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ASTM Selected Technical Papers
Effects of Radiation on Materials: 20th International Symposium
By
ST Rosinski
ST Rosinski
1
Symposium Chair and Editor
?
Electric Power Research Institute
?
Charlotte, North Carolina
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ML Grossbeck
ML Grossbeck
editor
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TR Allen
TR Allen
editor
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AS Kumar
AS Kumar
editor
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ISBN-10:
0-8031-2878-9
ISBN:
978-0-8031-2878-1
No. of Pages:
892
Publisher:
ASTM International
Publication date:
2001

The B&W Owners Group (B&WOG) developed the Master Integrated Reactor Vessel Surveillance Program (MIRVP) to encompass all domestic operating pressurized water reactors (PWRs) with reactor vessels that contain Linde 80 submerged-arc welds. These PWRs include the reactor vessels fabricated by Babcock & Wilcox (B&W) that include B&W-designed 177-Fuel Assembly (FA) plants and Westinghouse-designed plants. The B&WOG Reactor Vessel Working Group has sponsored studies over the past several years to develop an understanding of the mechanisms and trends of radiation embrittlement for reactor vessel submerged-arc welds fabricated using Linde 80 weld flux. As part of the MIRVP, a Westinghouse-designed capsule was included to provide a comparison of irradiation data in the Westinghouse neutronic environment with the B&W 177-FA environment. This paper presents the effect of irradiation environment on the embrittlement trends of Linde 80 submerged-arc welds based on mechanical test data available through the B&WOG and the literature, and existing trend curves.

1.
Fyfitch
,
S.
,
Gross
,
L. B.
, and
Lowe
,
A. L.
 Jr.
, “
Master Integrated Reactor Vessel Surveillance Program
,”
BAW-1543
, Revision 3,
B&W Nuclear Technologies, Inc.
,
Lynchburg, Virginia
,
02
1989
.
2.
Harbison
,
L. S.
, “
Master Integrated Reactor Vessel Surveillance Program
,”
BAW-1543
, Revision 4,
B&W Nuclear Technologies, Inc.
,
Lynchburg, Virginia
,
02
1993
.
3.
DeVan
,
M. J.
Supplement to the Master Integrated Reactor Vessel Surveillance Program
,”
BAW-1543
, Revision 4, Supplement 3,
Framatome Technologies, Inc.
,
Lynchburg, Virginia
,
02
1991
.
4.
Safety Evaluation by the Office of Nuclear Reactor Regulation B&W ReportBAW 1543, Revision 3 (TAC NO. 75131),
11
06
1991
.
5.
Stoller
,
R. E.
, “
Modeling the Influence of Irradiation Temperature and Displacement Rate on Hardening Due to Point Defect Clusters in Ferritic Steels
,”
Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175
,
Kumar
A. S.
,
Gelles
D. S.
,
Nanstad
R. K.
,
Little
E. A.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1993
, pp. 394–423.
6.
Odette
,
G. R.
, “
Recent Advances in Predicting Embrittlement of Reactor 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
, pp. 121–130.
7.
Lowe
,
A. L.
 Jr.
 et al
, “
Evaluation of Surveillance Capsule Temperatures
,”
BAW- 2040
,
Babcock &Wilcox
,
Lynchburg, Virginia
,
03
1989
.
8.
McCabe
,
D. E.
,
Nanstad
,
R. K.
,
Iskander
,
S. K.
, and
Swain
,
R. L.
, “
Unirradiated Materials Properties of Midland Weld WF-70
,” NUREG/CR-6249,
United States Nuclear Regulatory Commission
,
10
1994
.
9.
Eason
,
E. D.
,
Wright
,
J. E.
, and
Odette
,
G. R.
, “
Improved Embrittlement Correlations for Reactor Pressure Vessels Steels
,” NUREG/CR-6551,
United States Nuclear Regulatory Commission
,
11
1998
.
10.
Radiation Embrittlement of Reactor Vessel Materials
,”
Regulatory Guide 1.99
, Revision 2,
U. S. Nuclear Regulatory Commission
,
05
1988
.
11.
Draper
,
N. R.
and
Smith
,
H.
, “
Applied Regression Analysis (Second Edition)
,”
John Wiley & Sons
,
New York
,
1981
.
12.
Johnston
,
J.
, “
Econometric Methods (Second Edition)
,”
McGraw-Hill
,
New York
,
1972
.
13.
Vinod
,
H. D.
, and
Ullah
,
A.
, “
Recent Advances in Regression Methods
,”
Marcel Dekker Inc.
,
New York
,
1981
.
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