Two-Phase Flow Modeling of Critical Heat Flux for Subcooled and Low-Quality Flow Boiling

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dc.contributor.authorKwon, YM-
dc.contributor.authorSuk, SD-
dc.contributor.authorChang, Soon-Heung-
dc.date.accessioned2013-03-15T19:51:41Z-
dc.date.available2013-03-15T19:51:41Z-
dc.date.created2012-02-06-
dc.date.issued1998-
dc.identifier.citationThe 1st Korea-Japan Symposium on Nuclear Thermal Hydaulics and Safety, v., no., pp. --
dc.identifier.urihttp://hdl.handle.net/10203/123240-
dc.languageENG-
dc.titleTwo-Phase Flow Modeling of Critical Heat Flux for Subcooled and Low-Quality Flow Boiling-
dc.typeConference-
dc.type.rimsCONF-
dc.citation.publicationnameThe 1st Korea-Japan Symposium on Nuclear Thermal Hydaulics and Safety-
dc.identifier.conferencecountrySouth Korea-
dc.identifier.conferencecountrySouth Korea-
dc.contributor.localauthorChang, Soon-Heung-
dc.contributor.nonIdAuthorKwon, YM-
dc.contributor.nonIdAuthorSuk, SD-
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NE-Conference Papers(학술회의논문)
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