PRODUCT T3=', /F8.3/37X,'RESIDUAL NUCLEUS T4=«,F8.3> 805 F0RMAT(30X,'CENTER-OF-MASS INPUT VALUES FOR THE REACTION ',5A4/) 905 FORMAT(22X,' INPUT VALUES FOR THE REACTION ',5A4/) 806F0RMAT(' SIGMA-T(MB) ',8F10.3) 906 FORMATC D-SIGMA-0(MB/SR)•,8F10.3 )
807 FORMAT(4X,'A " ' , 1 2 , 9 X , 8 F 1 0 . 3 ) 907 F 0 R M A T ( 5 X , ' A ' ,12,9X,8F10.3 ) 808 FORMAT(' ANGLE(DEGREE) ' , 1 3 X , ' D I F F E R E N T I A L CROSS-SECTIONS (MB/SR / ) IN THE LABORATORY SYSTEM' ) 908 FORMAT(' ANGLE(DEGREE) ' , 1 7 X , ' E N E R G Y OF PARTICLE-3 (MEV) IN THE /LABORATORY SYSTEM' ) 809 FORMAT(IH ) 810 F n R M A T ( F 8 . 1 , l l X , 8 E 1 0 . 3 ) 910 F 0 R M A T ( F 8 . 1 , 9 X , 8 F 1 0 . 3 ) 811 F0RMAT(' INPUT CARDS ARE IN DISORDER ' ) 812 FORMATC A-COEFFIClENTS INCORRECTLY NORMALIZED ' ) 813 FORMATC INPUT ENERGY FALLS IN DOUBLE-VALUED REGION ' ) 1000 R E A D ( 5 , 8 0 0 ) T I T L E , T 1 , T 2 , T 3 , T 4 , 0 , M A R K , M O D E IF(M0DE)999,1001,1001 1 0 0 1 NN=0 T12=Tl+T2 T34=T3+T4 T23=T2-T3 TF=-0/T2*(T12-0/2.) TB=-0/TZ3*(T12-T3-0/2) 1 IF(NN)999,2,1000 2 DO 3 1 = 1 , 8 DO 3 J = l , 1 2 A(I,J)=0. 3 CONTINUE DO 15 1 = 1 , 8 READ(5,801)E(I),SIGMA(I),MAX(I) IF(E( n ) 9 9 9 , 4 , 5 4 NN = I GO TO 16 5 IF(E(I)-TB)6,6,7 6 WRITE(6,813) GO TO 999 7 MAXI=MAX(I) READ(5,802)EB1,(A(I,J),J=1,MAXI) C CHECKING OF INPUT CARDS IF(E(n-EBl)8,9,8 8 WRITE(6,81l) GO TO 999 9 IF(MODE)999,10,11 10 I F ( A B S ( A ( I , 1 ) - 1 . ) - 0 . 0 0 0 1 ) 1 4 , 1 3 , 1 3 11 ASUM=0. 0 0 12 J=1,MAXI ASUM=ASUM+A(I,J) 12 CONTINUE IF(ABS(ASUM-1.)-0.0001)14,13,13 13 W R I T E ( 6 , 8 1 2 ) GO TO 999
Nuclear Data Tables, Vol. I I , No. 7, 1973
616
* « * « « * « * * * * « * « * « 5) * * * « * « « « * *
NEUTRON PRODUCTION CROSS SECTIONS
APPENDIX. Program for Calculation of Laboratory a's from cm. Values 14 U = 1 . - T F / E ( I ) Vl=l.+e(I)/(2.*Tl) V2 = l . + E ( I ) / n 2
Ul = S 0 R T ( V l / ( l . + E ( n * T 2 * U / ( 2 . * T 3 « T A ) ) ) U2=(l.-Q/T12)*(l.+E(I)*T2*U/(T3*T34))/V2 G02(I)=V2#*2/(1.+2.*E(I)*T2/T12**2) W( I )=SQRT I T l * T 3 / ( 7 2 * 7 - ^ * 0 ) ) * U 1 * U 2 IF(MARK)X14.15,114 114 V = l . - T B / E ( n B2(n=V2/Vl
B3(n = (l.-(1.-V2)«(l.+V*T23/(2.*T3)))/Vl Z(I)=T12*(T2-T3)*V/(T1*T3)
15 CONTINUE 16 I F ( N N - 1 ) 1 7 , 9 9 9 , 1 8 17 K=8 GO TO 19
18 K=NN-1
19 MAXIM=MAX(K) PRINTING OF HEADINGS AND INPUT VALUES FOR CROSS SECTION TABLES WRITE(6,803 H E ( I I , I = l , K ) WRITE(6,804) WRITE(6,805)TITLE IF(M0DE)999,22,20 20 W R I T E t 6 j 9 0 6 H S I G M A { n , I = l , K ) DO 21 11=1,MAXIM
JJ=II-1 WRITE(6,907)JJ,(A(KK,II1,KK=1,K» 21 CONTINUE GO TO 24 22 WRITE(6,806)(SIGMA(J),J=1,K) DO 23 11 = 1,MAXIM JJ=II-1 WRITE(6,807)JJ,(A(KK,II),KK=1,K) 23 CONTINUE 24 WRITE(6,804) WRITE(6,808) DO 33 L=l,37 IF((L-2)/6*6-L+2)27,25,25 25 IF(L-2)26,27,26 26 WRITE(6,809) FIXATION OF LABORATORY EMISSION ANGLE 27 THETA=(L-1)«5 RAD=THETA*0.017453 COSl=COS
35 36 37 38 999
DO 38 L=l,37 IF((L-2)/6*6-L+2)37,35,35 IF(L-2)36,37,36 WRITE(6,809) THETA=(L-1)*5 WRITE(6,810)THETA,(ENERG(I,L),I=1,K) CONTINUE 60 TO 1 CALL EXIT END
6 1 7
Nuclear Data Tables, Vol. 1 1 . No. 7. 1973
H. LISKIEN AND A. PAULSEN
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D.L.ALLAN
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W.D.ALLEN AND A.T.G.FERGUSON,
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BA57A
E.M.BALABANOV, I.IA.BARIT, L.N.KATSAUROV, ATOMNAYA ENERGIYA SUPPL. 5, 37 (1957)
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PHYS.REV. 107, 1616
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BE46
W.E.BENNETT, C.E.MANDEVILLE, AND H.T.RICHARDS, PHYS.REV. 69, 41R
BL48
J.M.BLAIR, G.FREIER, E.LAMPI, W.SLEATOR,JR., AND PHYS.REV. 74, 1599 (1948) AND BR 57
B056
D.L.BOOTH, G.PRESTON, AND P.F.D.SHAW,
B059
G.F.BOGDANOV, N.A.VLASOV, C.P.KALININ, B.V.RYBAKOV, V.A.SIDOROV, SOV.PHYS.-JETP 9, 440 (1959)
BR49
E.BRETSCHFR
BR51
J.E.BROLLFY,JR.,
J.L.FOWLER,
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AND L.ROSEN, PHYS.REV. 107 , B20
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J.P.CONNER,
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V.A.DAVIDENKO,
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AND A.I.SAUKOV, J.NUCL.ENERGY
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DA58
W.W.DAEHNICK AND J.M.FOWLER,
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W.DEUCHARS, J.L.PERKIN, AND R.BATCHELOR, NUCL.INSTR.METH. 23, 305
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E.A.ELIOT, D.ROAF, AND P.F.D.SHAW,
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F056
J.L.FOWLER
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lU.F.TUTUROV,
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FU57
J.C.FULLER, W.E.DANCE, AND D.C.RALPH, PHYS.REV. 108, 91
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A.GALONSKY AND C.H.JOHNSON, PHYS.REV. 104, 421
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A.S.GANEEV, A.M.GOVOROV, G.M.OSETINSK11, A.N.RAKIVNENKO, V.S.SIKSIN, ATOMNAYA ENERGIYA SUPPL. 5, 21 (1957) J.H.GIBBONS AND R.L.MACKLIN, PHYS.REV. 114, 571
G056
G.V.GORLOV, B.M.GOKHBERG, V.M.MOROZOV, AND V.A.SHIGIN, SOV.PHYS.TECH.PHYS. 1, 964 (1956)
I.V.SIZOV,
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G060A
M.D.GOLDBERG AND J.M. LE BLANC, PHYS.REV. 119, 1992
G060B
L.GONZALEZ, J.RAPAPORT, AND J.J.VAN
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M.D.GOLDBERG AND J.M. LE BLANC, PHYS.REV. 122, 164
G061B
M.D.GOLDBERG, J.D.ANDERSON, J.P.STOERING, AND C.WONG, PHYS.REV. 122, 1510 (1961) (AND PRIVATE COMMUNICATION FROM M.D.GOLDBERG)
618
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(1956)
GI59
Nuclear Data Tables, Vol. 1 1 , No. 7, 1973
(1949)
REVS.MOD.PHYS. 28, 103 (1956)
(1960)
LOEF, PHYS.REV. 120, 1319 (1961)
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AND
NEUTRON PRODUCTION CROSS SECTIONS
REFERENCES FOR EXPERIMENTAL DATA Gn63 HE55 HU*9 JA50 JA56A JA56B KA59 Ke68 KN70 K055 K066 MA58 MA65 MC51 MC73A MI61 NA66 PA64 PA66 PA70 PF59 PF6B PR54 Rn57 SA51 SC72 SE59 Se60 SI68 SM57 ST52 ST56 ST60 TA49 TH66 TH69 TI54 VA57 VL55 V057 We52 WI53 WI60 WI61
M.O.GOLDBFRG, PROGRESS IN FAST NEUTRON PHYSICS, P.3 EDITED BY G.C.PHILLIPS, J.B.MARION, AND J.R.RISSER (UNIVERSITY OF CHICAGO PRESS, CHICAGO, 1963) A.HEMMENDINGER AND H.V.ARGO, PHYS.REV. 98, 70 (1955) G.T.HUNTER AND H.T.RICHARDS, PHYS.REV. 76, 1445 (1949) G.A.JARVIS, A.HEMMENDINGER, H.V.ARGO, AND R.F.TASCHEK, PHYS.REV. 79, 929 (1950) N.J&RMie AND J.0.SEAGRAVE, LA-2014 (1956) G.A.JARVIS, JA56A P.P.KANE, NUCL.PHYS. 10, 429 (1959) R.G.KERR AND J.D.ANDERSON, BULL.AM.PHYS.SOC. 13, 564 (196R) (AND PRIVATE COMMUNICATION FROM M.D.GOLDBERG) H.H.KNITTER (PRIVATE COMMUNICATION) A.T.KORITSKII, DISSERTATION (ACADEMY OF SCIENCES, USSR, 1955) A.P.KOBZEV, V . I .SALATSK 11 , AND S . A.TELEZHNIKOV , SOV.J.NUCL.PHYS. 3, 774 (1966) R.L.MACKLIN AND J.H.GIBBONS, PHYS.REV. 109, 105 (1958) R.L.MACKLIN AND J.H.GIBBONS, EANDC-50-S, VOL.I PAPER 13 (1965) K.G.MCNEILL AND G.M.KEYSER, PHYS.REV. 81, 602 (1951) D.K.MCDANIELS, M.DROSG, J.C.HOPKINS, AND J.D.SEAGRAVE (TO BE PUBLISHED) C.MILONE AND R.RICAMO, NUOVO CIM. 22, 116 (1961) V.NAGGIAR, L.LAFAYE, AND P.BREONCE, NUCL.INSTR.METH. 41, 77 (1966) A.PAULSEN AND H.LISKIEN, NUCL.PHYS. 56, 394 (1964) A.PAULSEN AND H.LISKIEN, PROC.CONF.ON NUCL.DATA FOR REACTORS, PARTS 1966, VOL.1 P.217 (IAEA, VIENNA, 1967) A.PAULSEN (PRIVATE COMMUNICATION) J,e,PERRY, E.HAnOAn, R.I.HRNKEL, G.A.JARVIS, AND R.K.SMITH, SF59 (AND PRIVATE COMMUNICATION FROM J ,1). SF AGRAVF ) A.PFFTKRMANS (PRIVATE COMMUNICATION) G.PRESTON, P.F.O.SHAW, AIMD S.A.YOUNG, PROC.ROY. SOC. ( LONDON ) A?26 , 206 ( 1954) L.ROSEN,JA56A A.R.SAYRES, K.W.JONES AND C.S.WU, PHYS.REV. 122, 1853 (1961) R.L.SCHULTE. M.COSACK. A.W.OBST, AND J.L.WFIL, NUCL.PHYS. A192, 609(1972) (AND PRIVATE COMMUNICATION FKOM J.L.WEiLl J.D.SEAGRAVE, PROC.CONF.ON NUCLEAR FORCES AND THE FEW NUCLEON PROBLEM, LONDON 1959, VOL.11 P.583 (PERGAMON PRESS, OXFORD, 1960) J.D.SEAGRAVE, L.CRANBERG, AND J.E.SIMMONS, PHYS.REV. 119, 1981 (1960) J.E.SIMMONS AND J.J.MALANIFY, BULL.AM.PHYS.SOC. 13, 564 (1968) (AND PRIVATE COMMUNICATION J.E.SIMMONS) R.K.SMITH AND J.E.PERRY,JR., BA57D, F056, JA56A T.F.STRATTON AND G.O.FREIER, PHYS.REV. 88, 261 (1952) L.STEWART, G.M.FRYE,JR., AND L.ROSEN, BULL.AM.PHYS.SOC. 1, 93 (1956) L.STEWART, J.E.BROLLEY,JR., ANO L.ROSEN, PHYS.REV. 119, 1649 (1960) R.F.TASCHEK, G.A.JARVIS, A.HEMMENDINGER, G.G.EVERHART, AND H.T.GITTINGS, PHYS.REV. 75, 1361 (1949) R.B.THEUS, W.I.MCGARRY, AND L.A.BEACH, NUCL.PHYS. 80, 273 (1966) S.T.THORNTON, NUCL.PHYS. A136, 25 (1969) U.TIMM, H.NEUERT, AND B.ELSNER, Z.PHYSIK 139, 425 (1954) A.K.VALTER AND A.P.KLlUCHAREV, BA57B N.A.VLASOV, S.P.KALININ, A.A.OGLOBLIN, L.N.SAMOILOV, V.A.SIDOROV, ANO V.I.CHUEV, SOV.PHYS.-JETP 1, 500 (1955) V.V.VOLKOV, P.E.VOROTNIKOV, E.A.KOLTYPIN, N.I.SIDOROV, AND G.B.IANKOV, ATOMNAYA ENERGIYA SUPPL. 5, 13 (1957) W.A.WENZEL ANO W.WHALING, PHYS.REV. 88, 1149 (1952) H.B.WILLARD, J.K.BAIR AND J.D.KINGTON, PHYS.REV. 90, 865 (1953) W.E.WILSON, D.B.FQSSAN, AND R.L.WALTER, BULL.AM.PHYS.SOC. 5, 410 (1960) (AND PRIVATE COMMUNICATION FROM M.D.GOLDBERG) W.E.WILSON, R.L.WALTER, AND O.B.FOSSAN, NUCL.PHYS. 27, 421 (1961) (AND PRIVATE COMMUNICATION FROM J.D.SEAGRAVE)
619
Nuclear Data Tables, Vol. 1 1 , No. 7 , 1973