Advanced Nuclear Power Technology Program A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors

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Advanced Nuclear Power Technology Program A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors ( advanced-nuclear-power-technology-program-supercritical-carb )

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As can be seen from Figure 4.4 for a certain pressure ratio (around 2.7 in this case) the pre-cooler outlet temperature is almost equal to the inlet temperature of 27oC. In order to transfer the required heat, very high flow rates that improve the heat transfer coefficient and a low cooling water temperature that increases the temperature difference across the pre-cooler are necessary. Once the cycle operates in the sub-critical region the pumping power quickly decreases and stabilizes as it reflects only the increased demand of heat rejection due to the reduction of cycle efficiency at higher pressure ratios. This indicates the difficulty of designing the cycle very close to the critical point. While the CO2 side does not have any problems, the water side of the pre-cooler is almost impossible to design. In order to achieve a reasonable net efficiency a very large pre- cooler volume is required. This suggests a region where the cycle should not be designed to operate. However, this complication would not significantly affect the cycle operation since if for some reason the cycle should enter this region during its operation the effect of specific heat variation would result in an increased compressor inlet temperature. The cycle would continue operation without a significant deterioration of efficiency. 0.03 0.02 0.01 0 2 2.5 3 3.5 4 Pressure ratio Reactor Recuperator low pressure side Precooler Recuperator high pressure side Figure 4.6 Fractional pressure drops for 60m3 total heat exchanger volume 78 Fractional Pressure Drops

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