SIMPLIFIED CRITICALITY SAFETY CALCULATIONS OF SPENT FUEL STORAGE POOL
29th Symposium of AER on VVER Reactor Physics and Reactor Safety (2019, Energoland, Mochovce NPP, Slovakia)
spent fuel disposal and actinide transmutation
This work is focused on criticality safety analysis of spent fuel storage pool for the NPP Mochovce 12. The MCNP5 code with the ENDF/B-VII libraries were applied to model the compact grid of the storage pool loaded with 4.87% enriched fuel assemblies. In order to increase the operational storage capacity of the compact grid, number of absorber assemblies were inserted into the pool instead of four empty rows now needed to reach the required subcriticality. Conservative approach was choosen and applied on parameters and simplifications. The methodology is focused on determination of the best geometrical configuration of the inserted absorber parts in the compact grid. The pre-calculations with simplified model were used to lower the calculation time which was affected by complexity of the model and calculation parameters. The best resulting scenarios were later used in more complex conservative MCNP model with higher precision and for optimalization of criticality safety analysis.