Skip to Main Content
Skip Nav Destination
ASTM Selected Technical Papers
Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study
By
LE Steele
LE Steele
1
Head
,
Thermostructural Materials Branch, Material Science & Technology Division, Naval Research Laboratory
,
Washington, D.C.
;
Specialist Meeting Chairman and editor
.
Search for other works by this author on:
ISBN-10:
0-8031-0263-1
ISBN:
978-0-8031-0263-7
No. of Pages:
228
Publisher:
ASTM International
Publication date:
1983

Commercial PWR and BWR power reactors in the United States each contain a series of pressure vessel steel surveillance capsules. These capsules typically contain neutron dosimeters, thermal monitors, Charpy V-notch impact specimens, and tension specimens. These capsules are periodically removed during the life of a reactor and evaluated to determine the effect of radiation on the pressure vessel steel. The pressure-temperature operating curves for the plant are adjusted as necessary by using the surveillance capsule results.

Much valuable information has been obtained from pressure vessel surveillance capsules. There are, however, numerous problems which have been encountered during the examination of these capsules. These problems could lead to a decrease in the amount of useful information obtained from a capsule. Areas in which problems have been observed include the overall surveillance program, capsule design and construction, specimen preparation and documentation, specimen testing and evaluation, and reporting.

Problems typical of those which have been observed are presented. In addition, recommendations for prevention of these problems are made.

1.
Bush
,
S. H.
,
Journal of Testing and Evaluation
 0090-3973, Vol.
2
, No.
6
,
1975
, p. 435.
2.
Steele
,
L. E.
, “
Neutron Radiation Embrittlement of Reactor Vessel Steels
,” Technical Report Series No.
163
,
IAEA
,
Vienna
,
1975
, p. 185.
3.
Perrin
,
J. S.
,
Fromm
,
E. O.
, and
Lowry
,
L. M.
, “
Remote Disassembly and Examination of Nuclear Pressure Vessel Surveillance Capsules
,” in
Proceedings
,
25th Conference on Remote Systems Technology
,
American Nuclear Society
,
Hinsdale, Ill
,
1977
.
4.
Hedgecock
,
P. D.
and
Perrin
,
J. S.
, “
Standards for Materials Behavior Under Neutron-Irradiation
,” presented at the
Fourth ASTM-EURATOM Symposium on Reactor Dosimetry
,
Gaithersburg, Md.
,
03
1982
.
5.
ASME Boiler and Pressure Vessel Code
, Section III, “
Rules for Construction of Nuclear Power Plants
,”
American Society of Mechanical Engineers
,
1981
.
6.
ASME Boiler and Pressure Vessel Code
, Section XI, “
Rules for Inservice Inspection of Nuclear Power Plant Components
,”
American Society of Mechanical Engineers
,
1981
.
7.
Title 10, Code of Federal Regulations, Part 50, “
Licensing of Production and Utilization Facilities
,”
Appendices G and H, U. S. Nuclear Regulatory Commission
.
8.
Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials
,” Regulatory Guide 1.99, Revision 1,
Office of Standards Development, U. S. Nuclear Regulatory Commission
,
04
1977
.
9.
McConnell
,
P.
,
Oldfield
,
W.
,
Oldfield
,
F. M.
, and
Server
,
W. L.
, “
Irradiated Nuclear Pressure Vessel Steel Data Base
,”
Electric Power Research Institute Topical Report
, PR1240-1, Palo Alto, Calif.,
12
1981
.
10.
Hawthorne
,
J. R.
in
Effects of Radiation on Materials: Eleventh Conference
, ASTM STP 782,
Brager
H. R.
and
Perrin
J. S.
, Eds.,
American Society for Testing and Materials
,
1982
, pp. 375-391.
11.
Oldfield
,
W.
,
Journal of Testing and Evaluation
 0090-3973, Vol.
7
, No.
6
,
1979
, pp. 326-333.
This content is only available via PDF.
You do not currently have access to this chapter.
Close Modal

or Create an Account

Close Modal
Close Modal