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Figure 6.43 Figure 6.44 Figure 7.1 Figure 7.2 Figure 7.3 Figure 7.4 Figure 7.5 Figure 7.6 Figure 7.7 Figure 7.8 Figure 7.9 Figure 7.10 Figure 7.11 Figure 7.12 Figure 7.13 Figure 7.14 Figure 7.15 Figure 7.16 Figure 7.17 Figure 7.18 Figure 7.19 Figure 7.20 Figure 7.21 Figure 8.1 Figure 9.1 Figure 9.2 Figure 9.3 Figure 9.4 Figure 9.5 Figure 9.6 Figure 9.7 Figure 9.8 Figure 9.9 Figure 9.10 Figure 9.11 Figure 9.12 Figure 9.13 Figure 9.14 Figure 9.15 Figure 9.16 Figure 9.17 Figure 10.1 Figure 10.2 Figure 10.3 Figure 10.4 Figure 10.5 Effect of re-heating on the recompression cycle 151 Efficiency for different total pressure drops in IHX and re-heaters 152 Primary loop geometry of a helium cooled gas fast reactor (GFR) [from Francois, 2003] 160 Indirect cycle cost relative to the direct cycle for different reactor inlet and outlet temperatures 163 Efficiency of indirect cycle for different reactor inlet and outlet temperatures 164 IHX cost for different reactor inlet and outlet temperatures 164 Recompression Cycle with one and two stages of re-heat 166 Relative cost of the indirect cycle with single re-heat compared to the direct cycle for different reactor inlet and outlet temperatures 167 Relative cost of the indirect cycle with two re-heats compared to the direct cycle for different reactor inlet and outlet temperatures 167 Efficiency of the indirect cycle with one re-heat for different reactor inlet and outlet temperatures 168 Efficiency of the indirect cycle with two re-heats for different reactor inlet and outlet temperatures 168 Total cost of all exchangers (IHX and re-heaters) for the indirect cycle with one re-heat for different reactor inlet and outlet temperatures 169 Total cost of all exchangers (IHX and re-heaters) for the indirect cycle with two re-heats for different reactor inlet and outlet temperatures 169 Relative costs of different indirect cycle options 171 Efficiencies of different indirect cycle options 172 Cost of all heat exchangers (IHX + re-heaters) for different indirect cycles 173 Cost optimized reactor inlet temperature for different indirect cycle options 173 Indirect cycle capital cost for different reactor inlet and outlet temperatures for lead alloy primary coolant 174 Efficiency of lead alloy / CO2 indirect cycle for different reactor inlet and outlet temperatures175 Relative cost for lead alloy / CO2 for different indirect cycle options 176 Lead alloy / CO2 indirect cycle efficiency for different cycle options 177 Intermediate heat exchanger costs for lead alloy / CO2 indirect cycle for different cycle options 178 Optimized reactor inlet and outlet temperatures for lead alloy / CO2 indirect cycle for different cycle options 180 Net efficiency and relative costs for different power cycles 198 Heat transfer coefficient of CO2 close to the critical point from Gnielinski correlation 203 Channel shape of the PCHE [from Dewson and Grady, 2003] 204 Assembling sequence of the new PCHE design [from Dewson and Grady, 2003] 208 Current operating experience of HEATRIC PCHEs [from Dewson and Grady, 2003] 209 Effective conduction length 210 Effect of conduction length on the PCHE volume 212 Stress rupture strength of alloy 800 214 Compressor characteristics –efficiency vs. mass flow rate 218 Compressor characteristics – pressure ratio vs. flow rate 218 Schematic of the main compressor 219 Schematic of the recompressing compressor 220 Recompressing compressor characteristics – efficiency vs. mass flow rate 220 Recompressing compressor characteristics – pressure ratio vs. mass flow rate 221 Turbine schematic 222 Turbine characteristic – efficiency vs. mass flow rate 222 Turbine characteristics – mass flow rate vs. pressure ratio 223 Comparison of turbine sizes for steam, helium and CO2 224 Temperature-entropy diagram of the supercritical CO2 cycle 228 High temperature and low temperature recuperator module layout 233 Pre-cooler modules and their layout 236 Physical configuration of the supercritical CO2 Power Conversion Unit 237 Comparison of the supercritical CO2 PCU and the GT-MHR PCU 237 xviPDF Image | Advanced Nuclear Power Technology Program A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors
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