基于蒙特卡罗方法的复合材料辐射屏蔽设计

辐射防护 ›› 2022, Vol. 42 ›› Issue (1): 41-47.

基于蒙特卡罗方法的复合材料辐射屏蔽设计

白鸿伟¹, 李达², 郭寻^1,3, 薛云飞¹, 靳柯^1,3

1.北京理工大学材料学院,北京 100081;
2.国家核安保技术中心,北京 102413;
3.北京理工大学前沿交叉科学研究院,北京 100081

收稿日期:2021-02-04 出版日期:2022-01-20 发布日期:2022-01-24
通讯作者: 靳柯。E-mail: jinke@bit.edu.cn
作者简介:白鸿伟(1998—),男,2019年毕业于河北工业大学功能材料专业,现为北京理工大学材料科学与工程专业在读硕士研究生。E-mail: 2910764980@qq.com
基金资助:
中国国家国防科工局乏燃料后处理科研项目《防中子辐射纤维及复合材料研究》资助。

Shielding design of radiation resistant composite material based on Monte Carlo method

BAI Hongwei¹, LI Da², GUO Xun^1,3, XUE Yunfei¹, JIN Ke^1,3

1. Beijing Institute of Technology School of Materials,Beijing 100081;
2. State Nuclear Security Technology Center, Beijing 102413;
3. Beijing Institute of Technology advanced research institute of multidisciplinary sciences,Beijing 100081

Received:2021-02-04 Online:2022-01-20 Published:2022-01-24

摘要/Abstract

摘要： 在乏燃料后处理厂的工作环境中可能存在着低能中子-γ射线混合辐射,严重威胁工作人员的人身安全。本文针对上述混合辐射环境,利用蒙特卡罗程序Geant4模拟计算了一种钨/硼纤维增强含硼/铋聚合物复合材料中不同材料参数对低能中子和γ射线综合防护效果的影响。结果显示,此种钨/硼纤维复合材料对低能中子和γ射线均具有良好的屏蔽效果。文章证实了纤维垂直排布方式具有比平行排布方式更优的屏蔽效果,且垂直排布方式下透过粒子束的强度分布更加均匀。此外,在聚合物基体中掺杂一定质量分数的硼/铋可以进一步增强复合材料的辐射屏蔽效果。依据这些结果我们认为此种复合材料可以为后处理厂等辐射环境中的防护服及相关防护用具提供参考。

关键词: 中子-γ射线混合辐射, 辐射屏蔽, Geant4, 钨/硼纤维

Abstract: Mixed low-energy neutron and γ-ray radiations may exist in the working environment of the spent fuel reprocessing plants, which threatens the health of staff. In this work, Monte Carlo simulations based on Geant4 software is applied to assist the design of composite materials, i.e., tungsten/boron fibers in the polymer substrate containing boron and bismuth, for shielding such mixed radiations by simulating the effects of various material parameters. The results show that this tungsten-boron composite material has an excellent shielding effect for both neutron and γ-ray radiations. It can be proved that the vertical arrangement of fibers has better shielding effect than parallel arrangement, since the distribution of transmission beam became more uniform when the fibers were arranged vertically. Moreover, the shielding effectiveness of this material can be further enhanced by adding bismuth into the polymer substrate. These findings can be expected to provide guidance not only for radiation protection suits, but also other relevant protective gears used in the radiation environment, such as reprocessing plants.

Key words: mixed neutron and γ-ray radiations, radiation shielding, Geant4, tungsten/boron fibers

中图分类号:

TL75+2

白鸿伟, 李达, 郭寻, 薛云飞, 靳柯. 基于蒙特卡罗方法的复合材料辐射屏蔽设计[J]. 辐射防护, 2022, 42(1): 41-47.

BAI Hongwei, LI Da, GUO Xun, XUE Yunfei, JIN Ke. Shielding design of radiation resistant composite material based on Monte Carlo method[J]. RADIATION PROTECTION, 2022, 42(1): 41-47.

参考文献 12

[1]	叶国安, 郑卫芳, 何辉, 等. 我国核燃料后处理技术现状和发展[J]. 原子能科学技术, 2020, 54(S1):75-83.YE Guoan, ZHENG Weifang, HE Hui, et al. Status and development of technology on reprocessing spent nuclear fuel in China[J]. Atomic Energy Science and Technology, 2020, 54(S1):75-83.
[2]	HE W,FENG Z,CHEN L. Research on biological sealing for openings in nuclear power plant[J]. IOP Conference Series: Earth and Environmental Science, 2021, 675(1):012097.
[3]	韩毅, 陈法国, 于伟跃, 等.中子屏蔽材料研究现状[J].材料导报, 2015, 29 (26): 483-487.HAN Yi, CHEN Faguo, YU Weiyue, et al. Investigation of the research status of neutron shielding materials[J]. Materials Review, 2015, 29 (26): 483-487.
[4]	李瑛, 崔亦斌, 穆晓曦, 等. 一种中子辐射防护服装材料及其制备方法: 201410165868.7[P]. 2014-09-03.
[5]	周元林, 张全平, 李银涛. 辐射防护聚合物复合纤维的制备方法:201610580993.3[P]. 2016-12-07.
[6]	Singha K, Anupam K, Debnath P, et al. 硼纤维的研究概述[J]. 国际纺织导报, 2013, 41(009):24-31.Singha K, Anupam K, Debnath P, et al. Study on boron fiber: review[J]. Melliand China, 2013, 41(009):24-31.
[7]	Allison J, Amako K, Apostolakis J, et al. Geant4 developments and applications[J]. IEEE Transactions on Nuclear Science, 2006, 53(1):270-278.
[8]	Agostinelli S, Allison J, Amako K, et al. Geant4—A simulation toolkit[J]. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2003, 506(3):250.
[9]	Allison J, Amako K, Apostolakis J, et al. Recent developments in Geant4[J]. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2016, 835:186-225.
[10]	中国疾病预防控制中心辐射防护与核安全医学所. 放射事故个人外照射剂量估算原则: GBZ/T 151—2002[S]. 中华人民共和国卫生部, 2002.
[11]	军事医学科学院放射医学研究所. 用于光子外照射放射防护的剂量转换系数: GBZ/T 144—2002[S]. 中华人民共和国卫生部, 2002.
[12]	柳伟钧,王强华. 防中子辐射纤维及复合材料的开发[J]. 上海建材,2012,6:10-12.LIU Weijun, WANG Qianghua. Development of anti-neutron radiation fibers and composites[J]. Shanghai Building Materials, 2012, 6:10-12.