Open AccessPhotoneutron and capture gamma dose calculations for a radiotherapy room made of high density concrete
Author(s) -
Asghar Mesbahi,
Hosein Ghiasi,
Rabee Seyed Mahdavi
Publication year - 2011
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp1102147m
Subject(s) - neutron capture , monte carlo method , neutron , physics , linear particle accelerator , gamma ray , photon , nuclear medicine , nuclear physics , radiation , beam (structure) , computational physics , optics , mathematics , medicine , statistics
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