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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 755 - 763 (9page)
이용수
초록· 키워드
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The critical flow phenomenon has been studied because of its significant effect for design basis accidents in nuclear power plants. Transition points from thermal non-equilibrium to equilibrium are different according to the geometric effect on the critical flow. This study evaluates the uncertainty parameters of the critical flow model for analysis of DBA (Design Basis Accident) with the MARS-KS (Multi-dimensional Analysis for Reactor Safety-KINS Standard) code used as an independent regulatory assessment. The uncertainty of the critical flow model is represented by three parameters including the thermal nonequilibrium factor, discharge coefficient, and length to diameter (L/D) ratio, and their ranges are determined using large-scale Marviken test data. The uncertainty range of the thermal non-equilibrium factor is updatedbythe MCDA(Model Calibration through Data Assimilation) method. The updateduncertainty range is confirmed using an LBLOCA (Large Break Loss of Coolant Accident) experiment in the LOFT (Loss of Fluid Test) facility. The uncertainty ranges are also used to calculate an LBLOCA of the APR (Advanced Power Reactor) 1400 NPP (Nuclear Power Plants), focusing on the effect of the PCT (Peak Cladding Temperature). The results reveal that break flow is strongly dependent on the degree of the thermal nonequilibrium state in a ruptured pipe with a small L/D ratio. Moreover, this study provides the method to handle the thermal non-equilibrium factor, discharge coefficient, and length to diameter (L/D) ratio in the system code.
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참고문헌 (15)
참고문헌 신청
H.K. Fauske / 1962 / Contribution to the Theory of Two-phase, One Component Critical Flow / ANL-6633
R. E. Henry / 1974 / The two-phase critical flow of one-component mixtures in nozzles, orifices and short tubes / ASME J. Heat Transf :179~187
F.J. Moody / 1965 / Maximum flow rate of a single component, two-phase mixture / ASME J. Heat Transf. :134~142
G.L. Sozzi / 1975 / Critical Flow of Saturated and Subcooled Water at High Pressure / NEDO-13418
F.R. Zaloudek / 1963 / Critical Flow of Hot Water through Short Tubes / General Electric HW-77594
R. E. Henry / 1974 / The two-phase critical flow of one-component mixtures in nozzles, orifices and short tubes / ASME J. Heat Transf :179~187
F.J. Moody / 1965 / Maximum flow rate of a single component, two-phase mixture / ASME J. Heat Transf. :134~142
G.L. Sozzi / 1975 / Critical Flow of Saturated and Subcooled Water at High Pressure / NEDO-13418
F.R. Zaloudek / 1963 / Critical Flow of Hot Water through Short Tubes / General Electric HW-77594
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