Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section
- Issue Date
- 2010-11-17
- Language
- ENG
- Citation
The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7)
- Appears in Collection
- NE-Conference Papers(학술회의논문)
- Files in This Item
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