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反应堆堆芯中子-温度测量探测器研制改进及试验验证
引用本文:马晓宇,邓涛. 反应堆堆芯中子-温度测量探测器研制改进及试验验证[J]. 核动力工程, 2021, 42(2): 105-109. DOI: 10.13832/j.jnpe.2021.02.0105
作者姓名:马晓宇  邓涛
作者单位:中国核工业集团有限公司,北京,100045
摘    要:反应堆堆芯中子-温度测量探测器组件是集成了铑自给能中子探测器与热电偶温度计的一体化探测器。该组件可同时测量堆芯中子注量率和燃料组件出口温度。本文重点介绍了堆芯中子-温度测量探测器组件研制过程中的设计方案,针对假想事故条件下可能出现的短路风险,提出优化结构和加工工艺的改进方案,并通过试验验证了方案的有效性,无限振动试验、拉力、热老化和辐照老化等试验结果表明探测器电气连续性能正常,绝缘电阻大于1 G?。设计和工艺改进方案满足探测器技术规格书的要求。

关 键 词:堆芯  中子  温度  探测器  改进

Improvement and Test Verification of Reactor-Core Neutron and Temperature Detector
Ma Xiaoyu,Deng Tao. Improvement and Test Verification of Reactor-Core Neutron and Temperature Detector[J]. Nuclear Power Engineering, 2021, 42(2): 105-109. DOI: 10.13832/j.jnpe.2021.02.0105
Authors:Ma Xiaoyu  Deng Tao
Affiliation:(China National Nuclear Corporation(CNNC),Beijing,100045,China)
Abstract:The reactor-core neutron and temperature detector is an integrated detector integrating rhodium self powered neutron detector and thermocouple thermometer. The detector can simultaneously measure the neutron fluence rate of the core and the outlet temperature of the fuel assembly. This paper focuses on the design improvement and process improvement plan in the process of detector development, which would significantly improve its reliability under accident conditions. It is verified through experiments that the improved scheme can meet the requirements of the detector technical specifications.
Keywords:Reactor-core  Neutron  Temperature  Detector  Improvement
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