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.
Zdroj: In Nuclear Engineering and Design 2000 200(1):157-175
Databáze: ScienceDirect