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5. Heat Transfer and Thermal Hydraulic Analyses Scoping analyses were performed using a simple, steady-state, Single-Channel Flow Analysis (SCFA) Mathcad code to parametrically consider the effects on the maximum fuel temperature, clad temperature, average pressure drop through the core, and resulting pumping power requirements as a function of the reactor power level, pin diameter, and coolant fraction. SCFA performs a one-dimensional (radial) heat transfer analysis on the fuel and cladding at the axial centerline of the core using the thermal conductivities of the fuel and cladding, along with a lumped parameter single-channel flow analysis using the coolant thermophysical properties. User input variables include the reactor power level, power density, active core height, total pin height including gas plenum, inlet and outlet coolant temperatures, and radial and axial peaking factors. The code calculates the core radius and total mass flow rate. The cladding thickness and gap thickness are fixed, and parametric analysis is performed using the pin diameter and coolant fraction for a triangular pitch. The Nusselt number, heat transfer coefficient, and friction factor are calculated parametrically to generate the fuel centerline temperature at the center of the reactor core, clad temperature at the center of the core, and average channel pressure drop. The pumping power is calculated for one channel and multiplied by the total number of fuel pins in the core to determine the total core pumping power. By analyzing the resulting plots, the appropriate pin diameter and coolant fraction can be determined such that the maximum fuel temperature, cladding temperature, pressure drop, and pumping power are maintained below prescribed limits. For the UO2 fuel and stainless-steel cladding, the maximum operating temperatures are assumed to be less than 2200°C and 800°C, respectively. It is desired that the pumping power be less than 1% of the total core power. Analyses are presented for a cladding thickness of 0.056 cm, gap of 0.008 cm, fuel pin active height of 1.6 m, fuel pin plenum of 1.0 m, core radius of 0.85 m, CO2 pressure of 20 MPa, core inlet temperature of 450°C, and core outlet temperature of 650°C. Core radial and axial peaking factors were both set to 1.4, allowing for an overall peaking factor of 2.0. Both 200 MWth and 400 MWth are presented to determine the potential upper bound on reactor power. Figures 9 through 12 show the 200 MWth parametric analyses for the core centerline fuel temperature, cladding temperature, average core pressure drop, and pumping power fraction. A smaller coolant fraction (cf) is desirable to allow for a higher core loading density, hence a smaller core. A smaller cf results in lower fuel and cladding temperatures as seen in Figures 9 and 10. However, a smaller cf results in a larger pressure drop and pumping power as seen in Figures 11 and 12. Likewise, a smaller diameter fuel pin results in lower fuel and cladding temperatures but also a larger pressure drop and pumping power. Two points were selected as a possible range of desirable conditions: a 0.2 cf with a 0.75 cm diameter pin, and a 0.3 cf with a 1.2 cm diameter pin. Both of these values result in approximately the same fuel loading. The 0.2 cf case has a maximum fuel centerline temperature of 880°C, cladding temperature of 600°C, and pumping power fraction of 0.008 (0.8%). The 0.3 cf case has a maximum fuel temperature of 1440°C, cladding temperature of 690°C, and pumping power fraction of 0.001 (0.1%). Both of these cases are acceptable for 200 MWth, with the 0.2 cf case having a slightly greater margin in the fuel temperature and larger pressure drop. 28PDF Image | Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR)
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