Full metadata record
DC Field | Value | Language |
---|---|---|
dc.citation.endPage | 1803 | - |
dc.citation.number | 5 | - |
dc.citation.startPage | 1789 | - |
dc.citation.title | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.citation.volume | 54 | - |
dc.contributor.author | Tran, Tuan Quoc | - |
dc.contributor.author | Cherezov, Alexey | - |
dc.contributor.author | Du, Xianan | - |
dc.contributor.author | Lee, Deokjung | - |
dc.date.accessioned | 2023-12-21T14:12:06Z | - |
dc.date.available | 2023-12-21T14:12:06Z | - |
dc.date.created | 2022-05-13 | - |
dc.date.issued | 2022-05 | - |
dc.description.abstract | RAST-F is a new full-core analysis code based on the two-step approach that couples a multi-group cross-section generation Monte-Carlo code MCS and a multi-group nodal diffusion solver. To demonstrate the feasibility of using MCS/RAST-F for fast reactor analysis, this paper presents the coupled nodal code verification results for the MET-1000 and CAR-3600 benchmark cores. Three different multi-group cross-section calculation schemes are employed to improve the agreement between the nodal and reference solutions. The reference solution is obtained by the MCS code using continuous-energy nuclear data. Additionally, the MCS/RAST-F nodal solution is verified with results based on cross-section generated by collision probability code TULIP. A good agreement between MCS/RAST-F and reference solution is observed with less than 120 pcm discrepancy in k(eff) and less than 1.2% root-mean-square error in power distribution. This study confirms the two-step approach MCS/RAST-F as a reliable tool for the three-dimensional simulation of reactor cores with fast spectrum. (C) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. | - |
dc.identifier.bibliographicCitation | NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.5, pp.1789 - 1803 | - |
dc.identifier.doi | 10.1016/j.net.2021.10.038 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.scopusid | 2-s2.0-85118826334 | - |
dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/58426 | - |
dc.identifier.url | https://linkinghub.elsevier.com/retrieve/pii/S1738573321006227 | - |
dc.identifier.wosid | 000787811100009 | - |
dc.language | 영어 | - |
dc.publisher | KOREAN NUCLEAR SOC | - |
dc.title | Verification of a two-step code system MCS/RAST-F to fast reactor core analysis | - |
dc.type | Article | - |
dc.description.isOpenAccess | TRUE | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.type.docType | Article | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.description.journalRegisteredClass | kci | - |
dc.subject.keywordAuthor | Nodal diffusion code | - |
dc.subject.keywordAuthor | RAST-F | - |
dc.subject.keywordAuthor | TPEN | - |
dc.subject.keywordAuthor | Fast reactor | - |
dc.subject.keywordPlus | SERPENT-DYN3D | - |
dc.subject.keywordPlus | MCS | - |
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