scholarly journals Beta and gamma dose calculations for PWR and BWR containments

1989 ◽  
Author(s):  
D.B. King
Keyword(s):  
Gamma Dose ◽  
Dose Calculations

Accuracy of Cloudshine Gamma Dose Calculations in the CAP-88 Dispersion Model

2017 ◽  
Vol 112 (4) ◽  
pp. 414-419 ◽  
Author(s):  
Michael W. McNaughton ◽  
Jessica M. Gillis ◽  
Elizabeth Ruedig ◽  
Jeffrey J. Whicker ◽  
David P. Fuehne
Keyword(s):  
Dispersion Model ◽  
Gamma Dose ◽  
Dose Calculations

scholarly journals Photoneutron and capture gamma dose calculations for a radiotherapy room made of high density concrete

2011 ◽  
Vol 26 (2) ◽  
pp. 147-152 ◽  
Author(s):  
Asghar Mesbahi ◽  
Hosein Ghiasi ◽  
Rabee Mahdavi
Keyword(s):  
Analytical Methods ◽  
Gamma Ray ◽  
Gamma Dose ◽  
High Density ◽  
Dose Calculations ◽  
Average Difference ◽  
Dose Equivalent ◽  
Entrance Door ◽  
Therapy Room ◽  
The Difference

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.

scholarly journals Gantry orientation effect on the neutron and capture gamma ray dose equivalent at the maze entrance door in radiation therapy

2012 ◽  
Vol 27 (1) ◽  
pp. 70-74 ◽  
Author(s):  
Hosein Ghiasi ◽  
Asghar Mesbahi
Keyword(s):  
Monte Carlo ◽  
Radiation Therapy ◽  
Gamma Ray ◽  
Mean Value ◽  
Gamma Dose ◽  
Monte Carlo Code ◽  
Dose Calculations ◽  
Entrance Door ◽  
Therapy Room ◽  
Gantry Angle

In the present study, the effect of gantry orientation on the photoneutron and capture gamma dose calculations for maze entrance door was evaluated. A typical radiation therapy room made of ordinary concrete was simulated using MCNPX Monte Carlo code. Gantry rotation was simulated at eight different angles around the isocenter. Both neutron and capture gamma dose vary considerably with gantry angle. The ratios of the maximum to the minimum values for neutron and capture gamma dose equivalents were 1.9 and 1.4, respectively. On the other hand, comparison of the Monte Carlo calculated mean value over all orientations with Monte Carlo calculated neutron and gamma dose showed that the Wu-McGinley method differed by 5% and 2%, respectively. However, for more conservative shielding calculations, factors of 1.6 and 1.3 should be applied to the calculated neutron and capture gamma doses at downward irradiation. Finally, it can be concluded that the gantry angle influences neutron and capture gamma dose at the maze entrance door and it should be taken into account in shielding considerations.

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