首页> 外文会议>Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC), 2011 IEEE >Nuclear MCNP simulation of the photoneutron dose contribution in linac radiotherapy treatments with multileaf collimation systems
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Nuclear MCNP simulation of the photoneutron dose contribution in linac radiotherapy treatments with multileaf collimation systems

机译:多叶准直系统在直线加速器放射治疗中的光中子剂量贡献的核MCNP模拟

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摘要

External Bremsstrahlung photon beams produced by medical linac accelerators (Linac) are the most commonly used radiation therapy treatments. The case of treatments which include photon energy beam exceeding 10 MeV produce an undesired dose received by patients due to photoneutron production in the accelerator head. Currently, sophisticated techniques such as multileaf collimators are used for a better definition of the target volume irradiation. In these cases it is important to evaluate the photoneutron dose produced by the excitation of the high atomic number materials (mainly tungsten) constituting the collimator leaves in order to optimize the radiation therapy treatment. A Monte Carlo simulation has been developped to calculate the photoneutron dose arising from an Elekta Precise unit head using a 15 MeV photon beam. The simulation has been performed using the MCNP5 code. Results are presented for the facility at Hospital Universitari Clínic de València setting a square 10 cm × 10 cm collimator configuration.
机译:由医用直线加速器(Linac)产生的外部Bre致辐射光子束是最常用的放射疗法。包括光子能量束超过10 MeV的治疗情况会由于加速器头中产生光中子而产生患者不希望的剂量。当前,诸如多叶准直仪之类的复杂技术被用于更好地确定目标体积辐射。在这些情况下,重要的是评估由激发构成准直仪叶片的高原子序数材料(主要是钨)产生的光中子剂量,以便优化放射治疗。已经开发了蒙特卡罗模拟,以使用15 MeV光子束计算Elekta精密单元头产生的光中子剂量。使用MCNP5代码进行了仿真。结果显示了瓦伦西亚大学医院的设施设置了10 cm×10 cm的方形准直仪配置。

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