scieee AI-readable full text Open interactive document viewer

Environmental Impact of Phosphogypsum-Derived Building Materials

Romero Hermida, Isabel; Flores Alés, Vicente; Hurtado Bermúdez, Santiago José; Santos, A.; Esquivias Fedriani, Luis María

Abstract

The aim of the present work was to characterize the products obtained from the treatment of phosphogypsum residue by means of two recovery routes, and also to evaluate the concentrations of heavy metals and radionuclides in the materials obtained and their leachates. In this way, it is possible to determine how the most hazardous components of phosphogypsum behave during procedures until their stabilization through CO2 fixation. This study provides an initial estimate of the possibilities of reusing the resulting products from a health and safety risk standpoint and their potential polluting capacity. The phases resulting from the transformations were controlled, and the behaviour of standard mortars manufactured from the resulting paste lime was studied. In all cases, an additional control of the leachate products was performed

Full text

International Journal of Environmental Research and Public Health Article Environmental Impact of Phosphogypsum-Derived Building Materials M. I. Romero-Hermida 1, V. Flores-Alés2,* , S. J. Hurtado-Bermúdez 3, A. Santos 4and L. Esquivias 1,5 1Física de la Materia Condensada, Universidad de Sevilla, 41012 Sevilla, Spain; isaromer[email protected] (M.I.R.-H.); [email protected] (L.E.) 2Construcciones Arquitectónicas II, Universidad de Sevilla, 41012 Sevilla, Spain 3CITIUS—S.G.I. Celestino Mutis, Universidad de Sevilla, 41012 Sevilla, Spain; [email protected] 4De Ciencias de la Tierra, Universidad de Cádiz, 11519 Cádiz, Spain; [email protected] 5Instituto de Ciencia de Materiales de Sevilla, CSIC—Universidad de Sevilla, 41092 Sevilla, Spain *Correspondence: [email protected]; Tel.: +34-954-556-656 Received: 28 May 2020; Accepted: 11 June 2020; Published: 14 June 2020   Abstract: The aim of the present work was to characterize the products obtained from the treatment of phosphogypsum residue by means of two recovery routes, and also to evaluate the concentrations of heavy metals and radionuclides in the materials obtained and their leachates. In this way, it is possible to determine how the most hazardous components of phosphogypsum behave during procedures until their stabilization through CO 2 fixation. This study provides an initial estimate of the possibilities of reusing the resulting products from a health and safety risk standpoint and their potential polluting capacity. The phases resulting from the transformations were controlled, and the behaviour of standard mortars manufactured from the resulting paste lime was studied. In all cases, an additional control of the leachate products was performed. Keywords: phosphogypsum; lime paste; mortar; heavy metals; radionuclides 1. Introduction One of the most contaminating industries is the phosphoric acid (H 3 PO 4 ) industry. This chemical is widely used in agricultural fertilizers, detergent additives, cleaning products, and insecticides. Phosphoric acid is produced from the treatment of calcium phosphate rocks with sulphuric acid. The chemical reaction of the industrial process is: Ca3(PO4)+3H2SO4+6H2O→2H3PO4+3(CaSO4)·2H2O. (1) The residue generated by this process, that is, mainly calcium sulphate di-hydrate, is commonly known as phosphogypsum (PG) [1]. PG is normally slurred with water and then pumped in enormous amounts to a nearby deposit. The fertilizer manufacturing industry in the province of Huelva (SW Spain) is based on an important production of phosphoric acid by wet processing of the phosphoric rock in an industrial plant from the 1960s. In some cases, such as in Huelva (SW Spain), these deposits may be located in the vicinity of populated towns or in coastal zones close to the phosphoric acid plants where they occupy large areas of land, thus representing a hazard to both the environment and local population [ 2 – 4 ]. In the case of Huelva (SW Spain), the material stored reaches 120 million tons and occupies an area of 1200 hectares near the estuary of the Tinto and Odiel river mouths [ 5 ]. The growing interest in the restoration of the environment by removing landfills and waste stacks is an incentive to search for potential low-cost applications of PG wastes. Int. J. Environ. Res. Public Health 2020,17, 4248; doi:10.3390/ijerph17124248 www.mdpi.com/journal/ijerph Int. J. Environ. Res. Public Health 2020,17, 4248 2 of 17 Untreated PG could certainly be used in several industrial applications. However, it contains heavy metals and radionuclides, which are harmful to the environment and human health [ 6 , 7 ]. This is an important drawback when it comes to reincorporating PG in the industrial production circuit in accordance with the principles of the clean circular economy [ 8 ]. Each year, nearly 200 Mt of PG are produced worldwide, but only 15% of pristine PG is re-used [ 9 , 10 ]. The properties of the material not only make it urgent to process and eventually remove the deposits entirely, but also offer many significant opportunities to recover valuable materials, thus supporting the circular economy and, as mentioned, adding value by CO2sequestration. The incorporation of construction and demolition waste in concrete and cement mortars is already a common practice, and the aim is to ensure the construction industry assumes part of the waste it produces [ 11 , 12 ]. The goal of this stream is to promote the use of conglomerates by incorporating waste to produce so-called “green concrete”. To achieve this, appropriate standards are urgently required, as well as interdisciplinary collaborations between the different stakeholders involved in construction [13]. PG is a source of calcium, which, in addition to being a CO 2 sequestering agent, is a construction material [ 14 , 15 ]. Research has demonstrated the high efficiency of portlandite precipitation by PG dissolution using an alkaline soda solution [ 16 ]; PG, reacting with ammonia, may be converted into ammonium sulphate and precipitated calcium carbonate [ 17 ], yielding reaction conversion efficiencies of >95% [ 18 ]. By means of other processes with PG, wastes, which are unable to fix CO 2 by themselves, can be successfully turned into effective CO 2 sinks [ 19 ]. CO 2 sequestration may also be achieved through mineral carbonation of waste PG using the technique of membrane electrolysis [ 20 ] and by the PG reduction thermal decomposition process [21]. In this study, PG was treated in two ways. The first option (procedure A) was based on its reaction with sodium hydroxide (Na(OH)) to obtain portlandite (Ca(OH) 2 ) in the form of lime paste in a thenardite (Na2SO4) solution [20]. Then, the lime reacts rapidly and completely with CO2, yielding precipitated calcium carbonate (PCC). The second option (procedure B) was based on dissolution in a highly alkaline liquid residue from the aluminium anodizing industry, rich in Na-Al. The resulting precipitate consisted of katoite (Ca 3 Al 2 (OH) 12 ). Katoite has high carbonation efficiency (80–100%), and produces a solid precipitate mainly composed of calcite (CaCO 3 ) and an aluminium hydroxide (Al(OH)3) solution [22]. Following the stream to reuse these wastes in the construction industry, the slaked lime produced can be used as a mortar component. Ca(OH) 2 improves the degree of cohesion of the materials by means of the carbonation reaction, thus reducing porosity. Its carbonation is a spontaneous process driven by diffusion and affected by natural variables [23]. PG is classified, according to the United States Environmental Protection Agency (US-EPA), 2018 [ 24 ], as a Technologically Enhanced Naturally Occurring Radioactive Material (TENORM). The main toxic and radioactive metals present in PG are Sr, As, Y, Cu, Pb, and the radioactive isotopes 226 Ra, 238 U, 230 Th, 210 Pb, and 210 Po [ 25 – 27 ]. Minority impurities, such as P, Cd, and Cr are also dragged out. These represent a risk of environmental contamination that affects living beings. The concentrations of these elements vary depending on the characteristics of the original phosphate rock [28]. To establish the limitations of the use of PG related to its content in the abovementioned elements, it is necessary to understand their leaching processes during treatment [ 29 ], from PG until its final stabilization as calcium carbonate. Thus, the environmental impact generated by its extraction from PG rafts and its possible recycling could be evaluated. The main aim of this work is the characterization and control of the phases resulting from PG waste transformation by two processes: Procedure A is based on treatment with Na(OH) in which the controls were performed on the portlandite obtained as lime paste in the first phase and also in the calcite resulting from carbonation. Additionally, lime mortars were manufactured from lime paste and standardized siliceous sand to verify the behaviour once the resulting material was stabilized [ 30 ], as well as its possible viability as construction material. Procedure B is based on the reaction with the Int. J. Environ. Res. Public Health 2020,17, 4248 3 of 17 residual liquid of the aluminium industry. It was carried out on the katoite from the first reaction and the final calcite obtained after the carbonation process. In all cases, an additional control of the leachate products in accordance with the toxicity characteristic leaching procedure (TCLP) was carried out [31]. 2. Materials and Methods Crude solid PG was supplied by Fertiberia from the stacks in Huelva, Spain. For its characterization, the residue was homogenized by means of a splitter. Then, the moisture content of raw PG was analysed, yielding a value of 21%. For the different tests, the remaining moisture was removed in an oven at 40 ◦ C for around 48 hours to preserve the structural water of the gypsum. Once dry, it was grounded in a mortar and used in the experiments without any other treatment. The process schemes can be seen in Figure 1. Int. J. Environ. Res. Public Health 2020, 17, x 3 of 17 In all cases, an additional control of the leachate products in accordance with the toxicity characteristic leaching procedure (TCLP) was carried out [31]. 2. Materials and Methods Crude solid PG was supplied by Fertiberia from the stacks in Huelva, Spain. For its characterization, the residue was homogenized by means of a splitter. Then, the moisture content of raw PG was analysed, yielding a value of 21%. For the different tests, the remaining moisture was removed in an oven at 40 °C for around 48 hours to preserve the structural water of the gypsum. Once dry, it was grounded in a mortar and used in the experiments without any other treatment. The process schemes can be seen in Figure 1. Figure 1. Schemes of both chemical processes. 2.1. Procedure A 2.1.1. Synthesis Lime putty was obtained by using the Cárdenas–Escudero method [16], with some modifications to scale the generation of by-products. In the first stage, 300 g of PG was suspended in 500 mL of distilled H2O under magnetic stirring. To this suspension, 180 g of NaOH in a 9 M solution was slowly added to favour the crystallization of the solid phase. The mixture was also stirred for the next 10 min. The reaction associated with this process was: CaSO4·2H2O + 2NaOH → Ca(OH)2 + Na2SO4 + 2H2O. (2) This process resulted in the precipitation of a whitish solid phase identified as putty lime and the Na2SO4 solution as a clear supernatant liquid. The solid phase was separated by centrifugation and labelled C_S. The liquid phase was discarded for this research. Several samples of the solid phase were dried in an oven at 40 °C in order to hydrate and carbonate them to preserve them from humidity and atmospheric CO2, so that they could be studied. 2.1.2. Carbonation Process Figure 1. Schemes of both chemical processes. 2.1. Procedure A 2.1.1. Synthesis Lime putty was obtained by using the C á rdenas–Escudero method [ 16 ], with some modifications to scale the generation of by-products. In the first stage, 300 g of PG was suspended in 500 mL of distilled H 2 O under magnetic stirring. To this suspension, 180 g of NaOH in a 9 M solution was slowly added to favour the crystallization of the solid phase. The mixture was also stirred for the next 10 min. The reaction associated with this process was: CaSO4·2H2O+2NaOH →Ca(OH)2+Na2SO4+2H2O. (2) This process resulted in the precipitation of a whitish solid phase identified as putty lime and the Na 2 SO 4 solution as a clear supernatant liquid. The solid phase was separated by centrifugation and labelled C_S. The liquid phase was discarded for this research. Several samples of the solid phase were dried in an oven at 40 ◦ C in order to hydrate and carbonate them to preserve them from humidity and atmospheric CO2, so that they could be studied. 2.1.2. Carbonation Process In the second stage, 2 g of the C_S sample was dispersed in 40 mL of distilled water under magnetic stirring in a reactor (mass ratio [C_S]/[H 2 O] =1/20). A flow of CO 2 (1 bar, 20 cm 3 /s) was Int. J. Environ. Res. Public Health 2020,17, 4248 4 of 17 bubbled through the suspension for 15 min at room temperature and pressure [ 1 ]. The sample was left to rest overnight in this CO2-rich water. The carbonation reaction was: Ca(OH)2+CO2→CaCO3+H2O. (3) The resulting solid phase, labelled Ca_S (mainly CaCO 3 ,), was separated by centrifugation and dried in an oven at 80 ◦ C. The supernatant was discarded, and samples of the solid phase were taken for study. 2.1.3. Lime Mortar Manufacturing Mortars were manufactured with lime putty obtained as described above, with 1:3 lime/sand and 0.5 by weight water/lime ratios. They were prepared with a water content that allowed a consistency of 185 mm, measured in accordance with the UNE-EN 1015-3/A1 standard [ 32 ] to ensure its workability. Prismatic samples were prepared in accordance with UNE-EN 1015-2/A1 standards [ 33 ]. The samples were then deposited for 21 days in climatic chambers (New Brunsaick Galaxy 170) to accelerate carbonation under realistic curing conditions of 25 ◦ C, 50–60% RH, and 10% vol. of CO 2 concentration. 2.2. Procedure B 2.2.1. Synthesis Verinsur S.A. (Jerez de la Frontera, Spain) provided the aluminium anodizing process waste. This was a clear solution with a pH of around 14, containing a small amount of a precipitate phase. For this study, the residue was filtered, and the precipitate discarded. The caustic liquid waste had a density of 1.32 g/cm 3 , and a composition of [Na] =110 ± 2 g/L (4.78 ± 0.09 M)) and [Al] =52 ± 2 g/L (1.93 ±0.07 M). The caustic liquid from the anodizing aluminium industry reacted with PG according to the reaction [23]: 3(CaSO4·2H2O) +6Na+(aq) +12OH-(aq) +2Al3+(aq) Int. J. Environ. Res. Public Health 2020, 17, x 4 of 17 In the second stage, 2 g of the C_S sample was dispersed in 40 mL of distilled water under magnetic stirring in a reactor (mass ratio [C_S]/[H2O] = 1/20). A flow of CO2 (1 bar, 20 cm3/s) was bubbled through the suspension for 15 min at room temperature and pressure [1]. The sample was left to rest overnight in this CO2-rich water. The carbonation reaction was: Ca(OH)2 + CO2 → CaCO3 + H2O. (3) The resulting solid phase, labelled Ca_S (mainly CaCO3,), was separated by centrifugation and dried in an oven at 80 °C. The supernatant was discarded, and samples of the solid phase were taken for study. 2.1.3. Lime Mortar Manufacturing Mortars were manufactured with lime putty obtained as described above, with 1:3 lime/sand and 0.5 by weight water/lime ratios. They were prepared with a water content that allowed a consistency of 185 mm, measured in accordance with the UNE-EN 1015-3/A1 standard [32] to ensure its workability. Prismatic samples were prepared in accordance with UNE-EN 1015-2/A1 standards [33]. The samples were then deposited for 21 days in climatic chambers (New Brunsaick Galaxy 170) to accelerate carbonation under realistic curing conditions of 25 °C, 50–60% RH, and 10% vol. of CO2 concentration. 2.2. Procedure B 2.2.1. Synthesis Verinsur S.A. (Jerez de la Frontera, Spain) provided the aluminium anodizing process waste. This was a clear solution with a pH of around 14, containing a small amount of a precipitate phase. For this study, the residue was filtered, and the precipitate discarded. The caustic liquid waste had a density of 1.32 g/cm3, and a composition of [Na] = 110 ± 2 g/L (4.78 ± 0.09 M)) and [Al] = 52 ±2 g/L (1.93 ± 0.07 M). The caustic liquid from the anodizing aluminium industry reacted with PG according to the reaction [23]: 3(CaSO4·2H2 O) + 6Na+ (aq) + 12OH-(aq) + 2Al3+ (aq) ↔ 3Na2SO4 + Ca3Al2(OH)12 + 6H2O. (4) The process was initiated by adding 12.5 g of PG to 25.0 mL of the aluminium-anodizing residue under magnetic stirring for 3 h in ambient pressure and temperature conditions [9,16]. The pH was 12.0 during the process. The formation of a grey precipitate was observed, labelled as PGAS, and a yellowish supernatant was discarded for this study. Both phases were separated by centrifugation, and then the solid phase was placed in an oven at 80 °C to preserve it from hydration and carbonation. Based on the chemical composition of the residues, this specific mass ratio corresponded to a stoichiometric molar ratio of [Ca2+]/[Al3+] = 1.5, targeting the chemical reaction (4). It should be noted that other stoichiometric relationships with different additions of water were tested. In this study, only the one that produced the best CO2 sequestering results, which was the final purpose, is presented. 3Na2SO4+Ca3Al2(OH)12 +6H2O. (4) The process was initiated by adding 12.5 g of PG to 25.0 mL of the aluminium-anodizing residue under magnetic stirring for 3 h in ambient pressure and temperature conditions [ 9 , 16 ]. The pH was 12.0 during the process. The formation of a grey precipitate was observed, labelled as PGAS, and a yellowish supernatant was discarded for this study. Both phases were separated by centrifugation, and then the solid phase was placed in an oven at 80 ◦ C to preserve it from hydration and carbonation. Based on the chemical composition of the residues, this specific mass ratio corresponded to a stoichiometric molar ratio of [Ca 2+ ]/[Al 3+ ]=1.5, targeting the chemical reaction (4). It should be noted that other stoichiometric relationships with different additions of water were tested. In this study, only the one that produced the best CO2sequestering results, which was the final purpose, is presented. 2.2.2. Carbonation Process In this step, 2 g from the PGAS sample were dispersed in 40 mL of distilled water [ 19 ]. The obtained mixture was subjected to a continuous flow of pure CO 2 ( ≈ 1 bar, 20 cm 3 /s) under magnetic stirring. The sample was carbonated according to the following reaction: Ca3Al2(OH)12 +3CO2→3CaCO3+2Al(OH)3+3H2O. (5) The pH during the process decreased monotonously from 12.8 until it stabilized at 6.7 after 110 min. This resulted in a new solid–liquid suspension whose phases were separated by centrifugation. The solid phase was labelled PGAB, and the liquid phase discarded. The reproducibility of the experiment was verified several times. Int. J. Environ. Res. Public Health 2020,17, 4248 5 of 17 2.3. Characterization Techniques Mineral characterization of the samples was performed by X-ray diffraction. The diffraction intensities were measured on a Bruker powder diffractometer (model D8-Advance A25) equipped with conventional Bragg–Brentano geometry and a Cu anode. X’Pert HighScore software (Malvern Panalytical, Malvern, UK) was used to analyse the results. An ICP-MS/MS Agilent 8800 (Agilent Technologies, Santa Clara, CA, USA) was used to analyse the elements and isotopes at trace and ultra-trace levels (ppm–ppt ranges). This equipment was provided with an octopolar reaction system (ORS), designed to minimize different types of spectrometric interference. The elementary concentrations in liquid samples were analysed with a conventional nebulizer Savillex X400 (ISC-Science. Oviedo, Spain) coupled with a CETAC ASX 520 sample introduction system. A specific interface allowed the samples to be analysed in the presence of high concentrations of hydrofluoric acid. Quantitative analyses were performed in accordance with the US-EPA 200.8 (1986) [ 34 ]. The solid samples were subjected to microwave-assisted acid digestion in 9 mL of concentrated HNO 3 and 3 mL of HF for 15 min at 200 ◦ C. After cooling, the contents of the vessel were filtered and transferred to a 25 mL volumetric flask with type I water from a Milli-Q Integral-3 (Millipore, Merck, Spain). The activity concentrations of the natural radionuclides were measured by high-resolution gamma-ray spectrometry. The detection system used consisted of a Reverse-Electrode Germanium (REGe) detector, model GR6040 (Canberra. Montigny-le-Bretonneux, France) shielded by an active anti-coincidence system containing an annular anti-Compton NaI detector. Canberra GENIE 2000 (Canberra. Montigny-le-Bretonneux, France) software was used to obtain spectra and for subsequent analysis. Canberra LABSOCS software (Canberra. Montigny-le-Bretonneux, France) was used to calculate the counting efficiency of the germanium detector. Cylindrical containers (liquid samples) and Petri dishes (solid samples) were used in the experimental measurements and sealed under vacuum to prevent the escape of radon gas, enabling achievement of secular equilibrium between radon and its daughters ( 226 Ra and 214 Pb). The activity concentrations of the gamma emitters were determined through the following energies: 210Pb (46.5 keV), 232Th (63.3 keV), 226Ra (351 keV of 214Pb), 235U (144 keV), and 40 K (1460 keV). The TCLP (1311 US-EPA) leaching test was performed to assess the effectiveness of the immobilization of the different components and obtain the degree of toxicity associated with the different residues. This procedure used an extraction liquid of pH 2.88 ± 0.05 consisting of 5.7 mL of glacial acetic acid diluted with 1L with deionized water. Of the solid sample, 100 g was added to an amount of extraction liquid, maintaining the 20 mL/g ratio, and placed in a rotary system at 30 ± 2 rpm for 18 hours and at a temperature of 22 ±3◦C. A Rh-tube Panalytical X-ray Fluorescence Spectrometer (AXIOS model) (Malvern Panalytical. Malvern, UK) was used to apply the XRF technique, enabling qualitative and quantitative chemical analysis from O to U in a wide range of concentrations, from major components to traces. 3. Results and Discussion 3.1. Evolution of Environmental Risk 3.1.1. Evaluation of Major Elements and Trace Elements from the Treatment of PG with a Soda in Solution (a) Phosphogypsum The XRD analysis confirmed the almost exclusive presence of gypsum in the sample of unprocessed PG [17], with a residual amount of quartz (SiO2) originating from the mother phosphate rock. According to the XRF analysis results, shown in Table 1, the PG was mainly composed of Ca (32 wt. %, as CaO) and S (46 wt. %, as SO 3 ). These results were similar to those reported in other Int. J. Environ. Res. Public Health 2020,17, 4248 6 of 17 studies [ 1 ] and corresponded to a Ca/S ≈ 0.993 molar ratio, very close to the expected Ca/S ≈ 1 molar ratio. The main impurities of the PG were Si (2.52 wt. %, as SiO2) and P (0.65 wt. %, as P2O5). Table 1. Majority elements in both chemical processes. Majority Elements (wt. %) PG C_S PGAS PGAB Fe2O3nd nd nd 0.01 ±0.01 MnO nd nd nd nd MgO nd nd nd nd CaO 32 ±1 49 ±2 21 ±1 32 ±2 Na2O 0.01 ±0.01 12.5 ±0.6 20.5 ±0.7 2.29 ±0.08 K2O 0.02 ±0.01 nd 0.02 ±0.01 0.03 ±0.01 TiO2nd nd nd nd P2O50.65 ±0.02 1.02 ±0.01 0.38 ±0.01 0.47 ±0.01 SO346 ±3 13.6 ±0.2 27 ±2 14.4 ±0.9 Cl nd nd nd nd F nd nd nd nd SrO nd nd nd nd BaO nd nd nd nd LOI 18.4 ±0.4 19.4 ±0.2 14.4 ±0.2 33 ±0.1 wt. %: weight percentage; PG: phosphogypsum; C_S: lime putty; PGAS: katoite precipitate; PGAB: calcite from katoite carbonation. The main heavy metals and radionuclides observed in the PG were: Sr, Cr, As, Cu, Cd, Pb, U, and Th. The minority elements identified are shown in Table 2, together with the PG sample leaching results obtained from TCLP. Table 2. Contents of trace elements (mg/kg) in the PG (phosphogypsum) sample. Leaching results (mg/L) obtained from the application of the TCLP (Toxicity Characteristic Leaching Procedure) technique to the PG sample (L_f: phosphogypsum leaching), and reference (mg/kg) of the global average concentration of typical uncontaminated soils. The limit values permitted by the US-EPA (United StatesEnvironmental Protection Agency) for metals in leachates extracted from the TCLP test and the maximum permissible limits of heavy metals in water for domestic use according to the US-EPA, WHO (World Health Organization), and EU (European Union) (according to German legislation). Metal PG (mg/kg) L_f (mg/L) Limits Allowed (mg/kg) TCLP (U S—EPA) U S—EPA WHO EU V 2.9 ±0.7 0.0161 ±0.0001 97 0.05 Cr 6.3 ±0.2 <0.023 92 5.0 0.10 0.05 0.05 Co <0.6 <0.0024 17.3 Ni <3 0.026 ±0.001 47 0.02 0.02 Zn <42 0.600 ±0.007 67 5.0 3.0 As <0.6 0.0052 ±0.0004 4.8 5.0 0.05 0.01 0.01 Se <30 <0.006 0.09 1.0 Sr 360 ±10 1.89 ±0.03 320 4.0 Cd 1.8 ±0.4 0.0072 ±0.0007 0.09 1.0 0.005 0.003 0.005 Ba 37 ±1 0.0433 ±0.0008 628 100.0 2.0 0.30 Pb 1.8 ±0.1 0.0053 ±0.0001 17 5.0 0.015 0.01 0.01 Th 1.1 ±0.2 <0.0013 10.5 U 5 ±1 0.0081 ±0.0001 2.7 The concentrations of V, Cr, Ba, Pb, and Th were well below those typically found in undisturbed soils (Table 2) [ 35 ]. However, the concentration of Cd was ≈ 20 times higher than the typical value, the concentration of Sr was ≈ 1.2 times higher, and the content of U was approximately half of its value in uncontaminated soils. It should be noted that the concentrations of Cd and Sr were lower than different PG sources analysed in the literature (Idaho, South Africa, and Tunisia) [ 29 ]. The concentrations of other metals were below the detection limit. Int. J. Environ. Res. Public Health 2020,17, 4248 7 of 17 All these results, when compared with the limit values permitted by the US-EPA for metals in leachates extracted with the TCLP test (Table 2), were well below the established limits. No information is available for some metals, such as V, Co, Ni, Zn, and Sr. More strict criteria would be applicable if the aforementioned numbers are compared with those stipulated in legislation regulating drinking water for human consumption. For this reason, the maximum permissible limits of the metals studied were taken in accordance with the US-EPA (1986), the World Health Organization, and the EU (Drinking Water Directive, 1998) (Table 2) [ 36 ]. Additionally, for vanadium, German legislation was taken as a basis for purification [ 37 , 38 ]. Even so, the level of leachate concentration did not exceed the established limits, except for Ni, which slightly exceeded these limits (30%). Considering the results obtained, the PG analysed in this study does not generate major environmental risks, and therefore, no corrective measures should be applied. However, caution must be taken before any categorical assertion, because PG is heterogeneous, and its heavy metal and radionuclide contents depend on the depth at which the PG is found [39–41]. (b) Soda solution treatment by-products The XRD diffractogram of the C_S sample is shown in Figure 2. As expected according to its composition (Table 1), there was a major presence of CaO, corresponding to slaked lime and Na 2 O and SO 3 due to the sodium sulphate. The lime was composed of 65.3% Ca(OH) 2 , 13.5% SO 3 , silica impurities (quartz), and phosphates (1.02% P2O5), and did not contain MgO. Int. J. Environ. Res. Public Health 2020, 17, x 8 of 17 . Figure 2. XRD (X Ray Diffraction of the samples Ca_S (calcite from lime putty carbonation) (above) and C_S (lime putty) (below). C: Calcite, Q: Quartz, P : Portlandite, T: Thenardite. The concentrations of Cr, Co, Ni, Zn, and Th (Table 3) were below the average concentrations found in typical uncontaminated soils. Those of As and Sr were higher by factors of ≈1.5 and 1.3, respectively. However, the concentrations of Se, Cd, U were substantially higher, as much as ≈37.5 times higher in the case of Cd. The increase in the concentration of U, ≈4 times higher than that of typical soil, was not surprising since it is a material obtained from PG, which is considered a NORM material, that is, one which is rich in U-Th radionucleide series. c) Carbonation by-products The XRD analysis of this sample indicated that the portlandite carbonated completely, resulting only in calcite (Figure 2). The characteristics of this sample have been reported elsewhere [1]. In this case (Table 3), as may be expected, the concentrations of trace elements and radionuclides coincided almost completely with those found in the C_S sample. d) Mortar probes As expected, the majority in the discarded sand was calcite. The portlandite was fully carbonated. Small reflections of residual thenardite in the lime were also observed (Figure 3). . Figure 3. XRD of mortar sample. C: Calcite, Q: Quartz, T: Thenardite. Figure 2. XRD (X Ray Diffraction of the samples Ca_S (calcite from lime putty carbonation) (above) and C_S (lime putty) (below). C: Calcite, Q: Quartz, P: Portlandite, T: Thenardite. The UNE-EN 459-2 standard [ 42 ] states that lime content must always be higher than 55%, although higher values may be required. Nevertheless, the UNE-EN 196-2: 2014 standard [ 43 ] requires that sulphate content, given in terms of SO 3 , must be less than 2%. Regarding the MgO content, the standard requires this to be less than 5%. The SO 3 content exceeded the limit established in the regulations, and therefore, preventive measures are required to correct it. The concentrations of Cr, Co, Ni, Zn, and Th (Table 3) were below the average concentrations found in typical uncontaminated soils. Those of As and Sr were higher by factors of ≈ 1.5 and 1.3, respectively. However, the concentrations of Se, Cd, U were substantially higher, as much as ≈ 37.5 times higher in the case of Cd. The increase in the concentration of U, ≈ 4 times higher than that of typical soil, was not surprising since it is a material obtained from PG, which is considered a NORM material, that is, one which is rich in U-Th radionucleide series. Int. J. Environ. Res. Public Health 2020,17, 4248 8 of 17 Table 3. Trace elements of portlandite (C_S), calcite (Ca_S), and mortar samples. Leaching results obtained from the application of the TCLP (Toxicity Characteristic Leaching Procedure) technique to the sample of portlandite (L_p), calcite (L_c), and mortar (L_m). METAL C_S (mg/kg) L_p (mg/L) Ca_S (mg/kg) L_c (mg/L) Mortar (mg/kg) L_m (mg/L) V<0.1 <0.007 <0.1 <0.007 0.3 ±0.1 0.109 ±0.001 Cr 13.8 ±0.2 0.083 ±0.003 11.5 ±0.4 <0.023 9 ±2<0.023 Co 0.275 ±0.004 <0.0024 0.23 ±0.01 0.0048 ±0.0002 0.165 ±0.03 0.0049 ±0.0002 Ni 1.80 ±0.02 0.023 ±0.001 2.3 ±0.1 0.046 ±0.001 0.347 ±0.05 0.039 ±0.001 Zn 10.1 ±0.2 0.67 ±0.02 9.7 ±0.5 <0.214 9.6 ±1.2 <0.221 As 7 ±2<0.002 5.2 ±0.4 <0.002 3.9 ±1.1 <0.002 Se 2.36 ±0.08 <0.0059 2.33±0.08 <0.006 1.2 ±0.7 <0.0061 Sr 413 ±6 2.17 ±0.05 353 ±1 3.03 ±0.04 170 ±20 2.31 ±0.01 Cd 3.37 ±0.04 <0.0008 3.6 ±0.1 <0.0008 1.4 ±0.4 <0.0008 Ba 83 ±2 0.062 ±0.002 72 ±1 0.1203 ±0.0009 36 ±2 0.0658 ±0.0004 Pb 3.25 ±0.05 0.0066 ±0.0003 3.5 ±0.2 <0.0009 1.43 ±0.04 <0.0009 Th 1.5 ±0.2 <0.0013 2.69 ±0.08 <0.0013 0.32 ±0.05 <0.0013 U 10.7 ±0.3 <0.0012 9.7 ±0.3 0.0508 ±0.0003 3.9 ±0.3 0.0302 ±0.0003 (c) Carbonation by-products The XRD analysis of this sample indicated that the portlandite carbonated completely, resulting only in calcite (Figure 2). The characteristics of this sample have been reported elsewhere [1]. In this case (Table 3), as may be expected, the concentrations of trace elements and radionuclides coincided almost completely with those found in the C_S sample. (d) Mortar probes As expected, the majority in the discarded sand was calcite. The portlandite was fully carbonated. Small reflections of residual thenardite in the lime were also observed (Figure 3). Int. J. Environ. Res. Public Health 2020, 17, x 8 of 17 . Figure 2. XRD (X Ray Diffraction of the samples Ca_S (calcite from lime putty carbonation) (above) and C_S (lime putty) (below). C: Calcite, Q: Quartz, P : Portlandite, T: Thenardite. The concentrations of Cr, Co, Ni, Zn, and Th (Table 3) were below the average concentrations found in typical uncontaminated soils. Those of As and Sr were higher by factors of ≈1.5 and 1.3, respectively. However, the concentrations of Se, Cd, U were substantially higher, as much as ≈37.5 times higher in the case of Cd. The increase in the concentration of U, ≈4 times higher than that of typical soil, was not surprising since it is a material obtained from PG, which is considered a NORM material, that is, one which is rich in U-Th radionucleide series. c) Carbonation by-products The XRD analysis of this sample indicated that the portlandite carbonated completely, resulting only in calcite (Figure 2). The characteristics of this sample have been reported elsewhere [1]. In this case (Table 3), as may be expected, the concentrations of trace elements and radionuclides coincided almost completely with those found in the C_S sample. d) Mortar probes As expected, the majority in the discarded sand was calcite. The portlandite was fully carbonated. Small reflections of residual thenardite in the lime were also observed (Figure 3). . Figure 3. XRD of mortar sample. C: Calcite, Q: Quartz, T: Thenardite. Figure 3. XRD of mortar sample. C: Calcite, Q: Quartz, T: Thenardite. In the case of the mortar, since it is a very heterogeneous system on a millimeter scale, it was necessary to take different aliquots to obtain reliable information because the masses that can be digested by ICP are very small, resulting in a dispersion of the concentrations of the trace elements. The average results of four aliquots taken are presented in Table 3. It can be observed that, when mixing the lime with sand, the initial concentrations of most of the trace elements decreased. The average concentrations of As and Sr were below the limits established by current regulations. However, those of Se, Cd, and U were moderately above those limits. Besides the trace element concentrations, the results from the application of the TCLP technique are shown for the L_p, L_c, and L_m samples in Table 3. These results are compared with the maximum permissible limits established by the TCLP (US-EPA), Int. J. Environ. Res. Public Health 2020,17, 4248 9 of 17 indicated in Table 2. It has been verified that all the values were well below the established limits. Thus, it can be concluded that the monitored metals were effectively immobilized. It was also verified that these values were below the permissible limits established by TCLP (US-EPA). However, there is no information on permissible limits for some metals, such as Zn, Ni, V, and Sr. The concentrations of all the elements screened did not exceed the maximum permissible limits for drinking water. The V limit exceeded the maximum permitted by German law by a factor of ≈2.2. 3.1.2. Contents of Major and Trace Elements in the Treatment of PG with Aluminium Residue (a) Aluminium waste The density of the aluminium residue was 1.32 g/cm 3 measured by Hg pycnometry with pH =14 and [Na] =110 ± 2 g/L (4.78 ± 0.09 M) and [Al] =52 ± 2 g/L (1.93 ± 0.07 M), according to ICP-OES results. (b) Synthesis The XRD pattern of the solid by-product resulting from an attack of the PG with the aluminium waste is represented in Figure 4, labelled PGAS. The main associated reflections corresponded to katoite and thenardite, as expected according to Equation (3). It should be noted that no residual gypsum was detected, indicating that the reaction was complete. The compositional analysis of the PGAS by-product by XRF (Table 1) confirmed the presence of Ca, Al, S, and Na as the main components, in the relative molar fractions Ca:Al (1.51) and Na:S (1.96), typical of katoite and thenardite, respectively, confirming that the reaction was indeed complete. Int. J. Environ. Res. Public Health 2020, 17, x 10 of 17 . Figure 4. XRD of the samples PGAB: calcite (above) and PGAS: katoite precipitate (below). C: Calcite, Q: Quartz, K: Katoite, T: Thenardite. c) Carbonation. The XRD pattern of the carbonated sample (Figure 4) presents the calcite reflections accompanied by those of the remaining quartz impurities from the PG. No thenardite reflections were observed, confirming its complete dissolution during the carbonation process. However, the XRF analysis (Table 1) revealed the presence of substantial contents of certain chemical species not detected by XRD, indicating their amorphous character. These were mainly Al and S, and to a lesser extent, Na. The contents of trace elements present in the PGAS sample (Table 4), such as V, Cr, As, Sr, Ba, and Th were well below the concentrations in undisturbed soils. However, the concentration of Cd (1.1 ± 0.2 mg kg) exceeded the typical concentration by a factor of 12.5. In contrast, the concentration of U (2.5 ± 0.3 mg / kg) was within the limit permitted for uncontaminated soils. Table 4. Contents of trace elements in the PGAS (katoite precipitate) and PGAB (calcite) samples. Leaching results obtained from the application of the TCLP (Toxicity Characteristic Leaching Procedure) technique to the PGAS (L_k) and PGAB (L_ck) samples. Metal PGAS (mg/kg) L_k (mg/L) PGAB (mg/kg) L_ck (mg/L) V 8.0 ± 0.3 <0.007 5.8 ± 0.3 0,.0225 ± 0,04 Cr 5.3 ± 0.4 <0.023 6.7 ± 0.6 0.030 ± 0.004 Co <0.6 <0.0024 <0.6 <0,0024 Ni <3 0.0082 ± 0.0003 <3 0.0050 ± 0.0004 Zn <41 0.0740 ± 0.0005 <41 <0.212 As 1.8 ± 0.8 <0.002 1.4 ± 0.2 <0.002 Se <30 <0.006 <30 <0.0059 Sr 248 ± 10 1.69 ± 0.02 345 ± 5 1.46 ± 0.1 Cd 1.1 ± 0.2 <0.0008 1.6 ± 0.2 <0.0008 Ba 27 ± 3 0.0344 ± 0.0001 36 ± 1 0.0024 ± 0.02 Pb 1.5 ± 0.2 <0.0009 1.6 ± 0.1 <0.0009 Th 0.9 ± 0.1 <0.0013 1.1 ± 0.1 <0.0013 U 2.5 ± 0.3 <0.0012 2.9 ± 0.2 <0.0012 Figure 4. XRD of the samples PGAB: calcite (above) and PGAS: katoite precipitate (below). C: Calcite, Q: Quartz, K: Katoite, T: Thenardite. (c) Carbonation. The XRD pattern of the carbonated sample (Figure 4) presents the calcite reflections accompanied by those of the remaining quartz impurities from the PG. No thenardite reflections were observed, confirming its complete dissolution during the carbonation process. However, the XRF analysis (Table 1) revealed the presence of substantial contents of certain chemical species not detected by XRD, indicating their amorphous character. These were mainly Al and S, and to a lesser extent, Na. The contents of trace elements present in the PGAS sample (Table 4), such as V, Cr, As, Sr, Ba, and Th were well below the concentrations in undisturbed soils. However, the concentration of Cd (1.1 ± 0.2 mg kg) exceeded the typical concentration by a factor of 12.5. In contrast, the concentration of U (2.5 ±0.3 mg/kg) was within the limit permitted for uncontaminated soils. Int. J. Environ. Res. Public Health 2020,17, 4248 16 of 17 38. Mart í nez-L ó pez, C.; Mej í a-Arcila, J.M.; Torres-Agredo, J. Mej í a-de-Guti é rrez, R. Evaluation of the toxicity characteristics of two industrial wastes valorized by geopolymerization process. DYNA 2015 ,190, 74. [CrossRef] 39. Mac í as, F.; P é rez-L ó pez, R.; Ruiz-C á novas, C.; Carrero, S.; Cruz-Hern á ndez, P. Environmental assessment and management of phosphogypsum according to european and United States of America regulation. Procedia Earth Planet. Sci. 2017,17, 666–669. [CrossRef] 40. Ruiz-C á novas, C.; P é rez-L ó pez, R.; Mill á n, R.; Nieto, J.M. Preliminary study of Huelva phosphogypsum stacks as a potential source of elements of economic interest. Geogaceta 2017,62, 103–106. 41. Suárez, F.M.; Perez-Lopez, R.; Ruiz-Canovas, C. Evaluación Ambiental de los Fosfoyesos de Huelva Según Normativas de Europa y Norteamérica. Mineral. Soc. J. 2015,20, 85–86. [CrossRef] 42. UNE-EN 459-2: 1994. Cement and Lime Test Methods. Part 1. Determination of Mechanical Resistance; UNE-EN: Madrid, Spain, 1994. 43. UNE-EN 196-2: 2014. Cement and Lime Test Methods. Part 2: Chemical Analysis of Cements; UNE-EN: Madrid, Spain, 2014. 44. Carvalho, F.P. Disposal of phosphogypsum waste containing enhanced levels of radioactivity. In Proceedings of the International Last Conference on Management of Radioactive Waste from non-power applications–Sharing the IAEA-CN-87/6, Saint Paul’s Bay, Malta, 5–9 November 2001; pp. 67–68. 45. Bolivar, J.P.; Garc í a-Tenorio, R.; Garcia-Leon, M. On the fractionation of natural radioactivity in the production of phosphoric acid by the wet acid method. J. Radioanal. Nucl. Chem. 1996,214, 77–78. [CrossRef] 46. International Atomic Energy Agency-Annual Report for 2004. Available online: https://www.iaea.org/es/ publications/reports/annual-report-2004 (accessed on 10 December 2019). 47. US-EPA. Recommended Water Quality Criteria. 2002. Available online: https://www.elaw.org/es/content/us- %E2%80%93-us-epa-national-recommended-water-quality-criteria-2002 (accessed on 10 December 2019). 48. US-EPA. Guidelines for Exposure Assessment. 1992. Available online: https://cfpub.epa.gov/ncea/risk/ recordisplay.cfm?deid=15263 (accessed on 10 December 2019). 49. US-EPA. National Primary Drinking Water Regulations; Radionuclides; Final Rule. Part II. 40 CFR Parts 9, 141, and 142. 2000. Available online: https://nepis.epa.gov/Exe/ZyPURL.cgi?Dockey=2000238H.TXT (accessed on 10 December 2019). 50. Royal Decree, 314/2016, de 29 de Julio, por el que se Establecen los Criterios Sanitarios de la Calidad del Agua de Consumo Humano. Official State Gazette (State Agency BOE), n º 183 (2016), Madrid (in Spanish). Available online: https://www.boe.es/eli/es/rd/2016/07/29/314 (accessed on 10 December 2019). 51. Al Attar, L.; Al-Oudat, M.; Kanakri, S.; Budeir, Y.; Khalily, H.; Al Hamwi, A. Radiological impacts of phosphogypsum. J. Eenviron. Manag. 2011,92, 2151–2158. [CrossRef] 52. Bol í var, J.P.; Garc í a-Tenorio, R.; Vaca, F. Radio ecological study of and estuarine system located in the south of Spain. Water Res. 2000,34, 2941–2950. [CrossRef] 53. UNSCEAR. United Nations Scientific Committee on the Effects of Atomic Radiation; Sources and Effects of Ionizing Radiation: New York, NY, USA, 1993. 54. Mir ó , C.; Á vila, J.M.; Garc í a, M.; Pastor-Villegas, S.J. Riesgos debido a la radiactividad natural de pizarras de construcción. Inf. Tecnol. 2010,21, 9–16. [CrossRef] 55. EC-European Commission, Radiation Protection. 112-radiological Protection Principles Concerning the Natural Radioactivity of Building Materials, Directorate-General Environment, Nuclear Safety and Civil Protection; EC-European Commission, Radiation Protection: Brussels, Belgium, 1999. 56. Belivermis, M.; Kilic, N.; Cotuk, Y.; Topcuoglu, S. The effects of physicochemical properties on gamma emitting natural radionuclide levels in the soil profile of Istanbul. Environ. Monit. Assess. 2010 ,163, 15–26. [CrossRef] 57. Beretka, J.; Mathew, P.J. Natural radioactivity of Australian building materials, waste and byproducts. Health Phys. 1985,48, 87–95. [CrossRef] [PubMed] 58. El-Taher, A. Gamma spectroscopic analysis and associated radiation hazards of building materials used in Egypt. Radiat. Prot. Dosim. 2009,138, 166–173. [CrossRef] [PubMed] 59. G á zquez-Gonz á lez, M.J. Caracterizaci ó n y Valorizaci ó n de Residuos Generados en la Industria de Producci ó n de Dióxido de Titanio. Ph.D. Thesis, Universidad de Huelva, Huelva, Spain, 2011. Int. J. Environ. Res. Public Health 2020,17, 4248 17 of 17 60. Krieger, R. Radioactivity of construction materials. Betonw. Fert. Tech. 1981,47, 468. 61. International Commission on Radiological Protection. Internacional Commision on Radiological Protection. Recommendations of ICRP; Publication 26; Pergamon Press: Oxford, UK, 1977. © 2020 by the authors. Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (http://creativecommons.org/licenses/by/4.0/).