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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purposes of this chapter the comparison is based on the achievable thermal efficiency (i.e. the mass flow rates will be determined such that the cycle will produce 300 MWe based on the thermal efficiency, this has an effect on the total energy balance). Table 12.1 summarizes the main cycle characteristics. The cycles are compared at the optimum designs. Helium Brayton cycle operating conditions were taken from [Wang et al., 2002]. The system fractional pressure drops and the recuperator effectiveness (95%) for the helium cycles are from the same reference as well. The only difference from MIT PBMR data is the turbomachinery efficiency, which was taken the same as for the reference CO2 cycle design in order to compare the cycles at the same conditions. Before we proceed with the comparison it is important to note that the cycles are compared based on their thermal efficiencies, due to lack of data needed to correct the thermal efficiency to the net efficiency. The thermal efficiency is the most optimistic of the possible efficiency definitions and cannot be reached in the real design. If the real net efficiencies were used the helium cycle efficiencies would suffer a larger penalty than for the CO2 cycle, mainly because of more demanding requirements on component cooling (due to significantly higher temperatures) and helium leakage. The supercritical CO2 cycle, which operates at 550oC will not require extensive cooling to satisfy ASME requirements on class I pressure boundaries [1998 ASME, 1998], (probably simple, conventional insulation will be sufficient) and should suffer much less from CO2 leakage due to the tri-atomic configuration of CO2 and its higher molecular weight. These losses are not negligible in the case of the helium Brayton cycle. For example, the ESKOM helium cycle, which uses a 900oC turbine inlet temperature and a 2 compressor cycle configuration claims a net efficiency of only 41-42 %. From Table 12.1 we can see that the thermal efficiency is on the order of 51%. Thus, losses from leakage, primary pressure boundary cooling and core bypass account for about 5% loss in the efficiency (1% generator losses, 0.5% mechanical losses, 1.5% pumping power for precooler and inter-cooler, 1% additional station loads). The radiation losses from the system are also much higher in the case of the helium cycle due to its higher system temperature, whereas radiation losses in the case of CO2 are negligible. 255

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