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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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dc.citation.number 2 -
dc.citation.startPage 103915 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 58 -
dc.contributor.author Bae, Banseok -
dc.contributor.author Park, Youngjae -
dc.contributor.author Lee, Yunju -
dc.contributor.author Kim, Ji Hyun -
dc.contributor.author Kim, Hyungdae -
dc.date.accessioned 2025-12-02T13:12:57Z -
dc.date.available 2025-12-02T13:12:57Z -
dc.date.created 2025-10-20 -
dc.date.issued 2026-02 -
dc.description.abstract This study experimentally investigates the influence of CRUD on reflood heat transfer performance under bottom reflood conditions following the actuation of ECCS during LOCA in a PWR. To simulate the in-reactor environment, CRUD-deposited test specimens were fabricated under prototypical PWR water chemistry conditions, and reflood experiments were conducted using a single heated rod configuration. Key thermal-hydraulic parameters-including quench front propagation speed, rewetting temperature, critical heat flux, and film boiling heat transfer coefficient-were quantitatively evaluated through high-speed flow visualization and inverse heat conduction analysis based on wall temperature measurements from an embedded thermocouple. The experimental results revealed that, on CRUD-deposited surfaces, the quench front formed earlier and propagated upward at a speed up to 2.3 times faster than that observed on bare surfaces. The CHF increased by up to 1.9 times, while the rewetting temperature rose by as much as 80 degrees C. The film boiling heat transfer coefficient in the post-CHF region was enhanced by up to 13.6 %, and the overall quenching time was reduced by approximately 50 %. High-speed visualization revealed frequent local vapor film collapses and direct liquid-surface contact events on the CRUD-deposited surfaces. These results indicate that the porous microstructure and hydrophilic surface characteristics of CRUD may promote coolant supply and induce vapor film destabilization, thereby enhancing reflood heat transfer performance of overheated fuel rods during LOCA. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.58, no.2, pp.103915 -
dc.identifier.doi 10.1016/j.net.2025.103915 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-105018073277 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/88761 -
dc.identifier.wosid 001584479700001 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Experimental investigation of reflood heat transfer characteristics on CRUD-deposited surfaces -
dc.type Article -
dc.description.isOpenAccess TRUE -
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 CRUD -
dc.subject.keywordAuthor Reflood -
dc.subject.keywordAuthor Quenching -
dc.subject.keywordAuthor Critical heat flux(CHF) -
dc.subject.keywordAuthor Film boiling -
dc.subject.keywordAuthor ECCS performance -
dc.subject.keywordPlus FUEL CRUD -
dc.subject.keywordPlus WATER -
dc.subject.keywordPlus CORROSION -

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