Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section

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dc.contributor.authorPark, Hae Min-
dc.contributor.authorKim, Taeil-
dc.contributor.authorHeo, Sun-
dc.contributor.authorJeong, Yong Hoon-
dc.date.accessioned2013-03-28T10:53:33Z-
dc.date.available2013-03-28T10:53:33Z-
dc.date.created2012-02-06-
dc.date.issued2010-11-17-
dc.identifier.citationThe 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), v., no., pp. --
dc.identifier.urihttp://hdl.handle.net/10203/165049-
dc.languageENG-
dc.titleCritical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section-
dc.typeConference-
dc.type.rimsCONF-
dc.citation.publicationnameThe 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7)-
dc.identifier.conferencecountrySouth Korea-
dc.identifier.conferencecountrySouth Korea-
dc.contributor.localauthorJeong, Yong Hoon-
dc.contributor.nonIdAuthorPark, Hae Min-
dc.contributor.nonIdAuthorKim, Taeil-
dc.contributor.nonIdAuthorHeo, Sun-
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NE-Conference Papers(학술회의논문)
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