Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo Simulation
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 constitue...
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MDPI AG
2022-09-01
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| Series: | Materials |
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| Online Access: | https://www.mdpi.com/1996-1944/15/19/6667 |
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| author | Marzieh Hassanpour Mehdi Hassanpour Simin Faghihi Saeedeh Khezripour Mohammadreza Rezaie Parvin Dehghanipour Mohammad Rashed Iqbal Faruque Mayeen Uddin Khandaker |
| author_facet | Marzieh Hassanpour Mehdi Hassanpour Simin Faghihi Saeedeh Khezripour Mohammadreza Rezaie Parvin Dehghanipour Mohammad Rashed Iqbal Faruque Mayeen Uddin Khandaker |
| author_sort | Marzieh Hassanpour |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-03-09T21:31:14Z |
| format | Article |
| id | doaj.art-33d25a5235eb463e84bd1912862c4162 |
| institution | Directory Open Access Journal |
| issn | 1996-1944 |
| language | English |
| last_indexed | 2024-03-09T21:31:14Z |
| publishDate | 2022-09-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Materials |
| spelling | doaj.art-33d25a5235eb463e84bd1912862c41622023-11-23T20:54:41ZengMDPI AGMaterials1996-19442022-09-011519666710.3390/ma15196667Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo SimulationMarzieh Hassanpour0Mehdi Hassanpour1Simin Faghihi2Saeedeh Khezripour3Mohammadreza Rezaie4Parvin Dehghanipour5Mohammad Rashed Iqbal Faruque6Mayeen Uddin Khandaker7Space Science Centre (ANGKASA), Institute of Climate Change (IPI), Universiti Kebangsaan Malaysia, Bangi 43600, MalaysiaSpace Science Centre (ANGKASA), Institute of Climate Change (IPI), Universiti Kebangsaan Malaysia, Bangi 43600, MalaysiaDepartment of Engineering, Khorasgan (Isfahan) Branch, Islamic Azad University, Arghavanieh, Isfahan 8155139998, IranDepartment of Molecular and Atomic Physics, Faculty of Modern Science and Technology, Graduate University of Advanced Technology, Kerman 7631885356, IranDepartment of Nuclear Engineering, Faculty of Modern Sciences and Technologies, Graduate University of Advanced Technology, Kerman 7631885356, IranDepartment of Physics, Payame Noor University (PNU), Tehran 1599959515, IranSpace Science Centre (ANGKASA), Institute of Climate Change (IPI), Universiti Kebangsaan Malaysia, Bangi 43600, MalaysiaCentre for Applied Physics and Radiation Technologies, School of Engineering and Technology, Sunway University, Bandar Sunway, Petaling Jaya 47500, MalaysiaIn 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.https://www.mdpi.com/1996-1944/15/19/6667metamaterialneutron radiation shieldingcurrent transmission rateMCNPXconcrete |
| spellingShingle | Marzieh Hassanpour Mehdi Hassanpour Simin Faghihi Saeedeh Khezripour Mohammadreza Rezaie Parvin Dehghanipour Mohammad Rashed Iqbal Faruque Mayeen Uddin Khandaker Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo Simulation Materials metamaterial neutron radiation shielding current transmission rate MCNPX concrete |
| title | Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo Simulation |
| title_full | Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo Simulation |
| title_fullStr | Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo Simulation |
| title_full_unstemmed | Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo Simulation |
| title_short | Introduction of Graphene/h-BN Metamaterial as Neutron Radiation Shielding by Implementing Monte Carlo Simulation |
| title_sort | introduction of graphene h bn metamaterial as neutron radiation shielding by implementing monte carlo simulation |
| topic | metamaterial neutron radiation shielding current transmission rate MCNPX concrete |
| url | https://www.mdpi.com/1996-1944/15/19/6667 |
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