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dc.contributor.advisorSerfontein, D.E.
dc.contributor.authorRichards, Guy Anthony
dc.date.accessioned2014-05-29T08:06:28Z
dc.date.available2014-05-29T08:06:28Z
dc.date.issued2012
dc.identifier.urihttp://hdl.handle.net/10394/10585
dc.descriptionMIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2012en_US
dc.description.abstractSocial and environmental justice for a growing and developing global population requires significant increases in energy use. A possible means of contributing to this energy increase is to incinerate plutonium from spent fuel of pressurised light water reactors (Pu(PWR)) in high-temperature reactors such as the Pebble Bed Modular Reactor Demonstration Power Plant 400 MWth (PBMR-DPP-400). Previous studies showed that at low temperatures a 3 g Pu(PWR) loading per fuel sphere or less had a positive uniform temperature reactivity coefficient (UTC) in a PBMR DPP-400. The licensing of this fuel design is consequently unlikely. In the present study it was shown by diffusion simulations of the neutronics, using VSOP-99/05, that there is a fuel design containing thorium and plutonium that achieves a negative maximum UTC. Further, a fuel design containing 12 g Pu(PWR) loading per fuel sphere achieved a negative maximum UTC as well as the other PBMR (Ltd.) safety limits of maximum power per fuel sphere, fast fluence and maximum temperatures. It is proposed that the low average thermal neutron flux, caused by reduced moderation and increased absorption of thermal neutrons due to the higher plutonium loading, is responsible for these effects. However, to fully understand the mechanisms involved a detailed quantitative analysis of the roll of each factor is required. A 12 g Pu(PWR) loading per fuel sphere analysis shows a burn-up of 180.7 GWd/tHM which is approximately double the proposed PBMR (Ltd.) low enriched uranium fuel burn-up. The spent fuel has only a decrease of 24.5 % in the Pu content which is sub-optimal with respect to proliferation and waste disposal objectives. Incinerating Pu(PWR) in the PBMR-DPP 400 MWth is potentially licensable and economically feasible and should be considered for application by industry.en_US
dc.language.isoenen_US
dc.subjectHigh Temperature Gas-cooled Reactoren_US
dc.subjectHTGRen_US
dc.subjectHTRen_US
dc.subjectPBMR DPP-400en_US
dc.subjectVSOP-99/05en_US
dc.subjectReactor grade plutoniumen_US
dc.subjectUniform temperature reactivity coefficient (UTC)en_US
dc.titleThe influence of thorium on the temperature reactivity coefficient in a 400 MWth pebble bed high temperature plutonium incinerator reactoren
dc.typeThesisen_US
dc.description.thesistypeMastersen_US


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