Modelling radiation transport in voxel geometries with the Monte Carlo code MCNPX

The paper summarizes the research activities at ENEA Bologna to develop a voxel option within the Monte Carlo code MCNPX. An integrated methodology (MCNPX-VOXEL) has been presented that solves the radiation transport problem in voxel geometries and is based on an extension of the Monte Carlo Code MCNPX. A set of medical data (e.g. CT or NMR), representing the geometry of a real patient or of an anthropomorphic dosimetric phantom is transferred to the MCNPX-VOXEL code directly from the original DICOM format.