Computational Fluid Dynamics for Gas-Liquid Flows
Call for Papers
Computational Fluid Dynamics (CFD) codes are widely used in industrial applications for single-phase flows (e.g., in the automotive or aircraft industries). On the other hand, the application of CFD for multiphase systems is not mature. For safety analyses related to reliable nuclear light water reactors, simulations for different scenarios including two-phase flow situations are required. Examples are the prevention from departure from nucleate boiling (DNB) which is related to critical heat flux (CHF) or the pressurized thermal shock (PTS) problem which has to be considered in connection with some hypothetical loss of coolant accident (LOCA) scenarios and may also lead to two-phase flow situations in the cold leg and in the downcomer.
The problems in modeling of such gas-liquid flows arise from the fact that the mass, momentum, and heat transfer between the phases is strongly coupled with the complex interfacial structure. The currently applied system codes based on correlations are valid for special geometries, scales, and flow patterns. This limits the transferability of small-scale experimental findings to real plant scales. On the other hand, CFD-type models should depend only on local flow parameters and are for this reason much more flexible regarding geometry and scale. The increased computer power now permits CFD simulations for multiphase flows and many investigations have been done in the recent years.
In view of the above, it has been decided to bring out a special issue on “Computational Fluid Dynamics for Gas-Liquid Flows”. Topics of interest include, but are not limited to:
- Qualification, validation, and application of CFD codes for gas-liquid flows relevant in nuclear reactor systems, including:
- Status and limits of presently available CFD codes
- Special requirements on CFD codes for nuclear applications
- Closure models
- New modeling strategies
- Code development
- Uncertainty analysis
- Simulations for two-phase flow configurations
- Special flow situations relevant in nuclear installations: PTS, CHF, Dryout
- Experimental database
- Uncertainty analysis
- Application of best practice guidelines (BPG)
Papers are invited from experts working in areas mentioned above for publication in the special issue.
Authors should follow the Science and Technology of Nuclear Installations manuscript format described at the journal site http://www.hindawi.com/journals/stni/. Prospective authors should submit an electronic copy of their complete manuscript through the journal Manuscript Tracking System at http://mts.hindawi.com/, according to the following timetable:
| Manuscript Due | April 1, 2008 |
| First Round of Reviews | July 1, 2008 |
| Publication Date | October 1, 2008 |
Guest Editors
Dirk Lucas, Institute of Safety Research, Forschungszentrum Dresden-Rossendorf e.V., P.O Box 510 119, 01314 Dresden, Germany
Yassin A. Hassan, Department of Nuclear Engineering, 129 Zachry Engineering Center, Texas A&M University, MS 3133, College Station, TX 77843-3133, USA
Fabio Moretti, DIMNP, Universita di Pisa, Via Diotisalvi 2, 56100 Pisa, Italy
Iztok Tiselj, Reactor Engineering Division, Institute “Jozef Stefan”, Jamova 39, 1000 Ljubljana, Slovenia
