TAILIEUCHUNG - Thermal neutron albedo and flux for different geometries neutron guide

This paper presents a study on thermal neutron reflection properties of neutron guide for cylinder, spindle, elliptic and parabolic geometries using 241Am-Be neutron source ( Ci) and BF3 detector, whereas neutron guide is important instrument for transportation of neutrons. To this goal, the required inner and outer radii of neutron guide have been calculated to achieve the highest guided thermal neutron flux based on MCNPX Monte Carlo code. | Thermal neutron albedo and flux for different geometries neutron guide Nuclear Engineering and Technology 51 (2019) 1075e1080 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: Original Article Thermal neutron albedo and flux for different geometries neutron guide S. Azimkhani a, *, D. Rezaei Ochbelagh b, F. Zolfagharpour a a Department of Physics, Faculty of Sciences, University of Mohaghegh Ardabili, . Box 179, Ardabil, Iran b Department of Energy Engineering & Physics, Amirkabir University of Technology (Tehran Polytechnic), Tehran, Iran a r t i c l e i n f o a b s t r a c t Article history: This paper presents a study on thermal neutron reflection properties of neutron guide for cylinder, Received 8 April 2018 spindle, elliptic and parabolic geometries using 241Am-Be neutron source ( Ci) and BF3 detector, Received in revised form whereas neutron guide is important instrument for transportation of neutrons. To this goal, the required 16 December 2018 inner and outer radii of neutron guide have been calculated to achieve the highest guided thermal Accepted 7 January 2019 Available online 8 January 2019 neutron flux based on MCNPX Monte Carlo code. The maximum flux of cylinder geometry with a length 50 cm has been obtained at an inner radius 9 cm and an outer radius 21 cm. Also, the maximum value of thermal neutron albedo is ± at 12 cm thickness of parabolic guide. Keywords: Thermal neutron © 2019 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the Reflection CC BY-NC-ND license (). Neutron guide Flux Parabolic Albedo 1. Introduction nickel or titanium to reflect neutrons [8]. Currently, elliptic and ballistic geometries are investigated for neutron guides [9,10]. Performance improvement of low-activity neutron source

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• Nuclear engineering and technology
• Thermal neutron albedo
• Flux for different geometries neutron guide
• Elliptic and parabolic geometries
• MCNPX Monte Carlo code
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
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