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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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dc.citation.startPage 107915 -
dc.citation.title COMPUTER PHYSICS COMMUNICATIONS -
dc.citation.volume 264 -
dc.contributor.author Choi, Sooyoung -
dc.contributor.author Kim, Wonkyeong -
dc.contributor.author Choe, Jiwon -
dc.contributor.author Lee, Woonghee -
dc.contributor.author Kim, Hanjoo -
dc.contributor.author Ebiwonjumi, Bamidele -
dc.contributor.author Jeong, Eun -
dc.contributor.author Kim, Kyeongwon -
dc.contributor.author Yun, Dongmin -
dc.contributor.author Lee, Hyunsuk -
dc.contributor.author Lee, Deokjung -
dc.date.accessioned 2023-12-21T15:38:01Z -
dc.date.available 2023-12-21T15:38:01Z -
dc.date.created 2021-09-07 -
dc.date.issued 2021-07 -
dc.description.abstract This paper presents a methodology developed and implemented in the neutron transport code STREAM to perform high-fidelity, multicycle, multiphysics simulations of light water reactor whole-core problems. STREAM uses state-of-the-art methodologies to achieve high accuracy and computational performance. Further, it can compute fine-mesh neutron transport solutions for three-dimensional (3D) whole-core problems using the 3D method of characteristics/diamond-difference (MOC/DD). For multigroup calculation, STREAM generates problem-dependent multigroup cross-sections using intrinsic cross-section libraries and a resonance self-shielding method. To perform the multicycle analysis of commercial power reactors, many advanced methods and features have been developed and implemented. In this paper, the methodologies and features of STREAM are presented, followed by the whole-core simulation capability. (c) 2021 Elsevier B.V. All rights reserved. Superscript/Subscript Available -
dc.identifier.bibliographicCitation COMPUTER PHYSICS COMMUNICATIONS, v.264, pp.107915 -
dc.identifier.doi 10.1016/j.cpc.2021.107915 -
dc.identifier.issn 0010-4655 -
dc.identifier.scopusid 2-s2.0-85103787876 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/53864 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S0010465521000515?via%3Dihub -
dc.identifier.wosid 000687751400005 -
dc.language 영어 -
dc.publisher ELSEVIER -
dc.title Development of high-fidelity neutron transport code STREAM? -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Computer Science, Interdisciplinary Applications; Physics, Mathematical -
dc.relation.journalResearchArea Computer Science; Physics -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor STREAM -
dc.subject.keywordAuthor Neutron transport -
dc.subject.keywordAuthor Resonance self-shielding -
dc.subject.keywordAuthor Whole-core transport analysis -
dc.subject.keywordAuthor Verification -
dc.subject.keywordAuthor and validation -
dc.subject.keywordPlus METHODOLOGY -
dc.subject.keywordPlus IMPACT -

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