Abstract
Cement based materials may contain varying levels of radionuclides, mainly 226Ra (from the 238U series), 232Th and 40K, which are used to determine the Activity Concentration Index ("ACI"). According to the European directive Euratom 2013/59 in these materials, the “ACI” must be < 1 to be suitable for their use in construction. In this paper, data on the activity concentration of natural radionuclides in cement-based materials (i.e. cements, additions, pigments and aggregates) as well as their chemical composition are presented. Radioactivity measurements have been determined by using gamma spectroscopy the chemical compositions have been determined by X-Ray Fluorescence. Data for cements measured shown that white cements present a lower concentration of activity than conventional CEM I. In addition, the CAC (Calcium aluminate cements) present high activity concentration in the 232Th series. Regarding additions, FA (Fly Ash) are those that present the highest concentration of activity in the 238U and 232Th series, while olive biomass ashes are those supplementary cementitious materials that show the highest concentration of activity for 40K. Some pigments used in mortar and concrete technology were also characterized. Granitic and volcanic rocks, potentially used as aggregates present much higher activity concentration than the siliceous aggregate.
Highlights
Cement based materials may contain varying levels of radionuclides, mainly 226Ra, 232Th and 40K, which are used to determine the Activity Concentration Index ("ACI")
Radioactivity measurements have been determined by using gamma spectroscopy the chemical compositions have been determined by X-Ray Fluorescence
fly ash (FA) (Fly Ash) are those that present the highest concentration of activity in the 238 U and 232 Th series, while olive biomass ashes are those supplementary cementitious materials that show the highest concentration of activity for 40K
Summary
Physics Radioactivity and Radiological hazards in cement based materials Tables The chemical oxide compositions of the materials were determined on S8 Tiger Bruker X-ray fluorescence (XRF) spectrometer. Loss on ignition was calculated as per European standard EN196-2:2014 [1] Radiological measurements of the samples were carried out by means of gamma ray spectrometry using a system with two high purity germanium detectors one of them is coaxial (Type p), and the other are BEGe (Broad Energy Germanium detector). For radiological measurements of the samples, and in order to ensure secular equilibrium between 226Ra and 232Th and their progenies, a plastic cylindrical beaker containers with 75.4 mm of diameter and 31 mm height were used. They were completely filled with each sample, hermetically sealed to avoid 222Rn losses and let stand for at least 25 days before their measurement. The data can be used for radiological studies, as well as for dose rate calculations and the Activity Concentration Index of each of the cement based materials
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