Nuclear Engineering and Technology

  • 제41권8호
  • /
  • Pages.1025-1044
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  • 2009
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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DEVELOPMENT OF A SUPERCRITICAL CO2 BRAYTON ENERGY CONVERSION SYSTEM COUPLED WITH A SODIUM COOLED FAST REACTOR

  • 발행 : 2009.10.31
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초록

Systematic research has been conducted by KAERI to develop a supercritical carbon dioxide Brayton cycle energy conversion system coupled with a sodium cooled fast reactor. For the development of the supercritical $CO_2$ Brayton cycle ECS, KAERI researched four major fields, separately. For the system development, computer codes were developed to design and analyze the supercritical $CO_2$ Brayton cycle ECS coupled with the KALIMER-600. Computer codes were developed to design and analyze the performance of the major components such as the turbomachinery and the high compactness PCHE heat exchanger. Three dimensional flow analysis was conducted to evaluate their performance. A new configuration for a PCHE heat exchanger was developed by using flow analysis, which showed a very small pressure loss compared with a previous PCHE while maintaining its heat transfer rate. Transient characteristics for the supercritical $CO_2$ Brayton cycle coupled with KALIMER-600 were also analyzed using the developed computer codes. A Na-$CO_2$ pressure boundary failure accident was analyzed with a computer code that included a developed model for the Na-$CO_2$ chemical reaction phenomena. The MMS-LMR code was developed to analyze the system transient and control logic. On the basis of the code, the system behavior was analyzed when a turbine load was changed. This paper contains the current research overview of the supercritical $CO_2$ Brayton cycle coupled to the KALIMER-600 as an alternative energy conversion system.

키워드

참고문헌

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피인용 문헌

  1. Muon Radiolysis Affected by Density Inhomogeneity in Near-Critical Fluids vol.181, pp.4, 2014, https://doi.org/10.1667/RR13516.1
  2. Brayton Cycle as Power Conversion System vol.2018, pp.1687-6083, 2018, https://doi.org/10.1155/2018/6801736
  3. Corrosion Behavior of Heat-Resistant Materials in High-Temperature Carbon Dioxide Environment vol.70, pp.8, 2018, https://doi.org/10.1007/s11837-018-2975-0
  4. in nuclear engineering: A review pp.1757-4838, 2018, https://doi.org/10.1177/1757482X18765377