Photoneutron and capture gamma dose calculations for a radiotherapy room made of high density concrete
Neutron and capture gamma ray dose equivalent along the maze and entrance door of a radiation therapy room made of high density concrete was calculated using analytical and Monte Carlo methods. The room geometry and the 18 MV photon beam of a Varian 2100C/D linac were simulated using MCNPX MC code....
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Published in | Nuclear Technology and Radiation Protection Vol. 26; no. 2; pp. 147 - 152 |
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Main Authors | , , |
Format | Journal Article |
Language | English |
Published |
VINCA Institute of Nuclear Sciences
01.09.2011
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Subjects | |
Online Access | Get full text |
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Abstract | Neutron and capture gamma ray dose equivalent along the maze and entrance
door of a radiation therapy room made of high density concrete was calculated
using analytical and Monte Carlo methods. The room geometry and the 18 MV
photon beam of a Varian 2100C/D linac were simulated using MCNPX MC code.
Four analytical methods including Kersey, French, McCall, and Wu-McGinley
methods were used in the current study. Average difference of 13-30% was seen
between analytical and MC methods along the maze for photoneutron
calculations. The difference between Wu-McGinley and MC methods was about 17%
for capture gamma ray calculations. It was concluded that the analytical
methods overestimate both neutron and capture gamma ray dose equivalents
compared to MC. Moreover, it was shown that the analytical methods can be
used as conservative estimators for neutron and capture gamma calculations.
Primenom analitickih i Monte Karlo metoda izracunate su ekvivalentne doze od
neutrona i prateceg gama zracenja duz lavirinta i ulaznih vrata sobe za
radioterapiju, nacinjene od betona velike gustine. Geometrija sobe i snop 18
MeV-skih fotona iz linearnog akceleratora Varian 2100C/D, simulirani su
koriscenjem MCNPX Monte Karlo programa. Cetiri analiticke metode - Kersijeva,
Frencova, Mekkolova i Vu-Mekginlijeva, koriscene su u ovoj studiji. Razlike
izmedju analitickih i Monte Karlo metoda u proracunu fotoneutrona duz
lavirinta iznosila su 13-30%, u srednjem. U proracunu prateceg gama zracenja,
razlika izmedju Vu-Mekginlijeve metode i Monte Karlo simulacije bila je oko
17%. Zakljuceno je da analiticke metode uporedjene sa Monte Karlo simulacijom,
precenjuju ekvivalentnu dozu i neutrona i prateceg gama zracenja, te da mogu
biti upotrebljene u cilju konzervativne procene doza. |
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AbstractList | Neutron and capture gamma ray dose equivalent along the maze and entrance
door of a radiation therapy room made of high density concrete was calculated
using analytical and Monte Carlo methods. The room geometry and the 18 MV
photon beam of a Varian 2100C/D linac were simulated using MCNPX MC code.
Four analytical methods including Kersey, French, McCall, and Wu-McGinley
methods were used in the current study. Average difference of 13-30% was seen
between analytical and MC methods along the maze for photoneutron
calculations. The difference between Wu-McGinley and MC methods was about 17%
for capture gamma ray calculations. It was concluded that the analytical
methods overestimate both neutron and capture gamma ray dose equivalents
compared to MC. Moreover, it was shown that the analytical methods can be
used as conservative estimators for neutron and capture gamma calculations.
Primenom analitickih i Monte Karlo metoda izracunate su ekvivalentne doze od
neutrona i prateceg gama zracenja duz lavirinta i ulaznih vrata sobe za
radioterapiju, nacinjene od betona velike gustine. Geometrija sobe i snop 18
MeV-skih fotona iz linearnog akceleratora Varian 2100C/D, simulirani su
koriscenjem MCNPX Monte Karlo programa. Cetiri analiticke metode - Kersijeva,
Frencova, Mekkolova i Vu-Mekginlijeva, koriscene su u ovoj studiji. Razlike
izmedju analitickih i Monte Karlo metoda u proracunu fotoneutrona duz
lavirinta iznosila su 13-30%, u srednjem. U proracunu prateceg gama zracenja,
razlika izmedju Vu-Mekginlijeve metode i Monte Karlo simulacije bila je oko
17%. Zakljuceno je da analiticke metode uporedjene sa Monte Karlo simulacijom,
precenjuju ekvivalentnu dozu i neutrona i prateceg gama zracenja, te da mogu
biti upotrebljene u cilju konzervativne procene doza. Neutron and capture gamma ray dose equivalent along the maze and entrance door of a radiation therapy room made of high density concrete was calculated using analytical and Monte Carlo methods. The room geometry and the 18 MV photon beam of a Varian 2100C/D linac were simulated using MCNPX MC code. Four analytical methods including Kersey, French, McCall, and Wu-McGinley methods were used in the current study. Average difference of 13-30% was seen between analytical and MC methods along the maze for photoneutron calculations. The difference between Wu-McGinley and MC methods was about 17% for capture gamma ray calculations. It was concluded that the analytical methods overestimate both neutron and capture gamma ray dose equivalents compared to MC. Moreover, it was shown that the analytical methods can be used as conservative estimators for neutron and capture gamma calculations. |
Author | Mesbahi, Asghar Ghiasi, Hosein Mahdavi, Rabee |
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door of a radiation therapy room made of high density concrete was calculated
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Title | Photoneutron and capture gamma dose calculations for a radiotherapy room made of high density concrete |
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