Thermo-hydraulic feasibility study for the power-upgraded of Tehran Research Reactor compact core

This study investigates the power upgrade of the Tehran Research Reactor (TRR) to enhance neutron flux for various applications. Two strategies are proposed: (۱) utilizing spent fuel for economic feasibility and (۲) adopting a compact core layout to maximize neutron flux. Neutronic simulations reveal that the compact core with ۲۶ fuel assemblies can safely operate at ۸.۵ MW, achieving a thermal neutron flux greater than ۱.۵×۱۰۱۴ n.cm-۲·s-۱. Thermal-hydraulic analysis shows that, with a power peaking factor (PPF) of ۲.۷, safety criteria are met at ۸.۵ MW. Reducing the power to ۸.۳ MW ensures full compliance with all safety requirements. Under a conservative approach with a PPF of ۳.۰, a safe operational power of ۷.۵ MW is achievable. Moreover, lowering the coolant inlet temperature by ۳ °C improves reactor performance, allowing safe operation at ۸.۵ MW, with potential to exceed ۹ MW at high mass flow rates while maintaining safety margins.

کلیدواژه ها:

TRR ، MTR_PC ، CITVAP code ، compact core ، power peaking factor (PPF) ، coolant inlet temperature