Japan Atomic Energy Agency
Author in the following contributions
- Progress of Design and related Researches of Sodium-cooled Fast Reactor in Japan
- Identification of important phenomena under sodium fire accidents based on PIRT process
- Numerical Investigation of Sodium Spray Combustion Test with SPHINCS code
- Numerical Simulation Method of Thermal Hydraulics in Wire-wrapped Fuel Pin Bundle of Sodium-cooled Fast Reactor
- Numerical Analysis of EBR-II Shutdown Heat Removal Test-17 using 1D Plant Dynamic Analysis Code coupled with 3D CFD Code
