ارزیابی ایمنی ترموهیدرولیکی کانال دام شار نوترون رآکتور تحقیقاتی تهران برای انجام آزمون پرتودهی سوخت

In the research conducted on the potential use of the Tehran Research Reactor (TRR) for domestic fuel testing, a compact core configuration has been developed. This configuration includes a central neutron flux trap channel to achieve the desired linear heat rate for fuel testing. In this study, a safety analysis of loading the fuel irradiation capsule in the neutron flux trap channel is performed from a thermal-hydraulics perspective under steady-state conditions. The differences in coolant channels between the irradiation capsule and adjacent fuel plates cause a change in coolant flow distribution in the core after loading the fuel irradiation capsule in the neutron flux trap channel. The study investigates the effect of loading the fuel irradiation capsule on heat removal from the fuel plate adjacent to the neutron flux trap channel, which is the hottest fuel plate in the core. ANSYS Fluent software is used for the analysis, allowing for simultaneous simulation of rod-type fuels within the irradiation capsule and the fuel plates adjacent to the neutron flux trap channel. The simulation results show that the maximum clad temperature of the fuel plates adjacent to the irradiation capsule will be approximately 370K, which is lower than the saturation temperature under the reactor operating pressure and below the maximum permissible clad temperature to avoid corrosion. The maximum fuel temperature is 375.9K, which falls within permissible limits. These results indicate safe operation of the TRR core from a thermal-hydraulics perspective if the fuel irradiation capsule is loaded in the flux trap channel.