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4. Reactor Core Conceptual Design and Plant Layout The SC-GFR concept is a gas-cooled RSR concept where the overall size and output power level is commensurate with modular factory construction of the pressure vessel, reactor, and power conversion system, and with the overall capital cost maintained at a level of less than $5,000 per kilowatt of electrical power output. The plan is that the facility would be built and the reactor and power conversion system would then be shipped to the facility and installed. The licensing process would be similar to that proposed for current power reactors being considered. With this consideration, one of the main focus areas of the SC-GFR concept is to keep the reactor and pressure vessel as small as reasonably possible, while still allowing for a reasonable power level and operating history. 4.1 Reactor Fuel and Core Description A 200 MWth reactor system was chosen as a reasonable reactor power output for an RSR type system, although additional work will be presented in this report for a reactor power of 400 MWth. In order to determine the core size, enrichment, fuel pin diameter, pitch, reactor diameter, fuel pin length, and burnup lifetime, a number of objectives had to be established. These objectives are as follows: Core power level of 200 MWth; Core reactivity burnup life of ~20 years; Minimal reactivity change over core lifetime; Core pressure drop less than 1% of total reactor power; Small reactivity void coefficient; Acceptable cladding and peak fuel temperature; and Acceptable fuel and cladding burnup. A number of iterations were performed between thermal hydraulic and burnup analyses in order to converge on an optimum conceptual configuration that incorporates all of the aspects of the objectives. The thermal hydraulic analysis, burnup, and k effective (keff) analyses will be presented in the following sections of this report. Although more complex and rigorous analyses will follow in future work, the results presented represent a good first estimate of a conceptual core design. Figure 3 shows a Monte Carlo N-Particle code (MCNP, 2003) neutronics model of the reactor core. The core was modeled in three dimensions with each fuel pin individually specified. The fuel pins are set on a triangular pitch. Each fuel pin is cylindrical with fuel, gap, and cladding specified. The core is cylindrical with a reflector surrounding it. For this conceptual stage of the work, no control rods or other hardware were included in the design. Figure 4 shows a conceptual illustration of the reactor vessel and core. The reactor vessel will most likely be fabricated from a high-nickel content stainless steel, to reduce corrosion over its lifetime. Other lower-cost steels may be considered in the future if it can be shown that the corrosion rate is slow for the inlet coolant temperature, or if liners can be used with thermal breaks to reduce the temperature of the vessel. Other vessel configurations can also be considered, including a liner within a pre-stressed concrete structure. 19PDF Image | Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR)
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