KOREAN DEVELOPMENT OF ADVANCED THERMAL-HYDRAULIC CODES FOR WATER REACTORS AND HTGRs: SPACE AND GAMMA

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dc.contributor.authorNo, Hee-Cheonko
dc.contributor.authorHa, Sang-Junko
dc.contributor.authorKim, Kyung-Dooko
dc.contributor.authorLim, Hong-Sikko
dc.contributor.authorLee, Eo-Hwakko
dc.contributor.authorJin, Hyung-Gonko
dc.date.accessioned2013-08-08T05:46:53Z-
dc.date.available2013-08-08T05:46:53Z-
dc.date.created2013-02-28-
dc.date.created2013-02-28-
dc.date.issued2013-01-
dc.identifier.citationNUCLEAR TECHNOLOGY, v.181, no.1, pp.24 - 43-
dc.identifier.issn0029-5450-
dc.identifier.urihttp://hdl.handle.net/10203/174627-
dc.description.abstractThe Korea nuclear industry has been developing the thermal-hydraulic system analysis Safety and Performance Analysis CodE (SPACE) and the GAs Multicomponent Mixture Analysis (GAMMA) code for safety analysis of pressurized water reactors (PWRs) and high-temperature gas-cooled reactors (HTGRs), respectively. SPACE will replace outdated vendor-supplied codes and will be used for the safety analysis of operating PWRs and for the design of an advanced PWR. SPACE consists of up-to-date physical models of two-phase flow dealing with multidimensional two-fluid, three-fieldflow GAMMA consists of multidimensional governing equations consisting of the basic equations for continuity, momentum conservation, energy conservation of the gas mixture, and mass conservation of n species. GAMMA is based on a porous media model so that thermofluid and chemical reaction behaviors in a multicomponent mixture system and heat transfer within solid components, free and forced convection between a solid and a fluid, and radiative heat transfer between solid surfaces can be dealt with. GAMMA has a two-dimensional helium turbine model based on the throughflow calculation and a coupled neutronics thermal-hydraulic model. Extensive code assessment has been performed for the verification and validation of SPACE and GAMMA.-
dc.languageEnglish-
dc.publisherAMER NUCLEAR SOC-
dc.subjectAIR-INGRESS ACCIDENT-
dc.subjectANNULAR-FLOW-
dc.subjectNUCLEAR GRAPHITE-
dc.subjectENTRAINMENT-
dc.subjectOXIDATION-
dc.titleKOREAN DEVELOPMENT OF ADVANCED THERMAL-HYDRAULIC CODES FOR WATER REACTORS AND HTGRs: SPACE AND GAMMA-
dc.typeArticle-
dc.identifier.wosid000312973800004-
dc.identifier.scopusid2-s2.0-84872745997-
dc.type.rimsART-
dc.citation.volume181-
dc.citation.issue1-
dc.citation.beginningpage24-
dc.citation.endingpage43-
dc.citation.publicationnameNUCLEAR TECHNOLOGY-
dc.contributor.localauthorNo, Hee-Cheon-
dc.contributor.nonIdAuthorHa, Sang-Jun-
dc.contributor.nonIdAuthorKim, Kyung-Doo-
dc.contributor.nonIdAuthorLim, Hong-Sik-
dc.contributor.nonIdAuthorLee, Eo-Hwak-
dc.type.journalArticleArticle; Proceedings Paper-
dc.subject.keywordAuthorSPACE-
dc.subject.keywordAuthorGAMMA-
dc.subject.keywordAuthorsafety analysis code-
dc.subject.keywordPlusAIR-INGRESS ACCIDENT-
dc.subject.keywordPlusANNULAR-FLOW-
dc.subject.keywordPlusNUCLEAR GRAPHITE-
dc.subject.keywordPlusENTRAINMENT-
dc.subject.keywordPlusOXIDATION-
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