Within the Reactor Pressure Vessel (RPV) plant life time project, Electricite´ de France (EDF) must carry out studies showing the RPV integrity during severe loading conditions as the Small Break Loss Of Coolant Accidents (SBLOCA) scenarios. A recent thermal-hydraulic SBCLOCA scenario study, concerning a certain RPV geometry, showed two-phase-flow conditions appears in the cold leg. The single phase flow CFD tools, usually used in these cases, are unsuitable to carry out such studies. That is the reason why EDF is developing a new CFD code (called Neptune_Code) implementing two-phase flow models. In order to improve the physical phenomena knowledge and the existent experimental data for Neptune_Code development, EDF carried out an experimental study concerning the stratified flow (salt water) and free surface (water air) behavior during a representative ECC scenario with partial uncovered cold leg. This paper focuses mainly on the experimental method and the measurements obtained in three tests showing the effects of the uncovered cold leg level on the stratified flow and the free surface behavior.
Skip Nav Destination
ASME 2005 Fluids Engineering Division Summer Meeting
June 19–23, 2005
Houston, Texas, USA
Conference Sponsors:
- Fluids Engineering Division
ISBN:
0-7918-4199-5
PROCEEDINGS PAPER
Stratified Flow and Free Surface of an Uncovered Reactor Pressure Vessel Cold Leg: Water-Air Experimental Results
Thierry Bichet,
Thierry Bichet
Electricite´ de France, Chatou Cedex, France
Search for other works by this author on:
Alain Martin,
Alain Martin
Electricite´ de France, Chatou Cedex, France
Search for other works by this author on:
Fre´de´ric Beaud
Fre´de´ric Beaud
Electricite´ de France, Villeurbanne Cedex, France
Search for other works by this author on:
Thierry Bichet
Electricite´ de France, Chatou Cedex, France
Alain Martin
Electricite´ de France, Chatou Cedex, France
Fre´de´ric Beaud
Electricite´ de France, Villeurbanne Cedex, France
Paper No:
FEDSM2005-77121, pp. 389-396; 8 pages
Published Online:
October 13, 2008
Citation
Bichet, T, Martin, A, & Beaud, F. "Stratified Flow and Free Surface of an Uncovered Reactor Pressure Vessel Cold Leg: Water-Air Experimental Results." Proceedings of the ASME 2005 Fluids Engineering Division Summer Meeting. Volume 2: Fora. Houston, Texas, USA. June 19–23, 2005. pp. 389-396. ASME. https://doi.org/10.1115/FEDSM2005-77121
Download citation file:
5
Views
Related Proceedings Papers
Related Articles
DSG Under Two-Phase and Stratified Flow in a Steel Receiver of a Parabolic Trough Collector
J. Sol. Energy Eng (May,2002)
Modeling of the Onset of Gas Entrainment From a Stratified Two-Phase Region Through Branches on a Curved Surface
J. Fluids Eng (July,2006)
Studies of Wavy Stratified and Stratified/Atomization Gas-Liquid Flow
J. Energy Resour. Technol (June,2003)
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Source Term Assessments in PSA Level 2 for the Outage Period (PSAM-0168)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
NRC Safety Research Priorities for Reactor Vessel Embrittlement, Annealing, and Surveillance Dosimetry
Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study