[en] The fuel coolant interaction (FCI) experiment CORECT II is very interesting because it used actual reactor materials (i.e. uranium dioxide and sodium), it produced a relatively high amount of work, and is a well characterized experiment. In this paper an attempt to interpret this experiment on the basis of model calculations performed with the MURTI code is described. These calculations give information on a possible sequence of events during the experiment, they make the importance of various experimental conditions evident, and they provide guidance in applying the experimental information to situations with different boundary conditions. This investigation is in fact a first step towards an experimental verification of the code. The FCI model allows the inclusion of many effects that may be necessary to be accounted for such as vapour blanketing, continuous fragmentation, inhomogeneous mixing zones, etc. Also, in contrast to most other models, the treatment of the sodium allows for temperature gradients in the sodium and a completely free sequence of states, instead of assuming a liquid phase followed by a vapour phase. After a short description of the experiment, some details of the modelling are discussed especially those in which the original model had to be adjusted to the experiment. Results begin with a presentation of the nominal case which gave the best agreement with the experiment. Special emphasis is devoted to two cases which show a tendency of sodium to act essentially as a heat dissipator under conditions which may be encountered in safety analysis