Neutron shielding properties of TPX/B4C composites based on Monte Carlo method

Author:

Chen Zhigang,Gong Junjun,Jie Shuai

Abstract

Abstract As the key and difficult point of shielding protection, many domestic and foreign scholars have carried out a lot of experimental research on neutron shielding materials. In this paper, the research progress, advantages and disadvantages of common neutron shielding materials are discussed, and the neutron shielding process of TPX/B4C composites is simulated by Monte Carlo method, and the results are compared with the Boron polyethylene, lead boron polyethylene, aluminum based boron carbide mentioned in the literature. Based on the simulation results, it is concluded that the thermal neutron absorption rate of TPX/B4C composites with the thickness of 1cm is 98.3%, the fast neutron shielding rate of 1MeV is 1.457, and the neutron shielding reduction factor and neutron dose reduction factor of americium beryllium neutron source are obviously better than the other three materials. The simulation results show that TPX/B4C Composite can be used as a new kind of high temperature neutron shielding material.

Publisher

IOP Publishing

Subject

General Engineering

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