Actions for Reactor primary coolant system pipe rupture study. Progress report No. 38, October--December 1976. [BWR] [electronic resource].

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Reactor primary coolant system pipe rupture study. Progress report No. 38, October--December 1976. [BWR] [electronic resource].

Published
Cincinnati, Ohio : General Electric Company, 1977.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 22 : digital, PDF file
Additional Creators
General Electric Company and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The pipe rupture study is designed to extend the understanding of failure-causing mechanisms and to provide improved capability for evaluating reactor piping systems to minimize the probability of failures. Following a detailed review to determine the effort most needed to improve nuclear system piping (Phase I), analytical and experimental efforts (Phase II) were started in 1965. The progress report summarizes the recent accomplishments of a broad program in (a) basic fatigue crack growth rate studies focused on LWR primary piping materials in a simulated BWR primary coolant environment, and (b) studies directed at quantifying weld sensitization in Type-304 stainless steel.
Report Numbers
E 1.99:geap-10207-38
geap-10207-38
Subject(s)
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Note
Published through SciTech Connect.
02/01/1977.
"geap-10207-38"
View MARC record | catkey: 14372783