CFD-DEM analysis of realistically heated pebble bed geometry

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dc.contributor.authorMardus-Hall, Ren_AU
dc.contributor.authorYeoh, GHen_AU
dc.contributor.authorHo, Men_AU
dc.date.accessioned2023-06-29T06:26:25Zen_AU
dc.date.available2023-06-29T06:26:25Zen_AU
dc.date.issued2019-08-18en_AU
dc.date.statistics2023-06-29en_AU
dc.description.abstractPebble-bed, molten salt cooled reactors (PB-FHR) are a prominent reactor design and stepping stone between current generation reactors and Gen IV liquid fuelled molten salt reactor designs. They utilize spherical fuel elements as used in previous gas cooled pebble-bed reactors, while the coolant is a molten salt capable of much higher temperatures than conventional light-water reactors with the advantage of remaining at atmospheric pressure. This study implements a realistic power distribution, determined from a neutronic analysis, on to a packed bed of fuel pebbles. Utilizing coupled computational fluid dynamics (CFD) and discrete element methods (DEM) it is possible to observe the fluid and pebble flow and heat transfer characteristics in such PB-FHR systems. Previous work by the authors considered an isothermal case and a uniform power distribution across the pebble bed. The inclusion of a realistic power distribution allows for realization of accurate temperature profiles throughout the coolant fluid and fuel pebbles. The coupled nature of the method includes the pebble-pebble, pebble-fluid, and fluid-pebble exchange of momentum and energy. Current results are for a PB-FHR geometry at steady state adapted from a pebble recirculation experiment. The pebbles within the core are all assumed to be fuel pebbles, with no dummy graphite or absorber pebbles present. Analysis has demonstrated the strongly non-uniform power distribution present in the fuel pebbles in such a reactor. This non-uniformity is exacerbated at the near wall region due to the moderator effect where fuel pebbles have a marked increase in power. © 2019 The Authors.en_AU
dc.identifier.booktitleProceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019)en_AU
dc.identifier.citationMardus-Hall, R., Yeoh, G., & Ho, M. (2019). CFD-DEM analysis of realistically heated pebble bed geometry. Paper presented to the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, (NURETH 2019), 18-23 Aug 2019, Portland, OR. In Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019). (pp. 1726-1739). Retrieved from: https://www.ans.org/pubs/proceedings/article-46184/en_AU
dc.identifier.conferenceenddate23 August 2019en_AU
dc.identifier.conferencename18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, (NURETH 2019)en_AU
dc.identifier.conferenceplacePortland, Oregonen_AU
dc.identifier.conferencestartdate18 August 2019en_AU
dc.identifier.isbnISBN: 978-1-5108-9345-0en_AU
dc.identifier.pagination1726-1739en_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/15073en_AU
dc.language.isoenen_AU
dc.publisherAmerican Nuclear Societyen_AU
dc.relation.urihttps://www.ans.org/pubs/proceedings/article-46184/en_AU
dc.subjectPebble bed reactorsen_AU
dc.subjectDesignen_AU
dc.subjectGas cooled reactorsen_AU
dc.subjectAtmospheric pressureen_AU
dc.subjectHeat transferen_AU
dc.subjectMolten Salt cooled reactorsen_AU
dc.titleCFD-DEM analysis of realistically heated pebble bed geometryen_AU
dc.typeConference Paperen_AU
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