Reactor Primary Coolant System Pipe Rupture Study Progress Report No. 40, April--June 1977

摘要

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. This 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. (ERA citation 03:018103)