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NOTE: minus values indicate savings attributable to supercritical CO2 8.6.2 Cost Estimations Based on the adjustments and cost calculations presented in the preceding sections the cost of the supercritical CO2 direct cycle nuclear plant was estimated. Table 8.9 shows the main cost accounts for the HTGR using the supercritical CO2 basic cycle without the isolation cooling loop and with the titanium pre-cooler. Table 8.10 shows the savings achieved on GCRA’s HTGR if the supercritical CO2 cycle is used instead of steam. To better judge the potential of each cycle Table 8.11 and Table 8.12 compare\ the steam, helium and supercritical CO2 cycles; two major parameters are compared, the total capital cost and the capital cost per kWe. Table 8.11 Fractional costs of the different supercritical CO2 cycle designs Turbomachinery* Temperature (oC) Conservative 550 Conservative 650 Conservative 700 Best Estimate 550 Best Estimate 650 Best Estimate 700 Capital Cost per kWe Total Capital Cost Capital Cost per kWe Total Capital Cost Capital Cost per kWe Total Capital Cost Capital Cost per kWe Total Capital Cost Capital Cost per kWe Total Capital Cost Capital Cost per kWe Total Capital Cost vs. Steam Cycle 0.865 0.922 0.784 0.922 0.755 0.922 0.822 0.921 0.753 0.922 0.726 0.922 vs. Helium Cycle 1.0553 0.896 0.956 0.897 0.922 0.897 1.004 0.896 0.919 0.897 0.886 0.897 * see Chapter 10 for conservative and best estimate turbomachinery efficiencies Table 8.11 compares different cycle designs, the basic cycle with turbine inlet temperature of 550oC, the advanced design with turbine inlet temperature of 650oC and the advanced design with turbine inlet temperature of 700oC, all with the conservative and best estimate turbomachinery efficiencies. The cycles are direct without the isolation loop and with the titanium pre-cooler. The table shows that the supercritical CO2 cycle realizes about 8% savings versus the total capital cost of the HTGR with steam cycle. The reason why this saving does not change with operating temperature of the 197PDF Image | Advanced Nuclear Power Technology Program A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors
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