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.
Modelling radiation transport in voxel geometries with the Monte Carlo code MCNPX
Daffara, Claudia;
2004-01-01
Abstract
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.
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