Skip Nav Destination
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
eBook Chapter
A Utility Perspective on Management of Reactor Pressure Vessel Embrittlement
By
JS Perrin
JS Perrin
1
Technical consultant
, Public Service Electric & Gas Company
, P.O. Box 236, Hancocks Bridge, NJ 08038
.
Search for other works by this author on:
Page Count:
8
-
Published:1993
Citation
Perrin, J. "A Utility Perspective on Management of Reactor Pressure Vessel Embrittlement." Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume). Ed. Steele, L. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959 : ASTM International, 1993.
Download citation file:
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.
References
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.
This content is only available via PDF.
You do not currently have access to this chapter.
Email alerts
Related Chapters
Characteristics of the IAEA Correlation Monitor Material for Surveillance Programs
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Third Volume)
Irradiation Response and Annealing Behavior of Pressure Vessel Model Steels and Iron Ternary Alloys Measured with Positron Techniques
Effects of Radiation on Materials: 15th International Symposium
Positron Lifetime Characterization of Irradiated Pressure Vessel Model Alloys
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Third Volume)
In-Service Evaluation of French Pressurized Water Reactor Vessel Steel
Effects of Radiation on Materials: 15th International Symposium
Related Articles
Further Results on Attenuation of Neutron Embrittlement Effects in a Simulated RPV Wall
J. ASTM Int. (May,2010)
International Comparison of Impact Reference Materials (2004)
J. ASTM Int. (February,2006)
A Procedure for Extended Extrapolation of Creep Rupture Data
J. Test. Eval. (January,2003)