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

Hao Yu, Yinbiao He, Xinxin Wu, Shenjie Gu, Xin Liu, Hongchang Wang
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Abstract

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.
反应堆压力容器核心锻件力学性能规范对比研究
本文根据ASME规范和RCC-M规范对压水堆(PWR)核电站堆芯锻件的室温最小屈服强度的不同规定,对其力学性能进行了研究。本文首先研究了两种不同核心锻件规范的起源,然后分析了屈服强度、抗拉强度、回火温度和韧性对两种规范中锻件力学性能的影响。结果表明,材料在室温下的最小屈服强度接受值与力学设计分析值不一致。最后,对编制适合中国压水堆核电机组的区域锻件力学性能规范提出了建议。该工作为指导中国压水堆核电机组规范的制定提供了可行的实施路径。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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