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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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DC Field Value Language
dc.citation.conferencePlace KO -
dc.citation.title International Symposium on NPP Technology and HRD -
dc.contributor.author Choi, Sooyoung -
dc.contributor.author Kong, Chidong -
dc.contributor.author Khassenov, Azamat -
dc.contributor.author Lee, Deokjung -
dc.date.accessioned 2023-12-19T23:07:04Z -
dc.date.available 2023-12-19T23:07:04Z -
dc.date.created 2017-07-18 -
dc.date.issued 2014-11-27 -
dc.identifier.bibliographicCitation International Symposium on NPP Technology and HRD -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/38969 -
dc.language 영어 -
dc.publisher International Symposium on NPP Technology and HRD -
dc.title Methodology and Verification of Neutron Transport Code STREAM for Analysis of Innovative Reactor Core Design -
dc.type Conference Paper -
dc.date.conferenceDate 2014-11-27 -

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