scholarly journals Numerical modeling of dense flows of two-phase media with shock waves using two-fluid models

2018 ◽  
Author(s):  
P. S. Utkin ◽  
S. V. Fortova
Keyword(s):  
Numerical Modeling ◽  
Shock Waves ◽  
Fluid Models ◽  
Two Phase ◽  
Dense Flows ◽  
Two Fluid

Modeling of Sodium Two-Phase Flow With the TRACE Code

2009 ◽  
Author(s):  
Aurelia Chenu ◽  
Konstantin Mikityuk ◽  
Rakesh Chawla
Keyword(s):  
Single Phase ◽  
Two Phase Flow ◽  
Flow Simulation ◽  
Phase Flow ◽  
Fluid Models ◽  
Code System ◽  
Two Phase ◽  
Liquid Flows ◽  
Transfer Mechanisms ◽  
Two Fluid

In the framework of PSI’s FAST code system, the TRACE thermal-hydraulics code is being extended for representation of sodium two-phase flow. As the currently available version (v.5) is limited to the simulation of only single-phase sodium flow, its applicability range is not enough to study the behavior of a Sodium-cooled Fast Reactor (SFR) during a transient in which boiling is anticipated. The work reported here concerns the extension of the two-fluid models, which are available in TRACE for steam-water, to sodium two-phase flow simulation. The conventional correlations for ordinary gas-liquid flows are used as basis, with optional correlations specific to liquid metal when necessary. A number of new models for representation of the constitutive equations specific to sodium, with a particular emphasis on the interfacial transfer mechanisms, have been implemented and compared with the original closure models. As a first application, the extended TRACE code has been used to model experiments that simulate a loss-of-flow (LOF) accident in a SFR. The comparison of the computed results, with both the experimental data and SIMMER-III code predictions, has enabled validation of the capability of the modified TRACE code to predict sodium boiling onset, flow regimes, dryout, flow reversal, etc. The performed study is a first-of-a-kind application of the TRACE code to two-phase sodium flow. Other integral experiments are planned to be simulated to further develop and validate the two-phase sodium flow methodology.

Numerical modeling of supersonic two-phase jet flows with explicit separation of shock waves

1987 ◽  
Vol 53 (1) ◽  
pp. 763-767
Author(s):  
�. I. Vitkin ◽  
L. T. Perel'man ◽  
Yu. V. Khodyko
Keyword(s):  
Numerical Modeling ◽  
Shock Waves ◽  
Jet Flows ◽  
Two Phase

Flux Scheme: A Method for General Non-Conservative Two-Fluid Systems

2003 ◽  
Author(s):  
Anela Kumbaro
Keyword(s):  
Numerical Modeling ◽  
Source Term ◽  
Term Treatment ◽  
Two Phase ◽  
Advection Scheme ◽  
Fluid Systems ◽  
Boundary States ◽  
Upwind Discretization ◽  
Improved Accuracy ◽  
Two Fluid

This paper is concerned with numerical modeling issues arising when using a flux scheme for the approximation of two-phase flows. The paper puts emphasis on a general treatment of boundary conditions and reports on the interaction between an upwind discretization of the source terms and the boundary states. An upwind source term treatment consistent with the advection scheme results on an improved accuracy. Numerical results are provided to illustrate the method.

First and Second-Order Accurate Schemes for Two-Fluid Models

1998 ◽  
Vol 120 (2) ◽  
pp. 363-368 ◽  
Author(s):  
Iztok Tiselj ◽  
Stojan Petelin
Keyword(s):  
Two Phase Flow ◽  
Second Order ◽  
Minor Role ◽  
Phase Flow ◽  
Fluid Models ◽  
Two Phase ◽  
Large Computer ◽  
Wide Range ◽  
Fast Transients ◽  
Two Fluid

The six-equation two-fluid model of two-phase flow taken from the RELAP5/MOD3 computer code has been used to simulate three simple transients: a two-phase shock tube problem, the Edwards Pipe experiment, and water hammer due to rapid valve closure. These transients can be characterized as fast transients, since their characteristic time-scales are determined by the sonic velocity. First and second-order accurate numerical methods have been applied both based on the well-known, Godunov-type numerical schemes. Regarding the uncertainty of the two-fluid models in today’s large computer codes for the nuclear thermal-hydraulics, use of second-order schemes is not always justified. While this paper shows the obvious advantage of second-order schemes in the area of fast transients, first-order accurate schemes may still be sufficient for a wide range of two-phase flow transients where the convection terms play a minor role compared to the source terms.

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