4. DESCRIPTION OF TEST
Severe core damage experiment with quenching, of a full length simulated fuel bundle, heated with internal tungsten heaters. Investigations of the material relocation dynamics, quench phenomena and hydrogen generation.
The out-of-pile experiment CORA-13 was executed in November 1990.
In the experiments the decay heat is simulated by electrical heating. Great emphasis is given to the fact that the test bundles contain all
materials used in light-water reactor fuel elements, to investigate the different material interactions. Pellets, cladding, grid spacers,
absorber rods and the pertinent guide tubes are typical of those of commercial LWRs with respect to their compositions and radial