[en] A satisfactory fast reactor safety analysis requires a comprehensive experimental and theoretical research program. The structural integrity of the reactor core in case of any local failure has to be demonstrated. Such local events may be due to random pin failure which is very likely. As a consequence contact between molten fuel and coolant may occur. The existing uncertainties in the understanding of the physical mechanisms observed during this molten fuel-coolant-interaction (MFCI) emphasize the importance of the comprehensiveness of this research program. This paper describes the effort done at GfK Karlsruhe in cooperation with UKAEA and EURATOM to predict the core deformations caused by local failure within an LMFBR core. These activities try to cover all important questions currently discussed in the analysis of possible core damage. It may be concluded that the reactor can be scrammed in time under pessimistic-realistic pressure transients and that the deformations do not exceed tolerable limits. The computer methods are general enough as to allow for different core designs with varying geometries, material properties, etc. (Auth.)