BETA experiments on melt-concrete interaction: the role of zirconium and the potential sump water contact during core melt-down accidents

• Published in: Nuclear engineering and design Vol. 154; no. 1; pp. 61 - 68
• Main Authors: Alsmeyer, H., Adelhelm, C., Dillmann, H.-G., Foit, J.J., Heinle, M., Ratajczak, W., Schneider, H., Schumacher, G., Skokan, A., Stiefel, S., Tromm, W.
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.02.1995; Elsevier
• Subjects: Applied sciences; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Installations for energy generation and conversion: thermal and electrical energy; Water; Zirconium; Melting; Simulation; Gas release; Concrete; Oxidation; Experimental study; Computer aided design; Reactor core; Erosion; Nuclear reactor

In the BETA test facility of Kernforschungszentrum Karlsruhe, prototypical core melts can be simulated in concrete structures sufficient in size to allow a computer-code-assisted extrapolation to be made to the reactor geometry. Three experiments have been carried out to investigate special aspects...