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USING HANDHELD PLASTIC SCINTILLATOR DETECTORS TO TRIAGE INDIVIDUALS EXPOSED TO A RADIOLOGICAL DISPERSAL DEVICE

机译:使用手持式塑料闪烁检测仪对暴露于放射线分散装置的个人进行分类

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摘要

After a radiological dispersal device (RDD) event, people could become internally contaminated by inhaling dispersed radioactive particles. A rapid method to screen individuals who are internally contaminated is desirable. Such initial screening can help in prompt identification of those who are highly contaminated and in prioritising individuals for further and more definitive evaluation such as laboratory testing. The use of handheld plastic scintillators to rapidly screen those exposed to an RDD with gamma-emitting radionuclides was investigated in this study. The Monte Carlo N-Particle transport code was used to model two commercially available plastic scintillation detectors in conjunction with anthropomorphic phantom models to determine the detector response to inhaled radionuclides. Biokinetic models were used to simulate an inhaled radionuclide and its progression through the anthropomorphic phantoms up to 30 d after intake. The objective of the study was to see if internal contamination levels equivalent to 250 mSv committed effective dose equivalent could be detected using these instruments. Five radionuclides were examined: ~(60)Co, ~(137)Cs, ~(192)Ir, ~(131)I and ~(241)Am. The results demonstrate that all of the radionuclides except ~(241)Ani could be detected when placing either one of the two plastic scintillator detector systems on the posterior right torso of the contaminated individuals.
机译:放射扩散装置(RDD)事件发生后,人们可能会因吸入分散的放射性颗粒而被内部污染。需要一种快速的方法来筛选内部受污染的个体。这样的初始筛选可以帮助迅速识别高度污染的人群,并为个人提供进一步和更明确的评估(例如实验室测试)的优先级。在这项研究中,研究了使用手持式塑料闪烁体来快速筛选那些暴露于RDD的伽马发射放射性核素。蒙特卡罗N粒子传输代码与拟人体模模型一起用于对两个市售的塑料闪烁探测器进行建模,以确定探测器对吸入放射性核素的响应。使用生物动力学模型来模拟吸入放射性核素及其在拟人体模中的摄取过程,直至摄入后30 d。研究的目的是观察是否可以使用这些仪器检测到相当于250 mSv承诺有效剂量当量的内部污染水平。检查了五个放射​​性核素:〜(60)Co,〜(137)Cs,〜(192)Ir,〜(131)I和〜(241)Am。结果表明,当将两个塑料闪烁体探测器系统中的一个放置在受污染人员的右后躯干上时,可以检测到除〜(241)Ani以外的所有放射性核素。

著录项

  • 来源
    《Radiation Protection Dosimetry》 |2012年第1期|p.101-108|共8页
  • 作者单位

    Georgia Institute of Technology, Nuclear and Radiological Engineering Program, Atlanta, GA 30332-0475,USA Oak Ridge National Laboratory, 545 Oak Ridge Turnpike, Oak Ridge, TN 37830, USA;

    Georgia Institute of Technology, Nuclear and Radiological Engineering Program, Atlanta, GA 30332-0475,USA;

    Georgia Institute of Technology, Nuclear and Radiological Engineering Program, Atlanta, GA 30332-0475,USA, Idaho State University, Nuclear Engineering Department, Pocatello, ID 83209, USA;

    Radiation Studies Branch, Centers for Disease Control and Prevention, Atlanta, GA, USA;

  • 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
  • 关键词

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