Thermal neutron albedo and flux for different geometries neutron guide
| Autor: | D. Rezaei Ochbelagh, Farhad Zolfagharpour, S. Azimkhani |
|---|---|
| Jazyk: | angličtina |
| Rok vydání: | 2019 |
| Předmět: |
Physics
020209 energy Astrophysics::High Energy Astrophysical Phenomena Nuclear Theory Flux 02 engineering and technology Radius Albedo lcsh:TK9001-9401 Neutron temperature 030218 nuclear medicine & medical imaging Computational physics 03 medical and health sciences 0302 clinical medicine Nuclear Energy and Engineering 0202 electrical engineering electronic engineering information engineering Reflection (physics) Neutron source Cylinder lcsh:Nuclear engineering. Atomic power Neutron Astrophysics::Earth and Planetary Astrophysics Nuclear Experiment |
| Zdroj: | Nuclear Engineering and Technology, Vol 51, Iss 4, Pp 1075-1080 (2019) |
| ISSN: | 1738-5733 |
| Popis: | 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 (5.2 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. 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 ± 0.001 at 12 cm thickness of parabolic guide. Keywords: Thermal neutron, Reflection, Neutron guide, Flux, Parabolic, Albedo |
| Databáze: | OpenAIRE |
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