核安全2024，Vol.23Issue(2)：59-64,6.
核级17-4PH不锈钢小型部件去污与热老化评估
Decontamination and Thermal Aging Evaluation of Small Nuclear Grade 17-4PH Stainless Steel Components
摘要
Abstract
The pressurizer spray valve used in pressurized water reactor is an important part of adjusting the pressure of the pressurizer,its stem material is 17-4PH,which faces the problems of surface contamination and thermal aging in this service environment.The feasibility of removing the activation layer by surface processing was studied,and the thermal aging of small parts was studied after being lengthened by electron beam welding technology.The results show that the effect of surface processing to reduce the radioactivity is effective and can meet the management requirement,the electron beam welding ensures the mechanical strength of the welding sample,and the thermal aging experiment shows that the valve stem has an obvious risk of thermal aging in this service environment.Through decontamination,welding,and mechanical property analysis,it is proved that this evaluation process can be used for thermal aging evaluation of contaminated nuclear power small components.关键词
17-4PH/去污/电子束焊接/热老化Key words
17-4PH/decontamination/electron-beam welding/thermal aging分类
能源科技引用本文复制引用
李乾武,陈开,万璟,史芳杰,杨广宇..核级17-4PH不锈钢小型部件去污与热老化评估[J].核安全,2024,23(2):59-64,6.基金项目
国家重点研发计划:核电站重要设备部件先进智能老化监检测技术开发与验证,项目编号:2020YFB1901500 （）
