Experimental investigation of the late phase of spent fuel pool accidents

Experimental programmes have been carried out in order to investigate the behaviour of nuclear fuel components in high-temperature air atmosphere, which characterises the main conditions of the late phase of spent fuel pool accidents. The tests provided new data on the oxidation of zirconium cladding in different atmospheres, on the oxidation and release of ruthenium from fuel pellets and on the integral behaviour of fuel bundles. The integral test confirmed that water injection into the spent fuel storage pool is the right measure to terminate a severe accident.

Keywords: spent fuel storage, storage pools, SFSP, zirconium cladding, oxidation kinetics, ruthenium oxidation, ruthenium release, quenching, VVER reactors, spent fuel accidents, nuclear accidents, nuclear power plants, nuclear energy, high temperature air, nuclear safety, fuel bundles, water injection, fuel rods