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Volumn 65, Issue 5-6, 2000, Pages 222-226

Investigation on two-phase flow stability in a natural circulation system

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; COMPUTER SIMULATION; HEAT TRANSFER; HYDRODYNAMICS; REACTOR CORES; THERMODYNAMIC STABILITY; NATURAL CONVECTION; OSCILLATING FLOW;

EID: 0034314925     PISSN: 09323902     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article
Times cited : (6)

References (10)
  • 2
    • 0015648327 scopus 로고
    • Review of two-phase flow instability
    • Tong, L. S.: Review of Two-Phase Flow Instability. Nuclear Engineering and Design 25 (1973) 165
    • (1973) Nuclear Engineering and Design , vol.25 , pp. 165
    • Tong, L.S.1
  • 3
    • 0023157581 scopus 로고
    • Experimental study on two-phase flow instability in system including downcomers
    • Fukuda, K. et al.: Experimental Study on Two-phase Flow Instability in System Including Downcomers. J. of Nuclear Science and Technology 24 (1987) 266
    • (1987) J. of Nuclear Science and Technology , vol.24 , pp. 266
    • Fukuda, K.1
  • 4
    • 0008741025 scopus 로고
    • Thermally induced flow oscillation in vertical two-phase natural circulation loop
    • Lee, S. Y. and Ishii, M.: Thermally Induced Flow Oscillation in Vertical Two-phase Natural Circulation Loop. Nuclear Engineering and Design 122 (1990) 119
    • (1990) Nuclear Engineering and Design , vol.122 , pp. 119
    • Lee, S.Y.1    Ishii, M.2
  • 5
    • 0006030629 scopus 로고
    • Flow rate and density oscillations during two-phase natural circulation in PWR typical conditions
    • DÁuria, F. and Galassi, G. M.: Flow rate and Density Oscillations during Two-Phase Natural Circulation in PWR Typical Conditions. Nuclear Engineering and Design 122 (1990) 209
    • (1990) Nuclear Engineering and Design , vol.122 , pp. 209
    • Dáuria, F.1    Galassi, G.M.2
  • 6
    • 43949162690 scopus 로고
    • Technical design features and safety analysis of the 200 MW nuclear heating reactor
    • Wang, D. Z.; Zheng, W. X. et al.: Technical design features and safety analysis of the 200 MW nuclear heating reactor. Nuclear Engineering and Design 143 (1993) 1
    • (1993) Nuclear Engineering and Design , vol.143 , pp. 1
    • Wang, D.Z.1    Zheng, W.X.2
  • 7
    • 0343191039 scopus 로고
    • An investigation of the two-phase flow stability on a low-temperature heating reactor
    • Tsinghua University
    • Wu, S. R.; Yao, M. S.; Bo, J. H. and Jang, S. Y.: An Investigation of the Two-phase Flow Stability on a low-temperature heating reactor. INET Report, Tsinghua University, 1987 (in Chinese)
    • (1987) INET Report
    • Wu, S.R.1    Yao, M.S.2    Bo, J.H.3    Jang, S.Y.4
  • 8
    • 0342321497 scopus 로고
    • HRTL-200 thermal-hydraulic test loop
    • Tsinghua University, in Chines
    • Wu, S. R.; Jia, H. J.; Li, H. X. et al.: HRTL-200 Thermal-hydraulic Test Loop. INET Report, Tsinghua University, 1993 (in Chines)
    • (1993) INET Report
    • Wu, S.R.1    Jia, H.J.2    Li, H.X.3
  • 9
    • 0141778007 scopus 로고
    • An experimental study on hydrodynamic stability of low quality two-phase flow with natural circulation
    • Fluid Mechanics and Thermodynamics, Dubrovnik, Yugoslavia, Sept. Elsevier
    • Wu, S. R.; Wang, D. Z.; Yao, M. S. et al.: An Experimental Study on Hydrodynamic Stability of Low Quality Two-Phase Flow With Natural Circulation. Proceedings of the First World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics, Dubrovnik, Yugoslavia, Sept. 1988, Elsevier, pp. 1120-1127
    • (1988) Proceedings of the First World Conference on Experimental Heat Transfer , pp. 1120-1127
    • Wu, S.R.1    Wang, D.Z.2    Yao, M.S.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.