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방인철

Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.startPage 106971 -
dc.citation.title ANNALS OF NUCLEAR ENERGY -
dc.citation.volume 135 -
dc.contributor.author Jeong, Yeong Shin -
dc.contributor.author Kim, Ji Yong -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2023-12-21T18:12:07Z -
dc.date.available 2023-12-21T18:12:07Z -
dc.date.created 2019-08-27 -
dc.date.issued 2020-01 -
dc.description.abstract This paper proposes the new pattern of wire wrap spacer, called U-pattern to enhance coolant mixing and reduce pressure drop for liquid metal cooled reactor fuel assembly. It is designed by designating its winding direction and pin arrangement without any additional structures for fuel assembly. To evaluate its thermal-hydraulic performance, both experimental and numerical approaches are performed; flow visualization experiments using a combined particle image velocimetry (PIV) and matching index-of-refraction (MIR) technique and CFD simulation. The visualized flow field in both axial and lateral planes shows that U-pattern wire wrap spacer has a stronger swirl flow in center subchannel compared to the conventional case. To extend the application ranges to the normal LMFR operation condition, CFD analysis is conducted using ANSYS-CFX. Simulation results indicate 8.60 °C decrease of peak cladding temperature and 5.2% reduced pressure drop respectively. Rod bundle with U-pattern wire spacer has a similar range of bundle loss coefficient at Re < 8500, and a smaller than the conventional one at Re > 10,000. Measurement and calculation results for the U-pattern exhibit that flow is re-distributed to have flatter temperature profile and larger flow channel with the removal of the wire wrap spacer at the center pin brings a lower flow resistance. Therefore, the U-pattern wire wrap spacer for LMFR can enhance the thermal margin and improve economics by promoting thermal mixing and reduction in pressure loss. -
dc.identifier.bibliographicCitation ANNALS OF NUCLEAR ENERGY, v.135, pp.106971 -
dc.identifier.doi 10.1016/j.anucene.2019.106971 -
dc.identifier.issn 0306-4549 -
dc.identifier.scopusid 2-s2.0-85070207413 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/30330 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S0306454919304669?via%3Dihub -
dc.identifier.wosid 000496898500020 -
dc.language 영어 -
dc.publisher Elsevier Ltd -
dc.title Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assembly -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Computational fluid dynamics (CFD) -
dc.subject.keywordAuthor Liquid metal-cooled fast reactor (LMFR) -
dc.subject.keywordAuthor Particle image velocimetry (PIV) -
dc.subject.keywordAuthor Swirl flow -
dc.subject.keywordAuthor Wire wrap spacer -
dc.subject.keywordPlus ROD BUNDLES -
dc.subject.keywordPlus FLOW -
dc.subject.keywordPlus DROP -
dc.subject.keywordPlus MODELS -

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