• 文献标题:   Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo Simulation
  • 文献类型:   Article
  • 作  者:   HASSANPOUR M, HASSANPOUR M, FAGHIHI S, KHEZRIPOUR S, REZAIE M, DEHGHANIPOUR P, FARUQUE MRI, KHANDAKER MU
  • 作者关键词:   metamaterial, neutron radiation shielding, current transmission rate, mcnpx, concrete
  • 出版物名称:   MATERIALS
  • ISSN:  
  • 通讯作者地址:  
  • 被引频次:   4
  • DOI:   10.3390/ma15196667
  • 出版年:   2022

▎ 摘  要

In this paper, graphene/h-BN metamaterial was investigated as a new neutron radiation shielding (NRS) material by Monte Carlo N-Particle X version (MCNPX) Transport Code. The graphene/h-BN metamaterial are capable of both thermal and fast neutron moderator and neutron absorber process. The constituent phases in graphene/h-BN metamaterial are chosen to be hexagonal boron nitride (h-BN) and graphene. The introduced target was irradiated by an Am-Be neutron source with an energy spectrum of 100 keV to 15 MeV in a Monte Carlo simulation input file. The resulting current transmission rate (CTR) was investigated by the MCNPX code. Due to concrete's widespread use as a radiation shielding material, the results of this design were also compared with concrete targets. The results show a significant increase in NRS compared to concrete. Therefore, metamaterial with constituent phase's graphene/h-BN can be a suitable alternative to concrete for NRS.