316不锈钢长时总体一次薄膜应力强度许用值预测方法研究

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。 

Prediction Method for Long-Term Smt of 316 Stainless Steel

General primary membrane stress (S_mt ) 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 (S_t), expected minimum stress-to-rupture (S_r ) 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.