Scope:
The purpose of the Workshop is to provide a platform for 
presentation of the current state-of-the-art in the field 
of two-phase flows and heat transfer in nuclear fuel 
assemblies. Both experimental and numerical research and 
development will be included. 
- In the numerical part the focus will be on the 
Computational Fluid Dynamics (CFD) approach used for the 
prediction of velocity, turbulence, void fraction and wall 
temperature in the fuel assembly geometry.
- In the experimental part the focus will be on 
measurement methods which provide data suitable for 
validation of the CFD codes, that is measurements of local 
parameters like flow velocity, turbulence, void fraction, 
interfacial area density, etc., using methods like laser-
doppler velocimetry, hot-film/wire anemometry, particle 
image velocimetry, and others, which are suitable for 
complex geometries.

Topics of particular interest:
- Subcooled boiling (including, but not limited to: 
conjugate heat transfer, bubble formation and departure, 
bubble migration and dynamics, interfacial area 
concentration, DNB mechanisms, two-phase law of the wall)
- Annular two-phase flow (including, but not limited 
to: evaporating liquid film, drop entrainment and 
deposition rates, drop size and dynamics in turbulent 
stream)
- Post-dryout (PDO) heat transfer (including, but 
not limited to: vapor-droplet heat transfer, wall vapor 
and wall-droplets heat transfer, influence of obstacles on 
PDO heat transfer)
- Turbulence (including, but not limited to: single-
phase flow turbulence in fuel assemblies, turbulence in 
disperse bubbly flow, turbulence in disperse droplet flow)