Sanjuán Miguel Ángel, Suárez-Navarro José Antonio, Argiz Cristina, Barragán Marta, Hernáiz Guillermo, Cortecero Miriam, Lorca Pedro
Spanish Institute for Cement and Its Applications (IECA), C/José Abascal, 53, 28003 Madrid, Spain.
Department of Environment, Environmental Radioactivity and Radiological Surveillance (CIEMAT), Avenida Complutense 40, 28040 Madrid, Spain.
Materials (Basel). 2022 May 9;15(9):3395. doi: 10.3390/ma15093395.
The objective of this study is to assess whether the carbonation process can modify the physicochemical characteristics of the natural radionuclides of the three natural radioactive series, together with K. Three mortar specimens with different percentages of ground granulated blast-furnace slag (GGBFS), cured under water for 1, 3, 7, 14, or 28 days, were subjected to a natural carbonation process. Activity concentrations for the solid and ground mortars were determined by gamma spectrometry and by radiochemical separation of isotopic uranium. The novelty of this paper relies principally on the study we have carried out, for the first time, of the radiological characteristics of carbonated Portland cement mortars. It was found that the chemical properties of the 3 mortar specimens were not affected by the carbonation process, with particular attention placed on uranium (U, U, and U), the activity concentrations of which were equivalent to the Ra results and ranged from 5.5 ± 1.6 Bq kg to 21.4 ± 1.2 Bq kg for the U. The average activity concentrations for the 3 types of mortars were lower than 20.1 Bq kg, 14.5 Bq kg, and 120.2 Bq kg for the Ra, Th (Pb), and K, respectively. Annual effective dose rates were equivalent to the natural background of 0.024 mSv. In addition, it was observed that the variation rate for the Rn emanation was due primarily to the Portland cement hydration and not due to the pore size redistribution as a consequence of the carbonation process. This research will provide new insights into the potential radiological risk from carbonated cement-based materials. Moreover, the assessment that is presented in this study will convey valuable information for future research that will explore the activity concentration of building materials containing NORM materials.
本研究的目的是评估碳酸化过程是否会改变三个天然放射性系列的天然放射性核素以及钾的物理化学特性。对三个含有不同比例磨细粒化高炉矿渣(GGBFS)的砂浆试件进行了研究,它们在水中养护1、3、7、14或28天,之后进行自然碳酸化过程。通过伽马能谱法以及同位素铀的放射化学分离来测定固体和磨细砂浆的活度浓度。本文的新颖之处主要在于我们首次对碳酸化波特兰水泥砂浆的放射学特性进行了研究。结果发现,3个砂浆试件的化学性质未受碳酸化过程影响,特别关注了铀(U、U和U),其活度浓度与镭的结果相当,U的活度浓度范围为5.5±1.6 Bq/kg至21.4±1.2 Bq/kg。三种类型砂浆的平均活度浓度,镭低于20.1 Bq/kg,钍(铅)低于14.5 Bq/kg,钾低于120.2 Bq/kg。年有效剂量率相当于0.024 mSv的天然本底。此外,观察到氡析出率的变化主要是由于波特兰水泥水化,而非碳酸化过程导致的孔径重新分布。这项研究将为碳酸化水泥基材料潜在的放射学风险提供新的见解。此外,本研究中的评估将为未来探索含天然放射性物质(NORM)材料的建筑材料活度浓度的研究提供有价值的信息。