Feasibility study of photo-neutron flux in various irradiation channels of Ghana MNSR using a Monte Carlo code |
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Authors: | SA Birikorang EHK Akaho BJB Nyarko E Ampomah-Amoako Debrah K Seth RA Gyabour RBM Sogbgaji |
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Affiliation: | 1. Department of Nuclear Engineering & Material Science, School of Nuclear and Allied Sciences (SNAS), University of Ghana, P.O. Box AE 1, Atomic Energy, Accra, Ghana;2. National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG 80, Legon, Accra-Ghana |
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Abstract: | Computer simulation was carried out for photo-neutron source variation in outer irradiation channel, inner irradiation channels and the fission channel of a tank-in-pool reactor, a Miniature Neutron Source Reactor (MNSR) in sub-critical condition. Evaluation of the photo-neutron was done after the reactor has been in sub-critical condition for three month period using Monte Carlo Neutron Particle (MCNP) code. Neutron flux monitoring from the Micro Computer Control Loop System (MCCLS) was also investigated at sub-critical condition. The recorded neutron fluxes from the MCCLS after investigations were used to calculate the power of the reactor at sub-critical state. The computed power at sub-critical state was used to normalize the un-normalized results from the MCNP. |
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Keywords: | Photo-neutrons Monte Carlo code Irradiation channel Neutron flux |
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