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Spectrum-dose conversion operator of NaI(Tl) and CsI(Tl) scintillation detectors for air dose rate measurement in contaminated environments

机译:NaI(Tl)和CsI(Tl)闪烁探测器的光谱剂量转换算子,用于在受污染的环境中测量空气剂量率

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摘要

Spectrum-dose conversion operators, the G(E) functions, for common NaI(T1) scintillation survey meters and CsI(T1) detectors are obtained for measurements in a semi-infinite plane of contaminated ground field by photon-emitting radionuclides (ground source). The calculated doses at a height of 100 cm from the ground in 137Cs-contaminated environments by the Monte Carlo simulation technique are compared with those obtained using the G(E) functions by assuming idealized irradiation geometries such as anterior posterior or isotropic. The simulation reveals that one could overestimate air dose rates in the environment by a maximum of 20-30% for Nal(T1) detectors and 40-50% for CsI(TI) detectors depending on photon energy when using the G(E) functions assuming idealized irradiation geometries for ground source measurements. Measurements obtained after the nuclear accident in Fukushima reveal that the doses calculated using a G(E) function for a unidirectional irradiation geometry are 1.17 times higher than those calculated using a G(E) function for the ground source in the case of a CsI(T1) scintillation detector, which has a rectangular parallelepiped crystal (13 x 13 x 20 mm(3)). However, if a G(E) function is used assuming irradiation to a surface of the detector, the doses agree with those of the ground source within 2%. These results indicate that in contaminated environments, the commonly used scintillation-based detectors overestimate doses within the acceptable limit. In addition, the degree of overestimation depends on the irradiation direction of each detector assumed for developing the G(E) function. With regard to directional dependence of the detectors, reliable air dose rates in the environment can be obtained using the G(E) function determined in unidirectional irradiation geometry, provided that the irradiation surface of the crystal is determined properly. (C) 2016 Elsevier Ltd. All rights reserved.
机译:获得了光谱剂量转换算子,G(E)函数,用于普通NaI(T1)闪烁测量仪和CsI(T1)检测器,以通过光子发射放射性核素在被污染地面的半无限平面中进行测量(地面源)。通过假定理想的照射几何形状(例如前后或各向同性),将在137Cs污染的环境中距离地面100 cm处通过Monte Carlo模拟技术计算出的剂量与使用G(E)函数获得的剂量进行比较。仿真显示,使用G(E)功能时,根据光子能量,可以高估Nal(T1)检测器和CsI(TI)检测器的空气剂量率,最高可达20-30%,而CsI(TI)检测器的空气剂量率最高可达40-50%假设理想的辐射几何形状用于地面源测量。在福岛核事故之后获得的测量结果表明,对于CsI(),使用G(E)函数计算的单向照射几何剂量比使用G(E)函数计算的地面源剂量高1.17倍。 T1)闪烁检测器,它具有长方体晶体(13 x 13 x 20 mm(3))。但是,如果使用G(E)函数假设照射到检测器的表面,则剂量与地面源的剂量应在2%之内。这些结果表明,在受污染的环境中,常用的基于闪烁的探测器会高估可接受范围内的剂量。此外,高估程度取决于为开发G(E)函数而假定的每个检测器的照射方向。关于检测器的方向依赖性,只要适当确定晶体的照射表面,就可以使用在单向照射几何形状中确定的G(E)函数获得环境中可靠的空气剂量率。 (C)2016 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Journal of Environmental Radioactivity》 |2017年第3期|419-426|共8页
  • 作者

    Tsuda Shuichi; Saito Kimiaki;

  • 作者单位

    Japan Atom Energy Agcy, Nucl Sci & Engn Ctr, Res Grp Radiat Transport Anal, Tokai, Ibaraki 3191195, Japan;

    Japan Atom Energy Agcy, Sect Fukushima Res & Dev, Fukushima Environm Safety Ctr, Tokyo 1008577, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);美国《化学文摘》(CA);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Scintillation detector; Mapping project; G(E) function; KURAMA;

    机译:闪烁探测器;映射项目;G(E)功能;KURAMA;

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