Treating voxel geometries in radiation protection dosimetry with a patched version of the Monte Carlo codes MCNP and MCNPX
Anno: 2007
Autori: Burn K.W., Daffara C., Gualdrini G., Pierantoni M., Ferrari P.
Affiliazione autori: ENEA — Ente per le Nuove Tecnologie, l’Energia e l’Ambiente, FIS-NUC, V.M.M. Sole 4, 40129 Bologna, Italy; CNR — Istituto Nazionale di Ottica Applicata, Largo E.Fermi 6, 50125 Firenze, Italy; ENEA, BAS-ION-IRP, V. dei Colli 16, 40136 Bologna, Italy; IOR, Ospedale Rizzoli, IT Service, Salita S.Benedetto 1, 40136 Bologna, Italy
Abstract: The question of Monte Carlo simulation of radiation transport in voxel geometries is addressed. Patched versions of the MCNP and MCNPX codes are developed aimed at transporting radiation both in the standard geometry mode and in the voxel geometry treatment. The patched code reads an unformatted FORTRAN file derived from DICOM format data and uses special subroutines to handle voxel-to-voxel radiation transport. The various phases of the development of the methodology are discussed together with the new input options. Examples are given of employment of the code in internal and external dosimetry and comparisons with results from other groups are reported.
Giornale/Rivista: RADIATION PROTECTION DOSIMETRY
Volume: 123 (3) Da Pagina: 345 A: 353
Parole chiavi: Monte Carlo; MCNP/X; Voxel geometries; Dosimetry; DOI: 10.1093/rpd/ncl150Citazioni: 1dati da “WEB OF SCIENCE” (of Thomson Reuters) aggiornati al: 2024-04-28Riferimenti tratti da Isi Web of Knowledge: (solo abbonati) Link per visualizzare la scheda su IsiWeb: Clicca quiLink per visualizzare la citazioni su IsiWeb: Clicca qui