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dc.contributor.authorSpedding, James
dc.contributor.authorHo, Mark
dc.contributor.authorLu, Weijian
dc.date.accessioned2022-02-05T21:54:33Z
dc.date.available2022-02-05T21:54:33Z
dc.date.copyright4/16/2021 12:00:00 AM
dc.date.issued2021
dc.identifier.issn2332-8983
dc.identifier.otherners_007_04_041401.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276555
dc.description.abstractThe open pool Australian light-water (OPAL) reactor cold neutron source (CNS) is a 20 L liquid deuterium thermosiphon system which has performed consistently but will require replacement in the future. The CNS deuterium exploits neutronic heating to passively drive the thermosiphon loop and is cryogenically cooled by forced convective helium flow via a heat exchanger. In this study, a detailed computational fluid dynamics (CFD) model of the complete thermosiphon system was developed for simulation. Unlike previous studies, the simulation employed a novel polyhedral mesh technique. Results demonstrated that the polyhedral technique reduced simulation computational requirements and convergence time by an order of magnitude while predicting thermosiphon performance to within 1% accuracy when compared with prototype experiments. The simulation model was extrapolated to OPAL operating conditions and confirmed the versatility of the CFD model as an engineering design and preventative maintenance tool. Finally, simulations were performed on a proposed second-generation CNS design that increases the CNS moderator deuterium volume by 5 L, and results confirmed that the geometry maintains the thermosiphon deuterium in the liquid state and satisfies the CNS design criteria.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleComputational Fluid Dynamics Simulations of the Cold Neutron Source at the OPAL Reactor
dc.typeJournal Paper
dc.journal.volume7
dc.journal.issue4
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4049054
dc.journal.fristpage041401-1
dc.journal.lastpage041401-11
dc.page11
dc.treeJournal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 004
dc.contenttypeFulltext


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