Hosein Ghiasi1, Asghar Mesbahi2. 1. Medical Physics Department, Medical School, Tabriz University of Medical Sciences, Tabriz, Iran. 2. Medical Physics Department, Medical School, Tabriz University of Medical Sciences, Tabriz, Iran ; Radiation Oncology Department, Imam Hospital, Tabriz, Iran.
Abstract
BACKGROUND: Photoneutrons are produced in radiation therapy with high energy photons. Also, capture gamma rays are the byproduct of neutrons interactions with wall material of radiotherapy rooms. AIM: In the current study an analytical formula was proposed for capture gamma dose calculations in double bend mazes in radiation therapy rooms. MATERIALS AND METHODS: A total of 40 different layouts with double-bend mazes and a 18 MeV photon beam of Varian 2100 Clinac were simulated using MCNPX Monte Carlo (MC) code. Neutron capture gamma ray dose equivalent was calculated by the MC method along the maze and at the maze entrance door of all the simulated rooms. Then, all MC resulted data were fitted to an empirical formula for capture gamma dose calculations. Wu-McGinley analytical formula for capture gamma dose equivalent at the maze entrance door in single-bend mazes was also used for comparison purposes. RESULTS: For capture gamma dose equivalents at the maze entrance door, the difference of 2-11% was seen between MC and the derived equation, while the difference of 36-87% was found between MC and the Wu-McGinley methods. CONCLUSION: Our results showed that the derived formula results were consistent with the MC results for all of 40 different geometries. However, as a new formula, further evaluations are required to validate its use in practical situations. Finally, its application is recommend for capture gamma dose calculations in double-bend mazes to improve shielding calculations.
BACKGROUND: Photoneutrons are produced in radiation therapy with high energy photons. Also, capture gamma rays are the byproduct of neutrons interactions with wall material of radiotherapy rooms. AIM: In the current study an analytical formula was proposed for capture gamma dose calculations in double bend mazes in radiation therapy rooms. MATERIALS AND METHODS: A total of 40 different layouts with double-bend mazes and a 18 MeV photon beam of Varian 2100 Clinac were simulated using MCNPX Monte Carlo (MC) code. Neutron capture gamma ray dose equivalent was calculated by the MC method along the maze and at the maze entrance door of all the simulated rooms. Then, all MC resulted data were fitted to an empirical formula for capture gamma dose calculations. Wu-McGinley analytical formula for capture gamma dose equivalent at the maze entrance door in single-bend mazes was also used for comparison purposes. RESULTS: For capture gamma dose equivalents at the maze entrance door, the difference of 2-11% was seen between MC and the derived equation, while the difference of 36-87% was found between MC and the Wu-McGinley methods. CONCLUSION: Our results showed that the derived formula results were consistent with the MC results for all of 40 different geometries. However, as a new formula, further evaluations are required to validate its use in practical situations. Finally, its application is recommend for capture gamma dose calculations in double-bend mazes to improve shielding calculations.
Authors: Rebecca M Howell; Michele S Ferenci; Nolan E Hertel; Gary D Fullerton; Timothy Fox; Lawrence W Davis Journal: Radiat Prot Dosimetry Date: 2005 Impact factor: 0.972
Authors: Stephen F Kry; Mohammad Salehpour; David S Followill; Marilyn Stovall; Deborah A Kuban; R Allen White; Isaac I Rosen Journal: Int J Radiat Oncol Biol Phys Date: 2005-07-15 Impact factor: 7.038