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DC Field | Value | Language |
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dc.citation.endPage | 151 | - |
dc.citation.startPage | 141 | - |
dc.citation.title | ANNALS OF NUCLEAR ENERGY | - |
dc.citation.volume | 111 | - |
dc.contributor.author | Jo, Yunki | - |
dc.contributor.author | Hursin, Mathieu | - |
dc.contributor.author | Lee, Deokjung | - |
dc.contributor.author | Ferroukhi, Hakim | - |
dc.contributor.author | Pautz, Andreas | - |
dc.date.accessioned | 2023-12-21T21:16:56Z | - |
dc.date.available | 2023-12-21T21:16:56Z | - |
dc.date.created | 2017-10-12 | - |
dc.date.issued | 2018-01 | - |
dc.description.abstract | This paper presents an evaluation of a Monte Carlo (MC) neutron transport code as a tool to generate nuclear cross section data for nuclear reactor core simulators. The goal is not to replace deterministic lattice calculations with MC simulations but to provide an audit tool. A boiling water reactor (BWR) assembly is modeled with a deterministic lattice physics code CASMO-5 and with a MC code SERPENT-2 for a simplified set of histories and branch cases. The work reported in this paper is a continuation of authors’ previous analysis of a BWR in the reference 13 and SERPENT-2 is used instead of SERPENT-1 to overcome excessive memory usage and execution time of the latter. CASMO-5 and SERPENT-2 are compared with those of a hybrid CASMO-5 + SERPENT-2 scheme which uses the depletion solver of CASMO-5 and the transport solver of SERPENT-2. Their results are compared for an assembly model, in terms of k-inf, macroscopic cross sections, assembly discontinuity factors and diffusion coefficients. The differences are less than 1% except for diffusion coefficients of 5% difference. Subsequently, a nuclear cross section data library is generated for SIMULATE-3 core simulator. A full core depletion calculation is performed and k-eff, axial and radial power distributions are compared. The discrepancies of k-eff between CASMO-5/SIMULATE-3 and SERPENT-2/SIMULATE-3 are smaller than 250 pcm, and the differences of axial relative power fraction (RPF) root mean square errors are smaller than 8%. The differences of radial RPF root mean square errors are smaller than 1.5%. | - |
dc.identifier.bibliographicCitation | ANNALS OF NUCLEAR ENERGY, v.111, pp.141 - 151 | - |
dc.identifier.doi | 10.1016/j.anucene.2017.08.061 | - |
dc.identifier.issn | 0306-4549 | - |
dc.identifier.scopusid | 2-s2.0-85028961325 | - |
dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/22793 | - |
dc.identifier.url | http://www.sciencedirect.com/science/article/pii/S0306454916302626?via%3Dihub | - |
dc.identifier.wosid | 000413877800014 | - |
dc.language | 영어 | - |
dc.publisher | PERGAMON-ELSEVIER SCIENCE LTD | - |
dc.title | Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code | - |
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 | CASMO-5 | - |
dc.subject.keywordAuthor | Monte Carlo cross sections generation | - |
dc.subject.keywordAuthor | SERPENT-2 | - |
dc.subject.keywordAuthor | SIMULATE-3 | - |
dc.subject.keywordPlus | PERFORMANCE | - |
dc.subject.keywordPlus | REACTORS | - |
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