钒自给能探测器中子响应计算方法

钒自给能探测器被广泛用作核动力反应堆的堆内固定式探测器,为堆芯中子注量率分布测量连续不断地提供信息。研究钒自给能探测器的响应电流计算方法,为堆芯在线功率分布监测与探测器设计优化提供理论依据。首先描述钒自给能探测器的响应机理与特性,然后基于Warren提出的理论模型,详细介绍中子响应电流控制方程及电子逃脱概率的计算方法,最后根据公开报道的典型钒探测器规格与实验数据进行数值模拟分析。结果显示,单位长度热中子灵敏度计算值与测量值相对偏差在±5%以内,论证了该方法的有效性与计算精度。

Calculation method of neutron response of vanadium self-powered detectors

Background:Vanadium self-powered detectors (SPDs) are widely used as in-core fixed detectors in nuclear power plants, to continuously provide measurement data for in-core neutron flux map monitoring.Purpose: This study aims at the calculation method of neutron response current for vanadium SPDs, providing a theoretical basis for on-line in-core power distribution monitoring and detector design optimization.Methods:First of all, the response mechanism and characteristics of vanadium SPDs are described, then the neutron response current control equation and calculation method of electron escape probability, based on Warren's analytical model, are presented. Finally, the numerical modeling for the typical vanadium detector specifications is performed and compared with the experimental data.Results: The results show that the deviation of thermal neutron sensitivity per unit length is within ±5% between the computation data and the measured value.Conclusion: It demonstrates the validity and accuracy of the method.