본문 바로가기
KERD
논문KCI 등재

Study on load tracking characteristics of closed Brayton conversion liquid metal cooled space nuclear power system

2

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

It is vital to output the required electrical power following various task requirements when the space reactor power supply is operating in orbit. The dynamic performance of the closed Brayton cycle thermoelectric conversion system is initially studied and analyzed. Based on this, a load tracking power regulation method is developed for the liquid metal cooled space reactor power system, which takes into account the inlet temperature of the lithium on the hot side of the intermediate heat exchanger, the filling quantity of helium and xenon, and the input amount of the heat pipe radiator module. After comparing several methods, a power regulation method with fast response speed and strong system stability is obtained. Under various changes in power output, the dynamic response characteristics of the ultra-small liquid metal lithium-cooled space reactor concept scheme are analyzed. The transient operation process of 70 % load power shows that core power variation is within 30 % and core coolant temperature can operate at the set safety temperature. The second loop’s helium-xenon working fluid has a 65K temperature change range and a 25 % filling quantity. The lithium at the radiator loop outlet changes by less than ±7 K, and the system’s main key parameters change as expected, indicating safety. The core system uses less power during 30 % load power transient operation. According to the response characteristics of various system parameters, under low power operation conditions, the lithium working fluid temperature of the radiator circuit and the high-temperature heat pipe operation temperature are limiting conditions for low-power operation, and multiple system parameters must be coordinated to ensure that the radiator system does not condense the lithium working fluid and the heat pipe.

Abstract

It is vital to output the required electrical power following various task requirements when the space reactor power supply is operating in orbit. The dynamic performance of the closed Brayton cycle thermoelectric conversion system is initially studied and analyzed. Based on this, a load tracking power regulation method is developed for the liquid metal cooled space reactor power system, which takes into account the inlet temperature of the lithium on the hot side of the intermediate heat exchanger, the filling quantity of helium and xenon, and the input amount of the heat pipe radiator module. After comparing several methods, a power regulation method with fast response speed and strong system stability is obtained. Under various changes in power output, the dynamic response characteristics of the ultra-small liquid metal lithium-cooled space reactor concept scheme are analyzed. The transient operation process of 70 % load power shows that core power variation is within 30 % and core coolant temperature can operate at the set safety temperature. The second loop’s helium-xenon working fluid has a 65K temperature change range and a 25 % filling quantity. The lithium at the radiator loop outlet changes by less than ±7 K, and the system’s main key parameters change as expected, indicating safety. The core system uses less power during 30 % load power transient operation. According to the response characteristics of various system parameters, under low power operation conditions, the lithium working fluid temperature of the radiator circuit and the high-temperature heat pipe operation temperature are limiting conditions for low-power operation, and multiple system parameters must be coordinated to ensure that the radiator system does not condense the lithium working fluid and the heat pipe.

참고문헌 (24)

  1. The Role of Nuclear Power and Nuclear Propulsion in the Peaceful Exploration of Space, "A. Stanculescu", IAEA, ~ (2005)
  2. The Role of Nuclear Power and Nuclear Propulsion in the Peaceful Exploration of Space, "A. Stanculescu", IAEA, ~ (2005)
  3. M. Gibson, "Higher Power Design Concepts for NASA’s Kilopower reactor", 2020 IEEE Aerospace Conference (2020)
  4. I.P. David, "Design and Analysis of the SAFE-400 Space Fission reactor", Space Technology and Applications International Forum-STAIF 2002, pp.578~588 (2002), American Institute of Physics
  5. M. S. El-Genk, ""SAIRS"-Scalable AMTEC integrated reactor space power system", Prog. Nucl. Energy, 45(1), pp.25~59 (2004)
  6. Y.G. Dragunov, "Fast-neutron gas-cooled reactor for the megawatt-class space bimodal nuclear thermal system", Engineering and Automation Problems, (2), pp.117~120 (2015)
  7. S. A. Wright, "Pin-type gas cooled reactor for nuclear electric propulsion", AIP Conference Proceedings, 654(1), pp.408~419 (2003), AIP
  8. Zeguang Li, "Design of a hundred-kilowatt level integrated gas-cooled space nuclear reactor for deep space application", Nuclear Enginerring and Design, 361, pp.11569~ (2020)
  9. Characteristics of the Soviet TOPAZ II Space Power System, "N. G. Gunther", Space Power Inc, ~, pp.Report No. SPI-52-1 (1990)
  10. SP-100. A Flexible Technology for Space Power from 10s to 100s of kWe, "P. R. Pluta", IEEE, ~ (1989)
  11. S. A. Hatton, "Sectored compact space reactor(SCoRe)concepts with a supplemerntary lunar regolith reflector", Prog. Nucl. Energy, 51(1), pp.93~108 (2009)
  12. M. S. El-Genk, "A performance comparison of SiGe and skutterudite based segmented thermometric devices", Proceedings Space Technology and Applications International Forum (STAIF-02), pp.107~115 (2002), American Institute of Physics
  13. M. S. El-Genk, "High efficiency segmented thermoelectric unicouple for operation between 973 and 300 K", Energy Convers. Manag, 44, pp.1069~1088 (2003)
  14. Wuye Zhong, "A review of technology development of thermionic energy conversion for space application", Journal of Deep Space Exploration, 7(1), pp.47~60 (2020)
  15. Lei Zhu, "Analysis approach for performance of vapor-fed alkali metal thermal to electric converter", Atomic Energy Sci. Technol, 50(10), pp.1834~1839 (2016)
  16. B. B. Bevard, "Technology development program for an advanced potassium rankine power conversion system compatible with several space reactor designs", Proceedings of the Space Technology and Applications International Forum (STAIF-03), pp.629~640 (2003), American Institute of Physics
  17. Closed Brayton Cycle Power Conversion Unit for Fission Surface Power Phase I Final report, "L. F. Robert", Glenn Research Center, National Aeronautics and Space Administration, ~, pp.NASA (2010), CR-2010-215673
  18. N. F. Lamartine, "Design of a simplified closed brayton cycle for a space reactor application", AIP Conference Proceedings, 1103(486), pp.486~491 (2009), AIP
  19. Free-piston Striling Power Conversion Unit for Fission Surface Power, Phase I Final report, "J. G. Wood", NASA, ~, pp.NASA (2010), CR-2010-216750
  20. A Small Fission Power System with Stirling Power Conversion for NASA Science missions, "M. Lee", NASA Glenn Research Center, ~, pp.NASA (2012), TM-2011-217204
  21. G. P. Alexander, "Load-following voltage controller design for a static space nuclear power system", Nucl. Sci. Eng, 136(2), pp.227~246 (2000)
  22. Huaqi Li, "Development of metal lithum coolant termophysical properties calculation model and code for space reactors", Nucl. Power Eng, 2(38), pp.1~ (2017)
  23. Xue Qi, "Research on load operation strategy of supercritical carbon dioxide nuclear power system", Nucl. Sci. Eng, 4 (2022)

관련 논문AI추천

Thermal-hydraulic and load following performance analysis of a heat pipe cooled reactorJiao Guanghui, Peng Minjun, Wang Jianjun, Xia Genglei한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제5호Conceptual design for a 5 kWe space nuclear reactor power systemChen Chao, He Meisheng, Li Taosheng, Li Yang, Ma Shengqin, Mei Huaping, Sun Yongju, Wang Haixia, Wang Liang, Yu Dali, Yu Jie, Zhang Jiansong한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제9호Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uraniumCao Xiaogang, Huang Xi, Liu Yibao, Sun Yanting, Wen Xiaojian, Zeng Qiusun, Zou Xiaoliang한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제12호Study on the operation scheme of a pool-type lead-bismuth fast reactorLi Muping, Sun Aodi, Sun Peiwei, Wei Xinyu, Zhang Ru한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제8호Thermal-hydraulic analysis of He–Xe gas mixture in 2×2 rod bundle wrapped with helical wiresChen Siyuan, Qiu Suizheng, Su G.H., Tian Wenxi, Wang Chenglong한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제7호Conceptual design of a dual drum-controlled space molten salt reactor (D2-SMSR): Neutron physics and thermal hydraulicsDeng Haoyue, Ji Chen, Song Yongnian, Tang Xiaobin, Zhao Hangbin, Zhuang Nailiang한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제6호

이 간행물의 다른 논문 (39건)