Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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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)
  • Received : 2018.04.08
  • Accepted : 2019.01.07
  • Published : 2019.05.25
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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.

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References

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