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 (5.2 Ci) and BF3 detector, whereas neutron guide is important instrument for transportation of neutrons. To this goal, the requ...
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| Veröffentlicht in: | Nuclear engineering and technology 2019, 51(4), , pp.1075-1080 |
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| Hauptverfasser: | , , |
| Format: | Artikel |
| Sprache: | eng |
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| Online-Zugang: | Volltext |
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| Zusammenfassung: | 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 |
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| ISSN: | 1738-5733 2234-358X |
| DOI: | 10.1016/j.net.2019.01.004 |