钒自给能探测器中子响应计算方法

毕光文; 汤春桃; 杨波

doi:10.11889/j.0253-3219.2017.hjs.40.060604

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钒自给能探测器中子响应计算方法

核能科学与工程 | 更新时间：2021-05-19

- 钒自给能探测器中子响应计算方法
- Calculation method of neutron response of vanadium self-powered detectors
- 核技术 2017年40卷第6期文章编号：060604
- 作者机构：
  
  上海核工程研究设计院上海 200233
- 作者简介：
  
  [ "毕光文, 男, 1985年出生, 2011年于上海核工程研究设计院获硕士学位, 从事反应堆物理设计分析工作", "BI Guangwen, male, born in 1985, graduated from Shanghai Nuclear Engineering Research and Design Institute with a master's degree in 2011, engaged in the work of reactor physics" ]
- 基金信息：
- DOI：10.11889/j.0253-3219.2017.hjs.40.060604
  中图分类号： TL329
- 收稿日期：2017-01-10，
  
  修回日期：2017-02-27，
  
  纸质出版日期：2017-06-10
- 稿件说明：
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毕光文, 汤春桃, 杨波. 钒自给能探测器中子响应计算方法[J]. 核技术, 2017,40(6):060604

Guangwen BI, Chuntao TANG, Bo YANG. Calculation method of neutron response of vanadium self-powered detectors[J]. Nuclear techniques, 2017, 40(6): 060604
毕光文, 汤春桃, 杨波. 钒自给能探测器中子响应计算方法[J]. 核技术, 2017,40(6):060604 DOI： 10.11889/j.0253-3219.2017.hjs.40.060604.

Guangwen BI, Chuntao TANG, Bo YANG. Calculation method of neutron response of vanadium self-powered detectors[J]. Nuclear techniques, 2017, 40(6): 060604 DOI： 10.11889/j.0253-3219.2017.hjs.40.060604.

摘要

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。

Abstract

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.

关键词

Keywords

references

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W Jaschik , W Seifritz . Model for calculating prompt-response self-powered neutron detectors . Nuclear Science and Engineering , 1974 . 53 61 - 78 . https://www.researchgate.net/publication/236382564_Model_for_calculating_prompt-response_self-powered_neutron_detectors .

H D Warren , N H Shah . Neutron and gamma-ray effects on self-powered in-core radiation detectors . Nuclear Science and Engineering , 1974 . 54 395 - 415 . http://www.ans.org/pubs/journals/nse/a_23434 .

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Weinberg A M, Wigner E P. The physical theory of neutron chain reactions[C]. USA:The University of Chicago Press, 1958:711.

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