Use of Fracture Mechanics in Reactor Vessel Surveillance

[+] Author and Article Information
T. R. Mager, S. E. Yanichko

Pressurized Water Reactor Systems Division, Westinghouse Electric Corp., Pittsburgh, Pa.

J. Basic Eng 93(2), 259-264 (Jun 01, 1971) (6 pages) doi:10.1115/1.3425222 History: Received July 30, 1970; Online October 27, 2010


This paper presents the basis for utilizing fracture mechanics technology based upon data obtained from small Charpy V-notch specimens incorporated in reactor vessel surveillance programs. Included is a brief background on linear elastic fracture mechanics and a discussion of reactor surveillance programs in general. Data obtained from published literature are organized and an empirical approach is proposed to utilize the fracture mechanics technique in surveillance programs. A typical problem is included to demonstrate that the approach discussed can be successfully applied to nuclear pressure vessel safety analysis.

Copyright © 1971 by ASME
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