Modeling and analysis of Tehran research reactor against loss of flow accident

Nuclear Reactor safety analysis is an important issue with several aspects. The fuel clad is the first shield against the fuel radioactive material propagation. With considering that, fuel and clad melting down point temperature, and channel coolant film boiling temperature are safety criteria for this system. In this project, Modeling of Tehran research reactor against the loss of flow accidents by TRANS code has been done.This scenarios are:• Pump Breakdown and Primary Pump Scram (case 1)• Pump Breakdown and FLOW Scram (case-2)• Spurious Opening of the flapper valve and the Safety Flapper Scram (case-3)• Spurious Opening of the flapper valve and the pool level Scram (case-4)Results shows that, 3 scenarios haven t cross from safety criteria but only case 4 has cross from criteria. Finally this results were compared with and validated by IAEA safety analysis report results.

کلیدواژه ها:

Safety Analysis ، Tehran Research Reactor ، Loss of Flow Accident ، TRANS code