硼化钨材料中子屏蔽性能及次级γ剂量产生的模拟研究

辐射防护 ›› 2023, Vol. 43 ›› Issue (4): 343-352.

硼化钨材料中子屏蔽性能及次级γ剂量产生的模拟研究

池晓淼^1,2, 韩毅^1,2, 刘立业¹, 陈法国^1,2, 李国栋^1,2, 沈华亚^1,2, 杨明明^1,2, 孙岩松^1,2

1.中国辐射防护研究院,太原 030006;
2.辐射安全与防护山西省重点实验室,太原 030006

收稿日期:2022-07-21 出版日期:2023-07-20 发布日期:2023-07-25
通讯作者: 韩毅。E-mail:heaven0china@163.com
作者简介:池晓淼(1994—),男,2017年毕业于哈尔滨工程大学核科学与核技术专业,获学士学位;2020年毕业于哈尔滨工程大学核科学与技术专业,获硕士学位,助理研究员。E-mail:chixiaomiao_heu@163.com

Research on neutron shielding performance and the secondary γ dose simulation of tungsten boride material

CHI Xiaomiao^1,2, HAN Yi^1,2, LIU Liye¹, CHEN Faguo^1,2, LI Guodong^1,2, SHEN Huaya^1,2, YANG Mingming^1,2, SUN Yansong^1,2

1. China Institute for Radiation Protection, Taiyuan 030006;
2. Shanxi Key Laboratory for Radiation Safety and Protection, Taiyuan 030006

Received:2022-07-21 Online:2023-07-20 Published:2023-07-25

摘要/Abstract

摘要： 对辐射防护材料硼化钨的中子吸收和次级γ射线屏蔽性能进行分析。采用Geant4程序,对材料厚度0~2 cm、能量为热中子~20 MeV的入射中子进行模拟分析。研究结果表明:(1)硼化钨材料主要作用于热中子~10^-2 MeV中子的吸收屏蔽。由不同材料对应的中子宏观分出截面和材料密度可知,厚度一定时,W₂B₅的中子吸收性能最优,质量一定时,WB₄中子吸收性能最优。以热中子为例,W₂B₅ 材料的中子宏观分出截面约为B203材料的8.67倍,是PB202屏蔽材料的40.59倍;(2)相比于传统中子吸收材料,W-B系化合物在低能中子吸收方面优势更为显著;(3)随着入射中子能量的增大,次级γ剂量对总剂量的贡献呈下降趋势;随着硼化钨材料厚度的增加,次级γ剂量对总剂量的贡献不断升高。为明确硼化钨应用场景及优势,实现中子源屏蔽装置的优化设计提供数据参考,具有实际的工程指导价值。

关键词: 硼化钨系化合物, Geant4, 中子吸收, 次级γ射线

Abstract: In order to neutron absorption and secondary γ ray shielding performance. In this paper, the Geant4 program is used to simulate and analyze the incident neutrons with material thickness from 0 to 2 cm and energy from thermal neutron to 20 MeV. The results show that: (1) W-B series compounds mainly act on the absorption and shielding of neutron energy from thermal neutrons to 10^-2 MeV; When the thickness is constant, the neutron absorption performance of W₂B₅ is the best; When the mass is constant, WB₄ has the best neutron absorption performance. (2) From the neutron macroscopic cross section and material density of different materials, compared with traditional neutron absorbing materials, W-B series compounds have more significant advantages in low-energy neutron absorption. Taking thermal neutrons as an example, the neutron macroscopic l cross section of W₂B₅ material is about 8.67 times that of B203 material and 40.59 times that of PB202 shielding material.(3) the contribution of the secondary γ dose to the total dose decrease with the increase of the incident neutron energyand the contribution of the secondary γ dose to the total dose increase with the increase of the thickness of the shielding material. study provides a reference for the realization of the optimal design of neutron shielding devices for clarifying the application advantages and application scenarios of W-B series compounds, and has practical engineering guidance value.

Key words: W-B series compounds, Geant4, neutron absorption, secondary γ-ray

中图分类号:

TL77

池晓淼, 韩毅, 刘立业, 陈法国, 李国栋, 沈华亚, 杨明明, 孙岩松. 硼化钨材料中子屏蔽性能及次级γ剂量产生的模拟研究[J]. 辐射防护, 2023, 43(4): 343-352.

CHI Xiaomiao, HAN Yi, LIU Liye, CHEN Faguo, LI Guodong, SHEN Huaya, YANG Mingming, SUN Yansong. Research on neutron shielding performance and the secondary γ dose simulation of tungsten boride material[J]. RADIATION PROTECTION, 2023, 43(4): 343-352.

参考文献

[1] 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.
[2] 李德平, 潘自强. 辐射防护手册:第一分册辐射源与屏蔽[M]. 北京:原子能出版社, 1987.
LI Deping, PAN Ziqiang. Radiation protection manual: Division I. radiation source and shielding[M]. Beijing:Atomic Energy Press, 1987.
[3] Windsor C G,Astbury J O,Davidson J J, et al. Tungsten boride shields in a spherical tokamak fusion power plant[J]. Nuclear Fusion, 2021, 61(8):086018 (14pp).
[4] 韩燚君,董鹏,喇培清,等. NaCl含量对盐助燃烧合成超细硼化钨粉体相组成和粒度的影响及其作用机制[J]. 稀有金属材料与工程, 2018, 47(378):135-142.
HAN Yijun, DONG Peng, LA Peiqing, et al. Effect and mechanism of Nacl content on phase and size of submicron tungsten boride powders by salt-assisted combustion synthesis[J]. Rare Metal Materials and Engineering, 2018, 47(378): 135-142.
[5] Neguyen D Hieu,Ngo M Chu, Tokoi Yoshinori, et al.Nanoparticle synthesis of transition metal borides by pulsed discharge of compacted powder[J]. Journal of the American Ceramic Society, 2021,104(9):4351-4367.
[6] Rose P F. ENDF-201: ENDF/B-VI summary documentation[R]. ENDF/B-VI MOD 2 Evaluation. 1991.
[7] 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.
[8] 史笠含. 硼化钨材料的制备与性能研究[D].东北大学, 2012.
SHI Lihan. Study on preparation and properties of tungsten boride material[D]. North Eastern University,2012.
[9] ICRP. Conversion coefficients for use in radiological protection against external radiation[R]. ICRP Publication 74.Annals of the ICRP, 1997:26.
[10] Athanasakis M, Ivanov E, del Rio E, et al. A high temperature W₂B-W composite for fusion reactor shielding[J]. Journal of Nuclear Materials, 2020, 532: 152062.
[11] 吕继新, 陈建廷. 高效能屏蔽材料铅硼聚乙烯[J]. 核动力工程, 1994, 15(4):370-374.
LU Jixin, CHEN Jianting, High effective shielding material lead-baron polyethylene[J]. Nuclear Power Engineering, 1994, 15(4):370-374.
[12] Gauthier M M. Engineered materials handbook[M].Metals Park, Ohio:ASM Internation,1987.
[13] 张磊, 贾铭椿, 龚军军,等. 中子辐照铅硼聚乙烯致次级γ剂量模拟研究[J]. 核电子学与探测技术, 2017, 37(6):575-579.
ZHANG Lei, JIA Mingchun, GONG Junjun, et al. Simulated study on the secondary γ dose from neutron irradiating lead boron polyethylene[J]. Nuclear Electronics & Detection Technology, 2017, 37(6):575-579.