Transient experiments on fast reactor core thermal-hydraulics and its numerical analysis: Inter-subassembly heat transfer and inter-wrapper flow under natural circulation conditions
Autor: | Nishimura, M. *, Kamide, H., Hayashi, K., Momoi, K. |
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Zdroj: | In Nuclear Engineering and Design 2000 200(1):157-175 |
Databáze: | ScienceDirect |
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