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反应堆压力容器辐照脆化状态评估
引用本文:朱光强,尉言辉. 反应堆压力容器辐照脆化状态评估[J]. 核动力工程, 2018, 39(4): 39-42. DOI: 10.13832/j.jnpe.2018.04.0039
作者姓名:朱光强  尉言辉
作者单位:核动力运行研究所核设备研究设计中心;中核核电运行管理有限公司技术三处
摘    要:基于大量相似辐照脆化试验测试数据和实际辐照监督测试数据,采用统计分析的方法,选出适合于某核电厂反应堆压力容器(RPV)的辐照脆化评估公式。以该核电厂已经完成的辐照监督管测试数据为输入,对RPV当前的辐照脆化状态进行了评估,并推算、分析了RPV在寿期末的结构完整性;基于辐照脆化计算结果,绘制了各运行阶段RPV的压力-温度限值曲线(P-T曲线),并给出运行建议。 

关 键 词:反应堆压力容器   辐照脆化   状态评估   P-T 曲线

Status Assessment of RPV Irradiation Embrittlement
Abstract:Based on a large number of similar irradiation embrittlement test data and actual radiation monitoring test data, a formula for evaluating the irradiation embrittlement of the reactor pressure vessel (RPV) of a nuclear power plant is selected using the method of statistical analysis. The irradiation supervision tube test data of the nuclear power plant has been completed as input data, and the present irradiation embrittlement status of RPV was evaluated. The structural integrity of RPV at the end of life was calculated and analyzed. Based on the calculation results of irradiation embrittlement, the P-T curves of RPV in each operation stage are plotted, and the operation suggestions are given. 
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