Optimal design of the carbon fiber reinforcing B4C/Al neutron absorbing materials

ZHANG Peng; ZHANG Zhewei

doi:10.11889/j.0253-3219.2015.hjs.38.030605

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Optimal design of the carbon fiber reinforcing B4C/Al neutron absorbing materials

更新时间：2021-03-03

- Optimal design of the carbon fiber reinforcing B4C/Al neutron absorbing materials
- NUCLEAR TECHNIQUES Vol. 38, Issue 3, Article number: 030605(2015)
- 作者机构：
  
  1. 太原理工大学物理与光电工程学院,太原,030024
  2. 太原理工大学材料科学与工程学院,太原,030024
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2015.hjs.38.030605
  CLC：
- Published：09 March 2015
- 稿件说明：
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ZHANG Peng, ZHANG Zhewei. Optimal design of the carbon fiber reinforcing B4C/Al neutron absorbing materials[J]. Nuclear techniques, 2015, 38(3): 030605
DOI：

ZHANG Peng, ZHANG Zhewei. Optimal design of the carbon fiber reinforcing B4C/Al neutron absorbing materials[J]. Nuclear techniques, 2015, 38(3): 030605 DOI： 10.11889/j.0253-3219.2015.hjs.38.030605.

摘要

核电站中乏燃料储存格架用到的中子吸收材料需要兼具结构和功能一体化的要求，本文提出用碳纤维Cf增强B4C/Al中子吸收复合材料。利用Monte Carlo方法对碳纤维增强铝基碳化硼中子吸收材料(Cf/B4C/Al)的中子透射率进行模拟计算，研究B4C含量、Cf含量、不同能量中子入射以及材料厚度变化时对中子透射率的影响，并与B4C/Al材料进行比较。结果表明，在1 eV?0.1 MeV能量范围的中子入射下，当B4C含量小于35%时，加入碳纤维能明显改善B4C/Al材料的中子屏蔽性能；在100 eV中子入射下，材料的中子透射率随B4C含量增加呈现指数下降；且Cf/B4C/Al材料的中子透射率随碳纤维含量增加持续降低；当Cf含量达到10%时，材料中子透射率降至最低，之后趋于平稳。通过模拟计算，得到Cf/B4C/Al材料的各组分的最优配比为35vol.% B4C和10 vol.% Cf。

Abstract

Background: The neutron absorbing materials used for spent fuel storage grids in the nuclear power plant need to meet the structural and functional integration requirements. Purpose: This paper has proposed the high content B4C/Al neutron absorbing materials reinforced by carbon fiber. Methods: Monte Carlo method has been used to calculate the neutron transmittances of carbon-fiber reinforcing B4C/Al neutron absorbing materials (Cf/B4C/Al). Result: The effects of some factors on the neutron transmittances of Cf/B4C/Al composite have been studied such as B4C and Cf contents

incident neutron energy and material thickness

which also have been compared with those of B4C/Al materials. Conclusions: The results show that for 1 eV?0.1 MeV incident neutron

when the content of B4C is less than 35%

the addition of carbon fibers can significantly improve the neutron shielding performance of B4C/Al composite. For 100-eV incident neutron

the transmittance of the material decreases exponentially with the increase of B4C content. The neutron transmission of Cf/B4C/Al decreases with the increase of carbon fiber content up to 10%. The optimal component ratios of Cf/B4C/Al were designed as 35% B4C and 10% Cf. In order to shield the neutron radiation as effectively as a 0.5-mm-thick cadmium plate

the thickness of Cf/B4C/Al was also designed as 9.42 mm. The study will provide the theoretical guidance for the design and application of the neutron absorbing materials. Abstract

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