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On numerical modelling of multiphase flows and heat transfer in nuclear fuel assemblies

Autorzy
Identyfikatory
Warianty tytułu
Konferencja
8 Konferencja. Problemy Badawcze Energetyki Cieplnej. PBEC/sympozjum (VIII ; 11-14.12.2007 ; Warszawa, Polska)
Języki publikacji
EN
Abstrakty
EN
This paper presents the current methods used for the numerical modelling of multiphase flows and heat transfer in nuclear fuel assemblies. Special attention is devoted to the state-of-the-art Computational Fluid Dynamics (CFD) models and their application to prediction of velocity, temperature, pressure and turbulence intensity distributions in fuel assemblies with spacer grids. Such numerical methods require detailed experimental data for proper validation. In case of Boiling Water Reactor (BWR) applications one has to include the evaluation of phase distributions, since it affects the local moderator density, and thus the local reactivity in the fuel bundle. From a designer point of view the most interesting aspects include the evaluation of the influence of design details on the thermal and the nuclear performance of fuel assemblies.
Rocznik
Strony
19--29
Opis fizyczny
Bibliogr. 12 poz., rys., wykr.
Twórcy
autor
  • Royal Institute of Technology, Stockholm, Sweden
Bibliografia
  • H. Anglart, O. Nylund, N. Kurul, M.Z. Podowski, "CFD prediction of flow and phase distribution in fuel assemblies with spacers," Nucl. Eng. Des. Vol. 177, 212 (1997).
  • H. Anglart, Mechanistic Modeling of Slug Flows, PhD Dissertation, Rensselaer Polytechnic Institute, Troy, NY, USA, (2001).
  • Antal, S.P., Lahey, R.T. Jr. and Flaherty, J.E., "Analysis of phase distribution in fully developed laminar bubbly two-phase flow," Int. J. Multiphase Flow, 17, pp. 635-652, (1991).
  • Bosio, J. and Imset, O.R., "Three Dimensional Two-Phase Flow Distribution in a 7-Rod Bundle - Part I. Summary Results. Runs 30-46, 48-53, 57-58," Report SD-150/SDS-83 (1974).
  • A.H. Govan, G.F. Hewitt, D.G. Owen, T.R. Bott, An improved CHF modelling code, 2nd U.K. National Heat Transfer Conf., Glasgow (1988).
  • M. Ishii, Thermo-Fluid Dynamic Theory of Two-Phase Flow, Eyrolles (1975).
  • R.T. Lahey Jr., B.S. Shiralkar and D.W. Radcliffe, "Mass flux and enthalpy distribution in a rod bundle for single- and two-phase flow conditions," J. Heat Transfer, 43, 197 (1971).
  • Lahey, R.T. Jr., Lopez de Bertodano, M. and Jones, O.C. Jr., "Phase distribution in complex geometry conduits," Nucl. Eng. Des. 141, 177-201, (1993).
  • F.R. Menter, M. Kuntz and R. Bender, "A Scale-Adaptive Simulation Model for Turbulent Flow Predictins," AIAA-Paper 2003-0767, (2003).
  • A. Tomiyama, H. Tarnai, I. Zun and S. Hosokama, "Transverse migration of single bubbles in simple shear flow," Chem. Eng. Sci., 57, 1849-1858, (2002).
  • Windecker, H. Anglart, "Phase distribution in a BWR fuel assembly and evaluation of a multidimensional multifield model," Nuclear Technology, Vol. 134, 49 (2001).
  • G. Yadigaroglu and A. Maganas, "Equilibrium quality and mass flux distributions in an adiabatic three-subchannel test section," Nuclear Technology, 112, 359-372 (1995).
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-PWA3-0046-0002
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