Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR)

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Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR) ( supercritical-co2-direct-cycle-gas-fast-reactor-sc-gfr )

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Table 4. Reactor Core Parameters. Parameter Active Core Diameter (cm) Active Core Height (cm) Reflector Material Reflector Thickness (cm) Active Core Volume (m3) Total Mass of Fuel Meat (kg) V alue 170 160 Nickel (Ni) 15 3.63 20,600 The core pressure drop is a function of the core size, coolant flow rate, the fuel pin diameter, pitch, and pin length. The design objective is to maintain the pumping power though the core to a value less than 1% of the total core power, which is achievable for a pressure drop less than 0.3 MPa (44 psi). Two different fuel pin diameters and coolant fractions were analyzed for the concept: a 0.75 cm pin diameter with a coolant fraction of 0.2 and a 1.20 cm pin diameter with a coolant fraction of 0.3. For the same size reactor core, the fuel mass is almost equal. The impact on fuel temperatures and pressure drop through the core for different fuel sizes and coolant fractions will be discussed in a later section of this report. Other configurations may also be shown to be acceptable. The nickel reflector material and thickness were chosen somewhat arbitrarily. A high Z material with good scattering and coolant compatibility properties is desired. Materials with moderating properties were found to increase keff, but have deleterious effect on the burnup reactivity changes. Other materials may be found to work adequately as a reflector material. The reflector was modeled as a solid unit in the MCNP model, but can be made into pins or a solid with coolant channels. The reflector will be located in the downcomer section of the coolant. The reactor radius, height, and enrichment were chosen to minimize the change in reactivity over the core lifetime. For a 200 MWth power level, a small core is conceivable with an enrichment greater than 12%. However, burnable poisons and/or a higher worth reactivity control system would be required to maintain the reactor critical throughout the lifetime of the core. The core configuration in this concept allows for significant conversion of the U-238 to Pu-239 with only a small reactivity change over the core lifetime. This requires a somewhat larger core, but allows the fuel cycle to be sustainable. The first core loading would contain 12% enriched uranium fuel. Subsequent loadings would have larger quantities of the recycled Pu. The first core loading, 12% enriched and 20,600 kg, would cost approximately $150M. This cost would be a significant portion of the initial capital investment in the plant at $1,500/kW electric. However, assuming that the fuel would last 20 years, this capital investment would equate to a cost ~1.5 cents per kW-hr electric, which is not that much greater than for LWR fuel at ~1 cent per kW-hr electric. Subsequent cores using the reprocessed, recycled fuel would cost significantly less, on the order of ~$30M, since only reprocessing and fuel make-up costs would be required. 23

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