[1J05-09] Thermal Hydraulics of Sodium-Cooled Fast Reactors 1

[1J05] Development of fundamental numerical simulation system for integrated safety evaluation in various innovative sodium-cooled fast reactor

(1)Overall plan for development of systems

*Takashi Takata¹, Hirotaka Nakahara², Tohru Suzuki³, Yuji Ohishi⁴ (1. Japan Atomic Energy Agency, 2. Hitachi-GE Nuclear Energy, 3. Tokyo City University, 4. Osaka University)

Keywords:Sodium cooled fast reactor, Severe accident analysis, Numerical simulation

An integrated severe accident analysis system for safety of sodium cooled fast reactor has been stared to develop supported by MEXT Innovative Nulcear Reserch and Development Program from 2020. In the program, a user convenience of the system is also taken into consideration for providing to vendors and other institutes. The overall plan for the development is introduced in the paper.