SSR TRIGA 14 MW thermal hydraulic analysis

TRIGA research reactor requires periodic licensing by the Romania's Committee for Control of Nuclear Activities (CNCAN). The documents needed involve reactor safety analysis. In due process we made thermohydraulic reactor core analysis. There were required reactor natural convection and loss of flow accident documentation to prove that the facility can cope and mitigate the adverse phenomena. There were used validated computer codes for TRIGA reactors. There were analyzed the natural convection tests made during start-up tests and the computed results compared with that from Safety Analysis Report. The Loss of Flow Accident (LOFA), determined by the primary coolant pumps with the similar analysis made with other computer codes was compared with the LOFA test made during startup. The results proved to be satisfactory and the reactor operation was approved. (authors)