摘要
材料的总体一次薄膜应力强度许用值(Smt)是高温反应堆设备结构设计力学分析的重要判定依据,但美国机械工程师协会(ASME)的规范和法国《快堆核岛机械设备设计和建造规范》(RCC-MR)给出的最长30万小时的Smt不能满足长寿期反应堆的设计要求。本文基于ASME规范给出的30万小时许用应力、预计最小断裂应力及断裂应力系数等材料蠕变性能数据,采用Larson-Miller外推模型成功获得了50万小时长寿期的316不锈钢母材和焊缝的长时蠕变性能,可满足长寿期反应堆的设计要求。
General primary membrane stress(Smt)of material is the important parameter used for the mechanical analysis of high temperature reactor design,and the data of Smt at 300000 hours in the ASME code and RCC-MR code cannot meet the needs of long-life nuclear reactor design.Based on the data of allowable stress intensity(St),expected minimum stress-to-rupture(Sr)and stress rupture factors(R)at 300000 hours in the ASME code,the Smt at 500000 hours of 316 stainless steel base metal and weld required by long-life reactor design are obtained successfully by Larson-Miller extrapolation model.
作者
李长香
莫锦涛
段春辉
Li Changxiang;Mo Jintao;Duan Chunhui(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2020年第5期49-52,共4页
Nuclear Power Engineering
