Evaluation of Reactor Pressure Vessel Irradiation Embrittlement of VVER-1000 Nuclear Power Unit
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摘要: 反应堆压力容器(RPV)辐照监督及辐照脆化评价是保证核反应堆寿期内安全运行的重要手段。介绍了田湾核电站1、2号VVER-1000型机组辐照监督组件的设置和试验内容,并对1号机组1Л、2Л辐照监督组件的试验结果、辐照脆化预测模型和超前因子进行了分析讨论。结果表明,田湾核电站1号机组RPV母材和焊缝的辐照脆化效应均在原设计标准的范围内,RPV实际辐照脆化趋势与预测模型具有较好的一致性。建议下一套辐照监督组件的抽取时机为运行后第20 a。
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关键词:
- VVER-1000 /
- 反应堆压力容器(RPV) /
- 辐照监督 /
- 辐照脆化
Abstract: Irradiation surveillance and embrittlement evaluation of reactor pressure vessel is an important means to ensure the safe operation during reactor lifetime. This paper introduces the designation and test types of Tianwan NPP Unit 1 and 2（VVER-1000） unit irradiation surveillance sets. Also, the test results, irradiation embrittlement estimation models and lead factor are analyzed and discussed for the 1Л and 2Л sets of Tianwan NPP Unit 1. The irradiation surveillance data shows that the irradiation embrittlement effect of base metal and welds of RPV active area of Tianwan NPP Unit 1 is in the scope of the initial design. The RPV actual embrittlement trend is in good agreement with the estimation model. It is suggested that next irradiation surveillance set be unloaded during the 20 th year of reactor operation. -
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