[3K09-11] Sodium-Cooled Fast Reactors 2

[3K09] Improvement of integrative severe accident analysis code, SPECTRA

Development of evaluating module for core disruptive behavior, (1) Model concept and plan

*Ken-ichi Kawada¹, Tkashi Takata¹, Tohru Suzuki² (1. JAEA, 2. Tokyo City University)

Keywords:Fast reactor, Anticipated transient without scram (ATWS), Unprotected loss of flow (ULOF), Initiating phase, Transition phase

The integrative severe accident analysis code, SPECTRA, which consistently analyzes in- and ex-vessel behavior of sodium cooled fast reactor has been developed and improved. As part of this, development of a new module is ongoing, which consistently analyzes initiating and transition phase and has fast turnaround time. In this report, accident scenario for analyses, important physical phenomena and required models for new module were identified and development plan was presented.