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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.1
- 수록면
- 93 - 102 (10page)
- DOI
- https://doi.org/10.1016/j.net.2020.07.002
이용수
초록· 키워드
오류제보하기
The analysis of the fluid flow characteristics in reactor pressure vessel is an important part of the hydraulicdesign of nuclear power plant, which is related to the structure design of reactor internals, theflow distribution at core inlet and the safety of nuclear power plant. The flow distribution and mixingcharacteristics in the pressurized reactor vessel for the 1000MWe advanced pressurized water reactor isanalyzed by using Computational Fluid Dynamics (CFD) method in this study. The geometry model of thefull-scaled reactor vessel is built, which includes the cold and hot legs, downcomer, lower plenum, core,upper plenum, top plenum, and is verified with some parameters in DCD. Under normal condition, it isfound that the flow skirt, core plate holes and outlet pipe cause pressure loss. The maximum andminimum flow coefficient is 1.028 and 0.961 respectively, and the standard deviation is 0.019. Comparedwith other reactor type, it shows relatively uniform of the flow distribution at the core inlet. The coolantmixing coefficient is investigated with adding additional variables, showing that mass transfer of coolantoccurs near the interface. The coolant mainly distributes in the 90 area of the corresponding core inlet,and mixes at the interface with the coolant from the adjacent cold leg. 0.1% of corresponding coolant isstill distributed at the inlet of the outer-ring components, indicating wide range of mixing coefficientdistribution.
목차
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참고문헌 (17)
참고문헌 신청
G. Prasser / 2003 / Coolant mixing in a pressurized water reactor: deboration transients, steam-line breaks, and emergency core cooling injection / Nucl. Technol 143(1):37~56
R. J. Hertlein / 2003 / Experimental and numerical investigation of boron dilution transients in pressurized water reactors / Nucl. Technol 141(1):88~107
R. Ulrich / 2005 / The European Project FLOMIX-R: Fluid Mixing and Flow Distribution in the Reactor Circuit, Final Summary Report
T. Hohne / 2006 / Modeling of a buoyancy-driven flow experiment at the ROCOM test facility using the CFD codes CFX-5 and TRIO U / Nucl. Eng. Des 236(12):1309~1325
Kim Kihwan / 2013 / Experimental study of the APRþ reactor core flow and pressure distributions under 4-pump running conditions / Nucl. Eng. Des 265:957~966
R. J. Hertlein / 2003 / Experimental and numerical investigation of boron dilution transients in pressurized water reactors / Nucl. Technol 141(1):88~107
R. Ulrich / 2005 / The European Project FLOMIX-R: Fluid Mixing and Flow Distribution in the Reactor Circuit, Final Summary Report
T. Hohne / 2006 / Modeling of a buoyancy-driven flow experiment at the ROCOM test facility using the CFD codes CFX-5 and TRIO U / Nucl. Eng. Des 236(12):1309~1325
Kim Kihwan / 2013 / Experimental study of the APRþ reactor core flow and pressure distributions under 4-pump running conditions / Nucl. Eng. Des 265:957~966
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