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ASTM Selected Technical Papers
Effects of Radiation on Materials: 17th International Symposium
By
DS Gelles
DS Gelles
1
Battelle Pacific Northwest National Laboratory
?
Richland, WA Symposium Chairman and Editor
Search for other works by this author on:
RK Nanstad
RK Nanstad
2
Oak Ridge National Laboratory
?
Oak Ridge, TN Symposium Cochairman and Editor
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AS Kumar
AS Kumar
editor
3
University of Missouri-Rolla
?
Rolla, MO Symposium Cochairman and Editor
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EA Little
EA Little
editor
4Dept. of Materials Engineering
University College
,
Swansea,
UK
Symposium Cochairman and Editor
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ISBN-10:
0-8031-2016-8
ISBN:
978-0-8031-2016-7
No. of Pages:
1183
Publisher:
ASTM International
Publication date:
1996

The Babcock and Wilcox Owners Group (B&WOG) is sponsoring an on-going study to develop an understanding of radiation embrittlement of Linde 80 reactor vessel welds from a micro-mechanical viewpoint. Previous work that focused on characterizing the large microstructural features indicated that a large portion of the bulk copper content is in precipitate/inclusion/carbide form. This result indicates that copper in solid solution is considerably less than the bulk composition. Field-ion microscope atom probe investigations on unirradiated weld metals with bulk copper contents ranging from 0.22 to 0.38 wt%, also indicate significant amount of copper are tied up in precipitate/inclusion/carbide form. This results is significant since the bulk copper content (which includes both copper in solid solution and copper contained in precipitates, inclusions, and carbides) is used in Regulatory Guide 1.99, Revision 2 to determine radiation damage. This paper reviews these results.

Existing radiation embrittlement models superpose the changes in yield strength due to defect clusters and copper-rich precipitates induced by neutron irradiation. Low-copper Linde 80 welds display little or no increase in the 41 joule (30 ft-lb) transition temperature as a result of neutron irradiation which indicates that precipitation is the dominant component of radiation embrittlement for Linde 80 welds. Future work will include further microstructural characterizations of Linde 80 reactor vessel welds and applying the existing radiation embrittlement models to Linde 80 welds. This paper describes the detailed plans for future work.

1.
Lawless
,
K. R.
,
Pavinich
,
W. A.
,
Lowe
,
A. L.
, “
Microstructural Characterization of Submerged-Arc Weld Metals
,” Effects of Radiation on Materials: 13th International Symposium, ASTM STP 956,
Garner
F. A.
,
Henager
,
C. H.
 Jr.
, and
Igata
N.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1987
, pp. 321–332.
2.
Lawless
,
K. R.
,
Lowe
,
A. L.
, “
Further Microstructural Characterization of Submerged-Arc Weld Metals
,” Effects of Radiation on Materials: 15th International Symposium, ASTM STP 1125,
Stoller
R. E.
,
Kumar
A. S.
, and
Gelles
D. S.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1992
, pp. 186–199.
3.
Lawless
,
K. R.
,
Lowe
,
A. L.
, “
Further Microstructural Characterization of Submerged-Arc Weld Metals — II
,” Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175,
Kumar
A. S.
,
Gelles
D. S.
,
Nanstad
R. K.
, and
Little
E. A.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1993
, pp. 292–305.
4.
Sarver
,
L. W.
,
unpublished work performed on behalf of the B&W Owners Group
,
Babcock & Wilcox Co.
,
Alliance, Ohio
,
1993
.
5.
Vlak
,
W. A. H. M.
,
unpublished work performed on behalf of the B&W Owners Group
.
6.
Brenner
,
S. S.
,
Kowalik
,
J.
,
unpublished work performed on behalf of the B&W Owners Group
,
University of Pittsburgh
,
Pittsburgh, Pa.
,
15
11
1989
.
7.
Nanstad
,
R. K.
,
McCabe
D. E.
, and
Swain
,
R. L.
, “
Irradiation Effects in a Commercial LUS Weld
,” Heavy-Section Steel Irradiation Program, Semiannual Progress Report for October 1990–March 1991, NUREG/CR-5591, Prepared by
Corwin
W. R.
,
04
1994
.
8.
Moore
,
K. E.
,
Heller
,
A. S.
, “
B&W 177-FA Reactor Vessel Beltline Weld Chemistry Study
,” BAW-1799,
Babcock and Wilcox Utility Power Generation Division
,
Lynchburg, Va.
,
07
1983
.
9.
Fisher
,
S. B.
,
Harbottle
,
J. E.
,
Aldridge
,
N. B.
, “
Copper Precipitation in Pressure Vessel Steels
,” CEGB Report in 3 Parts, TPRD/B/0396/N84, TPRD/B/0397/N84, TPRD/B/0398/N84,
1984
.
10.
Fisher
,
S. B.
,
Buswell
,
J. T.
, “
A Model for PWR Vessel Embrittlement
,” CEGB Report, TPRD/B/0745/R86,
01
1986
.
11.
Lucas
,
G. E.
,
Odette
,
G. R.
, “
Recent Advances in Understanding Radiation Hardening and Embrittlement Mechanisms in Pressure Vessel Steels
” Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors,
American Nuclear Society
,
La Grange Park, Illinois
,
1986
, pp345–360.
12.
Odette
,
G. R.
,
Lucas
,
G. E.
, “
Irradiation Embrittlement of LWR Pressure Vessel Steels
,” EPRI NP-6114, Final Report,
Electric Power Research Institute
, Palo Alto, CA,
01
1986
.
13.
Odette
,
G. R.
, et al
, “
The Effect of Flux on the Irradiation Hardening of Pressure Vessel Steels
,” Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175,
Kumar
A. S.
,
Gelles
D. S.
,
Nanstad
R. K.
, and
Little
E. A.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1993
, pp. 292–305.
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