NUCLEAR ENGINEERINGAND DESIGN 23 (1972) 376 -378
NOR[It-HOLLAND
PUBLISHINGCOMt'A.N
AUTHOR INDEX OF VOLUME 23
Ando, Y , see Ktkuchl
23(1972) 156
Berry, H C, see Dwyer Berry, H C, see Dwyer Brosche, D , ZOCO V, a computer code for the calculation of time- and space-dependent pressure dlsmbutaons m reactor containments Bukur, D B , H S Isbin, Numerical solution of the Yamanouchi model for core spray cooling Burke, O W, see Sanathanan
23(1972)273 23(1972)295
Carthew, C W, F A Knautz, G T Chan, The design of the vacuum building for P:ckermg generating station Chan, G T , see Carthew Chen, S, Flow-reduced m-plane mstablhtles of curved pipes Chdton, A B , see Green Chflton, A B , E E Morns, Shaeldlng effectweness of ribbed slabs against gamma radmtlon Part II Engmeermgmethods Clark, F H, see Sanathanan
23(1972) 239 23(1972) 196 23(1972)321
23(1972) 199 23(1972) 199 23(1972) 29 23(1972)359 23 (1972)367 23(1972)32l
Doms, J M, H Goller, A mathematical model of control rod drop Dwyer, O E , H C Berry, Heat transfer to llqmd metals flowing turbulently and longitudinally through closely spaced rod bundles Part I Dwyer, O E , H C Berry, P J Hlavac, Heat transfer to hquxd metals flowing turbulently and longltudlnaUy through closely spaced rod bundles Part II Uniform heat flux at the inner surface of the cladding
23 (1972) 107
Eafler, W, see N11slng Ercoh, R , see Laura
23 (1972) 331 23 (1072) I
Farmer, F R , Uncertainty and risk in nuclear power plant design Forghlerx, R , G Papa, Transient heat transfer through a thin-walled circular pipe France, D M, T Glnsberg, Comparison of single and multlcell heat-transfer analyses near nuclear reactor assembly walls
23 (19"72) 236 23 (1972) 147
Gmsberg, T , see France Godfrey, D A , M M Moussa, Dynamic analysis of axlsymmetnc shells under arbitrary transient pressures Goller, H , see Donls Green, D W, E E Morris, K Prmss, A B Chllton, Shielding effectiveness of ribbed slabs against gamma radiation Part I Experimental and theoretical stu&es Grossman, R J , L J Hamilton, Vibration amplification by repetitive pulsing of rapidly heated cyhnders Gwaltney, R C, Localized loads applied to torlsphencal shells
23 (1972) 141
23(1972) 273
23 (1972) 295
23 (1972) 141
23 (1972) 188 23 (1972) 107 23 (t972) 359 23 (1972) 39 23 (1972) 53
377
Author index of volume 23
Hamtlton, L.J., see Grossman Hartma, Y, Y. Nishiwaki, An approxtmaUon of 7-ray buildup factors by geometrical progressaon Hams, R.W, The measurement of mechanical integrity m a reactor fuel element by the analysis of external vlbratmn signals I-hrao, S., see Ohmae Hlavac, P.J, see Dwyer Hungerford, H.E., Studies on engineering and economic aspects of a new iron mortar matenal for reactor slueldmg
23 (1972) 39 23 (1972) 210 23 (1972) 183 23 (1972) 309 23 (1972) 295 23 (1972) 347
Isbm, H.S, see Bukur
23(1972) 196
Kaneto, K., see Ohmae Ktkuclu, F., Y. Ando, Some fimte element solutions for plate bending problems by stmphfied hybnd &splacement method Knautz, F.A., see Carthew
23 (1972) 86 23 (1972) 156 23 (1972) 199
Laura, P A, R. Ercoh, A solution for the unsteady diffusion equation in an arbitrary, doubly connected regmn
23 (1972)
1
Mormo, A, see Ohmae Morris, E.E, see Green Morris, E.E., see Chflton Moussa, M.M., see Godfrey
23 (1972) 23 (1972) 23 (1972) 23 (1972)
309 359 367 188
Nagel, H., L. Wolf, Eme NidaerungsliSsungfur den thermlsehen Emlauf bet Kolbenstromung m einem sechsecktgen Kanal fOr den Fall konstanter W~mestromchchte am Kanalumfang Nakao, N., see Ohmae Nijsmg, R., W Elfler, Axially varying heat flux effects in tubes, fiat ducts and widely spaced rod bundles cooled by a turbulent flow of liquid metal Nlsluwakl, Y, see Hartma
23 (1972) 10 23 (1972) 309 23 (1972) 331 23 (1972) 210
Ohmae, K., A Ohtsukl, K. Kaneto, Fast reactor core deformatton due to stainless steel swelling and thermal bowing with trradiatlon enhanced and thermal creep Ohmae, K., A. Mormo, N. Nakao, S. Hirao, Channel deformation analysis for fast reactor fuel assemblies undergoing swelling and thermal bowing Ohtsukl, A, see Ohmae Olds, F.C, The energy muation
23 (1972) 309 23 (1972) 86 23 (1972) 121
Papa, G., see Forghlen Prelss, K., see Green
23 (1972) 147 23 (1972) 359
Sanathanan, C.K., A.A. Sandberg, F.H. Clark, O.W. Burke, R.S. Stone, Dynamic modeling of a large once-through steam generator Sandberg, A.A., see Sanathanan ShaddL M.U., Lead sluelding calculations for transport containers for commonly used radioisotopes Stone, R.S., see Sanathanan
23 (1972) 86
23 (1972) 321 23 (1972) 321 23 (1972) 229 23 (1972) 321
378
4uthor mdex of volume 23
Wolf, L , see Nagel Wright, W B , Lmear and nonhnear thermal gradients -- an interpretation of the nuclear components code - section III
23 (1972)
10
2 3 ( 1 9 7 2 ) 180