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http://dx.doi.org/10.7742/jksr.2019.13.7.917

Calculation of Neutron Energy Distribution from the Components of Proton Therapy Accelerator Using MCNPX  

Bae, Sang-Il (Department of Radiation Oncology, Dongnam institute of Radiological & Medical sciences)
Shin, Sang-Hwa (Department of Radiological Science, College of Health Sciences, Catholic University of Pusan)
Publication Information
Journal of the Korean Society of Radiology / v.13, no.7, 2019 , pp. 917-924 More about this Journal
Abstract
The passive scattering system nozzle of the proton therapy accelerator was simulated to evaluate the neutrons generated by each component in each nozzle by energy. The Monte Carlo N-Particle code was used to implement spread out Bragg peak with proton energy 220 MeV, reach 20 cm, and 6 cm length used in the treatment environment. Among the proton accelerator components, neutrons were the highest in scatterers, and the neutron flux decreased as it moved away from the central flux of the proton. This study can be used as a basic data for the evaluation of the radiation necessary for the maintenance and dismantling of proton accelerators.
Keywords
MCNPX; Proton therapy accelerator; Neutron; Bragg peak;
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