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KMID : 1151820190130070917
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Journal of the Korean Society of Radiology
2019 Volume.13 No. 7 p.917 ~ p.924
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Calculation of Neutron Energy Distribution from the Components of Proton Therapy Accelerator Using MCNPX
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Bae Sang-Il
Shin Sang-Hwa
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Abstract
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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.
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KEYWORD
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MCNPX, Proton therapy accelerator, Neutron, Bragg peak
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