DC Field | Value | Language |
---|---|---|
dc.contributor.author | No, Hee-Cheon | ko |
dc.contributor.author | Ha, Sang-Jun | ko |
dc.contributor.author | Kim, Kyung-Doo | ko |
dc.contributor.author | Lim, Hong-Sik | ko |
dc.contributor.author | Lee, Eo-Hwak | ko |
dc.contributor.author | Jin, Hyung-Gon | ko |
dc.date.accessioned | 2013-08-08T05:46:53Z | - |
dc.date.available | 2013-08-08T05:46:53Z | - |
dc.date.created | 2013-02-28 | - |
dc.date.created | 2013-02-28 | - |
dc.date.issued | 2013-01 | - |
dc.identifier.citation | NUCLEAR TECHNOLOGY, v.181, no.1, pp.24 - 43 | - |
dc.identifier.issn | 0029-5450 | - |
dc.identifier.uri | http://hdl.handle.net/10203/174627 | - |
dc.description.abstract | The 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 SPACE will replace outdated vendor-supplied codes and will be used for the safety analysis of operating PWRs and for the design of an advanced PWR.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.language | English | - |
dc.publisher | AMER NUCLEAR SOC | - |
dc.subject | AIR-INGRESS ACCIDENT | - |
dc.subject | ANNULAR-FLOW | - |
dc.subject | NUCLEAR GRAPHITE | - |
dc.subject | ENTRAINMENT | - |
dc.subject | OXIDATION | - |
dc.title | KOREAN DEVELOPMENT OF ADVANCED THERMAL-HYDRAULIC CODES FOR WATER REACTORS AND HTGRs: SPACE AND GAMMA | - |
dc.type | Article | - |
dc.identifier.wosid | 000312973800004 | - |
dc.identifier.scopusid | 2-s2.0-84872745997 | - |
dc.type.rims | ART | - |
dc.citation.volume | 181 | - |
dc.citation.issue | 1 | - |
dc.citation.beginningpage | 24 | - |
dc.citation.endingpage | 43 | - |
dc.citation.publicationname | NUCLEAR TECHNOLOGY | - |
dc.contributor.localauthor | No, Hee-Cheon | - |
dc.contributor.nonIdAuthor | Ha, Sang-Jun | - |
dc.contributor.nonIdAuthor | Kim, Kyung-Doo | - |
dc.contributor.nonIdAuthor | Lim, Hong-Sik | - |
dc.contributor.nonIdAuthor | Lee, Eo-Hwak | - |
dc.type.journalArticle | Article; Proceedings Paper | - |
dc.subject.keywordAuthor | SPACE | - |
dc.subject.keywordAuthor | GAMMA | - |
dc.subject.keywordAuthor | safety analysis code | - |
dc.subject.keywordPlus | AIR-INGRESS ACCIDENT | - |
dc.subject.keywordPlus | ANNULAR-FLOW | - |
dc.subject.keywordPlus | NUCLEAR GRAPHITE | - |
dc.subject.keywordPlus | ENTRAINMENT | - |
dc.subject.keywordPlus | OXIDATION | - |
Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.