Two experiments have been performed in the VULCANO facility in which prototypic corium has been spread over concrete. In the VE-U7 test, a mixture representative of what can be expected at the opening of EPR reactor-pit gate has been spread on siliceous concrete and on a reference channel in inert refractory ceramic. The spreading progression was not much affected by the presence of concrete and sparging gases. In the VE-U8 test, a UO2-ZrO2 mixture, prototypic of in-vessel corium, has been spread over a lime-siliceous concrete. Although residual power was not simulated in this experiment, up to 2 cm of concrete have been eroded during the test. Results in terms of spreading behaviour, effects of gases, concrete erosion and thermal attack are presented and discussed.
Skip Nav Destination
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Corium Spreading Over Concrete: The Vulcano VE-U7 and VE-U8 Tests
Christophe Journeau,
Christophe Journeau
CEA Cadarache, St Paul lez Durance, France
Search for other works by this author on:
Eric Boccaccio,
Eric Boccaccio
CEA Cadarache, St Paul lez Durance, France
Search for other works by this author on:
Pascal Fouquart,
Pascal Fouquart
CEA Cadarache, St Paul lez Durance, France
Search for other works by this author on:
Claude Je´gou,
Claude Je´gou
CEA Cadarache, St Paul lez Durance, France
Search for other works by this author on:
Pascal Piluso
Pascal Piluso
CEA Cadarache, St Paul lez Durance, France
Search for other works by this author on:
Christophe Journeau
CEA Cadarache, St Paul lez Durance, France
Eric Boccaccio
CEA Cadarache, St Paul lez Durance, France
Pascal Fouquart
CEA Cadarache, St Paul lez Durance, France
Claude Je´gou
CEA Cadarache, St Paul lez Durance, France
Pascal Piluso
CEA Cadarache, St Paul lez Durance, France
Paper No:
ICONE10-22278, pp. 413-421; 9 pages
Published Online:
March 4, 2009
Citation
Journeau, C, Boccaccio, E, Fouquart, P, Je´gou, C, & Piluso, P. "Corium Spreading Over Concrete: The Vulcano VE-U7 and VE-U8 Tests." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 413-421. ASME. https://doi.org/10.1115/ICONE10-22278
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
Cavitation Characteristics of Gate Valves and Globe Valves Used as Flow Regulators Under Heads Up to About 125 Feet
Trans. ASME (August,1957)
Determining Effective Thickness of Cylinders in Pressure Equipment With Significant Thickness Variations for Fitness for Service Assessments
J. Pressure Vessel Technol (May,2007)
An Alternate Method to API RP 14E for Predicting Solids Erosion in Multiphase Flow
J. Energy Resour. Technol (September,2000)
Related Chapters
Two Types of Priority and Gates and Their Markov Analyses (PSAM-0123)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Surface Analysis and Tools
Tribology of Mechanical Systems: A Guide to Present and Future Technologies
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Fourth Edition