RELAP5/MOD3 Model and Transient Analyses for Maria Research Reactor in Poland

The RELAPS/MOD3: input data model of the MARIA research reactor has been developed to provide the capability for the analysis of the reactor core under loss of flow and reactivity insertion transients. The model was qualified against the reactor data at steady state conditions and additionally against the existing reliable experimental data for a transient initiated by reactor scram. The results obtained with the code agree well with the experimental data. The RELAP transient simulation was performed for loss of forced flow accidents including two scenarios with protected and unprotected (no scram) reactor core. Calculations allow estimating time margin for reactor scram initiation and reactivity feedbacks contribution on the results. The presented input data model should be treated as the first step for developing of the model including the whole primary cooling circuit of the reactor. (author)