In the event of a highly unlikely core melt-down accident, scenarios with reactor pressure vessel failure and corium ( a mixture of UO2, ZrO2, Zr, Fe and fission products) relocation into the reactor cavity cannot be excluded. In this context large R&D efforts are directed towards ex-vessel corium behaviour, in particular on long-term corium retention and coolability within the containment. The two generic processes spreading of the corium under various initial and boundary conditions and cooling of the melt by direct water contact are the main issues addressed by the Corium Spreading and Coolability (CSC) Project. ENEA is a partner of CSC Project and contributes to the development and qualification of the THEMA Code in a very near cooperation with CEA and EdF. THEMA code is available through the CEA-ENEA cooperation agreement on future reactors. Hereunder there is a concise outline of ENEA performed work in the framework of CSC Project.
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