摘要
田湾核电站1、2号机组是国内引进的首批俄罗斯VVER-1000型机组,其反应堆压力容器内壁焊接有6套辐照监督组件用以监督压力容器材料的辐照脆化状态。由于设计超前因子较低,导致前期辐照监督组件抽取过多,影响机组延寿期间的安全性论证,且当前的抽取计划与机组长周期后的换料大修计划存在冲突,因此通过对现有试验数据的分析,结合理论计算的方法,评估推迟辐照监督组件抽取的可行性,为机组延寿留有更多的监督样品以及使得辐照监督的抽取计划与大大修计划保持一致。
Tianwan NPP Units 1&2 are VVER-1000 introduced from Russia.The inner wall of the reactor pressure vessel is welded with 6 sets of irradiation surveillance specimens to monitor the irradiation embrittlement state of the pressure vessel material.Due to the low leader factor of the design,there is too much extraction of irradiation surveillance specimens in the early stage,which affects safety demonstration during the life extension of the unit,and the current extraction plan conflicts with the refueling and overhaul plan after the long cycle of the unit.In this paper,based on the analysis of existing test data and method of theoretical calculation,the feasibility of postponing the extraction of irradiation surveillance specimens is evaluated,more surveillance specimens are reserved for the life extension of the unit,and the irradiation surveillance extraction plan is consistent with the major repair plan.
作者
马连骥
刘芳
MA Lianji;LIU Fang(CNNP Operation Maintenance Technology Co.,Ltd.,Hangzhou 610041,China;Lianyungang Higher Vocational and Technical School,Lianyungang 222000,China)
出处
《电工技术》
2024年第10期62-66,共5页
Electric Engineering
关键词
反应堆压力容器
VVER
辐照监督组件
脆化效应
reactor pressure vessel
VVER
irradiated surveillance specimens
embrittlement effect