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Volumn , Issue , 2004, Pages 973-984

CHF enhancement by vessel coating for external reactor vessel cooling

Author keywords

[No Author keywords available]

Indexed keywords

STEADY STATE BOILING; SUBSCALE BOUNDARY LAYER BOILING (SBLB); VESSEL COATINGS; VESSEL COOLING;

EID: 14844322933     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (4)

References (21)
  • 1
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    • In-vessel retention strategy for high power reactors
    • INEEL/EXT-020-1291
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    • Rempe, J.L.1    Suh, K.Y.2    Cheung, F.B.3    Kim, S.B.4
  • 2
    • 14844296844 scopus 로고    scopus 로고
    • Limiting factors for external reactor vessel cooling
    • NURETH-10
    • Cheung, F. B., "Limiting Factors for External Reactor Vessel Cooling," Keynote Lecture KL-09, NURETH-10, (2003).
    • (2003) Keynote Lecture , vol.KL-09
    • Cheung, F.B.1
  • 3
    • 1842811564 scopus 로고
    • Observation of the boiling process from a large downward facing torispherical surface
    • 3a. Chu, T. Y. et al., "Observation of the Boiling Process from a Large Downward Facing Torispherical Surface," Proceedings National Heat Transfer Conference, (1995).
    • (1995) Proceedings National Heat Transfer Conference
    • Chu, T.Y.1
  • 4
    • 0031163206 scopus 로고    scopus 로고
    • Ex-vessel boiling experiments: Laboratory and reactor-scale testing of the flooded cavity concept for in-vessel core retention
    • 3b. Chu, T. Y. et al., "Ex-vessel boiling Experiments: Laboratory and Reactor-Scale Testing of the Flooded Cavity Concept for In-Vessel Core Retention," Nuclear Engineering and Design, Vol. 169, pp. 77-88, (1997).
    • (1997) Nuclear Engineering and Design , vol.169 , pp. 77-88
    • Chu, T.Y.1
  • 6
    • 0031165348 scopus 로고    scopus 로고
    • The coolability limits of a reactor pressure vessel lower head
    • 4b. Theofanous, T. G. and Syri, S., "The Coolability Limits of a Reactor Pressure Vessel Lower Head," Nuclear Engineering and Design, Vol. 169, pp. 59-76, (1997).
    • (1997) Nuclear Engineering and Design , vol.169 , pp. 59-76
    • Theofanous, T.G.1    Syri, S.2
  • 7
    • 85067323200 scopus 로고    scopus 로고
    • The boiling crisis phenomenon - Part 1. nucleation and nucleate boiling heat transfer; part 2 - Dryout dynamics and burnout
    • 4c. Theofanous, T. G. et al., "The Boiling Crisis Phenomenon - Part 1. Nucleation and Nucleate Boiling Heat Transfer; Part 2 - Dryout Dynamics and Burnout," J. Experimental Thermal and Fluid Science, Vol. 26, pp. 775-810, (2002).
    • (2002) J. Experimental Thermal and Fluid Science , vol.26 , pp. 775-810
    • Theofanous, T.G.1
  • 9
    • 0031164218 scopus 로고    scopus 로고
    • SULTAN test facility for large-scale vessel coolability in natural convection at low pressure
    • 5a. Rouge, S., "SULTAN Test Facility for Large-Scale Vessel Coolability in Natural Convection at Low Pressure," Nuclear Engineering and Design, Vol. 169, pp. 185-195, (1997).
    • (1997) Nuclear Engineering and Design , vol.169 , pp. 185-195
    • Rouge, S.1
  • 10
    • 84855853542 scopus 로고    scopus 로고
    • Reactor vessel external cooling for corium retention SULTAN experimental program and modeling with CATHARE code
    • NEA/CSNI/R (98) 18, Garching, Germany
    • 5b. Rouge, S., Dor, I. and Geffraye, G, "Reactor Vessel External Cooling for Corium Retention SULTAN Experimental Program and Modeling with CATHARE Code," Workshop Proceedings on In-Vessel Core Debris Retention and Coolability, NEA/CSNI/R (98) 18, Garching, Germany, (1999).
    • (1999) Workshop Proceedings on In-vessel Core Debris Retention and Coolability
    • Rouge, S.1    Dor, I.2    Geffraye, G.3
  • 13
    • 14844287778 scopus 로고    scopus 로고
    • Critical heat flux experiments to support in-vessel retention feasibility study for an evolutionary advanced light water reactor design
    • 6c. Cheung, F. B. and Liu, Y. C., "Critical Heat Flux Experiments to Support In-Vessel Retention Feasibility Study for an Evolutionary Advanced Light Water Reactor Design," EPRI Technical Report-1003101, (2001).
    • (2001) EPRI Technical Report-1003101
    • Cheung, F.B.1    Liu, Y.C.2
  • 19
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    • A hydrodynamic critical heat flux model for saturated pool boiling on a downward facing curved heating surface
    • Cheung, F.B. and Haddad, K., "A Hydrodynamic Critical Heat Flux Model for Saturated Pool Boiling on a Downward Facing Curved Heating Surface," International journal of Heat and Mass Transfer, Vol. 40, No. 6, pp. 1291-1302, (1997).
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    • Cheung, F.B.1    Haddad, K.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.