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对反应堆压力容器材料进行辐照监督是保障压力容器在设计寿期内安全运行的一项重要措施,其中,冲击试验是重要组成部分。 秦山核电公司30万干瓦反应堆压力容器用A508-3钢制成,它是一种铁素体低合金钢。筒身段的参考无延性转变温度（RTNDT）低于-20℃。但由于反应堆的中子辐照效应,钢的韧性下降,无延性转变温度上升,钢材性能从韧性向脆性转变,从而增加了压力容器发生脆性断裂的可能性。 辐照监督的目的,在于监测压力容器环带区（即压力容器筒体正对活性区的环带）材料受中子辐照和热环境影响所造成的材料性能变化。根据《辐照监督大纲》,定期从堆内抽出监督试样进行试验,实测冲击韧性试验数据,得到△RTNDT,并用这些数据来确定反应堆开、停堆的压力-温
Radiation supervision of reactor pressure vessel materials is an important measure to ensure the safe operation of pressure vessels during the design life, of which impact tests are an important part. Qinshan Nuclear Power Company 300,000 kilowatts reactor pressure vessel made of A508-3 steel, it is a ferritic low alloy steel. The reference ductile section ductile transition temperature (RTNDT) is below -20 ° C. However, due to the neutron irradiation effect of the reactor, the ductility of the steel decreases, the ductile transition temperature rises, and the performance of the steel changes from ductile to brittle, thereby increasing the possibility of brittle fracture of the pressure vessel. The purpose of radiation monitoring is to monitor changes in material properties caused by neutron irradiation and thermal environment in the pressure zone of the pressure vessel (ie, the zone of the pressure vessel barrel facing the active zone). According to the “Irradiation Supervision Outline”, regular monitoring samples from the reactor were taken out of the test, the measured impact toughness test data, get △ RTNDT, and use these data to determine the reactor open, shutdown pressure - temperature