메뉴 건너뛰기




Volumn , Issue , 2004, Pages 1618-1626

Large scale verification of external RPV cooling in case of severe accident

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; COMPUTER SIMULATION; COOLING; ELECTRIC RESISTANCE; HEAT FLUX; HEAT TRANSFER; STEAM; THERMOCOUPLES; WETTING;

EID: 14844331100     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (14)

References (19)
  • 1
    • 0010666673 scopus 로고    scopus 로고
    • High heat flux nucleate boiling on the outer surface of a heated hemispherical vessel
    • High Heat Flux Nucleate Boiling on the Outer Surface of a Heated Hemispherical Vessel, AICHe Symp. Ser. Vol. 93, No. 314, pp.95-101, 1997
    • (1997) AICHe Symp. Ser. , vol.93 , Issue.314 , pp. 95-101
  • 3
    • 43949175222 scopus 로고
    • External cooling of a reactor vessel under severe accident conditions
    • Henry R.E. and Fauske H.K.External Cooling of a Reactor Vessel under Severe Accident Conditions, Nuclear Engineering and Design, 139 (1993), pp. 31-43
    • (1993) Nuclear Engineering and Design , vol.139 , pp. 31-43
    • Henry, R.E.1    Fauske, H.K.2
  • 6
    • 27144523297 scopus 로고
    • SULTAN test facility, large scale vessel coolability in natural convection at low pressure
    • Saratoga Springs, NY, USA, Sept. 10-15
    • Rouge S. SULTAN Test Facility, Large Scale Vessel Coolability in Natural Convection at Low Pressure, NURETH-7 Conf., Saratoga Springs, NY, USA, Sept. 10-15, 1995
    • (1995) NURETH-7 Conf.
    • Rouge, S.1
  • 7
    • 84855853542 scopus 로고    scopus 로고
    • Reactor vessel external cooling for corium retention, SULTAN experimental program and modeling with CATHARE code
    • Garching, Germany, March 3-6
    • Rouge S., Dor I. Geffraye G.Reactor Vessel External Cooling for Corium Retention, SULTAN Experimental Program and Modeling with CATHARE Code, OECD Workshop on IN-Vessel Debris Retention and Coolability, Garching, Germany, March 3-6, 1998
    • (1998) OECD Workshop on IN-vessel Debris Retention and Coolability
    • Rouge, S.1    Dor, I.2    Geffraye, G.3
  • 9
    • 14844317100 scopus 로고
    • The coolability limits of a reactor pressure vessel lower head
    • Saratoga Springs, NY, USA, Sept. 10-15
    • Theofanous T.G. and Syri S.The Coolability Limits of a Reactor Pressure Vessel Lower Head, NURETH-7 Conf., Saratoga Springs, NY, USA, Sept. 10-15, 1995
    • (1995) NURETH-7 Conf.
    • Theofanous, T.G.1    Syri, S.2
  • 11
    • 0031126693 scopus 로고    scopus 로고
    • A hydrodynamic critical heat flux model for saturated pool boiling on a downward facing curved heating surface
    • Cheung F.B., Haddad K.H.A Hydrodynamic Critical Heat Flux Model for Saturated Pool Boiling on a Downward Facing Curved Heating Surface, Int. J. Heat Transfer, 40 (1997), pp. 1291-1302
    • (1997) Int. J. Heat Transfer , vol.40 , pp. 1291-1302
    • Cheung, F.B.1    Haddad, K.H.2
  • 12
    • 19044378495 scopus 로고    scopus 로고
    • Natural convection boiling on the outer surface of a hemispherical vessel surrounded by a thermal insulation structure
    • Garching, May 3-6
    • Cheung F.B., Liu Y.C.Natural Convection Boiling on the Outer Surface of a Hemispherical Vessel Surrounded by a Thermal Insulation Structure, OECD Workshop on In-Vessel Debris Retention and Coolability, Garching, May 3-6, 1998
    • (1998) OECD Workshop on In-vessel Debris Retention and Coolability
    • Cheung, F.B.1    Liu, Y.C.2
  • 13
    • 0345350838 scopus 로고    scopus 로고
    • Fundamentals of boiling and multiphase flow under extreme conditions
    • Heat Transfer 1998, Kyongju
    • th IHTC, Vol. 1, pp. 131-147, Kyongju, 1998
    • (1998) th IHTC , vol.1 , pp. 131-147
    • Theofanous, T.G.1    Yuen, W.W.2
  • 15
    • 0003905161 scopus 로고    scopus 로고
    • Void fraction technology for design and analysis
    • March
    • Chexal et. al. Void Fraction Technology for Design and Analysis, EPRI-Report TR-106326, March 1997
    • (1997) EPRI-Report , vol.TR-106326
    • Chexal1
  • 16
    • 0001904923 scopus 로고    scopus 로고
    • The 1995 look-up table for critical heat fluxes in tubes
    • Groeneveld D.C., K. Leung et al.: The 1995 Look-up Table for Critical Heat Fluxes in Tubes. Nuclear Eng. And Design 163 (1996) pp 1-23
    • (1996) Nuclear Eng. and Design , vol.163 , pp. 1-23
    • Groeneveld, D.C.1    Leung, K.2
  • 17
    • 0347632644 scopus 로고
    • The effect of pressure, geometry and the equation of state upon the peak and minimum boiling heat flux
    • Linhard, J.H., Schrock V. E: The Effect of Pressure, Geometry and the Equation of State Upon the Peak and Minimum Boiling heat Flux, J. Heat Transfer, Vol. 85, 1963, pp. 261-272
    • (1963) J. Heat Transfer , vol.85 , pp. 261-272
    • Linhard, J.H.1    Schrock, V.E.2
  • 18
    • 85007655990 scopus 로고
    • On correlating the peak and minimum boiling heat fluxes with pressure and heat configuration
    • Lienhard J. H., Watanabe K.: On Correlating the Peak and Minimum Boiling Heat Fluxes With Pressure and Heat Configuration, J Heat Transfer, Vol. 88, 1966, pp. 94-100
    • (1966) J Heat Transfer , vol.88 , pp. 94-100
    • Lienhard, J.H.1    Watanabe, K.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.