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Neutronics calculation of the conceptual TRISO duplex fuel rod design

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dc.citedby6
dc.contributor.authorRabir M.H.en_US
dc.contributor.authorIsmail A.F.en_US
dc.contributor.authorYahya M.S.en_US
dc.contributor.authorid55898782000en_US
dc.contributor.authorid29067828200en_US
dc.contributor.authorid56287449000en_US
dc.date.accessioned2023-05-29T09:07:28Z
dc.date.available2023-05-29T09:07:28Z
dc.date.issued2021
dc.descriptionCylinders (shapes); High temperature reactors; Light water reactors; Oxide minerals; Thoria; Uranium dioxide; Annular fuel; Fissile materials; Fuel design; Fuel rod design; Fuel rods; Light water; Neutronics; Neutronics performance; Fuelsen_US
dc.description.abstractThe duplex fuel pellet includes UO2 components as seed and ThO2 blanket, originally designed to increase the breeding rate of fissile materials in light water breeder reactors. However, the seed portion alone concentrates most of the energy released from the fission reaction, which can make the seed temperature too high. The duplex fuel potential for the high-temperature reactor (HTR) using TRISO fuel has never been researched. MCNPX simulation was conducted to compare the neutronics performance of normal TRISO fuel with that of TRISO duplex fuel. Two types of HTR fuel rod, the cylinder and the annular rod, were simulated and compared to see whether the duplex neutron characteristics would be better in the cylinder or annular fuel compact design. The TRISO duplex rods produced higher burnup than normal rods up to 5% higher for cylinder and 6% for annular rods. The TRISO duplex rod is also capable of maintaining longer criticality, producing smaller kinf changes and reducing the potential for plutonium build-up. The proposed TRISO duplex conceptual fuel design has an interesting neutronic properties, which offers possibilities for future studies. � 2021 The Author(s)en_US
dc.description.natureFinalen_US
dc.identifier.ArtNo101005
dc.identifier.doi10.1016/j.nme.2021.101005
dc.identifier.scopus2-s2.0-85104600796
dc.identifier.urihttps://www.scopus.com/inward/record.uri?eid=2-s2.0-85104600796&doi=10.1016%2fj.nme.2021.101005&partnerID=40&md5=50f0d102c4c2e5953b6af96f33630441
dc.identifier.urihttps://irepository.uniten.edu.my/handle/123456789/26176
dc.identifier.volume27
dc.publisherElsevier Ltden_US
dc.relation.ispartofAll Open Access, Gold
dc.sourceScopus
dc.sourcetitleNuclear Materials and Energy
dc.titleNeutronics calculation of the conceptual TRISO duplex fuel rod designen_US
dc.typeArticleen_US
dspace.entity.typePublication
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