Review of current literature related to Generic Safety Issue 15
- 1 July 1990
- report
- Published by Office of Scientific and Technical Information (OSTI)
Abstract
Recent evaluations of surveillance samples in the High Flux Isotope Reactor at the Oak Ridge National Laboratory led to the conclusion that the embrittlement rates of several reactor pressure vessel (RPV) steels may be greater than originally anticipated. In June 1987, the Advisory Committee on Reactor Safeguards requested that the US Nuclear Regulatory Commission investigate the consequences of embrittlement of RPV supports. This report summarizes the current literature related to these studies, evaluates their contribution toward resolving Generic Safety Issues 15 concerning material embrittlement, and recommends any further action considered appropriate. This review also contains a short discussion of the uses of structural mechanics and fracture mechanics to analyze embrittlement. 15 refs., 1 fig., 3 tabs.Keywords
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