El-Taher A
Physics Department, Faculty of Science, Al-Azher University, Assuit Branch, 71542 Assuit, Egypt.
Radiat Prot Dosimetry. 2011 Jun;145(4):405-10. doi: 10.1093/rpd/ncq425. Epub 2010 Nov 30.
Representative environmental samples (sandy soil, limestone, marble and gravels) collected from Wadi El Assuity, protective area, Assuit governorate in Upper Egypt have been investigated radiometrically using NaI (Tl) gamma-ray spectrometer. The specific activity of the radionuclides in Bq kg⁻¹ for soil ranged between 10.5 and 18.7 for ²²⁶Ra, 1.5 to 4.6 for ²³²Th and from 94 to 107 for ⁴⁰K, for limestone ranged between 19 and 27.1 for ²²⁶Ra, 32.9 to 50 for ²³²Th and from 49 to 7 3 for ⁴⁰K, where, for marble ranged between 12.2 and 30.7 for ²²⁶Ra, 32.6 to 59.5 for ²³²Th and 55 to 70 for ⁴⁰K and for gravels ranged between 7.8 and 21.8 for ²²⁶Ra, 19.8 to 30.0 for ²³²Th and from 151 to 260 for ⁴⁰K. The mean activity concentrations of measured radionuclides were compared with other literature values. The absorbed dose rate, radium equivalent activity and external hazard index were calculated and compared with internationally recommended values. The gamma absorbed dose rates in the samples ranged between 8.44 and 50.89 nGy h⁻¹. These dose rates are consistent with the accepted worldwide average 55 nGy h⁻¹ for the public. All values obtained for radium equivalent activity are < 370 Bq kg⁻¹, which are acceptable for safe use. The calculated values of external hazard index obtained varied from 0.12 to 0.24. Since these values are lower than unity, one can say that the radiation hazard is insignificant for the population living in the investigated area. This permits the use of these materials sediments as building materials in any probable development projects at this area.
从埃及上埃及阿斯尤特省保护区瓦迪阿斯尤特采集的代表性环境样本(沙土、石灰石、大理石和砾石),已使用碘化钠(铊)γ射线光谱仪进行了放射性测量。土壤中放射性核素的比活度(单位为Bq kg⁻¹),²²⁶Ra在10.5至18.7之间,²³²Th在1.5至4.6之间,⁴⁰K在94至107之间;石灰石中,²²⁶Ra在19至27.1之间,²³²Th在32.9至50之间,⁴⁰K在49至73之间;大理石中,²²⁶Ra在12.2至30.7之间,²³²Th在32.6至59.5之间,⁴⁰K在55至70之间;砾石中,²²⁶Ra在7.8至21.8之间,²³²Th在19.8至30.0之间,⁴⁰K在151至260之间。将测得的放射性核素的平均活度浓度与其他文献值进行了比较。计算了吸收剂量率、镭当量活度和外照射危害指数,并与国际推荐值进行了比较。样本中的γ吸收剂量率在8.44至50.89 nGy h⁻¹之间。这些剂量率与全球公认的公众平均55 nGy h⁻¹一致。获得的所有镭当量活度值均<370 Bq kg⁻¹,可安全使用。计算得到的外照射危害指数值在0.12至0.24之间。由于这些值低于1,可以说对于生活在研究区域的人群,辐射危害微不足道。这使得这些材料沉积物可用于该地区任何可能的开发项目中的建筑材料。