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CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors

dc.contributor.authorRousseau, Pieter G.
dc.contributor.authorDu Toit, Charl G.
dc.contributor.authorVan Antwerpen, Herman J.
dc.contributor.researchID10184600 - Du Toit, Charl Gabriel De Kock
dc.contributor.researchID11681292 - Van Antwerpen, Hermanus Johannes
dc.date.accessioned2020-04-02T06:32:52Z
dc.date.available2020-04-02T06:32:52Z
dc.date.issued2019
dc.description.abstractAn overview is provided of the role of the various levels of CFD in the different stages of the design, analysis and evaluation of very-high-temperature reactor (VHTR) systems and molten salt reactor (MSR) systems. The biggest challenge in this regard is to satisfy all the phenomenological, physical and time scales in a single model of the complete reactor unit. This is currently not practically feasible but rather addressed by employing models at various levels of abstraction and detail. Simulation models that encompass a large geometrical and temporal scope, such as 1D plant-wide system models, typically use reduced-order models to represent underlying phenomena. For gas-cooled pebble bed reactors a significant amount of work has been done to characterize the flow and heat transfer characteristics within the bed. For prismatic block gas-cooled reactors model development is also well advanced. Gas-cooled reactor systems in general have also been analysed exhaustively at the larger system level. In the case of liquid fuel MSRs the focus has been on multiphysics approaches wherein the neutronics are coupled with the thermal-hydraulics in order to account for the neutron precursor drift due to the velocity field. The CFD work on solid fuel MSRs employed either a porous media approach, or if the discrete element approach was employed, only focused on a very small representative unit cell geometryen_US
dc.identifier.citationRousseau, P.G. et al. 2019. CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors. (In Joshi, J.B. & Nayak, A.K., eds. Advances of computational fluid dynamics in nuclear reactor design and safety assessment. p. 755-800.) [https://doi.org/10.1016/B978-0-08-102337-2.00010-9]en_US
dc.identifier.isbn978-0-08-102337-2
dc.identifier.urihttp://hdl.handle.net/10394/34488
dc.identifier.urihttps://www.sciencedirect.com/science/article/pii/B9780081023372000109
dc.identifier.urihttps://doi.org/10.1016/B978-0-08-102337-2.00010-9
dc.language.isoenen_US
dc.publisherWoodhead Publishingen_US
dc.subjectCFDen_US
dc.subjectHigh temperature reactoren_US
dc.subjectMolten salt reactoren_US
dc.subjectPebble bed reactoren_US
dc.subjectPrismatic block reactoren_US
dc.titleCFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactorsen_US
dc.typeBook chapteren_US

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