MCNP5-ORIGEN coupling system has been developed for criticality and burnup calculations.
214 fissions products have been considered in the calculation.
133 FPs were lumped into one pseudo nuclide using MIXE_ACE program for each burnup step.
Application the coupling system for the IAEA 10 MW reactor based on UZr-H1.6 fuel.
The results has been compared to those of ANL and MCNP6.