http://www.cnr.it/ontology/cnr/individuo/prodotto/ID58026

Treating voxel geometries in radiation protection dosimetry with a patched version of the Monte Carlo codes MCNP and MCNPX (Articolo in rivista)

Type

Label

Treating voxel geometries in radiation protection dosimetry with a patched version of the Monte Carlo codes MCNP and MCNPX (Articolo in rivista) (literal)

Anno

Alternative label

Burn K.W., Daffara C., Gualdrini G., Pierantoni M., Ferrari P. (2007)
Treating voxel geometries in radiation protection dosimetry with a patched version of the Monte Carlo codes MCNP and MCNPX
in Radiation protection dosimetry
(literal)

Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#autori

Pagina inizio

Pagina fine

Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#numeroVolume

Rivista

Note

Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#affiliazioni

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 (literal)

Titolo

Treating voxel geometries in radiation protection dosimetry with a patched version of the Monte Carlo codes MCNP and MCNPX (literal)

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. (literal)

Prodotto di