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首页> 外文期刊>Radiation Protection Dosimetry >AMBIENT NEUTRON DOSE EQUIVALENT OUTSIDE CONCRETE VAULT ROOMS FOR 15 AND 18 MV RADIOTHERAPY ACCELERATORS
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AMBIENT NEUTRON DOSE EQUIVALENT OUTSIDE CONCRETE VAULT ROOMS FOR 15 AND 18 MV RADIOTHERAPY ACCELERATORS

机译:适用于15和18 MV放射治疗加速器的环境中性剂量等效混凝土外翻室

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摘要

In this work, the ambient dose equivalent, H~*(10), due to neutrons outside three bunkers that house a 15- and a 18-MV Varian Clinac 2100C/D and a 15-MV Elekta Inor clinical linacs, has been calculated. The Monte Carlo code MCNPX (v. 2.5) has been used to simulate the neutron production and transport. The complete geometries including linacs and full installations have been built up according to the specifications of the manufacturers and the planes provided by the corresponding medical physical services of the hospitals where the three linacs operate. Two of these installations, those lodging the Varian linacs, have an entrance door to the bunker while the other one does not, although it has a maze with two bends. Various treatment orientations were simulated in order to establish plausible annual equivalent doses. Specifically anterior-posterior, posterior-anterior, left lateral, right lateral orientations and an additional one with the gantry rotated 30° have been studied. Significant dose rates have been found only behind the walls and the door of the bunker, near the entrance and the console, with a maximum of 12 μSv h~(-1). Dose rates per year have been calculated assuming a conservative workload for the three facilities. The higher dose rates in the corresponding control areas were 799μSv y~(-1) in the case of the facility which operates the 15-MV Clinac, 159 μSv y~(-1) for that with the 15-MV Elekta, and 21 μSv y~(-1) for the facility housing the 18-MV Varian. A comparison with measurements performed in similar installations has been carried out and a reasonable agreement has been found. The results obtained indicate that the neutron contamination does not increase the doses above the legal limits and does not produce a significant enhancement of the dose equivalent calculated. When doses are below the detection limits provided by the measuring devices available today, MCNPX simulation provides an useful method to evaluate neutron dose equivalents based on a detailed description of linac, patient and bunker.
机译:在这项工作中,已经计算了三个中子外部的中子当量的环境剂量当量H〜*(10),其中三个掩体容纳了15MV和18MV Varian Clinac 2100C / D和15MV Elekta Inor临床直线加速器。 。蒙特卡罗代码MCNPX(v。2.5)已用于模拟中子的产生和传输。根据制造商的规格以及由三个直线加速器运行所在医院的相应医疗物理服务所提供的飞机,已经建立了包括直线加速器和完整安装装置在内的完整几何形状。这些装置中有两个安装了瓦里安直线加速器,有一个通往掩体的入口,而另一个则没有,尽管它有两个弯曲的迷宫。为了确定合理的年度等效剂量,对各种治疗方法进行了模拟。具体来说,研究了前后,左右,左侧和右侧的方向,以及另一种将机架旋转30°的方向。仅在掩体的壁和门后面,入口和控制台附近发现了显着的剂量率,最大剂量率为12μSvh〜(-1)。假设三个设施的工作量比较保守,则计算每年的剂量率。对于操作15-MV Clinac的设备,在相应控制区域的较高剂量率是799μSvy〜(-1),对于使用15MV Elekta的设备是159μSvy〜(-1)。 μSvy〜(-1)用于容纳18-MV Varian的设备。已与在类似装置中执行的测量进行了比较,并找到了合理的协议。获得的结果表明,中子污染不会将剂量增加到法定限值以上,并且不会显着提高所计算的剂量当量。当剂量低于当今可用的测量设备提供的检测极限时,MCNPX模拟将基于直线加速器,患者和掩体的详细描述,提供一种评估中子剂量当量的有用方法。

著录项

  • 来源
    《Radiation Protection Dosimetry》 |2012年第4期|p.457-464|共8页
  • 作者单位

    Grupo de Fisica Nuclear Aplicada y Simulacion, Universidad Pedagogica y Tecnologica de Colombia, Tunja, Colombia;

    Servicio de Radiofisica y Proteccion Radiologica, Hospital Universitario 'Rio Hortega', Calle Dulzaina, 2, E-47012 Valladolid, Spain,Departamento de Radiologia, Universidad de Valladolid, E-47071 Valladolid, Spain;

    Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (CIEMAT), Avda. Complutense, 22, E-28040 Madrid, Spain;

    Departamento de Fisica Atomica, Molecular y Nuclear, Universidad de Granada, E-18071 Granada, Spain;

  • 收录信息 美国《科学引文索引》(SCI);美国《化学文摘》(CA);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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