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Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.endPage 613 -
dc.citation.number 3 -
dc.citation.startPage 598 -
dc.citation.title NUCLEAR TECHNOLOGY -
dc.citation.volume 196 -
dc.contributor.author Kim, Kyung Mo -
dc.contributor.author Jeong, Yeong Shin -
dc.contributor.author Kim, In Guk -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2023-12-21T22:50:19Z -
dc.date.available 2023-12-21T22:50:19Z -
dc.date.created 2016-12-26 -
dc.date.issued 2016-12 -
dc.description.abstract The importance of passive safety for commercial nuclear power plants has been emphasized after the nuclear accidents that occurred at Three Mile Island and Fukushima. A combination of unexpected human errors, severe natural disasters, and defects of system designs led to the accidents, thereby highlighting the vulnerability of established safety systems of commercial nuclear power plants. Various passive safety systems are under development to mitigate design-basis accidents. However, several uncertainties and problems have been pointed out. As a solution to the problems, this paper proposes various designs for a passive in-core cooling system (PINCs) based on hybrid heat pipes. The feasibility and coolability of the PINCs as a passive safety system for commercial pressurized water reactors was investigated using experimental works and numerical analyses. The PINCs showed sufficient coolability to mitigate station blackout conditions by delaying core uncovery. Additionally, several PINCs concepts for advanced nuclear power plants such as a small modular reactor and Generation IV reactors are suggested. -
dc.identifier.bibliographicCitation NUCLEAR TECHNOLOGY, v.196, no.3, pp.598 - 613 -
dc.identifier.doi 10.13182/NT16-32 -
dc.identifier.issn 0029-5450 -
dc.identifier.scopusid 2-s2.0-85002601608 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/21095 -
dc.identifier.url http://www.ans.org/pubs/journals/nt/a_39034 -
dc.identifier.wosid 000390524000015 -
dc.language 영어 -
dc.publisher AMER NUCLEAR SOC -
dc.title Development of passive in-core cooling system for nuclear safety using hybrid heat pipe -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Passive in-core cooling system -
dc.subject.keywordAuthor hybrid heat pipe -
dc.subject.keywordAuthor nuclear safety -
dc.subject.keywordPlus THERMOSIPHONS -
dc.subject.keywordPlus REMOVAL -
dc.subject.keywordPlus DESIGN -

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