Two-Phase Flow Simulation in Heat Pipe

2007 ◽  
Author(s):  
Bang-Ji Wang ◽  
C. R. Chen ◽  
J. R. Tsai
Keyword(s):  
Heat Pipe ◽  
Two Phase Flow ◽  
Flow Simulation ◽  
Phase Flow ◽  
Two Phase

Flow prediction of a heat pipe using gas-liquid two-phase flow simulation

2019 ◽  
Vol 2019.32 (0) ◽  
pp. 270
Author(s):  
Kaoru TAKEMURA ◽  
Yuki KAWAMOTO ◽  
Hiroaki NAGASHIMA ◽  
Shun TAKAHASHI ◽  
Manami KONDO ◽  
...  
Keyword(s):  
Heat Pipe ◽  
Two Phase Flow ◽  
Flow Simulation ◽  
Phase Flow ◽  
Two Phase ◽  
Flow Prediction

Two-phase flow simulation of reactor clarifiers

2008 ◽  
Vol 39 (3) ◽  
pp. 275-280 ◽  
Author(s):  
Wen-Jie Yang ◽  
Chu-Chuao Wang ◽  
Ren-Yi Hsu ◽  
Rome-Ming Wu
Keyword(s):  
Two Phase Flow ◽  
Flow Simulation ◽  
Phase Flow ◽  
Two Phase

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.

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