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EnglishThe 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.
| Titolo: | Modelling radiation transport in voxel geometries with the Monte Carlo code MCNPX | |
| Autori: | ||
| Data di pubblicazione: | 2004 | |
| 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. | |
| Handle: | http://hdl.handle.net/11562/627186 | |
| ISBN: | 8487078052 | |
| Appare nelle tipologie: | 04.01 Contributo in atti di convegno |
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