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DC Field | Value | Language |
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dc.citation.endPage | 680 | - |
dc.citation.number | 6 | - |
dc.citation.startPage | 668 | - |
dc.citation.title | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | - |
dc.citation.volume | 54 | - |
dc.contributor.author | Lemaire, Matthieu | - |
dc.contributor.author | Lee, Hyunsuk | - |
dc.contributor.author | Tak, Nam-il | - |
dc.contributor.author | Lee, Hyun Chul | - |
dc.contributor.author | Lee, Deokjung | - |
dc.date.accessioned | 2023-12-21T22:37:36Z | - |
dc.date.available | 2023-12-21T22:37:36Z | - |
dc.date.created | 2017-04-13 | - |
dc.date.issued | 2017-03 | - |
dc.description.abstract | This paper presents the application results of MCS/GAMMA+ to multi-physics analysis of OECD/NEA modular high temperature gas-cooled reactor (MHTGR) benchmark Phase I Exercise 3. It is a part of international R&D efforts lead by the Next Generation Nuclear Plant (NGNP) US project to improve the neutron-physics and thermal-fluid simulation of (high temperature gas-cooled reactors) HTGRs, one of the next generations of safer nuclear reactors. Accurate and validated analysis tools are indeed a crucial requirement for safety analysis and licensing of nuclear reactors. To guide this effort, a numerical benchmark on the MHTGR was created by the NGNP project and formally approved in 2012 for international participation by the OECD/NEA. The benchmark defines a common set of exercises and the comparison of solutions obtained with different analysis tools is expected to improve the understanding of simulation methods for HTGRs. The coupled neutronics/thermal-fluid solution presented in this paper was obtained with the neutron transport Monte Carlo code MCS developed by Ulsan National Institute of Science and Technology and the thermal-fluid code GAMMA+ developed by Korean Atomic Energy Research Institute. The purpose of this paper is to present the GAMMA+/MCS coupled system, the calculation methodology, and the obtained solutions. | - |
dc.identifier.bibliographicCitation | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.54, no.6, pp.668 - 680 | - |
dc.identifier.doi | 10.1080/00223131.2017.1299649 | - |
dc.identifier.issn | 0022-3131 | - |
dc.identifier.scopusid | 2-s2.0-85015668514 | - |
dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/21901 | - |
dc.identifier.url | http://www.tandfonline.com/doi/full/10.1080/00223131.2017.1299649 | - |
dc.identifier.wosid | 000399483300005 | - |
dc.language | 영어 | - |
dc.publisher | TAYLOR & FRANCIS LTD | - |
dc.title | Multi-physics steady-state analysis of OECD/NEA modular high temperature gas-cooled reactor MHTGR-350 | - |
dc.type | Article | - |
dc.description.isOpenAccess | FALSE | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.subject.keywordAuthor | MHTGR-350 | - |
dc.subject.keywordAuthor | HTGR | - |
dc.subject.keywordAuthor | VHTR | - |
dc.subject.keywordAuthor | coupled calculations | - |
dc.subject.keywordAuthor | benchmark | - |
dc.subject.keywordAuthor | thermal-fluid simulation | - |
dc.subject.keywordAuthor | Monte Carlo calculation | - |
dc.subject.keywordPlus | PRISMATIC VHTR CORE | - |
dc.subject.keywordPlus | HYDROGEN | - |
dc.subject.keywordPlus | FLOW | - |
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