Calculation of thermal neutron albedo for mono-material and bi-material reflectors  被引量:1

Calculation of thermal neutron albedo for mono-material and bi-material reflectors

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作  者:Sara Azimkhani Farhad Zolfagharpour Farhood Ziaie 

机构地区:[1]Department of Physics, University of Mohaghegh Ardabili [2]Radiation Application Research School, Nuclear Science & Technology Research Institute

出  处:《Nuclear Science and Techniques》2018年第9期185-191,共7页核技术(英文)

摘  要:Thermal neutron albedo has been investigated for different thicknesses of mono-material and bi-material reflectors. An equation has been obtained for a bi-material reflector by considering the neutron diffusion equation. The bi-material reflector consists of binary combinations of water, graphite, lead, and polyethylene. An experimental measurement of thermal neutron albedo has also been conducted for mono-material and bi-material reflectors by using a^(241) Am–Be(5.2 Ci) neutron source and a BF3 detector. The maximum value of thermal neutron albedo was obtained for a polyethylene–water combination(0.95 ± 0.02).Thermal neutron albedo has been investigated for different thicknesses of mono-material and bi-material reflectors. An equation has been obtained for a bi-material reflector by considering the neutron diffusion equation. The bi-material reflector consists of binary combinations of water, graphite, lead, and polyethylene. An experimental measurement of thermal neutron albedo has also been conducted for mono-material and bi-material reflectors by using a^(241) Am–Be(5.2 Ci) neutron source and a BF3 detector. The maximum value of thermal neutron albedo was obtained for a polyethylene–water combination(0.95 ± 0.02).

关 键 词:NEUTRON current BI-MATERIAL REFLECTOR Thermal NEUTRON ALBEDO BF3 detector Reflection Diffusion equation 

分 类 号:TL[核科学技术]

 

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