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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 1,154 - 1,161 (8page)
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The heat transfer characteristics between liquid lead bismuth eutectic (LBE) and helium are of great significance for the two-loop cooling system based on an accelerator-driven system(ADS). This paper presents an experimental study on the resistance characteristics and heat transfer performance in a LBE-helium experimental loop of ADS. Pressure drops in the LBE loop, the main heat transfer, and the coupled heat transfer characteristics between LBE and helium are investigated experimentally. The temperature of LBE has a significant effect on the LBE thermo-physical properties, and is therefore considered in the prediction of pressure drops. The results show that the overall heat transfer coefficient increases with the increasing helium flow rate and the decreasing inlet temperature of helium. Increasing the LBE Reynolds number and LBE inlet temperature promotes the heat transfer performance of main heat transfer and thus the overall heat transfer coefficient. The experimental results give an insight into the flow and heat transfer properties in a LBE-helium heat exchanger and are helpful for the optimization of an ADS system design.
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참고문헌 (17)
참고문헌 신청
C. Rubbia / 1996 / Status of the Energy Amplifier Concept / Proceeding of the 2nd International Conference on Accelerator-driven Transmutation Technologies and Applications
L. Cinotti / 2002 / The PbeBi cooled XADS status of development / J. Nucl. Mater 301:8~14
T. Schulenberg / 2005 / Thermal-hydraulics of Lead-Bismuth for Accelerator Driven Systems / The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics
S. Ishiyama / 2008 / Study of steam, helium and supercritical CO2turbine power generations in prototype fusion power reactor / Prog. Nucl. Energ 50:325~332
X. Cheng / 2006 / Investigation on turbulent heat transfer to leadebismuth eutectic flows in circular tubes for nuclear applications / Nucl. Eng. Des 236:385~393
L. Cinotti / 2002 / The PbeBi cooled XADS status of development / J. Nucl. Mater 301:8~14
T. Schulenberg / 2005 / Thermal-hydraulics of Lead-Bismuth for Accelerator Driven Systems / The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics
S. Ishiyama / 2008 / Study of steam, helium and supercritical CO2turbine power generations in prototype fusion power reactor / Prog. Nucl. Energ 50:325~332
X. Cheng / 2006 / Investigation on turbulent heat transfer to leadebismuth eutectic flows in circular tubes for nuclear applications / Nucl. Eng. Des 236:385~393
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