Investigative Study of Neutronic Safety Parameters of HPR and EPR Using the MCNP Code

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dc.contributor.authorAbrefah, R.G.
dc.contributor.authorAtsu, P.M.
dc.contributor.authorSogbadji, R.B.M.
dc.date.accessioned2019-12-11T11:51:42Z
dc.date.available2019-12-11T11:51:42Z
dc.date.issued2019-06-12
dc.descriptionResearch Articleen_US
dc.description.abstractAs part of technology assessment of proposed commercial nuclear power reactor technologies for Ghana’s Nuclear Power Programme, the neutronic safety parameters of the European Pressurized Reactor (EPR) and High Temperature Pressurized Reactor (HPR) reactor technologies are theoretically analyzed and compared. 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 HPR, which is still under construction and under theoretical safety analysis, showed good inherent safety features comparable to the already existing EPR technology.en_US
dc.identifier.otherhttps://doi.org/10.1080/00295450.2019.1618130
dc.identifier.urihttp://ugspace.ug.edu.gh/handle/123456789/34131
dc.language.isoenen_US
dc.publisherJournal Nuclear Technologyen_US
dc.relation.ispartofseries206;2020
dc.subjectReactivity temperature coefficientsen_US
dc.subjectmoderator void coefficienten_US
dc.subjectcriticalityen_US
dc.subjectneutron behavioren_US
dc.titleInvestigative Study of Neutronic Safety Parameters of HPR and EPR Using the MCNP Codeen_US
dc.typeArticleen_US

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