Preliminary design of an SCO2 conversion system applied to the sodium cooled fast reactor

Hongyi YANG , Xiaoyan YANG , Jun YANG , Quanbin ZHAO , Xiaokun WANG , Daotong CHONG , Chanjuan TANG , Chengyuan JIANG

Front. Energy ›› 2021, Vol. 15 ›› Issue (4) : 832 -841.

PDF (1198KB)
Front. Energy ›› 2021, Vol. 15 ›› Issue (4) : 832 -841. DOI: 10.1007/s11708-021-0777-5
RESEARCH ARTICLE
RESEARCH ARTICLE

Preliminary design of an SCO2 conversion system applied to the sodium cooled fast reactor

Author information +
History +
PDF (1198KB)

Abstract

The supercritical carbon dioxide (SCO2) Brayton cycle has become an ideal power conversion system for sodium-cooled fast reactors (SFR) due to its high efficiency, compactness, and avoidance of sodium-water reaction. In this paper, the 1200 MWe large pool SFR (CFR1200) is used as the heat source of the system, and the sodium circuit temperature and the heat load are the operating boundaries of the cycle system. The performance of different SCO2 Brayton cycle systems and changes in key equipment performance are compared. The study indicates that the inter-stage cooling and recompression cycle has the best match with the heat source characte-ristics of the SFR, and the cycle efficiency is the highest (40.7%). Then, based on the developed system transient analysis program (FR-Sdaso), a pool-type SFR power plant system analysis model based on the inter-stage cooling and recompression cycle is established. In addition, the matching between the inter-stage cooling recompression cycle and the SFR during the load cycle of the power plant is studied. The analysis shows that when the nuclear island adopts the flow-advanced operation strategy and the carbon dioxide flowrate in the SCO2 power conversion system is adjusted with the goal of maintaining the sodium-carbon dioxide heat exchanger sodium side outlet temperature unchanged, the inter-stage cooling recompression cycle can match the operation of the SFR very well.

Graphical abstract

Keywords

sodium-cooled fast reactor (SFR) / supercritical carbon dioxide (SCO2) / brayton cycle / load cycle

Cite this article

Download citation ▾
Hongyi YANG, Xiaoyan YANG, Jun YANG, Quanbin ZHAO, Xiaokun WANG, Daotong CHONG, Chanjuan TANG, Chengyuan JIANG. Preliminary design of an SCO2 conversion system applied to the sodium cooled fast reactor. Front. Energy, 2021, 15(4): 832-841 DOI:10.1007/s11708-021-0777-5

登录浏览全文

4963

注册一个新账户 忘记密码

References

[1]

Dostal V A. Supercritical carbon dioxide cycle for next generation nuclear reactors. Dissertation for the Doctoral Degree. Prague: Czech Technical University, 2004

[2]

Feher E G. The supercritical thermodynamic power cycle. Energy Conversion, 1968, 8(2): 85–90

[3]

Angelino G. Carbon dioxide condensation cycles for power production. Journal of Engineering for Power, 1968, 90(3): 287–295

[4]

Angelino G. Real gas effects in carbon dioxide cycles. In: Proceedings of ASME 1969 Gas Turbine Conference and Products Show, Cleveland, Ohio, USA, 2015

[5]

Ahn Y, Bae S J, Kim M, Review of supercritical CO2 power cycle technology and current status of research and development. Nuclear Engineering and Technology, 2015, 47(6): 647–661

[6]

Sarkar J, Bhattacharyya S. Optimization of recompression S-CO2 power cycle with reheating. Energy Conversion and Management, 2009, 50(8): 1939–1945

[7]

Sarkar J. Second law analysis of supercritical CO2 recompression Brayton cycle. Energy, 2009, 34(9): 1172–1178

[8]

Yari M, Sirousazar M. A novel recompression S-CO2 brayton cycle with pre-cooler exergy utilization. Proceedings of the Institution of Mechanical Engineers, Part A, Journal of Power and Energy, 2010, 224(7): 931–946

[9]

Akbari A D, Mahmoudi S M S. Thermoeconomic analysis & optimization of the combined supercritical CO2 (carbon dioxide) recompression Brayton/organic Rankine cycle. Energy, 2014, 78: 501–512

[10]

Moisseytsev A, Sienicki J J. Investigation of alternative layouts for the supercritical carbon dioxide Brayton cycle for a sodium-cooled fast reactor. Nuclear Engineering and Design, 2009, 239(7): 1362–1371

[11]

Guo J, Li M, Xu J, Thermodynamic performance analysis of different supercritical Brayton cycles using CO2-based binary mixtures in the molten salt solar power tower systems. Energy, 2019, 173: 785–798

[12]

Guo J, Li M, He Y, A study of new method and comprehensive evaluation on the improved performance of solar power tower plant with the CO2-based mixture cycles. Applied Energy, 2019, 256: 113837

[13]

Duan C, Wang J, Yang X. Features of supercritical carbon dioxide brayton cycle coupled with reactor. Atomic Energy Science and Technology, 2010, 44(11): 1341–1348 (in Chinese)

[14]

Duan C, Yang X, Wang J. Parameters optimization of supercritical carbon dioxide Brayton cycle. Atomic Energy Science and Technology, 2011, 45(12): 1489–1494 (in Chinese)

[15]

Liang D, Zhang Y, Guo Q, Modeling and analysis of nuclear reactor system using supercritical-CO2 Brayton cycle. Journal of Xiamen University (Natural Science), 2015, 54(5): 608–613 (in Chinese)

[16]

Yang J, Zhao Q, Wang X, Research on supercritical carbon dioxide power conversion system applied to sodium cold fast reactor. Atomic Energy Science and Technology, 2020, 54(10): 1818–1824 (in Chinese)

[17]

Wang Y, Guenette G, Hejzlar P, Compressor design for the supercritical CO2 Brayton cycle. In: 2nd International Energy Conversion Engineering Conference, Reston, Virigina, USA, 2004

[18]

Wang X, Qi S, Yang J, Development of system code FR-Sdaso for sodium cooled fast reactor. Atomic Energy Science and Technology, 2020, 54(11): 2045–2053 (in Chinese)

[19]

Ye S, Guo X, Thanh H, Development and verification of coast-down model for coolant pump of nuclear power plant based on time parameter. Atomic Energy Science and Technology, 2020, 54(4): 642–647 (in Chinese)

[20]

Qi S, Yang H, Yang X, Analysis of French Phenix end-of-life natural circulation test based on FR-Sdaso. Atomic Energy Science and Technology, 2020, 54(2): 273–280 (in Chinese)

[21]

Ye S, Yang H, Liu Y, Analysis of fixed and movable boundary models for once-through steam generator of sodium-cooled fast reactor. Atomic Energy Science and Technology, 2017, 51(7): 1219–1224 (in Chinese)

[22]

Yang J, Jia H, Yang X, Development and validation of decay heat model for sodium cooled fast reactor system code FR-Sdaso. Atomic Energy Science and Technology, 2020, 54(8): 1418–1425 (in Chinese)

RIGHTS & PERMISSIONS

Higher Education Press

AI Summary AI Mindmap
PDF (1198KB)

3043

Accesses

0

Citation

Detail

Sections
Recommended

AI思维导图

/