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REVIEW ARTICLES: Session II: Nuclear Power Plants

Radiation Embrittlement Mechanistic Modelling

[+] Author and Article Information
W. A. Pavinich

Grove Engineering, 9040 Executive Park Drive, Suite 218, Knoxville TN 37923

W. L. Server

ATI Consulting, 2010 Crow Canyon Place, Suite 160, San Ramon CA 94583

T. J. Griesbach

Electric Power Research Institute, 3412 Hillview Avenue, Palo Alto CA 94303

Appl. Mech. Rev 46(5), 162-170 (May 01, 1993) (9 pages) doi:10.1115/1.3120326 History: Online April 29, 2009

Abstract

The mechanistic models of radiation embrittlement for reactor vessel steels are reviewed and direction for improving these models is provided. Improvement in these mechanistic models will lead to predictive expressions for parameters of engineering interest. This paper provides the initial direction of modelling efforts that will improve existing or develop new predictive equations for damage attenuation, temperature effects, thermal annealing, the effect of post weld heat treatment, transition behavior and upper shelf behavior of reactor vessel steels.

Copyright © 1993 by American Society of Mechanical Engineers
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