[2E05-09] Next Generation Reactor Safety 2

[2E09] Transient Analysis Code for Molten Salt Reactor: DYMOS

Yoichiro Shimazu², *Ritsuo Yoshioka¹, Koji Ogasawara¹, Masaaki Furukawa³ (1. International Thorium Molten-Salt Forum, 2. University of Fukui, 3. Thorium Tech Solution Inc.)

Keywords:Molten Salt Reactor, Transient analysis, Safety Evaluation, Verification, DYMOS

As for the safety evaluation for MSR (Molten Salt Reactor), an appropriate code for transient analysis is required. Since this code (DYMOS) is required also for reactor licensing stage, the authors have been cooperating to establish it.

This code simulates the core by one-point kinetics equations, and also one-point model for heat exchangers. Considering the circulation of molten salt and time difference of inlet temperature, this code simulates all plant components including steam generators and turbine/generators.
In order to verify this code, actual experimental data at MSRE in USA were used. And, this code shows very good agreement with actual data. Also, this code shows reasonable results compared with other similar codes in foreign countries.