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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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dc.citation.endPage 2649 -
dc.citation.number 7 -
dc.citation.startPage 2635 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 54 -
dc.contributor.author Tran, Tuan Quoc -
dc.contributor.author Lee, Deokjung -
dc.date.accessioned 2023-12-21T14:06:42Z -
dc.date.available 2023-12-21T14:06:42Z -
dc.date.created 2022-08-03 -
dc.date.issued 2022-07 -
dc.description.abstract CEFR is a small core-size sodium-cooled fast reactor (SFR) using high enrichment fuel with stainless-steel reflectors, which brings a significant challenge to the deterministic methodologies due to the strong spectral effect. The neutronic simulation of the start-up experiments conducted at the CEFR have been performed with a deterministic code system RAST-F, which is based on the two-step approach that couples a multi-group cross-section generation Monte-Carlo (MC) code and a multi-group nodal diffusion solver. The RAST-F results were compared against the measurement data. Moreover, the characteristic of neutron spectrum in the fuel rings, and adjacent reflectors was evaluated using different models for generation of accurate nuclear libraries. The numerical solution of RAST-F system was verified against the full core MC solution MCS at all control rods fully inserted and withdrawn states. A good agreement between RAST-F and MCS solutions was observed with less than 120 pcm discrepancies and 1.2% root-mean-square error in terms of l e ft and power distribution, respectively. Meanwhile, the RAST-F result agreed well with the experimental values within two-sigma of experimental uncertainty. The good agreement of these results indicating that RAST-F can be used to neutronic steady-state simulations for small core-size SFR, which was challenged to deterministic code system. (C) 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.7, pp.2635 - 2649 -
dc.identifier.doi 10.1016/j.net.2022.01.027 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-85124310171 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/59031 -
dc.identifier.wosid 000824738500003 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Neutronic simulation of the CEFR experiments with the nodal diffusion code system RAST-F -
dc.type Article -
dc.description.isOpenAccess TRUE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.identifier.kciid ART002858719 -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor CEFR -
dc.subject.keywordAuthor Fast reactor -
dc.subject.keywordAuthor Nodal diffusion code -
dc.subject.keywordAuthor RAST-F -

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