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The KORSAR computer code modeling of annular-dispersed two-phase flow hydrodynamics

Abstract

The paper presents the description of the KORSAR computer code model for annular-dispersed two-phase flow hydrodynamics. The KORSAR thermal-hydraulic computer code has been developed at NITI (Russia) since 1996. It is designed to simulate transient and accident conditions in VVER type reactors. the modified system of two-fluid model conservation equations is realized in the KORSAR computer code for the annular-dispersed flow that enables to differentiate liquid phase component kinematics. The modified system is distinguished from the classical one by two important features: convective terms in the liquid phase conservation equations of mass and energy are broken up into two constituents representing liquid mass and energy transfer, respectively, by the film and droplets along the channel length; conservation equations of momentum are used for liquid film and gas-droplet core. The vector unknown variables of the modified system are film and gas-droplet core velocities. This fact allows three-fluid correlations to be employed for evaluating the liquid film and wall, and liquid film and gas-droplet core shear stresses. The adequacy of this model is defined to a great extent by the accuracy of empirical correlations for the droplets fraction in annular-dispersed two-phase flow. The paper contains description of the developed correlations for the  More>>
Authors:
Yudov, Y V [1] 
  1. Alexandrov Research Inst. of Technology, Sosnovy Bor (Russian Federation)
Publication Date:
Jul 01, 2003
Product Type:
Conference
Resource Relation:
Conference: ICONE-11: 11. international conference on nuclear engineering, Tokyo (Japan), 20-23 Apr 2003; Other Information: This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Track No. 07, Session 7-28, ICONE-36150; PBD: 2003; Related Information: In: ICONE-11: Proceedings of the 11th international conference on nuclear engineering, [3610] pages.
Subject:
42 ENGINEERING; AIR; DISPERSIONS; DROPLETS; ENTRAINMENT; FILMS; FLOW MODELS; GAS FLOW; HYDRAULICS; K CODES; LIQUID FLOW; PIPES; STEAM; TWO-PHASE FLOW; WATER; WWER TYPE REACTORS
OSTI ID:
20470121
Research Organizations:
Japan Society of Mechanical Engineers, Tokyo (Japan); American Society of Mechanical Engineers, New York (United States)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
TRN: JP0401597045203
Availability:
INIS
Submitting Site:
INIS
Size:
8 pages
Announcement Date:
Jun 21, 2004

Citation Formats

Yudov, Y V. The KORSAR computer code modeling of annular-dispersed two-phase flow hydrodynamics. Japan: N. p., 2003. Web.
Yudov, Y V. The KORSAR computer code modeling of annular-dispersed two-phase flow hydrodynamics. Japan.
Yudov, Y V. 2003. "The KORSAR computer code modeling of annular-dispersed two-phase flow hydrodynamics." Japan.
@misc{etde_20470121,
title = {The KORSAR computer code modeling of annular-dispersed two-phase flow hydrodynamics}
author = {Yudov, Y V}
abstractNote = {The paper presents the description of the KORSAR computer code model for annular-dispersed two-phase flow hydrodynamics. The KORSAR thermal-hydraulic computer code has been developed at NITI (Russia) since 1996. It is designed to simulate transient and accident conditions in VVER type reactors. the modified system of two-fluid model conservation equations is realized in the KORSAR computer code for the annular-dispersed flow that enables to differentiate liquid phase component kinematics. The modified system is distinguished from the classical one by two important features: convective terms in the liquid phase conservation equations of mass and energy are broken up into two constituents representing liquid mass and energy transfer, respectively, by the film and droplets along the channel length; conservation equations of momentum are used for liquid film and gas-droplet core. The vector unknown variables of the modified system are film and gas-droplet core velocities. This fact allows three-fluid correlations to be employed for evaluating the liquid film and wall, and liquid film and gas-droplet core shear stresses. The adequacy of this model is defined to a great extent by the accuracy of empirical correlations for the droplets fraction in annular-dispersed two-phase flow. The paper contains description of the developed correlations for the droplets fraction in pipes under conditions of dynamic flow equilibrium. The data base of these correlations includes 885 experimental points. Data were obtained using an air-water and saturated steam-water flows in the wide range of parameters: pipe diameter (8-31.8 mm), pressure (0.2-1.6 MPa), mixture mass flux (140-4000 kg/m{sup 2}s), gas quality (0.08-0.98). Confirmation of the present annular-dispersed flow model was performed in comparison with the experimental data in adiabatic tubes under low pressure air-water and high pressure steam-water conditions. (author)}
place = {Japan}
year = {2003}
month = {Jul}
}