Burn-up calculation of the neutronic and safety parameters of thorium-uranium mixed oxide fuel cycle in a Westinghouse small modular reactor
The datasets added here could be used to reproduce the burn-up calculation of the Neutronic and Safety parameters of thorium-uranium mixed oxide fuel using three fissile enrichment zones against the conventional single enrichment. The is meant to determine the choice of the three fissile enrichment for thorium-based fuel and its performance at long-lasting temperature differentials.
Steps to reproduce
Run a Monte Carlo simulation using MCNPX 2.7 code integrated with CINDER90 burn-up code.