Fuel burnup calculation of Ghana MNSR using ORIGEN2 and REBUS3 codes

dc.contributor.author	Abrefah, R.G.
dc.contributor.author	Nyarko, B.J.B.
dc.contributor.author	Fletcher, J.J.
dc.contributor.author	Akaho, E.H.K.
dc.date.accessioned	2018-12-06T12:51:02Z
dc.date.available	2018-12-06T12:51:02Z
dc.date.issued	2013-10
dc.description.abstract	Ghana Research Reactor-1 core is to be converted from HEU fuel to LEU fuel in the near future and managing the spent nuclear fuel is very important. A fuel depletion analysis of the GHARR-1 core was performed using ORIGEN2 and REBUS3 codes to estimate the isotopic inventory at end-of-cycle in order to help in the design of an appropriate spent fuel cask. The results obtained for both codes were consistent for U-235 burnup weight percent and Pu-239 build up as a result of burnup. © 2013 Elsevier Ltd.	en_US
dc.identifier.other	Volume 80, Pages 12-16
dc.identifier.other	https://doi.org/10.1016/j.apradiso.2013.05.007
dc.identifier.uri	http://ugspace.ug.edu.gh/handle/123456789/26255
dc.language.iso	en	en_US
dc.publisher	Applied Radiation and Isotopes	en_US
dc.subject	Burnup	en_US
dc.subject	Isotopic inventory	en_US
dc.subject	Plutonium	en_US
dc.subject	Reactivity rundown	en_US
dc.title	Fuel burnup calculation of Ghana MNSR using ORIGEN2 and REBUS3 codes	en_US
dc.type	Article	en_US

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