Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

The Model of Boiling Water Flow in the VVER-1000 Steam Generator

Document Type : Scientific Note

Authors

A Safavi
M. R Abdi
M Talebi
M. H Esteki
Abstract
2D and 3D numerical models of a steam generator for VVER-1000 type nuclear reactors used in the nuclear industry is presented. For the calculation Euler-Euler approach is applied for modeling the boiling heat transfer, boiling and recondensation. In the 3D model, the secondary side of the steam generator is simulated by the porosity model presented earlier by Stosic and Stevanovic. In the Porosity model, the tubes of the primary circuit are not described in detail, but they are modeled as sources of enthalpy and pressure loss. The physical models were implemented by user-defined programs in ANSYS-CFX12.1 computational fluid dynamics software. The results of the 3D thermal-hydraulic modeling of the steam generator in the Russian type VVER-1000 NPP for the full load operating condition are presented. The results clearly illustrate a void fraction distribution. Moreover, the role of submerged perforated sheet is investigated. The results are compared with a published paper in 1999 by Stevanovic. There is a good agreement between the introduced calculation. In addition, in the 2D model, the superficial velocity of water vapor is calculated as well.
 

Highlights

  1. V. Stavanovic, M. Studovic, 3D modelling as a support to thermal-hydraulic safety analyses with standard codes, Faculty of Mechanical Engineering, University of Belgrade (1999).
  2. G. Kristof, K. Szabo, T. Regert, Modeling of boiling water flow in the horizontal steam generator of the paks nuclear power plant, CFD. HU Ltd, Budapest, Hungry (2008).

 3.   T. Pättikangas, J. Niemi, V. Hovi, SGEN summary report: CFD modeling of horizontal steam generators (2010).

 4.   Y. M. Ferng, H. J. Chang, CFD investigation the impacts of changing operating conditions on the thermal–hydraulic characteristics in a steam generator, Nuclear Science and Technology Development Center, National Tsing Hua University (2007).

 5.   Z. V. Stosic and Stevanovic, V.D. advanced three-dimensional two-fluid porous media method for transient two-phase flow thermal-hydraulics in complex geometries. Numerical Heat Transfer, Part B, 41 (2002) 263–289.

  1. C. Vallee, T. Honne, H. M. Prasser, T. Suhnel, Experimental investigation and CFD simulation of horizontal stratified two-phase flow phenomena, Forschungszentrum Dresden-Rossendorf e.V., Dresden, Germany (2007).

 7.   N. G. Rassohin, Nuclear Power Plant Steam Generators, Atomizat, Moskva, 106 (1980).

 8.   A. G. Ageev, Elektricheskie stancii, 6 (1987).

 9.   I. Karppinen, Third Int, Sem. Horizontal Steam Generators-Lappeenranta (1994).

 10.V. I. Melikhov, O. I. Melikhov, B. I. Nigmatulin, Proc. Int. Conf. Two-phase flow modelling and experimentation, 1 (1995).

  1. V. Stavanovic, M. Studovic, 3D modelling as a support to thermal-hydraulic safety analyses with standard codes, Faculty of Mechanical Engineering, University of Belgrade (1999).
  2. G. Kristof, K. Szabo, T. Regert, Modeling of boiling water flow in the horizontal steam generator of the paks nuclear power plant, CFD. HU Ltd, Budapest, Hungry (2008).

 3.   T. Pättikangas, J. Niemi, V. Hovi, SGEN summary report: CFD modeling of horizontal steam generators (2010).

 4.   Y. M. Ferng, H. J. Chang, CFD investigation the impacts of changing operating conditions on the thermal–hydraulic characteristics in a steam generator, Nuclear Science and Technology Development Center, National Tsing Hua University (2007).

 5.   Z. V. Stosic and Stevanovic, V.D. advanced three-dimensional two-fluid porous media method for transient two-phase flow thermal-hydraulics in complex geometries. Numerical Heat Transfer, Part B, 41 (2002) 263–289.

  1. C. Vallee, T. Honne, H. M. Prasser, T. Suhnel, Experimental investigation and CFD simulation of horizontal stratified two-phase flow phenomena, Forschungszentrum Dresden-Rossendorf e.V., Dresden, Germany (2007).

 7.   N. G. Rassohin, Nuclear Power Plant Steam Generators, Atomizat, Moskva, 106 (1980).

 8.   A. G. Ageev, Elektricheskie stancii, 6 (1987).

 9.   I. Karppinen, Third Int, Sem. Horizontal Steam Generators-Lappeenranta (1994).

 10.V. I. Melikhov, O. I. Melikhov, B. I. Nigmatulin, Proc. Int. Conf. Two-phase flow modelling and experimentation, 1 (1995).

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