Automatic generation and validation of an ITER neutronics model from CAD data

This paper describes the application of the interface program McCad to a CAD model of ITER for the automatic generation of a neutronics geometry model for the Monte Carlo particle transport program MCNP. The validity of the generated geometry model was shown by comparing the results of stochastic MCNP volume calculations and the volumes provided by the CAD kernel of the interface program as well as by a neutron wall loading distribution calculation.