Description of the PLINIUS prototypic corium experimental platform and the safety issues relative to the operation of the platform

In the hypothetical case of a light water reactor severe accident, the reactor core could melt and form with structural materials and eventually concrete, aggressive and high-temperature mixtures called corium. The characterisation of these melts and their behaviour is a key issue to the improvement of nuclear reactor safety. This is the reason underlying the experiments carried out on the PLINIUS (PLatform for Improvements in Nuclear Industry and Utility Safety) prototypic experimental platform. In the first part of this paper, the four facilities of the PLINIUS platform namely: VULCANO, COLIMA, VITI and KROTOS will be described. The second part of this paper will be based on the management of the radiological risks arising from the use of depleted uranium dioxide in the corium melts of the platform. (authors)