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ASTM Selected Technical Papers
Effects of Radiation on Materials: 15th International Symposium
By
RE Stoller
RE Stoller
1
Oak Ridge National Laboratory
,
Oak Ridge, Tennessee
;
chairman and editor
Search for other works by this author on:
AS Kumar
AS Kumar
2
University of Missouri-Rolla
,
Rolla, Missouri
;
cochairman and editor
Search for other works by this author on:
DS Gelles
DS Gelles
3
Battelle Pacific Northwest Laboratory
,
Richland, Washington
;
cochairman and editor
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ISBN-10:
0-8031-1477-X
ISBN:
978-0-8031-1477-7
No. of Pages:
1339
Publisher:
ASTM International
Publication date:
1992

Tension tests and fractography were used to examine the radiation-induced evolution of Cu-5Ni and three commercially prepared precipitation-strengthened alloys after irradiation in the Fast Flux Test Facility (FFTF) at 684 and 800 K. The addition of nickel to copper resulted in increased ductility prior to irradiation but decreased ductility after irradiation. The postirradiation difference appears to arise from the influence of nickel on void swelling.

The precipitation-strengthened alloys in general exhibited drops in yield strength after irradiation and increased ductility. The major effect appeared to be related primarily to overaging of the precipitates (radiation-enhanced recrystallization).

1.
Brager
,
H. R.
,
Heinisch
,
H. L.
, and
Garner
,
F. A.
, “
Effects of Neutron Irradiation at 450°C and 16 dpa on the Properties of Various Commercial Copper Alloys
,”
Journal of Nuclear Materials
, Vols.
133–134
,
1985
, pp. 676–679.
2.
Brager
,
H. R.
, “
Effects of Neutron Irradiation to 63 dpa on the Properties of Various Commercial Copper Alloys
,”
Journal of Nuclear Materials
, Vols.
141–143
,
1986
, pp. 79–86.
3.
Brager
,
H. R.
, “
Microstructural Evaluation of Commercial Copper Alloys Irradiated in FFTF to 16 dpa at 450 C
Journal of Nuclear Materials
, Vols.
141–143
,
1986
, pp. 163–168.
4.
Anderson
,
K. R.
, “
Unusual Tensile and Fracture Behavior of Pure Copper at High Levels of Neu tron-Induced Swelling
,” this symposium.
5.
Anderson
,
K. R.
,
Garner
,
F. A.
,
Hamilton
,
M. L.
, and
Stubbins
,
J. F.
, “
Tensile Properties and Frac ture Behavior of Dispersion Strengthened Copper Alloys Irradiated in FFTF-MOTA
,” DOE/ER-0313/7,
Department of Energy
,
Washington, DC
,
1989
.
6.
Anderson
,
K. R.
, Ph.D. thesis,
University of Illinois
, Urbana,
1990
.
7.
Panayotou
,
N. F.
,
Atkin
,
S. D.
,
Puigh
,
R. J.
, and
Chin
,
B. A.
, “
Design and Use of Nonstandard Tensile Specimens for Irradiated Materials Testing
,”
The Use of Small-Scale Specimens for Testing Irradiated Materials
, ASTM STP 888,
Corwin
W. R.
and
Lucas
G. E.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1986
, pp. 201–219.
8.
Gallagher
,
P. C. J.
, “
The Influence of Alloying, Temperature, and Related Effects on the Stacking Fault Energy
,”
Metallurgical Transactions
, Vol.
1
,
1970
, pp. 2429–2461.
9.
Zinkle
S. J.
,
Kulcinski
,
G. L.
, and
Mansur
,
L. K.
, “
Radiation-Enhanced Recrystallization in Copper Alloys
,”
Journal of Nuclear Materials
, Vols.
141–143
,
1986
, pp. 188–192.
10.
Livak
,
R. J.
,
Zocco
,
T. G.
, and
Hobbs
,
L. W.
, “
Neutron Damaged Microstructures of High-Con ductivity Copper Alloys
,”
Journal of Nuclear Materials
, Vol.
144
,
1987
, pp. 121–127.
11.
Appello
,
M.
and
Fenici
,
P.
, “
Effect of Proton Irradiation on Tensile Properties of Cu and a Cu-Cr-Zr Alloy
,”
Journal of Nuclear Materials
, Vol.
152
,
1988
, pp. 348–350.
12.
Lee
,
A. K.
and
Grant
,
N. J.
, “
Properties of Two High Strength, High Temperature, High Conduc tivity Copper Basal Alloys
,”
Materials Science and Engineering
, Vol.
60
,
1983
, pp. 213–223.
13.
Lee
,
T. -S.
,
Hobbs
,
L. W.
,
Kohse
,
G.
,
Ames
,
M.
,
Harling
,
O. K.
, and
Grant
,
N. J.
, “
Microstructural Evolution and Swelling of High Strength, High Conductivity RS-PM Copper Alloys Irradiated to 13.5 dpa with Neutrons
,”
Journal of Nuclear Materials
, Vols.
141–143
,
1986
, pp. 179–183.
14.
Lee
,
A. K.
, Ph.D. thesis,
Massachusetts Institute of Technology
, Cambridge, MA,
1984
.
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