反应堆二次中子源参数计算方法

杨俊云; 李兰; 吕焕文; 谭怡; 肖锋; 景福庭; 唐松乾; 刘斌

doi:10.11889/j.0253-3219.2018.hjs.41.060605

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反应堆二次中子源参数计算方法

核能科学与工程 | 更新时间：2021-05-19

- 反应堆二次中子源参数计算方法
- A calculation method for parameters of secondary neutron source in nuclear reactor
- 核技术 2018年41卷第6期文章编号：060605
- 作者机构：
  
  中国核动力研究设计院核反应堆系统设计技术重点实验室成都 610213
- 作者简介：
  
  [ "杨俊云, 男, 1987年出生, 2016年于中国工程物理研究院获博士学位, 主要研究领域为源项与屏蔽计算", "YANG Junyun, male, born in 1987, graduated from China Academy of Engineering Physics with a doctoral degree in 2016, focusing on computation of source terms and nuclear shielding" ]
- 基金信息：
- DOI：10.11889/j.0253-3219.2018.hjs.41.060605
  中图分类号： TL4
- 收稿日期：2017-11-13，
  
  修回日期：2017-12-06，
  
  纸质出版日期：2018-06-10
- 稿件说明：
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杨俊云, 李兰, 吕焕文, 等. 反应堆二次中子源参数计算方法[J]. 核技术, 2018,41(6):060605

Junyun YANG, Lan LI, Huanwen LYU, et al. A calculation method for parameters of secondary neutron source in nuclear reactor[J]. Nuclear techniques, 2018, 41(6): 060605
杨俊云, 李兰, 吕焕文, 等. 反应堆二次中子源参数计算方法[J]. 核技术, 2018,41(6):060605 DOI： 10.11889/j.0253-3219.2018.hjs.41.060605.

Junyun YANG, Lan LI, Huanwen LYU, et al. A calculation method for parameters of secondary neutron source in nuclear reactor[J]. Nuclear techniques, 2018, 41(6): 060605 DOI： 10.11889/j.0253-3219.2018.hjs.41.060605.

摘要

基于详细的燃耗计算和粒子输运计算，获得二次中子源的源强、能谱和空间分布等关键参数的数值模拟方法。以某商用反应堆的换料实践为例，首先，通过对二次中子源的辐照和衰变过程的模拟，计算出换料时二次中子源棒内

124

Sb的含量；然后，使用MCNP（Monte Carlo N Particle Transport Code）程序及相应的连续能量核反应截面数据，对核反应堆换料结束时的二次中子源实施中子-光子耦合输运模拟，获得相应的二次中子源参数；最后，根据所得中子源参数对某反应堆的堆外探测器响应进行计算，得到了与实测值吻合较好的理论值，验证了该方法的可行性。

Abstract

Background

In the design of nuclear reactor

it is significant to determine the parameters of secondary neutron source.

Purpose

The aim of this paper is to elaborate a calculation method for parameters of secondary neutron source systematically.

Methods

Firstly

compositions of the fuel and secondary neutron source were generated by depletion calculation. Then

gamma production and photonuclear reaction in secondary neutron source were simulated. Specific parameters of secondary neutron source

such as source strength

energy spectrum and space distribution

have been obtained.

Results

The parameters of secondary neutron source have been used to calculate the response of detectors outside the core. The results are in agreement with the measurements.

Conclusion

The calculation method suggested in this paper is available.

关键词

Keywords

references

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