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为了保障核电站的安全运行,需要在反应堆核岛内放入监督管,监督管内放有测试力学性能的试样,定期抽取出来进行力学性能测试,以检验反应堆压力容器材料的辐照脆化趋势;同时,利用试验数据来修订反应堆冷却剂压力-温度限值曲线。本次试验的是恰希玛第2根监督管,本次监督管中的试样在堆内经历了第1循环至第4循环,从2000年5月3日—2007年2月15日,反应堆运行了1889d、1609等效满功率天(EFPD)。本次分别对压力容器材料的冲击性能、断裂力学、及最高辐照温度进行了试验和检验,利用试验结果对反应堆冷却剂压力-温度限值曲线进行了修订。
In order to ensure the safe operation of nuclear power plants, it is necessary to put supervision and control instruments in the reactor nuclear island, and to test the mechanical properties of the reactor pressure vessels to test the radiation embrittlement tendency of the reactor pressure vessels; At the same time, experimental data were used to modify the reactor coolant pressure-temperature limit curve. This test is the second Chashima supervision tube, the sample tube in the supervision of the reactor underwent the first cycle to the fourth cycle, from May 3, 2000 -2007 February 15, 2007, The reactor was operating at 1889 days with 1609 equivalent full-power days (EFPD). The impact properties, fracture mechanics and maximum irradiation temperature of pressure vessel material were tested and verified respectively. The pressure-temperature limit curve of reactor coolant was revised with the test results.