Department of Energy and Environmental Engineering,Sharif University of Technology
Department of Nuclesr Engineering,Sharif University of Technology
National Nuclear Safety Department,Atomic Energy Organization of Iran
Small and medium break LOCA accidents at low pressure and under low velocity conditions
have been studied in the TTL-2 Thermo-hydraulic Test Loop, experimentally. TTL-2 is a thermal
hydraulic test facility which is designed and constructed in NSTRI to study thermal hydraulic parameters
under normal operational and accident conditions of nuclear research reactors. A nodalization has been
developed for the TTL-2 and experimental results have been compared with RELAP5/MOD3.2 results.
The considered accidents are a 25% and 50% cold leg break without emergency core cooling systems.
Results show good agreement between experiments and RELAP5/MOD3.2 results. This research provides
experimental data for evaluation of thermo hydraulic codes for nuclear research reactors, and veries
that RELAP5/MOD3.2 has a good capability to estimate the thermal hydraulic behavior of low pressure
and low velocity thermal hydraulic systems, such as research reactors under steady state and transient