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ASTM Selected Technical Papers
Irradiation Effects on The Microstructure and Properties of Metals
By
FR Shober
FR Shober
1
Hanford Engineering Development Laboratory, Westinghouse Hanford Company
,
Richland, Wash.
;
symposium chairman
.
Search for other works by this author on:
ISBN-10:
0-8031-0388-3
ISBN:
978-0-8031-0388-7
No. of Pages:
494
Publisher:
ASTM International
Publication date:
1976

Void and dislocation structures in an Fe-25Ni-15Cr alloy were studied following irradiation with 2.8 MeV58Ni+ ions at temperatures between 600 and 750°C (1112 and 1382°F) to maximum damage levels up to 80 displacements per atom (dpa). Void formation was observed at all the temperatures investigated, with the maximum swelling between 650 and 700 °C (1202 and 1292°F). The swelling versus dose relationships exhibited an incubation dose followed by swelling at a rate that increased with increasing damage level. These data were consistent with previous swelling results for austenitic alloys irradiated with charged particles, which indicate that the swelling should become linear with irradiation dose at higher damage levels. Tangled dislocation networks were observed to form at low doses and to be fairly stable up to the highest damage levels examined. With the assumption of the observed stable dislocation networks, the dose dependence of swelling could be explained by a general form of the chemical rate theory for swelling due to void growth.

1.
Manning
,
I.
and
Mueller
,
G. P.
,
Computer Physics Communications
 0010-4655, Vol.
7
,
1974
, pp. 85–94.
2.
Torrens
,
I. M.
and
Robinson
,
M. T.
in
Radiation-Induced Voids in Metals
,
Corbett
J. W.
and
Ianniello
L. C.
, Eds., U.S. Atomic Energy Commission Symposium Series 26,
1972
, pp. 739–756.
3.
Sprague
,
J. A.
,
Review of Scientific Instruments
 0034-6748, Vol.
46
,
1975
, pp. 1171–1173.
4.
Diamond
,
S.
,
Baron
,
I. M.
,
Bleiberg
,
M. L.
,
Bajaj
,
R.
, and
Chickering
,
R. W.
, “
HVEM Quantitative Stereoscopy Through the Full Damage Range of an Ion-Bombarded Fe-Ni-Cr Alloy
,”
Proceedings
, International Conference on Radiation Effects and Tritium Technology for Fusion Reactors,
Gatlinberg, Tenn.
, 1–3 Oct. 1975, to be published.
5.
Makin
,
M. J.
and
Walters
,
G. P.
,
Proceedings
, Symposium on the Physics of Irradiation Produced Voids, Atomic Energy Research Establishment Report R7934,
Harwell, England
, 9–11 Sept. 1974, pp. 299–312.
6.
Johnston
,
W. G.
,
Lauritzen
,
T.
,
Rosolowski
,
J. H.
, and
Turkalo
,
A. M.
, “
The Effect of Metallurgical Variables on Void Swelling
,”
Proceedings
, American Society for Metals Materials Science Seminar on Radiation Damage in Metals,
Cincinnati, Ohio
, 9–10 Nov. 1975, to be published.
7.
Harkness
,
S. D.
and
Li
,
Che-Yu
,
Metallurgical Transactions
 0026-086X, Vol.
2
,
1971
, p. 1457.
8.
Wiedersich
,
H.
,
Radiation Effects
 0033-7579, Vol.
12
,
1972
, pp. 111–125.
9.
Brailsford
,
A. D.
and
Bullough
,
R.
,
Journal of Nuclear Materials
 0022-3115, Vol.
44
,
1972
, pp. 125–135.
10.
Mansur
,
L. K.
,
Okamoto
,
P. R.
,
Taylor
,
A.
, and
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,
Che-Yu
in
Properties of Reactor Structural Alloys After Neutron or Particle Irradiation
, ASTM STP 570,
American Society for Testing and Materials
,
1976
, pp. 272–289.
11.
Sprague
,
J. A.
,
Westmoreland
,
J. E.
,
Smidt
,
F. A.
 Jr.
, and
Malmberg
,
P. R.
,
Journal of Nuclear Materials
 0022-3115, Vol.
54
,
1974
, pp. 286–298.
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