In cooperation with the Iranian Nuclear Society

Document Type : Research Paper


1 پژوهشگاه

2 Faculty of Physics, University of Isfahan

3 Associate Professor Dept. of Nuclear Eng. Faculty of Physics University of Isfahan

4 Faculty member


In the researches performed regarding the use of Tehran research reactor (TRR) potential for domestic fuels test, a compact core configuration including a central neutron flux trap channel to reach the desired linear heat rate for fuel test is developed. In this research, safety analysis of loading the fuel irradiation capsule in the neutron flux trap channel is performed from thermal-hydraulics viewpoint under steady state condition. Due to the differences between the coolant channel between irradiation capsule and adjacent fuel plates and the other coolant channels in the core, the coolant flow distribution in the core changes after loading the fuel irradiation capsule in neutron flux trap channel. In this study, the effect of loading the fuel irradiation capsule on the heat removal from fuel plate adjacent to neutron flux trap channel, which is the hot fuel plate in the core, is investigated. In this analysis, ANSYS Fluent software with the capability of simultaneous simulation of the rod-type fuels within the irradiation capsule and the fuel plates adjacent to the neutron flux trap channel is applied. The simulation results indicate that maximum clad temperature of the fuel plates adjacent to irradiation capsule will be about 370K, which is lower than saturation temperature under the reactor operating pressure and also the maximum permissible clad temperature to avoid corrosion. Maximum fuel temperature will be 375.9K, which is within the permissible limits. These results indicate safe operation of TRR core from thermal-hydraulics viewpoint if fuel irradiation capsule is loaded in flux trap channel.


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