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Neutronic assessment of triso particle fuels in a small fluoride salt-cooled high-temperature reactor

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dc.contributor.authorMohamed H.en_US
dc.contributor.authorLindley B.A.en_US
dc.contributor.authorParks G.en_US
dc.contributor.authorLepp�nen J.en_US
dc.contributor.authorid57136356100en_US
dc.contributor.authorid49863846400en_US
dc.contributor.authorid7103057721en_US
dc.contributor.authorid27168608400en_US
dc.date.accessioned2023-05-29T06:13:32Z
dc.date.available2023-05-29T06:13:32Z
dc.date.issued2016
dc.descriptionEconomic and social effects; Fluorine compounds; High temperature reactors; Monte Carlo methods; Random processes; Axial direction; Beginning of lives; Computational expense; Monte Carlo codes; Multiplication factor; Neutronic calculations; Radial direction; Serpent; Fuelsen_US
dc.description.abstractThis study investigates the challenges and possible simplifications in modelling TRISO fuel compacts in a small fluoride salt-cooled high-temperature reactor (FHR), namely the 125 MWth SmAHTR. Modelling TRISO fuel compacts in Monte Carlo codes is non-trivial due to their heterogeneity and randomness. The complexity of the TRISO fuel technically requires thorough and elaborate modelling in order to obtain precise and accurate neutronic calculations. Unfortunately, the trade-offs are tedious modelling, long calculation times and computational expense. Hence, the objective of this study is to show some modelling justifications that can be made without losing accuracy in estimating the infinite multiplication factor, kinf. The Monte Carlo code used for the study is Serpent 2. This study is divided into two main parts: radial and axial analyses. In the radial analysis, a fuel assembly is modelled to study the effect of randomness in radial direction. On the other hand, the axial analysis only looks at a single fuel compact, as it is more concerned with the randomness in the axial direction. Results show that the effect of randomness is insignificant especially at beginning of life and also throughout the burnup period as long as the burnup regions of the models are highly discretized.en_US
dc.description.natureFinalen_US
dc.identifier.epage3282
dc.identifier.scopus2-s2.0-84992034566
dc.identifier.spage3275
dc.identifier.urihttps://www.scopus.com/inward/record.uri?eid=2-s2.0-84992034566&partnerID=40&md5=0b4bbd6db9511f5c0c5ebf187c84d8a5
dc.identifier.urihttps://irepository.uniten.edu.my/handle/123456789/22938
dc.identifier.volume5
dc.publisherAmerican Nuclear Societyen_US
dc.sourceScopus
dc.sourcetitlePhysics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century
dc.titleNeutronic assessment of triso particle fuels in a small fluoride salt-cooled high-temperature reactoren_US
dc.typeConference Paperen_US
dspace.entity.typePublication
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