MCNP6 unstructured mesh application to estimate the photoneutron distribution and induced activity inside a linac bunker

被引:5
|
作者
Juste, B. [1 ]
Morato, S. [1 ]
Miro, R. [1 ]
Verdu, G. [1 ]
Diez, S. [2 ]
机构
[1] Univ Politecn Valencia, Inst Seguridad Ind Radiofis & Medioambiental ISIR, Cami de Vera S-N, Valencia 46022, Spain
[2] Hosp Clin Univ Valencia, Av Blasco Ibanez 17, Valencia 46010, Spain
关键词
MCNP6; Unstructured mesh; Photoneutron reactions; Bunker; Induced activity; LinAc; LINEAR ACCELERATORS; RADIATION-THERAPY; MONTE-CARLO; ENERGY;
D O I
10.1016/j.radphyschem.2016.03.016
中图分类号
O64 [物理化学(理论化学)、化学物理学];
学科分类号
070304 ; 081704 ;
摘要
Unwanted neutrons in radiation therapy treatments are typically generated by photonuclear reactions. High-energy beams emitted by medical Linear Accelerators (LinAcs) interact with high atomic number materials situated in the accelerator head and release neutrons. Since neutrons have a high relative biological effectiveness, even low neutron doses may imply significant exposure of patients. It is also important to study radioactivity induced by these photoneutrons when interacting with the different materials and components of the treatment head facility and the shielding room walls, since persons not present during irradiation (e.g. medical staff) may be exposed to them even when the accelerator is not operating. These problems are studied in this work in order to contribute to challenge the radiation protection in these treatment locations. The work has been performed by simulation using the latest state of the art of Monte-Carlo computer code MCNP6. To that, a detailed model of particles transport inside the bunker and treatment head has been carried out using a meshed geometry model. The LinAc studied is an Elekta Precise accelerator with a treatment photon energy of 15 MeV used at the Hospital Clinic Universitari de Valencia, Spain. (C) 2016 Elsevier Ltd. All rights reserved.
引用
收藏
页码:18 / 22
页数:5
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