Application of Computational Fluid Dynamics in Nuclear Reactor Safety Analysis

Dear Colleagues,

In the last two decades, three-dimensional CFD codes have increasingly been used for the prediction of single-phase and multiphase flows under stationary or unsteady conditions in nuclear reactor applications. The motivation for this is that several important thermohydraulic phenomena cannot be predicted with the required accuracy and spatial resolution using traditional system analysis codes.

However, CFD codes contain empirical models to simulate turbulence, heat transfer, multiphase interaction, and chemical reactions. Such models must be validated before they can be confidently used in nuclear reactor applications. The necessary validation can only be performed by comparing model predictions with reliable data.

This Special Issue will focus on the following areas:

• Single-phase and multi-phase CFD simulations with a focus on validation will be welcome in areas such as single-phase and multi-phase heat transfer, free-surface flows, direct contact condensation, and turbulent mixing. These should relate to nuclear reactor safety issues, such as pressurized thermal shock, critical heat flux, pool heat exchangers, boron dilution, hydrogen distribution in containments, thermal striping and fatigue, etc. The use of systematic error quantification and the application of best practice guidelines (BPGs) are strongly encouraged.
• Experiments providing data suitable for CFD or CMFD validation are also welcome. These should include local measurements using multi-sensor probes, laser-based techniques (LDV, PIV, or LIF), hot-film/wire anemometry, imaging, or other advanced measuring techniques. Papers should include a discussion of measurement uncertainties.

Dr. Thomas Höhne
Guest Editor

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