硼化钨材料中子屏蔽性能及次级γ剂量产生的模拟研究

Abstract

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

CLC Number:

TL77

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.

References

[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.

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

PDF (PC)

Like

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 7

Metrics

Comments

Recommended 10

[1]	LI Hui, LI Deyuan, YAN Xuewen, ZHANG Pengpeng, CHEN Faguo, LI Hua. Research on the module structure design of simulation workplace neutron spectrum device based on DT neutron source [J]. RADIATION PROTECTION, 2023, 43(3): 209-217.
[2]	LI Hua, WEI Ziyang, ZHAO Yuan, LIU Liye, LI Hui, WEI Jiafu. Calculation and analysis of gamma-ray exposure buildup factor for common double-layer materials [J]. RADIATION PROTECTION, 2022, 42(5): 395-401.
[3]	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.
[4]	LI Changyuan, XIA Xiaobin, YANG Zhongtian, LIU Yuchen, ZHANG Zhihong, WANG Jianhua, CAI Jun, HU Jifeng. Analysis of thermal neutron shielding performance ofboron-aluminum composite material [J]. RADIATION PROTECTION, 2021, 41(1): 39-43.
[5]	Tsukasa Aso, Yoshimune Ogata, Hidesuke Itadzu. Verification of modified sum-peak method in Monte Carlo simulationof full energy peak and sum-peak efficiencies of a HPGe detector [J]. RADIATION PROTECTION, 2020, 40(6): 527-532.
[6]	Wang Guanying, Han Ran, Ouyang Xiaoping. Application of multi-directional weighting method in D-T fusion neutron spectrum measurement [J]. RADIATION PROTECTION, 2017, 37(5): 341-346.
[7]	Lei Ming, Liu Shuhuan, Zong Pengfei, Liu Bing. GEANT4 simulation of silicon-on-insulator microdosimeter for monitoring lineal spectra of neutron and gamma mixed field [J]. RADIATION PROTECTION, 2017, 37(3): 169-173.