Tally and geometry definition influence on the computing time in Radiotherapy Treatment Planning with MCNP Monte Carlo code

Author

Juste, B. ; Miro, R. ; Gallardo, S. ; Santos, A. ; Verdu, G.

Author_Institution

Dept. de Ingenieria Quimica y Nucl., Univ. Politecnica de Valencia

fYear

2006

fDate

Aug. 30 2006-Sept. 3 2006

Firstpage

5763

Lastpage

5766

Abstract

The present work has simulated the photon and electron transport in a Theratron 780reg (MDS Nordion) ⁶⁰Co radiotherapy unit, using the Monte Carlo transport code, MCNP (Monte Carlo N-Particle), version 5. In order to become computationally more efficient in view of taking part in the practical field of radiotherapy treatment planning, this work is focused mainly on the analysis of dose results and on the required computing time of different tallies applied in the model to speed up calculations

Keywords

Monte Carlo methods; dosimetry; radiation therapy; ⁶⁰Co; ⁶⁰Co radiotherapy unit; MCNP; MDS Nordion; Monte Carlo transport code; Theratron 780reg; electron transport; photon transport; radiotherapy treatment planning; Biological materials; Biomedical applications of radiation; Cobalt; Computational geometry; Computational modeling; Electrons; Hospitals; Imaging phantoms; Monte Carlo methods; Pulse measurements;

fLanguage

English

Publisher

ieee

Conference_Titel

Engineering in Medicine and Biology Society, 2006. EMBS '06. 28th Annual International Conference of the IEEE

Conference_Location

New York, NY

ISSN

1557-170X

Print_ISBN

1-4244-0032-5

Electronic_ISBN

1557-170X

Type

conf

DOI

10.1109/IEMBS.2006.259423

Filename

4463116