Westinghouse 1/7 실험장치의 증기발생기 입구플레넘 내의 자연대류 유동에 대한 CFD 해석방법론 개발 (DEVELOPMENT OF A CFD ANALYSIS METHODOLOGY FOR A NATURAL CONVECTIVE FLOW IN THE STEAM GENERATOR INLET PLENUM AT THE WESTINGHOUSE 1/7 TEST FACILITY)

서지정보

· 발행기관 : 한국전산유체공학회
· 수록지 정보 : 한국전산유체공학회지 / 25권 / 3호 / 34 ~ 43페이지
· 저자명 : 강형석, 김성일, 하광순

초록

Korea Atomic Energy Research Institute performed a CFD calculation of a natural convective flow in the steam generator inlet plenum at the Westinghouse 1/7 test facility to establish an analysis methodology for generating input parameters of the MELCOR code which will be used in analyzing the temperature induced steam generator tube rupture accident in an optimized power reactor 1000 MWe. Through this CFD analysis against the test results, we developed a CFD analysis methodology to accurately predict the recirculation ratio, thermal mixing fraction, and discharge coefficient with an error range of approximately ±10%. Though this CFD analysis methodology underestimated approximately 25% for the proposed hot tube number in the steam generator of the test results, we judged that this discrepancy may not be large when considering uncertainties resulted from 51 measured tube temperatures over all 216 tubes in the test facility. Finally, we found that the buoyancy turbulence generation plays an important role to control the natural convection flow in the steam generator inlet plenum because this model can enhance the recirculation flow. As a further work, we will apply the proposed CFD analysis methodology for other test cases conducted at the Westinghouse 1/7 test facility for producing various validation results.

영어초록

Korea Atomic Energy Research Institute performed a CFD calculation of a natural convective flow in the steam generator inlet plenum at the Westinghouse 1/7 test facility to establish an analysis methodology for generating input parameters of the MELCOR code which will be used in analyzing the temperature induced steam generator tube rupture accident in an optimized power reactor 1000 MWe. Through this CFD analysis against the test results, we developed a CFD analysis methodology to accurately predict the recirculation ratio, thermal mixing fraction, and discharge coefficient with an error range of approximately ±10%. Though this CFD analysis methodology underestimated approximately 25% for the proposed hot tube number in the steam generator of the test results, we judged that this discrepancy may not be large when considering uncertainties resulted from 51 measured tube temperatures over all 216 tubes in the test facility. Finally, we found that the buoyancy turbulence generation plays an important role to control the natural convection flow in the steam generator inlet plenum because this model can enhance the recirculation flow. As a further work, we will apply the proposed CFD analysis methodology for other test cases conducted at the Westinghouse 1/7 test facility for producing various validation results.

참고자료

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