A Monte Carlo-based method to estimate radiation dose from spiral CT: from phantom testing to patient-specific models

2003 ◽  
Vol 48 (16) ◽  
pp. 2645-2663 ◽  
Author(s):  
G Jarry ◽  
J J DeMarco ◽  
U Beifuss ◽  
C H Cagnon ◽  
M F McNitt-Gray
2005 ◽  
Vol 50 (17) ◽  
pp. 3989-4004 ◽  
Author(s):  
J J DeMarco ◽  
C H Cagnon ◽  
D D Cody ◽  
D M Stevens ◽  
C H McCollough ◽  
...  

2010 ◽  
Vol 38 (1) ◽  
pp. 397-407 ◽  
Author(s):  
Xiang Li ◽  
Ehsan Samei ◽  
W. Paul Segars ◽  
Gregory M. Sturgeon ◽  
James G. Colsher ◽  
...  

2020 ◽  
Vol 152 ◽  
pp. S1038-S1039
Author(s):  
J.F. Calvo Ortega ◽  
M. Hermida-López- ◽  
S. Moragues-Femenía ◽  
C. Laosa-Bello ◽  
J. Casals-Farran
Keyword(s):  

2015 ◽  
Vol 42 (9) ◽  
pp. 5510-5516 ◽  
Author(s):  
Ashley E. Rubinstein ◽  
Zhongxing Liao ◽  
Adam D. Melancon ◽  
Michele Guindani ◽  
David S. Followill ◽  
...  

2017 ◽  
Vol 178 (2) ◽  
pp. 213-222 ◽  
Author(s):  
Mahmoud Bagheri ◽  
Ali Asghar Parach ◽  
Seid Kazem Razavi-Ratki ◽  
Reza Nafisi-Moghadam ◽  
Mohammad Ali Jelodari

2005 ◽  
Vol 114 (1-3) ◽  
pp. 364-368 ◽  
Author(s):  
M. Salvadó ◽  
M. López ◽  
J. J. Morant ◽  
A. Calzado

2019 ◽  
Vol 6 (2) ◽  
pp. 31-41
Author(s):  
Jiankui Yuan ◽  
David Mansur ◽  
Min Yao ◽  
Tithi Biswas ◽  
Yiran Zheng ◽  
...  

ABSTRACT Purpose: We developed an integrated framework that employs a full Monte Carlo (MC) model for treatment-plan simulations of a passive double-scattering proton system. Materials and Methods: We have previously validated a virtual machine source model for full MC proton-dose calculations by comparing the percentage of depth-dose curves, spread-out Bragg peaks, and lateral profiles against measured commissioning data. This study further expanded our previous work by developing an integrate framework that facilitates its clinical use. Specifically, we have (1) constructed patient-specific applicator and compensator numerically from the plan data and incorporated them into the beamline, (2) created the patient anatomy from the computed tomography image and established the transformation between patient and machine coordinate systems, and (3) developed a graphical user interface to ease the whole process from importing the treatment plan in the Digital Imaging and Communications in Medicine format to parallelization of the MC calculations. End-to-end tests were performed to validate the functionality, and 3 clinical cases were used to demonstrate clinical utility of the framework. Results: The end-to-end tests demonstrated that the framework functioned correctly for all tested functionality. Comparisons between the treatment planning system calculations and MC results in 3 clinical cases revealed large dose difference up to 17%, especially in the beam penumbra and near the end of beam range. The discrepancy likely originates from a variety of sources, such as the dose algorithms, modeling of the beamline, and the dose metric. The agreement for other regions was acceptable. Conclusion: An integrated framework was developed for full MC simulations of double-scattering proton therapy. It can be a valuable tool for dose verification and plan evaluation.


2020 ◽  
Vol 35 (3) ◽  
pp. 177-181
Author(s):  
Afifah Hana Tsurayya ◽  
Azzam Zukhrofani Iman ◽  
R. Yosi Aprian Sari ◽  
Arief Fauzi ◽  
Gede Sutresna Wijaya

The research aims to measure the radiation dose rate over the radiation shielding which is made of paraffin and aluminium and to determine the best shield material for the safety of radiation workers. The examination used MCNP (Monte Carlo N-Particle) simulator to model the BNCT neutron source and the shield. The shield should reduce radiation to less than the dose limit of 10.42 µSv/h, which is assumed to be the most conservative limit when the duration of workers is 1920 h. The first design resulted in a radiation dose rate which was still greater than the limit. Therefore, optimization was done by adding the lead on the outer part of the shield. After optimization by adding the lead with certain layers, the radiation dose rate decreased, with the largest dose being 57.60 µSv/h. Some locations over the limit could be overcome by other radiation protection aspects such as distance and time. The paraffin blocks were covered by aluminium to keep the shield structure. The lead was used to absorb the gamma ray which resulted from the interaction between the neutrons and aluminium.


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