Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code
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 s...
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| Format: | Article |
| Language: | English |
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VINCA Institute of Nuclear Sciences
2019-01-01
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| Series: | Nuclear Technology and Radiation Protection |
| Subjects: | |
| Online Access: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2019/1451-39941900029A.pdf |
| _version_ | 1811335810176253952 |
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| author | Abrefah Rex G. Atsu Prince M. Sogbadji Robert B. M. |
| author_facet | Abrefah Rex G. Atsu Prince M. Sogbadji Robert B. M. |
| author_sort | Abrefah Rex G. |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-04-13T17:29:25Z |
| format | Article |
| id | doaj.art-41468df0271a4c6f92fa00dfa83921f4 |
| institution | Directory Open Access Journal |
| issn | 1451-3994 1452-8185 |
| language | English |
| last_indexed | 2024-04-13T17:29:25Z |
| publishDate | 2019-01-01 |
| publisher | VINCA Institute of Nuclear Sciences |
| record_format | Article |
| series | Nuclear Technology and Radiation Protection |
| spelling | doaj.art-41468df0271a4c6f92fa00dfa83921f42022-12-22T02:37:37ZengVINCA Institute of Nuclear SciencesNuclear Technology and Radiation Protection1451-39941452-81852019-01-0134323824210.2298/NTRP190108029A1451-39941900029ANeutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP codeAbrefah Rex G.0Atsu Prince M.1Sogbadji Robert B. M.2University of Ghana, Graduate School of Nuclear and Allied Sciences, Atomic Energy, Accra, Ghana + Ghana Nuclear Regulatory Authority, Atomic-Kwabenya, GhanaUniversity of Ghana, Graduate School of Nuclear and Allied Sciences, P.O. Box AE, Atomic Energy, Accra, GhanaUniversity of Ghana, Graduate School of Nuclear and Allied Sciences, Atomic Energy, Accra, Ghana + Ghana Atomic Energy Commission, Nuclear Power Institute, Legon, GhanaIn 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.http://www.doiserbia.nb.rs/img/doi/1451-3994/2019/1451-39941900029A.pdfreactivity temperature coefficientsmoderator void coefficientcriticalityneutron behavior |
| spellingShingle | Abrefah Rex G. Atsu Prince M. Sogbadji Robert B. M. Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code Nuclear Technology and Radiation Protection reactivity temperature coefficients moderator void coefficient criticality neutron behavior |
| title | Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code |
| title_full | Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code |
| title_fullStr | Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code |
| title_full_unstemmed | Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code |
| title_short | Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code |
| title_sort | neutronic safety analysis of proposed reactor technologies for ghana s nuclear power plant using the mcnp code |
| topic | reactivity temperature coefficients moderator void coefficient criticality neutron behavior |
| url | http://www.doiserbia.nb.rs/img/doi/1451-3994/2019/1451-39941900029A.pdf |
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