Computational Fluid Dynamics modeling of two phase flow in a boiling water reactor fuel assembly

Printer-friendly versionPDF version

Two-phase flow phenomena inside a BWR fuel bundle include coolant phase changes and multiple flow regimes which directly influence the coolant interaction with fuel assembly and, ultimately, the reactor performance. The CFD-BWR code is being developed as a specialized module built on the foundation of the commercial CFD code STAR-CD which provides general two-phase flow modeling capabilities. New models describing two-phase flow and heat transfer phenomena specific for BWRs are developed and implemented in the CFD-BWR module. A set of experiments focused on two-phase flow and phase-change phenomena has been identified for the validation of the CFD-BWR code and results of several experiment analyses are presented. The close agreement between the computed results, the measured data and the correlation results provides confidence in the accuracy of the models.

Author Company: 
Nuclear Engineering Division Argonne National Laboratory, CD-adapco,Institute of Theoretical and Mathematical Physics Russian Federal Nuclear Center (VNIIEF)
Author Name: 
Adrian Tentner
Simon Lo
Andrey Ioilev
Maskhud Samigulin
Vasily Ustinenko
Industries: 
Products: 
Conference: