Evaluation of sampling and analytical uncertainties and estimation of natural radioactivity levels in the soil samples in Kalpakkam, Tamilnadu.

IF 0.7 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES
Bommadeni Arun, Viswanathan S, Menaka M, Kothai Parthasarathy, Balasubramaniam Venkatraman
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Abstract

The high-purity germanium (HPGe) detector is used to quantify natural radioactivity concentrations in soil samples. The total uncertainty due to the contribution of the analytical method and sampling uncertainty is evaluated in this study. The relative sampling uncertainty values for 40K, 238U, and 232Th are found to be within 5%. The measured specific activity levels ranged between 225.6 ± 8.5 Bq/kg and 479.6 ± 13.0 Bq/kg for 40K, 12.1.6 ± 1.4 Bq/kg and 73.2 ± 2.7 Bq/kg for 238U, and 48.7 ± 2.6 Bq/kg and 548.7 ± 17.0 Bq/kg for 232Th, respectively. The radiological hazard parameters, such as absorbed dose rates and annual effective dose values, were estimated from the 40K, 238U, and 232Th activity concentration values. The absorbed dose rate values ranged between 45 nGy/h and 383 nGy/h with a mean value of 142 nGy/h. The annual effective dose values ranged from 0.06 mSv/y to 0.47 mSv/y with a mean value of 0.17 mSv/y.

泰米尔纳德邦卡尔帕克卡姆土壤样品中采样和分析不确定性的评估及自然放射性水平的估计。
高纯度锗(HPGe)检测器用于定量土壤样品中的天然放射性浓度。本研究评估了由分析方法和抽样不确定度所引起的总不确定度。40K、238U和232Th的相对采样不确定度值在5%以内。40K、238U和232Th的比活性分别为225.6±8.5 Bq/kg和479.6±13.0 Bq/kg、12.1.6±1.4 Bq/kg和73.2±2.7 Bq/kg和48.7±2.6 Bq/kg和548.7±17.0 Bq/kg。根据40K、238U和232Th活性浓度值估算吸收剂量率和年有效剂量值等辐射危害参数。吸收剂量率值在45 ~ 383 nGy/h之间,平均值为142 nGy/h。年有效剂量值为0.06毫西弗/年至0.47毫西弗/年,平均值为0.17毫西弗/年。
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来源期刊
Radiation protection dosimetry
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.
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