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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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dc.citation.endPage 11 -
dc.citation.number 7 -
dc.citation.startPage 1 -
dc.citation.title EPJ Nuclear Sciences & Technologies -
dc.citation.volume 11 -
dc.contributor.author Yunki Jo -
dc.contributor.author Lee, Deokjung -
dc.date.accessioned 2025-12-03T14:40:06Z -
dc.date.available 2025-12-03T14:40:06Z -
dc.date.created 2025-11-24 -
dc.date.issued 2025-03 -
dc.description.abstract The Monte Carlo code, MCS was developed at the Ulsan National Institute of Science and Technology (UNIST) in 2011. In the initial development phase, the primary focus was on developing a Monte Carlo code for the high-fidelity multicycle analysis of large-scale power reactors, especially pressurized water reactors. For the power reactor analysis, capabilities including refueling and shuffling of fuel assemblies, on-the-fly Doppler broadening of neutron cross-sections, and multiphysics coupling were implemented in the MCS. Beyond reactor analysis and capabilities, MCS has been developed to extend its applications. The MCS has been used for radiation shielding, group constants generation, sensitivity, uncertainty, and transient analysis. This study provides a general overview of MCS capabilities. -
dc.identifier.bibliographicCitation EPJ Nuclear Sciences & Technologies, v.11, no.7, pp.1 - 11 -
dc.identifier.doi 10.1051/epjn/2025001 -
dc.identifier.issn 2491-9292 -
dc.identifier.scopusid 2-s2.0-105023113733 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/88839 -
dc.identifier.wosid 001436250000002 -
dc.language 영어 -
dc.publisher EDP SCIENCES S A -
dc.title Current capabilities and future developments of Monte Carlo code MCS -
dc.type Article -
dc.description.isOpenAccess TRUE -
dc.type.docType Article -
dc.description.journalRegisteredClass scopus -

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