共 2 条
- [1] Development of integrated numerical analysis model for unsteady phenomena in upper plenum and hot-leg piping system of Japan Sodium-cooled Fast Reactor ASME Pressure Vessels Piping Div. Publ. PVP,
- [2] Application of the GIF Safety Design Criteria and Safety Design Guidelines on Decay Heat Removal System to Next Generation Sodium-Cooled Fast Reactor in Japan Proceedings of Advanced Reactor Safety, ARS 2024, 2024, : 121 - 130