Determination of the ambient dose equivalent H*(10) at high-altitude cities using a NaI(Tl) scintillator.

IF 0.8 4区环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES

Radiation protection dosimetry Pub Date : 2024-12-06 DOI:10.1093/rpd/ncae209

Carlos Lorenzo Nina Choque, Hugo Marcelo Rivera Bretel

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引用次数: 0

Abstract

The ambient dose equivalent rate H*(10) was determined at various locations in the metropolitan area of the cities of La Paz and El Alto in Bolivia. A NaI(Tl) scintillation detector was employed to infer the gamma-ray fluence, and the fluence was transformed in dose rates by means of the appropriate coefficients. In this paper, a full methodology for the estimation of dose rates associated with gamma rays emitted from the ground (terrestrial radiation) and the atmosphere is developed from measurements made with the scintillator instrument. The energy calibration and resolution of the apparatus are presented, followed by the estimation of its response and efficiency by means of Monte Carlo simulations. Lastly, the definition of H*(10) is used to determine the conversion coefficients needed to transform gamma-ray fluence in dose rates. With this methodology, rates for H*(10) around 123 ± 8 nSv/h were estimated using data collected in three city districts: Mallasa (3320 m a.s.l.), San Antonio (3620 m a.s.l.), and Zona Sur (3400 m a.s.l.). The dose rates are believed to be representative of the terrestrial radiation fields encountered in the highlands of Bolivia.

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使用 NaI（Tl）闪烁体测定高海拔城市的环境剂量当量 H*（10）。

我们在玻利维亚拉巴斯和埃尔阿尔托市大都市区的不同地点测定了环境剂量当量率 H*(10)。使用碘化鈉（鈦）閃爍探測器推算伽馬射線的流量，並利用適當的系數把流量轉換為劑量率。本文根据闪烁探测器的测量结果，提出了估算从地面（陆地辐射）和大气层发射的伽马射线剂量率的完整方法。文章介绍了闪烁仪的能量校准和分辨率，随后通过蒙特卡罗模拟估算了闪烁仪的响应和效率。最后，利用 H*(10)的定义来确定将伽马射线通量转换为剂量率所需的转换系数。通过这种方法，利用在三个城市地区收集到的数据，估算出 H*（10）的剂量率约为 123 ± 8 nSv/h：马拉萨（海拔 3320 米）、圣安东尼奥（海拔 3620 米）和南区（海拔 3400 米）。据信，这些剂量率代表了玻利维亚高原地区的陆地辐射场。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Radiation protection dosimetry 环境科学-公共卫生、环境卫生与职业卫生

CiteScore

1.40

自引率

10.00%

发文量

223

审稿时长

6-12 weeks

期刊介绍： Radiation Protection Dosimetry covers all aspects of personal and environmental dosimetry and monitoring, for both ionising and non-ionising radiations. This includes biological aspects, physical concepts, biophysical dosimetry, external and internal personal dosimetry and monitoring, environmental and workplace monitoring, accident dosimetry, and dosimetry related to the protection of patients. Particular emphasis is placed on papers covering the fundamentals of dosimetry; units, radiation quantities and conversion factors. Papers covering archaeological dating are included only if the fundamental measurement method or technique, such as thermoluminescence, has direct application to personal dosimetry measurements. Papers covering the dosimetric aspects of radon or other naturally occurring radioactive materials and low level radiation are included. Animal experiments and ecological sample measurements are not included unless there is a significant relevant content reason.