CRITICALITY CALCULATION FOR A SPENT FUEL STORAGE OF THE MARIA REACTOR

Teresa Kulikowska, Iwona Fidziukiewicz

Institute of Atomic Energy, 05-400 Otwock-Swierk, Poland


The criticality calculations for the pool with spent fuel elements from the MARIA reactor have been carried out. The criticality of the system has been calculated for normal operational conditions and for anticipated emergency situations resulting in a displacement of fuel elements. The purpose of the work is to indicate what precautions would ensure the required subcriticality of the pool in case of unintended displacements of fuel elements. It has been assumed that the central aluminium tube of fuel elements can be substituted by absorber rods to reduce the system reactivity.
The analysis has proved the subcriticality of the system in normal operational conditions. In case of an unintended displacement of fuel elements the required subcriticality condition can be violated even for the fuel burnt up to 35% and with the central aluminium tube substituted by an inconel rod. Thus, stronger poisoning of the system is required.