Calculations of secondary neutron dose from 18 MV IMRT

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

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 conference › Paper › peer-review

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 language	English (US)
Pages	600-606
Number of pages	7
State	Published - 2003
Event	Sixth International Meeting on Nuclear Applications of Accelerator Technology (AccApp'03): Accelerator Applications in a Nuclear Renaissance - San Diego, CA, United States Duration: Jun 1 2003 → Jun 5 2003

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Other	Sixth International Meeting on Nuclear Applications of Accelerator Technology (AccApp'03): Accelerator Applications in a Nuclear Renaissance
Country/Territory	United States
City	San Diego, CA
Period	6/1/03 → 6/5/03

All Science Journal Classification (ASJC) codes

General Engineering

Cite this

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title = "Calculations of secondary neutron dose from 18 MV IMRT",

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.",

author = "Ferenci, {Michele Sutton} and Howell, {Rebecca M.} and Ting, {Joseph Y.} and Davis, {Lawrence W.} and Hertel, {Nolan E.}",

year = "2003",

language = "English (US)",

pages = "600--606",

note = "Sixth International Meeting on Nuclear Applications of Accelerator Technology (AccApp'03): Accelerator Applications in a Nuclear Renaissance ; Conference date: 01-06-2003 Through 05-06-2003",

}

Calculations of secondary neutron dose from 18 MV IMRT. / Ferenci, Michele Sutton; Howell, Rebecca M.; Ting, Joseph Y. et al.
2003. 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.

Research output: Contribution to conference › Paper › peer-review

TY - CONF

T1 - Calculations of secondary neutron dose from 18 MV IMRT

AU - Ferenci, Michele Sutton

AU - Howell, Rebecca M.

AU - Ting, Joseph Y.

AU - Davis, Lawrence W.

AU - Hertel, Nolan E.

PY - 2003

Y1 - 2003

N2 - 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.

AB - 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.

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M3 - Paper

AN - SCOPUS:2642571978

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T2 - Sixth International Meeting on Nuclear Applications of Accelerator Technology (AccApp'03): Accelerator Applications in a Nuclear Renaissance

Y2 - 1 June 2003 through 5 June 2003

ER -

Calculations of secondary neutron dose from 18 MV IMRT

Abstract

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All Science Journal Classification (ASJC) codes

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