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http://dx.doi.org/10.1016/j.net.2019.01.004

Thermal neutron albedo and flux for different geometries neutron guide  

Azimkhani, S. (Department of Physics, Faculty of Sciences, University of Mohaghegh Ardabili)
Rezaei Ochbelagh, D. (Department of Energy Engineering & Physics, Amirkabir University of Technology (Tehran Polytechnic))
Zolfagharpour, F. (Department of Physics, Faculty of Sciences, University of Mohaghegh Ardabili)
Publication Information
Nuclear Engineering and Technology / v.51, no.4, 2019 , pp. 1075-1080 More about this Journal
Abstract
This paper presents a study on thermal neutron reflection properties of neutron guide for cylinder, spindle, elliptic and parabolic geometries using $^{241}Am-Be$ neutron source (5.2 Ci) and $BF_3$ 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. 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 $0.46{\pm}0.001$ at 12 cm thickness of parabolic guide.
Keywords
Thermal neutron; Reflection; Neutron guide; Flux; Parabolic; Albedo;
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