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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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Methodology and Verification of Neutron Transport Code STREAM for Analysis of Innovative Reactor Core Design

Author(s)
Choi, SooyoungKong, ChidongKhassenov, AzamatLee, Deokjung
Issued Date
2014-11-27
URI
https://scholarworks.unist.ac.kr/handle/201301/38969
Citation
International Symposium on NPP Technology and HRD
Publisher
International Symposium on NPP Technology and HRD

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