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秦山第二核电厂1、2号机组的辐照监督试验全部8个批次已经完成。通过不同快中子注量下辐照监督试样的力学试验,得到压力容器材料的强度、延伸率、冲击韧性等的变化值,以及上平台能量和韧脆转变温度变化值。与未辐照材料性能相比,监督管试样均有一定的辐照强化和脆化效应,韧脆转变温度有不同程度的上升,但均低于FIS公式预测值。综合评价认为:2个机组压力容器材料的辐照脆化效应均处于较低水平。
All 8 batches of irradiation supervisory test of Units 1 and 2 of Qinshan No.2 Nuclear Power Plant have been completed. The mechanical tests of supervised samples under different fast neutron fluence were performed to obtain the change of strength, elongation and impact toughness of pressure vessel materials, and the change of energy and ductile-brittle transition temperature of the upper platform. Compared with the unirradiated material, the supervising tube samples had some radiation strengthening and embrittlement effects, and the ductile-brittle transition temperature increased to some extent, but both were lower than the predicted value of FIS formula. The comprehensive evaluation shows that the radiation embrittlement effect of the pressure vessels of the two units is at a low level.