Simulation of neutron reflecting and shielding property of various materials

Xiong DING; Xinli SUN; Zhen LI; Yuanjiang ZHU; Wurui HUANG

doi:10.11889/j.0253-3219.2017.hjs.40.030201

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Simulation of neutron reflecting and shielding property of various materials

LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS | 更新时间：2021-05-19

- Simulation of neutron reflecting and shielding property of various materials
- NUCLEAR TECHNIQUES Vol. 40, Issue 3, Article number: 030201(2017)
- 作者机构：
  
  1.火箭军工程大学核工程系西安 710025
  2.海军装备研究院北京 100161
- 作者简介：
- 基金信息：
  
  Supported by National Natural Science Foundation of China
- DOI：10.11889/j.0253-3219.2017.hjs.40.030201
  CLC： TL77
- Received：15 November 2016，
  
  Revised：22 December 2016，
  
  Published：10 March 2017
- 稿件说明：
移动端阅览
Xiong DING, Xinli SUN, Zhen LI, et al. Simulation of neutron reflecting and shielding property of various materials[J]. Nuclear techniques, 2017, 40(3): 030201
DOI：

Xiong DING, Xinli SUN, Zhen LI, et al. Simulation of neutron reflecting and shielding property of various materials[J]. Nuclear techniques, 2017, 40(3): 030201 DOI： 10.11889/j.0253-3219.2017.hjs.40.030201.

摘要

利用Monte Carlo粒子输运计算程序SuperMC对厚度1-5 cm的多种材料进行中子反射和屏蔽性能分析计算。这些材料包括金属材料铍、铅、铜、含硼钢以及

238

U和非金属材料聚乙烯、氢化锂、混凝土，中子能段选取10

-5

eV-20 MeV。结果显示，中子反射能力和屏蔽性能都会随着材料厚度而增加，但增加的幅度逐渐减小。铍和聚乙烯在中子反射和屏蔽方面性能优越，而常用来屏蔽γ射线的铅在这两方面性能都是8种材料中最差的。

238

U只在材料厚度很小时性能卓著，随着材料厚度增加，其性能便远不如大部分材料。考虑到聚乙烯的力学性能较差，在屏蔽材料的选择上有很大的限制，所以在8种材料中，铍的综合性能相对较好。

Abstract

Background

Neutron reflectivity has a great impact on the transformation of nuclear energy

so the neutron reflection performance should be considered in the neutron shielding material.

Purpose

The aim is to analyze the neutron reflection and shielding properties of several materials.

Methods

The Monte Carlo particle transportation program named SuperMC is used for calculating neutron reflecting and shielding properties of various materials with thickness of 1-5 cm. These materials include metal materials (Be

boron steel and

238

U) and non-metal materials (Polyethylene (PE)

LiH and concrete).

Results & Conclusion

The neutron reflecting and shielding properties will increase as the thickness of the materials increases

but the increasing amplitude gradually decreases. The reflecting and shielding properties of Be and PE are superior to the other six materials. Besides

the reflecting and shielding properties of Pb are the worst of eight materials

though Pb is often used as the gamma-ray shielding material. In addition

only in the condition that the material thickness is relatively small and

238

U have an outstanding performance. However

with the increase in the thickness of the material

its performance will be far worse than most other materials. Considering the mechanical properties of materials

the comprehensive properties of Be are relatively better in eight materials.

关键词

Keywords

references

魏强林 , 杨波 , 王毅 , . 含硼钢对慢中子衰减性能的蒙特卡罗模拟 . 核技术 , 2010 . 33 ( 5 ): 367 - 369 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201005013.htm .

Qianglin WEI , Bo YANG , Yi WANG , . M-C simulation of slow neutron attenuation in boron-containing stainless steed . Nuclear Techniques , 2010 . 33 ( 5 ): 367 - 369 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201005013.htm .

李哲夫 , 薛向欣 . 含硼物质及环氧树脂复合材料的中子屏蔽性能 . 原子能科学技术 , 2011 . 45 ( 2 ): 223 - 229 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS201102017.htm .

Zhefu LI , Xiangxin XUE . Neutron shielding properties of boron-containing ore and epoxy composites . Atomic Energy Science and Technology , 2011 . 45 ( 2 ): 223 - 229 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS201102017.htm .

葛峰 , 王春光 , 张玉碧 . 中子屏蔽材料防护层设计 . 应用技术 , 2013 . 8 193 - 194 . http://www.cnki.com.cn/Article/CJFDTOTAL-KJCB201315156.htm .

Feng GE , Chunguang WANG , Yubi ZHANG . The design of neutron shielding material protective layer . Applied Technology , 2013 . 8 193 - 194 . http://www.cnki.com.cn/Article/CJFDTOTAL-KJCB201315156.htm .

柴浩 , 汤晓斌 , 陈飞达 , . 新型柔性中子屏蔽复合材料研制及性能研究 . 原子能科学技术 , 2014 . 48 ( 增1 ): 839 - 844 . DOI: 10.7538/yzk.2014.48.S0.0839 http://doi.org/10.7538/yzk.2014.48.S0.0839 .

Hao CHAI , Xiaobin TANG , Feida CHEN , . Preparation and performance of new type flexible neutron shielding composite . Atomic Energy Science and Technology , 2014 . 48 ( Suppl 1 ): 839 - 844 . DOI: 10.7538/yzk.2014.48.S0.0839 http://doi.org/10.7538/yzk.2014.48.S0.0839 .

徐军 , 康清 , 沈志强 , . 核防护用水泥基中子屏蔽材料的研究进展 . 材料开发与应用 , 2011 . 26 ( 5 ): 92 - 100 . DOI: 10.3969/j.issn.1003-1545.2011.05.022 http://doi.org/10.3969/j.issn.1003-1545.2011.05.022 .

Jun XU , Qing KANG , Zhiqiang SHEN , . Progress of cement-based neutron shielding materials in nuclear protecting . Department and Application of Materials , 2011 . 26 ( 5 ): 92 - 100 . DOI: 10.3969/j.issn.1003-1545.2011.05.022 http://doi.org/10.3969/j.issn.1003-1545.2011.05.022 .

曾心苗 , 周鹏 , 秦培中 , . 不同材料的中子透射MC模拟计算 . 核技术 , 2011 . 34 ( 3 ): 188 - 192 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201103007.htm .

Xinmiao ZENG , Peng ZHOU , Peizhong QIN , . Monte Carlo simulation of neutron transmission through various materials . Nuclear Techniques , 2011 . 34 ( 3 ): 188 - 192 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201103007.htm .

W S Ji , J W Lee , S Yu , . Polyerhylene/boroncontaining composites for radiation shielding . Thermochimica Acta , 2014 . 585 ( 1 ): 5 - 9 . https://www.researchgate.net/publication/261374550_Polyethyleneboron-containing_composites_for_radiation_shielding .

T Hayashi , K Tobita , Y Nakamori , . Advanced neutron shielding material using zirconium borohydride and zirconium hydride . Journal of Nuclear Materials , 2009 . 386 ( 1 ): 119 - 121 . https://www.researchgate.net/publication/229347824_Advanced_neutron_shielding_material_using_zirconium_borohydride_and_zirconium_hydride .

V P Sinch , N M Badiger , N Chanthima , . Evaluation of gamma-ray exposure build up factors and neutron shielding for bismuth borosilicate glasses . Radiation Physics and Chemistry , 2014 . 98 ( 1 ): 14 - 21 . http://www.sciencedirect.com/science/article/pii/S0969806X13006762 .

卢希庭 . 原子核物理 , : 北京原子能出版社 , 2010 . 299 - 301 .

Xiting LU . Nuclear physics , : Beijing Atomic Energy Press , 2010 . 299 - 301 .

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