CMRR冷中子源中子物理参数模拟计算

霍合勇; 孙勇; 唐彬; 尹伟; 刘斌; 吴洋; 曹超; 王胜; 李航

doi:10.11889/j.0253-3219.2018.hjs.41.020202

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CMRR冷中子源中子物理参数模拟计算

低能加速器技术、射线技术及应用 | 更新时间：2021-05-19

- CMRR冷中子源中子物理参数模拟计算
- Neutron physical parameter's simulation of CMRR cold neutron source
- 核技术 2018年41卷第2期文章编号：020202
- 作者机构：
  
  1.中国工程物理研究院核物理与化学研究所绵阳 621900
  2.中国工程物理研究院中子物理学重点实验室绵阳 621900
- 作者简介：
  
  [ "霍合勇, 男, 1977年出生, 2004年于东北师范大学获硕士学位, 主要从事核技术及其应用", "HUO Heyong, male, born in 1977, graduated from Northeast Normal University with a master's degree in 2004, mainly engaged in the nuclear technology and application" ]
  吴洋, E-mail:nuclearwyang@163.comWU Yang, E-mail: nuclearwyang@163.com
- 基金信息：
  
  国防基础科研计划(JCKY2017212B002);核安全项目(41426020401);国家重大研发计划(2016YFA0401502);国家自然科学基金(11605168);国家自然科学基金(11405153);国家自然科学基金(11375156);国家自然科学基金(11675153)
- DOI：10.11889/j.0253-3219.2018.hjs.41.020202
  中图分类号： TL99
- 收稿日期：2017-09-29，
  
  修回日期：2017-11-18，
  
  纸质出版日期：2018-02-10
- 稿件说明：
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霍合勇, 孙勇, 唐彬, 等. CMRR冷中子源中子物理参数模拟计算[J]. 核技术, 2018,41(2):020202

Heyong HUO, Yong SUN, Bin TANG, et al. Neutron physical parameter's simulation of CMRR cold neutron source[J]. Nuclear techniques, 2018, 41(2): 020202
霍合勇, 孙勇, 唐彬, 等. CMRR冷中子源中子物理参数模拟计算[J]. 核技术, 2018,41(2):020202 DOI： 10.11889/j.0253-3219.2018.hjs.41.020202.

Heyong HUO, Yong SUN, Bin TANG, et al. Neutron physical parameter's simulation of CMRR cold neutron source[J]. Nuclear techniques, 2018, 41(2): 020202 DOI： 10.11889/j.0253-3219.2018.hjs.41.020202.

摘要

为给中子导管中子输运与屏蔽计算提供输入参数，建立冷中子源（Cold Neutron Source，CNS）模型，制作正氢与仲氢蒙特卡罗（Monte Carlo N particle transport code，MCNP）截面数据库，计算了慢化室内不同穿透深度的中子注量率变化趋势、冷中子（Cold Neutron，CN）孔道入口处中子角分布与冷中子增益、中子导管入口处中子角分布与中子注量率空间分布。结果显示，液氢慢化剂使中子束内冷中子有显著的增益，随着中子在CN孔道内的传输中子束的准直性大大提高，为下一步开展中子导管计算提供了重要参考数据。

Abstract

Background

Cold neutron is generally yielded by cold neutron source (CNS) in large-size neutron source. The wavelength of cold neutron is similar to that of molecular or atomic structure of lots of materials

which could be adopted to study material macroscopical or macroscopic structure.

Purpose

This paper aims to provide input data for neutron transportation in neutron guide and shielding calculation of China Mianyang Research Reactor (CMRR).

Methods

CNS was modeled

and ortho-hydrogen and para-hydrogen Monte Carlo database was processed. We calculated the neutron flux in different depths inside the liquid hydrogen moderator

neutron angular distribution and cold neutron gain in the cold neutron (CN) channel's entrance

and got the neutron angular and spatial distributions at the intake of neutron guide.

Results

The results showed that liquid hydrogen could enhance the cold neutron gain

and neutron beam collimation was promoted by CN horizontal channel.

Conclusion

The calculation indicates CNS may significantly improve the performance of neutron beam.

关键词

Keywords

references

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