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Volumn 3, Issue , 2008, Pages 430-440

Computational fluid dynamics modeling of two-phase flow topologies in a boiling water reactor fuel assembly

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER; COMPUTATIONAL FLUID DYNAMICS MODELING; COMPUTER CODES; ENERGY EXCHANGES; EXPERIMENT ANALYSIS; EXPERIMENTAL OBSERVATION; FLOW REGIMES; FUEL ASSEMBLY; LOCAL TOPOLOGY; OPERATING CONDITION; PHASE SURFACE; SURFACE TOPOLOGY; VAPOR PHASIS;

EID: 70349155497     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE16-48442     Document Type: Conference Paper
Times cited : (44)

References (13)
  • 3
    • 84885304340 scopus 로고    scopus 로고
    • STAR-CD Version 3.20 Methodology Manual, Chapter 13,CD-adapco, UK. 2004.
    • STAR-CD Version 3.20 Methodology Manual, Chapter 13,CD-adapco, UK. 2004.
  • 4
    • 44349101575 scopus 로고    scopus 로고
    • Development and Validation of an Extended Two-Phase CFD Model for the analysis of Boiling Flow in Reactor Fuel Assemblies
    • Nice, France, May 13-18
    • A.Tentner, W.D.Pointer, T.Sofu, D.Weber, "Development and Validation of an Extended Two-Phase CFD Model for the analysis of Boiling Flow in Reactor Fuel Assemblies", Proc. Int. Conf. Advances in Nuclear Power Plants, Nice, France, May 13-18, 2007.
    • (2007) Proc. Int. Conf. Advances in Nuclear Power Plants
    • Tentner, A.1    Pointer, W.D.2    Sofu, T.3    Weber, D.4
  • 6
    • 84885328086 scopus 로고    scopus 로고
    • V.Ustinenko, M.Samigulin, A.Ioilev, S.Lo, A.Tentner, A.Lychagin, A.Razin, V.Girin, Ye.Vanyukov, Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis. OECD/NEA International Workshop on The Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS), Garching, Germany, September 5-7, 2006 (Nuclear Engineering and Design, 2007, in press)
    • V.Ustinenko, M.Samigulin, A.Ioilev, S.Lo, A.Tentner, A.Lychagin, A.Razin, V.Girin, Ye.Vanyukov, "Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis." OECD/NEA International Workshop on The Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS), Garching, Germany, September 5-7, 2006 (Nuclear Engineering and Design, 2007, in press)
  • 11
    • 0036722782 scopus 로고    scopus 로고
    • Flow stricture and bubble characteristics of steam-water two-phase flow in large- diameter pipe
    • K.Yoneda, A.Yasuo, T.Okawa. "Flow stricture and bubble characteristics of steam-water two-phase flow in large- diameter pipe", Nucl. Eng. Des., 2002, Vol.217, p.267-281.
    • (2002) Nucl. Eng. Des , vol.217 , pp. 267-281
    • Yoneda, K.1    Yasuo, A.2    Okawa, T.3
  • 12
    • 0026222455 scopus 로고
    • Analysis of phase distribution in fully developed laminar bubbly two phase flow
    • S.P.Antal., R.T.Lahey, J.E.Flaherty, "Analysis of phase distribution in fully developed laminar bubbly two phase flow", Int. J. Multiphase Flow, 1991. No.7, p.635-652.
    • (1991) Int. J. Multiphase Flow , Issue.7 , pp. 635-652
    • Antal, S.P.1    Lahey, R.T.2    Flaherty, J.E.3
  • 13
    • 0347355290 scopus 로고    scopus 로고
    • What is entrainment in vertical two-phase churn flow?
    • B.J.Azzopardi, E.Wren. "What is entrainment in vertical two-phase churn flow?", Int. J. Multiphase Flow, 2004, Vol.30, p. 89-103.
    • (2004) Int. J. Multiphase Flow , vol.30 , pp. 89-103
    • Azzopardi, B.J.1    Wren, E.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.