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DC Field | Value | Language |
---|---|---|
dc.citation.endPage | 4056 | - |
dc.citation.number | 11 | - |
dc.citation.startPage | 4048 | - |
dc.citation.title | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.citation.volume | 55 | - |
dc.contributor.author | Nguyen, Tung Dong Cao | - |
dc.contributor.author | Tran, Tuan Quoc | - |
dc.contributor.author | Lee, Deokjung | - |
dc.date.accessioned | 2023-12-14T17:10:20Z | - |
dc.date.available | 2023-12-14T17:10:20Z | - |
dc.date.created | 2023-12-11 | - |
dc.date.issued | 2023-11 | - |
dc.description.abstract | The feasibility of using the Monte Carlo code MCS to generate multigroup cross sections for nodal diffusion simulations RAST-F of liquid metal fast reactors is investigated in this paper. The performance of the MCS/RAST-F code system is assessed using steady-state simulations of the ANTS-100e core. The results show good agreement between MCS/RAST-F and MCS reference solutions, with a k(eff) difference of less than 77 pcm and root-mean-square differences in radial and axial power of less than 0.5% and 0.25%, respectively. Furthermore, the MCS/RAST-F reactivity feedback coefficients are within three standard deviations of the MCS coefficients. To validate the internal thermal-hydraulic (TH) feedback capability in RAST-F code, the coupled neutronic/TH1D simulation of ANTS-100e is performed using the case matrix obtained from MCS branch calculations. The results are compared to those obtained using the MARS-LBE system code and show good agreement with relative temperature differences in fuel and coolant of less than 0.8%. This study demonstrates that the MCS/RAST-F code system can produce accurate results for core steady-state neutronic calculations and for coupled neutronic/TH simulations. | - |
dc.identifier.bibliographicCitation | NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.11, pp.4048 - 4056 | - |
dc.identifier.doi | 10.1016/j.net.2023.07.020 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.scopusid | 2-s2.0-85168352806 | - |
dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/66422 | - |
dc.identifier.wosid | 001106674700001 | - |
dc.language | 영어 | - |
dc.publisher | KOREAN NUCLEAR SOC | - |
dc.title | Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system | - |
dc.type | Article | - |
dc.description.isOpenAccess | FALSE | - |
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 | MCS | - |
dc.subject.keywordAuthor | RAST-F | - |
dc.subject.keywordAuthor | Cross -section | - |
dc.subject.keywordAuthor | LFR | - |
dc.subject.keywordAuthor | ANTS-100e | - |
dc.subject.keywordAuthor | Thermal-hydraulic | - |
dc.subject.keywordPlus | MONTE-CARLO | - |
dc.subject.keywordPlus | VALIDATION | - |
dc.subject.keywordPlus | MCS | - |
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