Asaduzzaman Khandoker, Mannan Farhana, Khandaker Mayeen Uddin, Farook Mohideen Salihu, Elkezza Aeman, Amin Yusoff Bin Mohd, Sharma Sailesh, Abu Kassim Hasan Bin
Department of Physics, Faculty of Science, University of Malaya, Kuala Lumpur, Malaysia; Bangladesh Atomic Energy Commission, Dhaka-1207, Bangladesh.
Institute of Educational Leadership, University of Malaya, Kuala Lumpur, Malaysia.
PLoS One. 2015 Oct 16;10(10):e0140667. doi: 10.1371/journal.pone.0140667. eCollection 2015.
The concentrations of primordial radionuclides (226Ra, 232Th and 40K) in commonly used building materials (brick, cement and sand), the raw materials of cement and the by-products of coal-fired power plants (fly ash) collected from various manufacturers and suppliers in Bangladesh were determined via gamma-ray spectrometry using an HPGe detector. The results showed that the mean concentrations of 226Ra, 232Th and 40K in all studied samples slightly exceeded the typical world average values of 50 Bq kg(-1), 50 Bq kg(-1) and 500 Bq kg(-1), respectively. The activity concentrations (especially 226Ra) of fly-ash-containing cement in this study were found to be higher than those of fly-ash-free cement. To evaluate the potential radiological risk to individuals associated with these building materials, various radiological hazard indicators were calculated. The radium equivalent activity values for all samples were found to be lower than the recommended limit for building materials of 370 Bq kg(-1), with the exception of the fly ash. For most samples, the values of the alpha index and the radiological hazard (external and internal) indices were found to be within the safe limit of 1. The mean indoor absorbed dose rate was observed to be higher than the population-weighted world average of 84 nGy h(-1), and the corresponding annual effective dose for most samples fell below the recommended upper dose limit of 1 mSv y(-1). For all investigated materials, the values of the gamma index were found to be greater than 0.5 but less than 1, indicating that the gamma dose contribution from the studied building materials exceeds the exemption dose criterion of 0.3 mSv y(-1) but complies with the upper dose principle of 1 mSv y(-1).
采用高纯锗探测器通过γ射线能谱法测定了从孟加拉国不同制造商和供应商处收集的常用建筑材料(砖、水泥和沙子)、水泥原材料以及燃煤电厂副产品(粉煤灰)中天然放射性核素(镭-226、钍-232和钾-40)的浓度。结果表明,所有研究样品中镭-226、钍-232和钾-40的平均浓度分别略高于典型的世界平均值50 Bq kg⁻¹、50 Bq kg⁻¹和500 Bq kg⁻¹。本研究发现,含粉煤灰水泥的活度浓度(尤其是镭-226)高于无粉煤灰水泥。为评估与这些建筑材料相关的个体潜在放射性风险,计算了各种放射性危害指标。发现除粉煤灰外,所有样品的镭当量活度值均低于建筑材料推荐限值370 Bq kg⁻¹。对于大多数样品,α指数以及放射性危害(外部和内部)指数的值均在安全限值1以内。观察到室内平均吸收剂量率高于84 nGy h⁻¹的全球人口加权平均值,并且大多数样品的相应年有效剂量低于推荐的1 mSv y⁻¹剂量上限。对于所有调查材料,γ指数的值大于0.5但小于1,表明所研究建筑材料的γ剂量贡献超过了0.3 mSv y⁻¹的豁免剂量标准,但符合1 mSv y⁻¹的剂量上限原则。