Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2018, Vol. 29 ›› Issue (9): 130 doi: 10.1007/s41365-018-0466-1

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Calculation of thermal neutron albedo for mono- and bi-material reflectors

Sara Azimkhani1 • Farhad Zolfagharpour1 • Farhood Ziaie2   

  1. 1 Department of Physics, University of Mohaghegh Ardabili, P.O. Box 179, Ardabil, Iran
    2 Radiation Application Research School, Nuclear Science & Technology Research Institute, P.O. Box 11365-3486, Tehran, Iran
  • Received:2017-09-27 Revised:2018-03-23 Accepted:2018-03-27
  • Contact: Sara Azimkhani
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Sara Azimkhani, Farhad Zolfagharpour, Farhood Ziaie. Calculation of thermal neutron albedo for mono- and bi-material reflectors.Nuclear Science and Techniques, 2018, 29(9): 130     doi: 10.1007/s41365-018-0466-1


Thermal neutron albedo has been investigated for different thicknesses of mono-material and bi-material reflectors. An equation has been obtained for a bi-material reflector by considering the neutron diffusion equation. The bi-material reflector consists of binary combinations of water, graphite, lead, and polyethylene. An experimental measurement of thermal neutron albedo has also been conducted for mono-material and bi-material reflectors by using a 241Am–Be (5.2 Ci) neutron source and a BF3 detector. The maximum value of thermal neutron albedo was obtained for a polyethylene–water combination (0.95 ± 0.02).

Key words: Neutron current, Bi-material reflector, Thermal neutron albedo, BF3 detector, Reflection, Diffusion equation