尼日利亚奥贡州丹格特水泥厂周围土壤样品的天然放射性浓度和放射性评价

Olatunji Kehinde Olanipekun, B. Lateef
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摘要

背景:自然产生的放射性物质(标准)是人类暴露于电离辐射的重要来源,但在某些情况下,人为活动,如采矿,产生的废物在环境中含有高于本底水平的辐射,这种情况引起辐射保护方面的极大关注。丹格特水泥厂周围的采矿和生产已经进行了若干年,因此有必要评估放射性核素对本研究区域人口健康的可能风险程度。对伊贝塞丹格特水泥厂周围的放射性浓度进行了测量。采用伽玛射线能谱Nal (TI)闪烁探测器对表层土壤样品进行了测量。结果:测定结果表明,(238U - 226Ra)的活性浓度为18.33±1.91 ~ 29.14±4.4.2 Bqkg-1,平均为23.40 Bqkg-1; (232Th)的活性浓度为10.93±5.43 ~ 21.52±2.16 Bqkg-1,平均为16.50Bqkg-1; (40K)的活性浓度为291.78±15.50 ~ 338.60±3.922 Bqkg-1,平均为314.11 Bqkg-1。同样,吸收剂量范围为28.63 ~ 38.24nGy/h,平均为33.14nGy/h。计算的年有效剂量范围为0.035 ~ 0.047毫西弗/年,平均为0.040毫西弗/年。结论:获得的238U、232Th和40K的放射性浓度平均值低于UNSCEAR出版物中报道的相应全球值。计算的吸收剂量和年有效剂量值也低于建议的安全水平。
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Natural Radioactivity Concentration and Radiological Evaluation in Soil Samples Around Dangote Cement Factory Ibese, Ogun State, Nigeria
Background: Natural-occurring radioactive materials (NORMs) provide significant sources of human exposure to ionizing radiation but in certain cases, anthropogenic activities, like mining, have produced wastes that contain radiation above background levels in the environment, a situation that is of great concern for radiation protection. Around Dangote cement factory both mining and production have been on-going for some years, therefore there is need to evaluate the extent of the possible risk of the radionuclides to the health of the population in this study area. Measurements of radioactivity concentrations were carried out around Dangote Cement Factory Ibese. Samples of surface soil were measured using gamma-ray spectroscopy Nal (TI) scintillation detector. Results: Measurements showed that activity concentrations ranged from 18.33+ 1.91 Bqkg-1 to 29.14±4.4.2 Bqkg-1, with an average of 23.40 Bqkg-1 for (238U - 226Ra), 10.93±5.43 Bqkg-1 to 21.52±2.16 Bqkg-1 with an average of 16.50Bqkg-1 for 232Th, and 291.78±15.50 Bqkg-1 to 338.60±3.922 Bqkg-1 with an average of 314.11 Bqkg-1 for 40K. Similarly, the absorbed dose ranged from 28.63nGy/h to 38.24nGy/h with an average of 33.14nGy/h. The calculated annual effective dose ranged from 0.035mSv/y to 0.047mSv/y with an average of 0.040mSv/y. Conclusions: The average value of Radioactivity concentrations obtained for 238U, 232Th and 40K are lower than the corresponding global values reported in UNSCEAR publication. The calculated absorbed dose and annual effective dose values are also less than the recommended safe levels.
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