Unstructured mesh-grid multi-physics analysis with Monte Carlo iMC code for advanced fuel elements

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Publisher
American Nuclear Society
Issue Date
2020-06
Language
English
Citation

Transactions of the American Nuclear Society, ANS 2020, pp.738 - 741

ISSN
0003-018X
URI
http://hdl.handle.net/10203/278965
Appears in Collection
NE-Conference Papers(학술회의논문)
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