核电厂反应堆压力容器是堆内个可更换的重要部件,保证其安全可靠,对于核电厂口的安全运行具有重要意义。根据《秦山核电站反应堆压力容器材料辐照监督大纲》的要求,在反应堆压力容器中设置辐照监督管,监测反应堆压力容器环带区筒体及焊缝因中子辐照和热环境引起的材质性能变化。定期抽出辐照监督管,实测辐照监督试样延性断裂韧度JIC试验数据,作为判断压力容器材料辐照脆化程度的参考数据,并用于修定反应堆冷却剂压力-温度限值曲线,以防止压力容器发生脆断,从而保证反应堆安全运行。同时为压力容器以及核电厂的寿命评估和延寿积累数 Reactor pressure vessel of nuclear power plant is an important component that can be replaced in the reactor, which is safe and reliable, which is of great significance to the safe operation of nuclear power plant. According to “Qinshan Nuclear Power Plant Reactor Pressure Vessel Material Irradiation Supervision Outline” requirement, set up in the reactor pressure vessel irradiation supervision tube, reactor pressure vessel ring zone tube and weld seam due to neutron irradiation and thermal environment caused by the material Performance changes. The radiation supervisory tube was regularly extracted and the JIC test data of the ductile fracture toughness of the sample under the radiation supervision were measured as the reference data for judging the degree of irradiation embrittlement of the pressure vessel material and used to modify the pressure-temperature limit curve of the reactor coolant to Prevent the pressure vessel from brittle fracture, so as to ensure the safe operation of the reactor. At the same time for pressure vessels and nuclear power plant life assessment and longevity accumulation