硼化钨材料中子屏蔽性能及次级γ剂量产生的模拟研究  

Research on neutron shielding performance and the secondaryγdose simulation of tungsten boride material

作　　者：池晓淼 韩毅[1,2] 刘立业 陈法国[1,2] 李国栋[1,2] 沈华亚 杨明明[1,2] 孙岩松 CHI Xiaomiao;HAN Yi;LIU Liye;CHEN Faguo;LI Guodong;SHEN Huaya;YANG Mingming;SUN Yansong(China Institute for Radiation Protection,Taiyuan 030006;Shanxi Key Laboratory for Radiation Safety and Protection,Taiyuan 030006)

机构地区：[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

出　　处：《辐射防护》2023年第4期343-352,共10页Radiation Protection

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,W_(2)B_(5)的中子吸收性能最优,质量一定时,WB_(4)中子吸收性能最优。以热中子为例,W_(2)B_(5)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。In order to neutron absorption and secondaryγray 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 W_(2)B_(5)is the best;When the mass is constant,WB_(4)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 W_(2)B_(5)material is about 8.67 times that of B203 material and 40.59 times that of PB202 shielding material.(3)the contribution of the secondaryγdose to the total dose decrease with the increase of the incident neutron energyand the contribution of the secondaryγdose 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.

关 键 词：硼化钨系化合物 GEANT4 中子吸收 次级γ射线 

分 类 号：TL77[核科学技术—辐射防护及环境保护]