Studi Karakteristik Termohidrolik Pada Kanal Pendingin Teras Reaktor SMART Menggunakan CFD Ansys Fluent

Abstract

The Small Modular Reactor (SMR) type nuclear power plant is currently growing very rapidly by offering various kinds of safety features, both active and passive. One of the SMRs currently to be built and operated is the SMART (System-integrated Modular Advanced Reactor) reactor. The SMART reactor is designed to use conventional PWR fuel types but operates at a lower flow rate and core inlet temperature than conventional PWR. The existence of this basic difference needs to be a separate note for us in evaluating the safety of the SMART Reactor, especially for the thermohydraulic aspect. The thermohydraulic characteristics have been carried out previously using the MATRA code, however, the temperature distribution in the cooling sub channel is still unknown. Therefore, the purpose of this study is to calculate the temperature distribution in the cooling sub-channel on SMART. The program used in this study is CFD ANSYS. Ansys Fluent 2021 R1 Computational Fluid Dynamic (CFD) computer code was used to simulate coolant flow and heat transfer from fuel to coolant. The cooling sub channel was modeled consisting of four fuels with a diameter of 0.95 cm and a pitch of 1.26 cm in a rectangular arrangement surrounded by light water coolant. Based on the calculation, there is an increase in the average temperature of the coolant between the input and output sides of the coolant sub channel of 60 ℃, which is greater than the SMART reactor design. The fuel center and fuel cladding temperatures were calculated at 1100 ℃ and 350 ℃, respectively. This difference is caused by the modeling assumptions which is still far from the actual design. The model was assumed to consist of pure fuel and ignores the actual variations in fuel and fuel assembly. Keywords: SMART Reactor, CFD, Ansys Fluent, Thermal Hydraulic