Analysis of reactor cores with deterministic and stochastic methods. Investigation of alternative fuel cycles such as Th/U including breeding regimes. Development of innovative computational tools for assessing the control rod absorber depletion, the gamma heating of samples. Development of a dynamic stochastic neutronic code for conventional and innovative reactor cores including Accelerator Driven Systems. Improvement of the computational coupling procedures between neutronics and thermal hydraulics in multiphysics/multiscale reactor core analyses. Optimization of research reactors capabilities. Neutron spectrum tailoring for special irradiations using neutron screens.

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