597
Journal of Nuclear Materials 122 & 123 (1984) 597-601 North~Ho~d, Amsterdam
IN-SITU MICROSTR~CTURA~OBSERVATION Of RABIATION DAMAGE IN NICKEL PRODUCED BY ENERGETIC HEAVY PARTICLES* Shiori ISHINO, Koji FUKUYA,** Takeo MUROGA, Naoto S~KINURA and Hiroshi KAWANISHI Department of Nuclear engineering,The Univeristy of Tokyo, Hongo, Bunkyo-ku, Tokyo 113, Japan Microstr~c~uralchanges during 300 and 400 keV Ar+ irradiation in pure nickel between 300 and 773 K have been observed in-situ in an electron microscope. Some of the observations are recorded on a video tape. Various phenomena characteristicof cascade damage have been observed. Clustering of point defects is influenced strongly by the presence of point defects s’tnks: surfaces, pre-existing dislocations,loops and cavities. Wedge-shapedspecimens are utilized to sort out the complex behavior of microst~ctural evofutfon. Of great interest is the fact that under certain conditions, metastable defect clusters with a very short lifetime are formed durina irradiation at 773 K. The implication of these observationsto fusion neutron damage modeling is discussed. similar to that produced by 14 MeV neutrons.
I. INTROBUCTION Because of the nonexistenceof intense fusion
Cascade damage has been known to have a
neutron sources, it is of great importance for
pronounced effect on void swelling by the for-
radiation damage studies of fusion reactor mate-
mation of vacancy clusters. The structure of
rials to establish correlation of data obtained
cascades and subcascades has been studied
with existing radiation sourcest ffssion reac-
extensively by observing collapsed vacancy
tors, accelerators, HYEMs and so on, to the case
loops.4 However, recent observations indicate
of fusion reactors. The correlation should be
that there are other types of phenomena which
based on physical modeling of microstructural
are characteristicsof cascade damage, espe-
and microchcmical evolution during irradiation.
cially when the cascade is produced near point
However, the data, except those obtained by
defect sinks.3,B*S Some of these phenomena
HVEMs, are "snap shots.fi Continuous observation
have been treated by computer simulation calcw-
of damage evolution during heavy particle irra-
lations.7 The present study will proceed along
diation is highly desirable, since cascade
this line in more detail by using pure
damage produced by energetic heavy particles is
specimens. Emphasis will be placed on vacancy
one of the characteristicfeatures of fusion
loop for~tion near defect sinks such as sur-
neutron radiation damage.
nickel
faces and dislocations. The results will be
We have built a facility for in-situ observa-
compared with those obtained in pure aluminum
tion of radiation damage by heavy particles by
as well as those by computer simulations.
combinfng a 400 kV heavy ion acceleratorwith a
These results will provide a useful basis for
200 kV electron microscope.I-3 The facility
analyzing the results obtained by 14 MeV neu-
provides heavy ions with a range of PKA energies
tron irradiationsusing the RTNS-II facility.
*This work supported by Grant-fn-Aid for Pusfon Research from the Ministry of Education, Science and Culture. **Present address: Toshiba Corporation* Nuclear engineering Laboratory, Kawasaki, Japan. 0022-3115/84/%03.00 (North-Holland
0 Elsevier Science Publishers Physics Publishing Division)
B.V.
598
S. Ishino et al. / Observation of radiation damage in nickel
2. EXPERIMENTAL
TECHNIQUES
3. RESULTS AND DISCUSSION
2.1 Specimen The material
3.1 Cascade-dislocation used in this study is MARZ
Figure 1 shows microstructural
Grade nickel foil of 50 pm thickness with 99.995% purity,
purchased
search Corporation. weight ppm:
Re-
The specimens
CR:~. at 1173 K for 1
hr in a vacuum of 3x10-5 Pa and then cut out into discs of 3 mm in diameter. electropolished Tenupole
with a solution
electropolishing
by a apparatus
of 20 vol.% of perchloric
facility
elsewhere.I,6
2.3 Irradiation
us to
goniometer
microscope,
is observed
in self-ion-
at room temperature,3
in
has been
to be of vacancy type because with electrons
is irradiated
observation
placed inside the electron with 300 or 400 keV
on the specimen
The beam intensity
simulation
subse-
annihilates
also suggests
growth of vacancy clusters especially
the equivalent
temperatures
The ion
at an angle of
enhanced
near dislocations,
in the case of cascade
damage, at
where the vacancy
becomes finite but not too high.7
fact, in the present experiment,
on a high temperature
Ar+ ions at 300, 573, 673 and 773 K.
enon is most prominent
at 673 K, being much
less at 573 K because of low vacancy mobility as well as at 773 K because of the high emission rate of vacancies interesting
from clusters.
to note that according
It is
to tempera-
ture scaling by T/Tm or by T/Emv, 673 K in
cal-
using the EDEP-1 code are given in
Table 1. Dislocations fraction
are imaged under two beam dif-
conditions
reflections.
using (111) or (220) type
The thickness
of the specimen
estimated
by counting
Table 1.
Range and damage parameter
I nc
r
ent
equal thickness
is
fringes. for nickel. eV
8 x 1O-4
8.6 x 10-4
Depth of damage peak, nm
65
90
Mean range, nm
110
150
Peak damage rate in d s/s per 1 mA/m B
In
such a phenom-
ranges from 0.18 to
The range and damage parameters
2.0 mA/m2.
aluminum
quent irradiation
mobility
changes.
and microscopic
mounted
single-tilt
culated
facil-
A video
parts of the specimen and to
record rapid microstructural
70-90".
irradiated
A computer
system has been added, enabled
beam is incident
apparent only on one side of the dislocation.
estimated
acid
The details of the in-situ observation ity have been described
The specimen,
and a loop denuded zone becomes
the cluster.
2.2 In-situ observation
observe thicker
the
after starting
which the nature of the cluster
in acetic acid.
recording
disloca-
tion line immediately
A similar phenomenon
They are then
for TEM observations
twin-jet
Loops are formed near a pre-existing
irradiation,
are annealed
at 673 K with
a peak dose rate of 5x10-4 dpa/s to 0.1 dpa.
are, in
C:15, O:lZ, N:5, Mg:2, Si:17,
Cr:2, Fe:20, Sn:1.2,
changes
during a 400 keV Ar+ irradiation
from Materials
Major impurities
interaction
Fig. 1.
Microstructural changes of Ni irradiated with 400 keV Ar+ at 673 K.
S. Ishino et al. / Observation
nickel corresponds
to room temperature
num, where Tm is the melting
1.1 and 0.62 eV are assumed
in alumi-
temperature
and Emv is a vacancy migration
energy,
of radiation
for nickel and alumi-
that the phenomenon
is caused by cascade-dislocation that the clusters vacancy
shown in Fig. 1 interaction
around the dislocation
type formed due to preferential
tion of interstitials a mechanism copper.8
However,
to dislocations irradiation
absorp-
by the dislocation.
has been confirmed
and
are of
Such
in HVEM-irradiated
small loops being attached
in nickel after 14 MeV neutron
at 473 K using RTNS-II have been con-
firmed to be of interstitial
type.9
low dose neutron
in copper and other
metals
irradiation
has indicated
dislocations
Similarly,
that the loops around the
are of interstitial
type.10
fore, the nature of the small clusters
There-
still
of surface sinks
As a measure free zone width irradiation
is plotted
the thickness
importance
as a function of
distance
tion is 34.9 nm.
evolution
depends strongly especially
This indicates
on
an increasing
of the effect of the surface at
Here,
from the (2001 reflecin part
is thinner than 150 nm,
do not have an area1 density proportional the specimen
thickness.
to
Instead, the area1
density shows a maximum
at the region about 70
nm thick, and decreases
gradually
about 150 nm.
to zero at
The loops are considered
of the vacancy type produced effect of the surface
to be
by a strong sink
for interstitials.
On the other hand, in a region with a thickness greater than 200 nm, interaction interstitial dislocation
arrangement,
which
is common to
Between the two regions, interaction
as described
recombination,
location
However,
enhances
mostly
if the dislocation the presence
formation.
by
were
of the dis-
the local interstitial
thereby enhancing
vacancy cluster
in
In this region, point
defects might have been annihilated
strength,
among
loops gives rise to a tangled
bulk specimens.2
not present.
at
of a
with 400 keV
The loops, appearing
of the specimen which
mutual
as shown in Fig. 2.
of the specimen,
high temperature.
defect-
irradiated
Ar+ to a peak dose of 0.1 dpa at 673 K.
3.1 is most prominent.
of surface sink strength,
temperature
Microstructural
specimen
dislocation-cascade
remains to be clarified. 3.2 Effect
even deep inside the speci-
Figure 3 shows the microstructure
wedge-shaped
the extinction
num, respectively. We believe
higher temperatures men.
in K
for which
599
damage in nickel
sink
the chance of Here again, the
small loops are formed only on one side of the dislocation.
6or-----l
Dependence thickness
200
400
600
of microstructural
changes
on the
at 773 K is surmnarized in Table 2.
800
IRRADIATIONTEMPERATURE (K) Fig. 2.
Fig. 3. Temperature zone width.
dependence
of defect-free
Microstructure of wedge-shaped specimen of nickel irradiated with Ar+ at 673 K.
600
S. ishino
Table 2. Region
et al. / Ohservation
Change of microstructure
Thickness,nm
I
<
Defect
80-100
thicker
IV
Pusslble -.
than
III
at 773 K.
s,echanls,,,
~_ ._ __
___.___ vacancy stage of defect
Annihilation of fnrerstirials at surfaces facilitates formation of metastsble vacancy clusters originating from a high vacancy concentration in a cascade.
Interstitial loop growth Lo 50s60nm, then diminishing I” size. finally disappearing. Form&Ion of cavities afLer Iloop size reaches maXll”U,“. Formation of unstable vacancy clusters at a dose when I-loop size reaches maxuwm.
< 120 -200
III
damage in flickel
during 300 keV Ar+ irradiation
structure
Forniatlon of unstable clusters at the early Irradiation. No stable
<100~150
II
of radiation
Super~satilratlon cavity formdtlon.
Of
“aCPllc,es
results
I,,
‘This provides new sinks for both 1 and V and the stability of I-loop 15 gradually lost by abs”rblr,g vacancies. 00s.~ of appearance of unstable vacancy clusters corresponds to maxlmun, vacancy supersaturation.
Growth of lnterstltlal loops, some of which interact with each other to form coarse tangllng.the others reach maximum in size and finally dlsCavities or Ar bubbles appear. and unstable vacancy clusters are observed as in Region II.
Some of the dlslo‘atlon-like contrast the coarse tangling may arise from surface marking, produced by prevention of annihllatlon of dislocations moved the surface by oxide layer. Other mechanisms are the sane as Region II.
Most of the interstitial loops grow to form dense dislocation tangling as shown I” an ordinary bulk specimen.
As
1”
a bulk
sprclmen,
formatlo,,
of
in
to
I-
loop prevails. Density of tangled dislocations depends on number density of I-loops. When the tangling is dense. vacancy supersaturation 1s kept low and less chance of cavity formation results.
Two things may be pointed out as interesting
They cannot be attributed
phenomena;
since they can also be observed
in region II.
The frequency
cluster
first, the interstitial
a certain
size and then become unstable
the growth of cavities. a function
a formation
of irradiation
of metastable
will be described 3.3 Metastable Metastable
time for two individ-
been observed
are only observed
taken every 0.5 set from
screen.
The specimen
peak damage rate of l.2xlO-3
dpa/sec at 773 K.
clusters vacancy
As
small dots with size less
than about 5 nm are generated and disappear
is in
with the
peak damage is 2.3 dpa.
shown by the circles,
with a typical
in a flashy way lifetime of one
A few of them survive
We believe
Figure 5 shows
and is being irradiated
The accumulated
5, the frequency
for 15-30 seconds.
that they are metastable
vacancy
formed by a sudden increase of concentration
triggered
by a cascade.
forma-
to be propor-
In the case of
of the occurrence
of
the event is of the order of 1014/m2 set, which
sec.
at 673 K or below.
the video monitor
Figure
vacancy cluster
No such event has
confirmed
tional to the beam current.
is roughly
at 773 K.
to argon clusters
of the metastable
tion is qualitatively
in the next subsection.
a series of photographs
region III,
A second point is
vacancy clusters which
defect clusters
during irradiation
due to
Change of loop size as
ual loops is shown in Fig. 4.
second.
loops grow to
l/100 of the flux of 8.7xlOI5/m2
The local conditions
for the clusters
to
be formed may require that a strong sink bias for interstitials
should exist, and that the
size of the cascade should be large enough so that the clustering vacancies
could surmount
the loss of
by thermal emission.
3.4 Correlation
to fusion reactor conditions
The results described
above show that phe-
nomena in heavy ion irradiation
can be similar
to those observed
in neutron irradiated
rials, indicating
that the basic cascade pro-
cesses are similar
mate-
in both irradiations,
that the ion irradiation applied to mechanistic
studies.
However,
have to be well aware of the limitations; example,
the distortion
and
can be successfully we for
of defect distributions,
S. Ishino et al. / Observation
of radiation
601
damage in nickel
0.2
200
0
600
400
pm
800
IRRADIATION TIME (set)
Change of individual
Fig. 4.
especially implanted ments.
loop size at 773 K.
at high temperature,
the effect of
atoms, helium and other alloying
In the case of alloys, segregation
alloying
elements
of radiation
is one of the central
effects
eleof
issues
and must be clarified
Fig. 5. Unstable clusters of point defect (circled constant) observed during bombardment width 300 keV Ar+ ions at 773 K in Ni. The specimen has been bombarded to 2.3 dpa. The displacement rate is 1.2~10'~ dpaJsec. The time interval between snap shots is 0.5 sec.
in
2. K. Fukuya, H. Kawanishi and S. Ishino, J. Nucl. Mater. 1038104 (1981) 1385. 3. T. Muroga, K. Fukuya, H. Kawanishi and
the near future.
S. Ishino, J. Nucl. Mater. 1349. 4.
1036104
(1981)
CONCLUSIONS
(1) Cascade-dislocation
in nickel
at 673 K is similar
to that in aluminum
at 300 K, suggesting
similar phenomena
occurs (2)
interaction
at the same homologous
The stability
depend on the total sink strength
itself as exemplified interstitial (3)
deter-
defect structure by the behavior
of
loops at 773 K.
At 773 K, metastable with a typical
vacancy clusters
lifetime
of 1 second have
been found by video recording
Yamada Conf. V, Point Defects and Defect Interactions in Metals, eds. J. Takamura, M. Doyama and M. Kiritani (Univ. of Tokyo Press, 19821 799.
temperature.
of the defect is shown to
mined by the evolved
4. B. L. Eyre and C. A. English, Proc.
techniques.
6. S. Ishino, H. Kawanishi, K. Fukuya and T. Muroga, IEEE Trans. Nucl. Sci. NS-30 (1983) 1255. 7. T. Muroga and S. Ishino,
J.
Nucl. Mater.
117 (1983) 36.
8. M. Suehiro, N. Yoshida and M. Kiritani, Proc. Yamada Conf.,
ibid., 795.
9. M. Kiritani, N. Yoshida and S. Ishino,
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5. C. A. English, J. Nucl. Mater. 108&109 (1982) 104.
this volume. and K. Grant-
1979).
10.
I. M. Robertson, M. L. Jenkins and C. A. English, J. Nucl. Mater. 108&109 (1982)
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