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ASTM Selected Technical Papers
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume)
By
LE Steele
LE Steele
1
Consulting Professional Nuclear Engineer, Springfield, VA
;
Symposium Chairman and Editor
.
Search for other works by this author on:
ISBN-10:
0-8031-1478-8
ISBN:
978-0-8031-1478-4
No. of Pages:
416
Publisher:
ASTM International
Publication date:
1993

A utility perspective on evaluating and managing radiation embrittlement of pressure vessels is presented in this paper. Included are observations and experiences gained from pressure vessel surveillance capsule programs, and activities on flux reduction through the use of low-leakage core-loading patterns. Also included are pressure vessel embrittlement considerations relating to plant rerating and plant life extension.

1.
Radiation Embrittlement of Reactor Vessel Materials
,” Regulatory Guide 1.99, Revision 2,
U.S. Nuclear Regulatory Commission
,
Washington, DC
,
05
1988
.
2.
Salem Generating Station Units 1 and 2 Updated Final Safety Analysis Report
,” Docket Nos. 50-272 and 50-311,
Public Service Electric & Gas Company
, Hancocks Bridge, NJ.
3.
Yanichko
,
S. E.
,
Lippincott
,
E. P.
,
Albertin
,
L.
, and
Ray
,
N. K.
, “
Analysis of Capsule Z from the Public Service Electric and Gas Company Salem Unit No. 1 Reactor Vessel Surveillance Program
,” WCAP-11955,
09
1988
.
4.
Lucas
,
G. E.
,
Odette
,
G. R.
,
Sheckherd
,
J. W.
,
McConnell
,
P.
, and
Perrin
,
J.
, “
Subsized Bend and Charpy V-Notch Specimens for Irradiated Testing
,” in
The Use of Small-Scale Specimens for Testing Irradiated Materials
, ASTM STP 888,
American Society for Testing and Materials
,
Philadelphia
,
1986
, pp. 305–324.
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