Irradiation Surveillance of RPV for Unit 1&2 of QinshanⅡNPP
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摘要: 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。Abstract: Tests for all 8 irradiation capsules of unit 1&2 of QinshanⅡNPP were finished. Variation of strength, elongation and impact toughness of RPV steels with different fast neutron fluence was acquired. Upper shelf energy and ductile-to-brittle transition temperature(DBTT) shift were evaluated. Compared with non-irradiated materials, irradiation embrittlement effects were found in all specimens in irradiation capsules. DBTT shifts were lower than predicted value by FIS formula. Results showed that embrittlement effect of RPV steels for both units was relatively in low range.
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