Theoretical investigations and industrial scale tests for proving the function and efficiency of reactor safety elements. Final report

For new reactor designs, the integrity of the containment must be ensured even in the case of severe accidents, like core-melt accidents, in order to avoid emergency measures outside the reactor plant. With view to this goal the German Interest Group AGIK performed theoretical investigations and industrial scale tests for proving the function and efficiency of innovative reactor safety elements. Within the COMAS project representative experiments on the spreading behaviour of prototypic corium on different substratum materials were carried out accompanied by conceptual work on novel core catcher designs (INKA). Inherent safety against spontaneous failure of the Prestressed Cast Iron Pressure Vessel with special view on its suitability for LWR conditions was investigated in the VGD project. The PACOS work showed the feasibility of passive cooling elements inside the containment. (orig.)