BWRVIP-140NP: BWR Vessels and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel.

Technical Information Center Oak Ridge Tennessee

关键词: Nuclear power plants;    Light water reactors;    Water reactor vessel;    Crack propagation;    Fracture properties;   

RP-ID  :  DE2005839513

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

To prepare for this project, EPRI and BWRVIP conducted a workshop at Ponte Vedra Beach, Florida during February 19-21, 2003 (EPRI report 1007822). Attendees were invited to exchange relevant information on the effects of irradiation on austenitic materials in light water reactors and to produce recommendations for further work. EPRI reviewed the data, recommendations, and conclusions derived from the workshop and developed prioritized test matrices defining new data needs. Proposals were solicited, and selected proposals are the basis for the program described in this report. Results The planned test matrix for fracture toughness testing includes 21 tests on 5 materials.