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Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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Experimental Study on a Heat Pipe towards In-Core Decay Heat Removal Control Rod

Author(s)
Bang, In Cheol
Issued Date
2014-12-16
URI
https://scholarworks.unist.ac.kr/handle/201301/50806
Citation
10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10)
Publisher
Atomic Energy Society of Japan

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