冷却剂环境下应变速率对国产RPV低合金钢疲劳寿命影响的试验研究  

Experimental Study on the Effect of the Strain Rate on the Fatigue Life of Domestic RPV Low Alloy Steel in the Coolant Environment

作　　者：孙海涛 凌礼恭 方可伟[2] 高晨 吕云鹤 孙造占 SUN Haitao;LING Ligong;FANG Kewei;GAO Chen;LYU Yunhe;SUN Zaozhan(Nuclear and Radiation Safety Center,Beijing 100082,China;Suzhou Nuclear Power Research Institute,Suzhou of Jiangsu Prov.215004,China)

机构地区：[1]生态环境部核与辐射安全中心,北京100082 [2]苏州热工研究院有限公司,江苏苏州215004

出　　处：《核科学与工程》2022年第3期625-630,共6页Nuclear Science and Engineering

基　　金：国家重点研发计划“在役核电站重要构筑物及设备材料老化退化行为规律与预测模型研究(2019YFB1900900)”。

摘　　要：为研究分析压水堆核电站冷却剂环境下国产反应堆压力容器低合金钢材料的服役疲劳寿命,在实际反应堆压力容器产品锻件上取样并加工成测试试样,采用高温高压循环水试验回路开展模拟反应堆一回路冷却剂环境的材料疲劳试验,获得了疲劳试验数据和应变速率对低合金钢环境疲劳寿命的影响规律,分析了试验数据与ASME规范平均/设计疲劳曲线的关系,评价了ASME规范设计疲劳曲线和环境疲劳修正系数的适用性。In order to investigate and analyze the fatigue life of the low alloy steel of domestic reactor pressure vessel in pressurized water reactor coolant environment,experimental material was cut down from actual reactor pressure vessel product forgings are sampled and processed into test specimens.Low cycle fatigue tests have been performed using the high temperature and high pressure water fatigue testing system,the fatigue data and the effects of the strain rate on the fatigue life were acquired,and the relationship between testing data and ASME code design/mean fatigue curve was analyzed.The suitability of ASME code design fatigue curve and fatigue life environmental correction factor was evaluated.

关 键 词：环境影响疲劳问题 应变速率 反应堆压力容器 低合金钢 设计疲劳曲线 

分 类 号：TL351.6[核科学技术—核技术及应用]