Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section

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Issue Date
2010-11-17
Language
ENG
Citation

The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7)

URI
http://hdl.handle.net/10203/165049
Appears in Collection
NE-Conference Papers(학술회의논문)
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