Safety evaluation of the R-Tokamak

The safety evaluation of the R-tokamak was carried out by applying the ''safety analysis and evaluation methodology''. The purpose of this evaluation is to confirm the validity and usefulness of the methodology. The following results were obtained: (1) Safety characteristics of the R-tokamak design was clarified. In this process, the General Descriptive Model for the R-tokamak was constructed. (2) Design Basis Events for the R-tokamak were selected based on the function based safety analysis and they were classified according to the event categorization. Safety functions were investigated in relation with the DBEs. In results, the validity and effectiveness of our methodology were confirmed. (3) Tritium release to the environment was analysed using the containment system model with the tritium cleanup system. The result showed that the amount of released tritium was small (less than 2 Ci), and the pressure increase in the containment had a key effect on the tritium release to the environment. (author). 4 refs, 4 figs, 5 tabs