Evaluation of Welded and Repair-Welded Stainless Steel for LWR (Light Water Reactor) Service, Quarterly Report January-March 1984.

摘要

The Division of Engineering Technology, U.S. Nuclear Regulatory Commission, is sponsoring a program at Pacific Northwest Laboratory to evaluate welded and repair-welded stainless steel piping for light-water reactor (LWR) service. Stainless steels often become sensitized, or less resistant to stress corrosion cracking (SCC), after undergoing heating and cooling cycles such as those encountered in welding. The weld heat-affected zone (HAZ) is often the site of crack initiation. This program will therefore measure and model the development of a sensitized microstructure and its resultant resistance to SCC in welded and repair-welded stainless steel pipe. The result will be a method to assess the effects of welding variables on the SCC susceptibility of component-specific nuclear reactor welds/repairs. The progress achieved toward this objective during January - March 1984 is described in this report.