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- W2032930711 abstract "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." @default.
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- W2032930711 date "2011-07-01" @default.
- W2032930711 modified "2023-09-28" @default.
- W2032930711 title "Feasibility study of photo-neutron flux in various irradiation channels of Ghana MNSR using a Monte Carlo code" @default.
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- W2032930711 doi "https://doi.org/10.1016/j.anucene.2011.03.004" @default.
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