DC Field | Value | Language |
---|---|---|
dc.contributor.author | Shin, Sung Gil | ko |
dc.contributor.author | Lee, Jeong-Ik | ko |
dc.date.accessioned | 2022-09-02T08:00:10Z | - |
dc.date.available | 2022-09-02T08:00:10Z | - |
dc.date.created | 2022-09-02 | - |
dc.date.created | 2022-09-02 | - |
dc.date.issued | 2022-09 | - |
dc.identifier.citation | NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.9, pp.3526 - 3539 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | http://hdl.handle.net/10203/298286 | - |
dc.description.abstract | Nuclear thermal-hydraulic system analysis codes have been developed to simulate nuclear reactor systems, which solve simplified governing equations by replacing source terms with constitutive relations for simulating entire reactor systems with low computational resources. For half a century, many efforts have been made for wider versatility and higher accuracy of system codes, but various factors can affect the code analysis results, and it was difficult to isolate these factors and interpret them individually. In this study, two system codes, RELAP5 and TRACE, which have many users and are highly reliable, are selected to analyze only the effects of constitutive relations. The influence of constitutive relations is analyzed using in-house platforms that replicate constitute relations of RELAP5 and TRACE equally to exclude factors that may affect analysis results, such as governing equation solvers and user effects. Among the various constitutive relations, the analysis is performed on the wall variables expected to have the most influence on the analysis results. Part 1 paper presents the methodology and wall friction model comparison, while Part 2 paper shows wall heat transfer comparison of the two selected codes. | - |
dc.language | English | - |
dc.publisher | KOREAN NUCLEAR SOC | - |
dc.title | Comparative study of constitutive relations implemented in RELAP5 and TRACE – Part I: Methodology & wall friction | - |
dc.type | Article | - |
dc.identifier.wosid | 000863081700005 | - |
dc.identifier.scopusid | 2-s2.0-85132930514 | - |
dc.type.rims | ART | - |
dc.citation.volume | 54 | - |
dc.citation.issue | 9 | - |
dc.citation.beginningpage | 3526 | - |
dc.citation.endingpage | 3539 | - |
dc.citation.publicationname | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.identifier.doi | 10.1016/j.net.2022.03.036 | - |
dc.identifier.kciid | ART002867105 | - |
dc.contributor.localauthor | Lee, Jeong-Ik | - |
dc.description.isOpenAccess | N | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordAuthor | Thermal -Hydraulic Analysis Code | - |
dc.subject.keywordAuthor | Constitutive Relation | - |
dc.subject.keywordAuthor | Closure Model | - |
dc.subject.keywordAuthor | Wall Friction | - |
dc.subject.keywordAuthor | RELAP5TRACE | - |
dc.subject.keywordPlus | SAFETY SYSTEM CODES | - |
dc.subject.keywordPlus | REFLOOD MODEL | - |
dc.subject.keywordPlus | FLOW | - |
dc.subject.keywordPlus | VALIDATION | - |
dc.subject.keywordPlus | IMPROVEMENT | - |
dc.subject.keywordPlus | PREDICTION | - |
dc.subject.keywordPlus | NUMERICS | - |
dc.subject.keywordPlus | FONESYS | - |
Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.