中国实验快堆材料辐射损伤监测方案设计

IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY
Hu Ziao, Chen Xiao-xian, Chen Xiao-liang
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引用次数: 0

摘要

为了对先进燃料元件包壳材料的辐射效应进行监测,需要在反应堆内安装辐照监测罐,该罐内装有各种检测箔。然后利用探测器箔片测定中子能谱和中子通量,从而评价材料的辐射损伤。以中国实验快堆(CEFR)为研究对象,选择了7种中子探测器箔,设计了5种316不锈钢的监督方案。利用Monte Carlo程序和SPECTER程序计算了中子探测器的尺寸、辐照时间以及与辐射损伤的对应关系,最后给出了合理的监测方案。对结构材料的辐照实验具有指导意义,为大型商用快堆结构的辐照损伤监测提供了依据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor
In order to monitor the radiation effects of advanced fuel element cladding materials, it is necessary to install irradiation supervision tanks in the reactor, which contain kinds of detector foils. And then the detector foils are used to determine the neutron energy spectrum and neutron flux, so as to evaluate the radiation damage of the material. Taking China Experimental Fast Reactor (CEFR) as the research object, seven neutron detector foils were selected and five supervision schemes were designed in 316 stainless steel. The size of the neutron detector, the irradiation time and the corresponding relationship with the radiation damage are calculated by the Monte Carlo code and SPECTER program, and finally the sound monitoring scheme is given. It has guiding significance for irradiation experiments of structural materials, and provides a basis for monitoring the irradiation damage of large commercial fast reactor structures.
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来源期刊
CiteScore
0.80
自引率
25.00%
发文量
35
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