Monte Carlo Simulation of High Density B<sub>4</sub>C/Al neutron shielding materials

DAI Chunjuan LIU Xiqin LIU Zili

doi:10.11889/j.0253-3219.2013.hjs.36.030202

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Monte Carlo Simulation of High Density B₄C/Al neutron shielding materials

更新时间：2021-06-03

- Monte Carlo Simulation of High Density B₄C/Al neutron shielding materials
- NUCLEAR TECHNIQUES Vol. 36, Issue 3, Article number: 030202(2013)
- 作者机构：
  
  南京航空航天大学材料科学与技术学院核技术应用系
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2013.hjs.36.030202
  CLC： TL24;O242.2
- Published：2013
- 稿件说明：
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[1]戴春娟,刘希琴,刘子利.高密度B_4C/Al中子屏蔽材料的蒙特卡罗模拟[J].核技术,2013,36(03):17-21.

DAI Chunjuan LIU Xiqin LIU Zili. Monte Carlo Simulation of High Density B₄C/Al neutron shielding materials[J]. Nuclear techniques, 2013, 36(3): 030202
[1]戴春娟,刘希琴,刘子利.高密度B_4C/Al中子屏蔽材料的蒙特卡罗模拟[J].核技术,2013,36(03):17-21. DOI： 10.11889/j.0253-3219.2013.hjs.36.030202.

DAI Chunjuan LIU Xiqin LIU Zili. Monte Carlo Simulation of High Density B₄C/Al neutron shielding materials[J]. Nuclear techniques, 2013, 36(3): 030202 DOI： 10.11889/j.0253-3219.2013.hjs.36.030202.

摘要

采用蒙特卡罗方法

运用MCNP4C程序对能量为0.5–2MeV的中子及碳化硼含量为5%–15%、入射厚度为3–15cm的高密度B4C/Al复合材料进行中子透射性能计算。结果表明:碳化硼含量与透射系数呈一次线性下降关系

且透射系数下降幅度较小;中子能量升高

透射系数呈现起伏性

比如0.8MeV的中子比0.5MeV的中子透射系数要小;材料对能量为0.5MeV、0.8MeV、和1.2MeV的中子屏蔽效果较好;材料厚度与透射系数呈指数下降关系

且透射系数下降幅度较大

当材料厚度在13cm以上时

材料的屏蔽性能在90%以上。

Abstract

Background: B4C/Al composite is an ideal neutron shielding material with good mechanical property

which is successfully made as spent fuel container.Purpose: To study its shielding property under different conditions

so as to make use of it properly.Method: Monte-Carlo method is applied to calculate the shielding property of B4C/Al composite.Results: The content of B4C and transmission coefficient is a linear relationship

with a small drop.Transmission coefficient show up and down with the increasing neutron energy

When the neutron energy is 0.5

0.8 or 1.2 MeV

there is a low transmission coefficient.Material thickness and transmission coefficient is a exponential relationship

with a great drop.It can reach ideal shielding effect when it’s thickness is more than 13 cm.Conclusions: the content of carbide boron can not change neutron shielding effect significantly.B4C/Al composite is suitable for shielding neutron of 0.5

0.8

1.2 MeV.To reduced neutron radiation effect

adding thickness of material is the best way.

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Monte Carlo Simulation of High Density B4C/Al neutron shielding materials

DOI：10.11889/j.0253-3219.2013.hjs.36.030202

摘要

Abstract

关键词

Keywords

references

Monte Carlo Simulation of High Density B₄C/Al neutron shielding materials