Evaluation of the Safety Systems of Tehran Research Reactor Fuel Test Loop during Loss of Flow Accident

In order to enhance applicability of Tehran Research Reactor (TRR) for irradiation test of nuclear fuel and materials and considering TRR potential to provide required neutronic and thermal hydraulic conditions for irradiation tests on domestic fuel samples of research reactors, TRR fuel test loop with 10 bar nominal pressure and 20m3/h nominal flow rate is designed and fabricated to simulate thermal hydraulic conditions of the desired research reactor. In this paper, consequences of loss of flow in the loop due to primary pump breakdown are investigated and the functions of safety systems in response to this accident to provide continuous cooling of the fuels under test and mitigate any undesirable consequence are evaluated. In this regard, the probable scenarios are simulated using a RELAP5 model and the ability of the safety features of the loop to prevent any damage to the fuels under test is evaluated.