含硼不锈钢材料中子/γ综合屏蔽性能计算分析

张宇; 宋英明; 于小航; 时坚; 徐仲行; 王岩; 付孟婷

doi:10.11889/j.0253-3219.2019.hjs.42.090201

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含硼不锈钢材料中子/γ综合屏蔽性能计算分析

加速器技术、射线技术及应用 | 更新时间：2024-10-25

- 含硼不锈钢材料中子/γ综合屏蔽性能计算分析
- Calculation and analysis of neutron and gamma shielding performance based on boron-containing stainless steel materials
- 核技术 2019年42卷第9期文章编号：090201
- 作者机构：
  
  1.南华大学核科学技术学院衡阳 421001
  2.中国科学院大学北京 100049
  3.沈阳铸造研究所有限公司沈阳 110022
- 作者简介：
  
  张宇，男，1996年出生，南华大学核工程与核技术专业，研究领域为辐射安全工程与核辐射探测
  宋英明，E-mail：songyingming@tsinghua.org.cn
- 基金信息：
  
  高端装备轻合金铸造技术国家重点实验室开放基金(2018SYS04);创新性实验计划项目(2018XJXZ043)
- DOI：10.11889/j.0253-3219.2019.hjs.42.090201
  中图分类号： TL77，TL99
- 收稿日期：2018-11-29，
  
  修回日期：2019-05-24，
  
  纸质出版日期：2019-09-10
- 稿件说明：
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张宇,宋英明,于小航等.含硼不锈钢材料中子/γ综合屏蔽性能计算分析[J].核技术,2019,42(09):7-13.

ZHANG Yu,SONG Yingming,YU Xiaohang,et al.Calculation and analysis of neutron and gamma shielding performance based on boron-containing stainless steel materials[J].NUCLEAR TECHNIQUES,2019,42(09):7-13.
张宇,宋英明,于小航等.含硼不锈钢材料中子/γ综合屏蔽性能计算分析[J].核技术,2019,42(09):7-13. DOI： 10.11889/j.0253-3219.2019.hjs.42.090201.

ZHANG Yu,SONG Yingming,YU Xiaohang,et al.Calculation and analysis of neutron and gamma shielding performance based on boron-containing stainless steel materials[J].NUCLEAR TECHNIQUES,2019,42(09):7-13. DOI： 10.11889/j.0253-3219.2019.hjs.42.090201.

摘要

采用蒙特卡罗粒子输运程序与燃耗计算分析程序相结合（MCNP5/ORIGEN2.1）的方法对辐射防护不锈钢材料屏蔽性能和活化产物进行了综合计算分析。结合辐射屏蔽设计结构优化方法和性能计算的具体要求，给出了中子/γ综合屏蔽性能分析评价方法，针对核反应堆单层外照射三层屏蔽结构简化模型，模拟计算了硼不锈钢和普通不锈钢材料对中子/γ混合辐射场的中子、光子、（n

γ）反应产生的光子、材料内二次活化产物光子的屏蔽效果，并对防护材料的综合屏蔽性能进行了评价。

Abstract

Background

The simulation calculation of shielding performance of radiation protection materials at home and abroad is usually limited to one simulation of the Monte Carlo method

while the fine-grained calculation of gamma ray shielding of secondary products is less.

Purpose

This study aims to analyze shielding performance and activation products of boron-containing stainless steel materials.

Methods

Monte Carlo particle transport program combined with fuel consumption calculation and analysis program (MCNP5/ORIGEN2.1) was employed to calculate and analyze the shielding properties and activation products of stainless steel materials for radiation protection. Combined with the specific requirements of radiation shielding design

evaluation method of neutron/gamma integrated shielding performance was proposed. Based on the simplified model of three-layer shielding structure of single-layer external irradiation of nuclear reactor

the shielding effect of neutron in the neutron/γ mixed radiation field

photon

γ) reaction photons and secondary activation product photons inside the material were simulated by boron stainless steel and ordinary stainless steel

and the overall shielding performance of the protective material was evaluated.

Results & Conclusions

The actual average photon transmittance of boron stainless steel is slightly lower than that of ordinary stainless steel

both of them have the same gamma-ray shielding performance

but boron stainless steel has advantages over ordinary stainless steel in weight reduction.

关键词

Keywords

references

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