The melt droplets crust formation modelling, which is used in current FCI (fuel coolant interaction) codes, is rather basic. In the paper the development of the melt droplet heat transfer model, which enables the treatment of the material properties influence on the steam explosion is presented. The model is enough complex to correctly predict the crust development during the melt droplets cooling in the premixing phase. At the same time the model is enough simple that it can be practically implemented into FCI codes and is thus being an optimal model for FCI applications. Fragmentation criteria are derived in order to take into account the influence of the formed crust on the steam explosion process. The derived criteria are based on experimental results and the thin plate approximation. To enable the use of the model and the fragmentation criteria in FCI codes with Eulerian formulation, adequate transport equations for model parameters are given.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Modelling of Material Properties Influence in Fuel-Coolant Interaction Codes
Mitja Ursˇicˇ,
Mitja Ursˇicˇ
Jozˇef Stefan Institute, Ljubljana, Slovenia
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Matjazˇ Leskovar,
Matjazˇ Leskovar
Jozˇef Stefan Institute, Ljubljana, Slovenia
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Ivo Kljenak,
Ivo Kljenak
Jozˇef Stefan Institute, Ljubljana, Slovenia
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Borut Mavko
Borut Mavko
Jozˇef Stefan Institute, Ljubljana, Slovenia
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Mitja Ursˇicˇ
Jozˇef Stefan Institute, Ljubljana, Slovenia
Matjazˇ Leskovar
Jozˇef Stefan Institute, Ljubljana, Slovenia
Ivo Kljenak
Jozˇef Stefan Institute, Ljubljana, Slovenia
Borut Mavko
Jozˇef Stefan Institute, Ljubljana, Slovenia
Paper No:
ICONE17-75039, pp. 313-321; 9 pages
Published Online:
February 25, 2010
Citation
Ursˇicˇ, M, Leskovar, M, Kljenak, I, & Mavko, B. "Modelling of Material Properties Influence in Fuel-Coolant Interaction Codes." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 313-321. ASME. https://doi.org/10.1115/ICONE17-75039
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