核电站一回路管道铸造奥氏体不锈钢热老化评估  

Thermal aging evaluation of cast austenitic stainless steel for the primary loop pipe in nuclear power plants

作　　者：王毓[1] 刘江南[1] 王正品[1] 金耀华[1] 曹楠 要玉宏[1] WANG Yu;LIU Jiangnan;WANG Zhengpin;JIN Yaohua;CAO Nan;YAO Yuhong(School of Materials Science and Chemical Engineering,Xi'an Technological University,Xi'an 710021,China)

机构地区：[1]西安工业大学材料与化工学院,陕西西安710021

出　　处：《热力发电》2018年第7期64-68,共5页Thermal Power Generation

基　　金：国家自然科学基金项目(51371132);陕西省光电功能材料与器件重点实验室开放基金项目(2015SZSj-59-7)~~

摘　　要：压水堆核电站中的一回路主冷却剂管道用铸造奥氏体不锈钢(CASS)长期在反应堆环境下服役,面临热老化脆化问题。本文利用时效参数外延法,对其主要用钢Z3CN20-09M钢在长期运行后的热老化脆化程度进行评估,并对材料的使用寿命进行预测。评估结果表明:在时效参数P=3.48的时效状态下,Z3CN20-09M钢中的铁素体发生了调幅分解,产生了热老化脆化倾向;同时,拟合得出该材料在288~327℃服役后的总冲击能量随时效参数P的变化关系,预测冷热腿管道用Z3CN20-09M钢在接近延寿期60满功率运行年限服役是安全的。Cast austenitic stainless steel(CASS)used in main coolant pipes of the primary loop in pressurized-water reactor(PWR)nuclear power plants faces the problem of thermal aging embrittlement after long-time operation in the reactor environment.In this study,the aging parameter extrapolation method is used to evaluate the degree of thermal aging embrittlement and predict the service life of the mainly used Z3CN20-09M steel after long-time operation.The evaluation results indicate that,when the aging parameter P is 3.48,the spinodal decomposition takes place on the ferrite of Z3CN20-09M steels,which results in a thermal aging embrittlement tendency.In the meantime,the relationship between the total impact energy and aging parameter P of the Z3CN20-09M steel after service at 288℃to 327℃is obtained by fitting.It is predicted that the Z3CN20-09M steels used for the cold and hot leg pipe is safe when its extending service life is close to 60 effective full power years.

关 键 词：铸造奥氏体不锈钢 热老化脆化 时效参数外延法 总冲击能量 评估 寿命预测 

分 类 号：TG142.71[一般工业技术—材料科学与工程]