Calculations of secondary neutron dose from 18 MV IMRT

Michele Sutton Ferenci, Rebecca M. Howell, Joseph Y. Ting, Lawrence W. Davis, Nolan E. Hertel

Research output: Contribution to conferencePaper

Abstract

A preliminary examination of the secondary neutron dose from 18 MV Intensity Modulated Radiation Therapy (IMRT) was performed using the Monte Carlo code, MCNPX. A model of the Varian Clinac 2200C/2300C including the multileaf collimator was created to compute the neutron fluence and production in and around the treatment head. The neutron fluence results were folded with ICRP 74 fluence-to-dose conversion coefficients to obtain the ambient dose equivalent outside of the treatment head. The calculations are compared with measurements at the same location.

Original languageEnglish (US)
Pages600-606
Number of pages7
StatePublished - Dec 1 2003
EventSixth International Meeting on Nuclear Applications of Accelerator Technology (AccApp'03): Accelerator Applications in a Nuclear Renaissance - San Diego, CA, United States
Duration: Jun 1 2003Jun 5 2003

Other

OtherSixth International Meeting on Nuclear Applications of Accelerator Technology (AccApp'03): Accelerator Applications in a Nuclear Renaissance
CountryUnited States
CitySan Diego, CA
Period6/1/036/5/03

All Science Journal Classification (ASJC) codes

  • Engineering(all)

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  • Cite this

    Ferenci, M. S., Howell, R. M., Ting, J. Y., Davis, L. W., & Hertel, N. E. (2003). Calculations of secondary neutron dose from 18 MV IMRT. 600-606. Paper presented at Sixth International Meeting on Nuclear Applications of Accelerator Technology (AccApp'03): Accelerator Applications in a Nuclear Renaissance, San Diego, CA, United States.