The Supercritical Carbon Dioxide Power Cycle: Comparison to Other Advanced Power Cycles

Dostál, Václav; Hejzlar, Pavel; Driscoll, Michael J.

doi:10.13182/nt06-a3734

Cited by 315 publications

(100 citation statements)

References 4 publications

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“…SCO2 recompression Brayton cycles 26,27 are recently proposed as power conversion systems by several advanced sodium fast reactor designs, such as US ABTR design 1 . This section compares several power cycles, mainly between MCGC and SCO2 Brayton cycles for SFRs.…”

Section: Iiic Comparison With Other Power Cyclesmentioning

confidence: 99%

“…However, this ratio is lower for current SFR plant designs with steam cycles. The steam turbine plant equipment for SFR only accounts for about 20% of the total plant cost 27 . Due to higher power density and elimination of large and bulky equipment items like condensers which operate under sub-atmosphere pressure in steam cycles, the Brayton cycle PCS tends to be much smaller and more compact than steam cycles 31 .…”

Section: Optimization Of Pcs and Overall Plant Costmentioning

confidence: 99%

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Improving SFR economics through innovations from thermal design and analysis aspects

Zhao

Zhang

Mousseau

et al. 2009

Nuclear Engineering and Design

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Section: Iiic Comparison With Other Power Cyclesmentioning

confidence: 99%

Section: Optimization Of Pcs and Overall Plant Costmentioning

confidence: 99%

Improving SFR economics through innovations from thermal design and analysis aspects

Zhao

Zhang

Mousseau

et al. 2009

Nuclear Engineering and Design

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“…Furthermore, the net efficiency of the SCO 2 cycle was shown to be significantly less sensitive to penalties from core bypass flow and cycle pressure drops than the helium Brayton cycle [4].…”

Section: Introductionmentioning

confidence: 99%

Preliminary Design and Model Assessment of a Supercritical CO2 Compressor

et al. 2018

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Abstract:The compressor is a key component in the supercritical carbon dioxide (SCO 2 ) Brayton cycle. In this paper, the authors designed a series of supercritical CO 2 compressors with different parameters. These compressors are designed for 100 MWe, 10 MWe and 1 MWe scale power systems, respectively. For the 100 MWe SCO 2 Brayton cycle, an axial compressor has been designed by the Smith chart to test whether an axial compressor is suitable for the SCO 2 Brayton cycle. Using a specific speed and a specific diameter, the remaining two compressors were designed as centrifugal compressors with different pressure ratios to examine whether models used for air in the past are applicable to SCO 2 . All compressors were generated and analyzed with internal MATLAB programs coupled with the NIST REFPROP database. Finally, the design results are all checked by numerical simulations due to the lack of reliable experimental data. Research has found that in order to meet the de Haller stall criterion, axial compressors require a considerable number of stages, which introduces many additional problems. Thus, a centrifugal compressor is more suitable for the SCO 2 Brayton cycle, even for a 100 MWe scale system. For the performance prediction model of a centrifugal compressor, the stall predictions are compared with steady numerical calculation, which indicates that past stall criteria may also be suitable for SCO 2 compressors, but more validations are needed. However, the accuracy of original loss models is found to be inadequate, particularly for lower flow and higher pressure ratio cases. Deviations may be attributed to the underestimation of clearance loss according to the result of steady simulation. A modified model is adopted which can improve the precision to a certain extent, but more general and reasonable loss models are needed to improve design accuracy in the future.

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“…This power plant cycle was originally described by Dostal in his ScD Thesis/Topical Report [1], and subsequently referenced in a variety of other publications [2][3][4][5][6][7][8][9].…”

Section: Introductionmentioning

confidence: 99%

Optimization and Comparison of Direct and Indirect Supercritical Carbon Dioxide Power Plant Cycles for Nuclear Applications

Harvego

McKellar

2011

Volume 4: Energy Systems Analysis, Thermodynamics and Sustainability; Combustion Science and Engineering; Nanoengineering for E

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Results of analyses performed using the UniSim process analyses software to evaluate the performance of both a direct and indirect supercritical CO 2 Brayton power plant cycle with recompression at different reactor outlet temperatures are presented. The direct supercritical CO 2 power plant cycle transferred heat directly from a 600 MW t reactor to the supercritical CO 2 working fluid supplied to the turbine generator at approximately 20 MPa. The indirect supercritical CO 2 cycle assumed a helium-cooled Very High Temperature Reactor (VHTR), operating at a primary system pressure of approximately 7.0 MPa, delivered heat through an intermediate heat exchanger to the secondary indirect supercritical CO 2 recompression Brayton cycle, again operating at a pressure of about 20 MPa. For both the direct and indirect power plant cycles, sensitivity calculations were performed for reactor outlet temperature between 550°C and 850°C.The UniSim models used realistic component parameters and operating conditions to model the complete reactor and power conversion systems. CO 2 properties were evaluated, and the operating ranges of the cycles were adjusted to take advantage of the rapidly changing properties of CO 2 near the critical point. The results of the analyses showed that, for the direct supercritical CO 2 power plant cycle, thermal efficiencies in the range of approximately 40 to 50% can be achieved over the reactor coolant outlet temperature range of 550°C to 850°C. For the indirect supercritical CO 2 power plant cycle, thermal efficiencies were approximately 11 -13% lower than those obtained for the direct cycle over the same reactor outlet temperature range. NOMENCLATURE INTRODUCTIONThis study provides an evaluation and comparison of the performance of direct and indirect supercritical CO 2 power plant cycles operating in a reactor outlet temperature range between 550°C and 850°C. The power plant cycle selected for this study is referred to as a supercritical CO 2 closed Brayton cycle (also known as the Joule cycle) with recompression.This power plant cycle was originally described by Dostal in his ScD Thesis/Topical Report [1], and subsequently referenced in a variety of other publications [2][3][4][5][6][7][8][9].The Next Generation Nuclear Plant (NGNP) is a proposed full scale facility to be used to demonstrate the commercial potential of a high temperature gas-cooled nuclear reactor for electricity and process heat applications.The current reference design for the NGNP is a helium-cooled Very High Temperature Reactor (VHTR) operating with a 750°C reactor coolant outlet temperature. For NGNP applications, the supercritical CO 2 recompression Brayton cycle would be operated as an indirect power conversion cycle, in which the helium-cooled VHTR, operating at a primary system pressure of approximately 7.0 MPa, delivers heat through an intermediate heat exchanger to the secondary indirect supercritical CO 2 recompression Brayton cycle operating at a pressure of about 20 MPa. However, the direct supercritical

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The Supercritical Carbon Dioxide Power Cycle: Comparison to Other Advanced Power Cycles

Cited by 315 publications

References 4 publications

Improving SFR economics through innovations from thermal design and analysis aspects

Improving SFR economics through innovations from thermal design and analysis aspects

Preliminary Design and Model Assessment of a Supercritical CO2 Compressor

Optimization and Comparison of Direct and Indirect Supercritical Carbon Dioxide Power Plant Cycles for Nuclear Applications

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