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Volumn 126, Issue 2, 1997, Pages 229-238

Critical flow of initially highly subcooled water through a short capillary

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EID: 0009642692     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE97-A24476     Document Type: Article
Times cited : (7)

References (23)
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  • 6
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    • (1971) J. Heat Transfer , vol.83 , pp. 179
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  • 7
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    • An Isentropic Stream Tube Model for Flashing Two-Phase Vapor-Liquid Flow
    • G. B. WALLIS and H. J. RICHTER, "An Isentropic Stream Tube Model for Flashing Two-Phase Vapor-Liquid Flow," J. Heat Transfer, 100, 595 (1978).
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  • 8
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    • Separated Two-Phase Flow Model: Application to Critical Two-Phase Flow
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    • A Two-Fluid Model for Non-Equilibrium Two-Phase Critical Discharge
    • C. F. SCHWELLNUS and M. SHOUKRI, "A Two-Fluid Model for Non-Equilibrium Two-Phase Critical Discharge," Can. J. Chem. Eng., 69, 188 (1991).
    • (1991) Can. J. Chem. Eng. , vol.69 , pp. 188
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  • 11
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    • Two-Phase Flow Experiments Through Intergranular Stress Corrosion Cracks
    • Monterey, California, September 1-2, 1983, NUREG/CP-0051, U.S. Nuclear Regulatory Commission
    • R. P. COLLIER and D. M. NORRIS, "Two-Phase Flow Experiments Through Intergranular Stress Corrosion Cracks," Proc. CSNI Leak-Before-Break Conf., Monterey, California, September 1-2, 1983, NUREG/CP-0051, p. 273, U.S. Nuclear Regulatory Commission (1983).
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  • 12
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    • Two-Phase Critical Flow in Slits
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    • Amos, C.N.1    Schrock, V.E.2
  • 15
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    • Prediction of Leak Rates Through Intergranular Stress Corrosion Cracks
    • Monterey, California, September 1-2, 1983, NUREG/ CP-00151, U.S. Nuclear Regulatory Commission
    • D. ABDOLLAHIAN, B. CHEXAL, and D. M. MORRIS, "Prediction of Leak Rates Through Intergranular Stress Corrosion Cracks," Proc. CSNI Leak-Before-Break Conf., Monterey, California, September 1-2, 1983, NUREG/ CP-00151, p. 300, U.S. Nuclear Regulatory Commission (1983).
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  • 18
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  • 20
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    • M. EPSTEIN, R. HENRY, W. MIDVIDY, and R. PAULS, "One-Dimensional Modeling of Two-Phase Jet Expansion and Impingement," Proc. 2nd Int. Topi. Mtg. Nuclear Reactor Thermal-Hydraulics, Santa Barbara, California, January 11-14, 1983, Vol. II, p. 769, American Nuclear Society (1983).
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.