Preliminary Discussion on Comparison and Analysis on Nuclear Power Plant Materials Standards of ASME and RCC-M
This paper is to compare the sections on materials between ASME-BVC and RCC-M code. This paper states the layout structure and the content about NPP materials specified in the two codes and shows the comparison results. This paper emphasizes particularly on the basic differences between two codes; ASME code focuses on fracture toughness requirements for pressure-retaining ferrite materials and RCC-M code focuses on Susceptibility to intergranular corrosion for austenitic and austenitic-ferrite stainless steel.
NING Dong WANG Yongdong Li Hui BAO Zhanggen
shanghai nuclear engineering research and design institute (SNERDI) Shanghai,China SNERDI ShanghaiChina SNERDI Shanghai,China
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-10
2010-05-17(万方平台首次上网日期,不代表论文的发表时间)