Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel

Autor: Hao Yu, Yinbiao He, Xinxin Wu, Shenjie Gu, Xin Liu, Hongchang Wang
Rok vydání: 2022
Zdroj: Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues.
DOI: 10.1115/icone29-90363
Popis: In this paper, the mechanical properties of core forgings in Pressurized Water Reactor (PWR )NPPs in China were studied according to different rules of minimum yield strength at room temperature stipulated in ASME codes and RCC-M codes. First, this paper investigates the origin of two different codes for core forgings, then analyses the effects of yield strength, tensile strength, tempering temperature and toughness on the mechanical properties of forgings in both of codes. And then the results showed that the acceptance value of minimum yield strength at room temperature materials does not correspond to the mechanical design and analysis value. Finally, some suggestions for compiling the c’ore area forgings mechanical properties codes suitable for China’s PWR NPPs were given. This work provided a feasible implementation path for guiding the formulation of China’s PWR NPP codes.
Databáze: OpenAIRE