Neutronic safety analysis of proposed reactor Technologies for Ghana's nuclear power Plant using the MCNP code

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dc.contributor.author Abrefah, R.G.
dc.contributor.author Atsu, P.M.
dc.contributor.author Sogbadji, R.B.M.
dc.date.accessioned 2019-12-13T15:54:29Z
dc.date.available 2019-12-13T15:54:29Z
dc.date.issued 2019-08-15
dc.identifier.other http://doi.org/10.2298/NTRP190108029A
dc.identifier.uri http://ugspace.ug.edu.gh/handle/123456789/34188
dc.description Research Article en_US
dc.description.abstract In pursuance of sufficient, stable and clean energy to solve the ever-looming power crisis in Ghana, the Nuclear Power Institute of the Ghana Atomic Energy Commission has on the agenda to advise the government on the nuclear power to include in the country's energy mix. After consideration of several proposed nuclear reactor technologies, the Nuclear Power Institute considered a high pressure reactor or vodo-vodyanoi energetichesky reactor as the nuclear power technologies for Ghana's first nuclear power plant. As part of technology assessments, neutronic safety parameters of both reactors are investigated. The MCNP neutronic code was employed as a computational tool to analyze the reactivity temperature coefficients, moderator void coefficient, criticality and neutron behavior at various operating conditions. The high pressure reactor which is still under construction and theoretical safety analysis, showed good inherent safety features which are comparable to the already existing European pressurized reactor technology. en_US
dc.language.iso en en_US
dc.publisher Nuclear Technology & Radiation Protection en_US
dc.relation.ispartofseries 34;3
dc.subject reactivity temperature coefficients en_US
dc.subject moderator void coefficient en_US
dc.subject criticality en_US
dc.subject neutron behavior en_US
dc.title Neutronic safety analysis of proposed reactor Technologies for Ghana's nuclear power Plant using the MCNP code en_US
dc.type Article en_US


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