Uranium minerals from the San Marcos District, Chihuahua, Mexico

The mineralogy of the two uranium deposits (Victorino and San Marcos I) of Sierra San Marcos, located 30 km northwest of Chihuahua City, Mexico, was studied by optical microscopy, powder X-ray diffraction with Rietveld analysis, scanning electron microscopy with energy dispersive X-ray analysis, inductively coupled plasma spectrometry, and gamma spectrometry. At the San Marcos I deposit, uranophane Ca(UO₂)₂Si₂O₇·6(H₂O) (the dominant mineral at both deposits) and metatyuyamunite Ca(UO₂)(V₂O₈)·3(H₂O) were observed. Uranophane, uraninite (UO_2+x), masuyite Pb(UO₂)₃O₃(OH)·3(H₂O), and becquerelite Ca(UO₂)₆O₄(OH)₆ ·(8H₂O) are present at the Victorino deposit. Field observations, coupled with analytical data, suggest the following sequence of mineralization: (1) deposition of uraninite, (2) alteration of uraninite to masuyite, (3) deposition of uranophane, (4) micro-fracturing, (5) calcite deposition in the micro-fractures, and (6) formation of becquerelite. The investigated deposits were formed by high-to low-temperature hydrothermal activity during post-orogenic evolution of Sierra San Marcos. The secondary mineralization occurred through a combination of hydrothermal and supergene alteration events. Becquerelite was formed in situ by reaction of uraninite with geothermal carbonated solutions, which led to almost complete dissolution of the precursor uraninite. The Victorino deposit represents the second known occurrence of becquerelite in Mexico, the other being the uranium deposits at Peña Blanca in Chihuahua State.     

Reaction mechanism of uranyl in the presence of zero-valent iron nanoparticles

The current study provides an investigation of abiotic reduction of an oversaturated uranyl solution driven by iron nanoparticle oxidation. The reactivity of nano-scale zero-valent iron (ZVI) under mildly oxic conditions (1.2% O₂ and 0.0017% CO₂) was studied in 1000 ppm uranyl solution in the pH range 3-7, at reaction times from 10 min to 4 h. Reductive precipitation of UO₂ was observed as the main process responsible for the removal of uranium from solution with the kinetics of reaction becoming increasingly favourable at higher pH. Despite working with an oversaturated uranium solution, the precipitation of UO₂ occurred in preference to precipitation of UO₃·2H₂O (metaschoepite) at reaction times between 1 and 4 h and for uranyl solutions initially set up at pH ?5. Characterisation of both solid and solution phases was performed using X-ray photoelectron spectroscopy (XPS), focused ion beam (FIB) imaging, X-ray diffraction (XRD) and inductively coupled plasma atomic emission spectroscopy (ICP-AES).     

The effect of Si and Al concentrations on the removal of U(VI) in the alkaline conditions created by NH3 gas

Remediation of uranium in the deep unsaturated zone is a challenging task, especially in the presence of oxygenated, high-carbonate alkalinity soil and pore water composition typical for arid and semi-arid environments of the western regions of the U.S. This study evaluates the effect of various pore water constituencies on changes of uranium concentrations in alkaline conditions, created in the presence of reactive gases such as NH₃ to effectively mitigate uranium contamination in the vadose zone sediments. This contaminant is a potential source for groundwater pollution through slow infiltration of soluble and highly mobile uranium species towards the water table. The objective of this research was to evaluate uranium sequestration efficiencies in the alkaline synthetic pore water solutions prepared in a broad range of Si, Al, and bicarbonate concentrations typically present in field systems of the western U.S. regions and identify solid uranium-bearing phases that result from ammonia gas treatment. In previous studies (Szecsody et al. 2012; Zhong et al. 2015), although uranium mobility was greatly decreased, solid phases could not be identified at the low uranium concentrations in field-contaminated sediments. The chemical composition of the synthetic pore water used in the experiments varied for silica (5–250 mM), Al³⁺ (2.8 or 5 mM), HCO₃⁻ (0–100 mM) and U(VI) (0.0021–0.0084 mM) in the solution mixture. Experiment results suggested that solutions with Si concentrations higher than 50 mM exhibited greater removal efficiencies of U(VI). Solutions with higher concentrations of bicarbonate also exhibited greater removal efficiencies for Si, Al, and U(VI). Overall, the silica polymerization reaction leading to the formation of Si gel correlated with the removal of U(VI), Si, and Al from the solution. If no Si polymerization was observed, there was no U removal from the supernatant solution. Speciation modeling indicated that the dominant uranium species in the presence of bicarbonate were anionic uranyl carbonate complexes (UO₂(CO₃)₂⁻² and UO₂(CO₃)₃⁻⁴) and in the absence of bicarbonate in the solution, U(VI) major species appeared as uranyl-hydroxide (UO₂(OH)₃⁻ and UO₂(OH)₄⁻²) species. The model also predicted the formation of uranium solid phases. Uranyl carbonates as rutherfordine [UO₂CO₃], cejkaite [Na₄(UO2)(CO₃)₃] and hydrated uranyl silicate phases as Na-boltwoodite [Na(UO₂)(SiO₄)·1.5H₂O] were anticipated for most of the synthetic pore water compositions amended from medium (2.9 mM) to high (100 mM) bicarbonate concentrations.     

Alteration of uraninite from the Nopal I deposit,Pen˜a Blanca District,Chihuahua, Mexico,compared to degradation of spent nuclear fuel in the proposed U.S. high-level nuclear waste repository at Yucca Mountain,Nevada

At the Nopal I uranium deposit, primary uraninite (nominally UO_2+x) has altered almost completely to a suite of secondary uranyl minerals. The deposit is located in a Basin and Range horst composed of welded silicic tuff; uranium mineralization presently occurs in a chemically oxidizing and hydrologically unsaturated zone of the structural block. These characteristics are similar to those of the proposed U.S. high-level nuclear waste (HLW) repository at Yucca Mountain, Nevada. Petrographic analyses indicate that residual Nopal I uraninite is fine grained (5–10 μm) and has a low trace element content (average about 3 wt%). These characteristics compare well with spent nuclear fuel. The oxidation and formation of secondary minerals from the uraninite have occurred in an environment dominated by components common in host rocks of the Nopal I system (e.g. Si, Ca, K, Na and H₂O) and also common to Yucca Mountain. In contrast, secondary phases in most other uranium deposits form from elements largely absent from spent fuel and from the Yucca Mountain environment (e.g. Pb, P and V). The oxidation of Nopal I uraninite and the sequence of alteration products, their intergrowths and morphologies are remarkably similar to those observed in reported corrosion experiments using spent fuel and unirradiated UO₂ under conditions intended to approximate those anticipated for the proposed Yucca Mountain repository. The end products of these reported laboratory experiments and the natural alteration of Nopal I uraninite are dominated by uranophane [nominally Ca(UO₂)₂Si₂O₇·6H₂O] with lesser amounts of soddyite [nominally (UO₂)₂SiO₄·2H₂O] and other uranyl minerals. These similarities in reaction product occurrence developed despite the differences in time and physical—chemical environment between Yucca Mountain-approximate laboratory experiments and Yucca Mountain-approximate uraninite alteration at Nopal I, suggesting that the results may reasonably represent phases likely to form during long-term alteration of spent fuel in a Yucca Mountain repository. From this analogy, it may be concluded that the likely compositional ranges of dominant spent fuel alteration phases in the Yucca Mountain environment may be relatively limited and may be insensitive to small variations in system conditions.     

Dissolution of uranophane: An AFM, XPS, SEM and ICP study

Dissolution experiments on single crystals of uranophane and uranophane-β, Ca(H₂O)₅[(UO₂)(SiO₃(OH)]₂, from the Shinkolobwe mine of the Democratic Republic of Congo, were done in an aqueous HCl solution of pH 3.5 for 3 h, in HCl solutions of pH 2 for 5, 10 and 30 min, and in Pb²⁺-, Ba-, Sr-, Ca- and Mg-HCl solutions of pH 2 for 30 min. The basal surfaces of the treated uranophane crystals were examined using atomic-force microscopy (AFM), X-ray photoelectron spectroscopy (XPS) and scanning electron microscopy (SEM). Solutions after dissolution experiments on single crystals and synthetic powders were analysed with inductively coupled plasma-optical emission spectroscopy (ICP-OES) and mass spectroscopy (ICP-MS). The morphology of the observed etch pits (measured by AFM) were compared to the morphology, predicted on the basis of the bond-valence deficiency of polyhedron chains along the edges of the basal surface. Etch pits form in HCl solutions of pH 2. Their decrease in depth with the duration of the dissolution experiment is explained with the stepwave dissolution model, which describes the lowering of the surrounding area of an etch pit with continuous waves of steps emanated from the etch pit into the rest of the crystal surface. Hillocks form in an HCl solution of pH 3.5, and the chemical composition of the surface (as indicated by XPS) shows that these hillocks are the result of the precipitation of a uranyl-hydroxy-hydrate phase. Well-orientated hillocks form on the surface of uranophane in a SrCl₂-HCl solution of pH 2. They are part of an aged silica coating of composition Si₂O₂(OH)₄(H₂O)_n. An amorphous layer forms on the surface of uranophane in a MgCl₂-HCl solution of pH 2, which has a composition and structure similar to silicic acid. Small crystallites of uranyl-hydroxy-hydrate phases form on the surface of uranophane after treatment in Pb(NO₃)₂-HCl and BaCl₂-HCl solutions of pH 2. Dissolution experiments on synthetic uranophane powders show that in the early stage of the experiments, the dissolution rate of uranophane increase in the sequence Pb(NO₃)₂-HCl < BaCl₂-HCl < CaCl₂-HCl < HCl < SrCl₂-HCl < MgCl₂-HCl, indicating that the dissolution of uranophane is more enhanced in solutions containing divalent cations of small ionic radii and high Lewis acidity (Mg, MgCl⁺).     

Uranophane dissolution and growth in CaCl2-SiO2(aq) test solutions

The dissolution and growth of uranophane [Ca(UO₂)₂(SiO₃OH)₂·5H₂O] have been examined in Ca- and Si-rich test solutions at low temperatures (20.5 ± 2.0 °C) and near-neutral pH (∼6.0). Uranium-bearing experimental solutions undersaturated and supersaturated with uranophane were prepared in matrices of ∼10⁻² M CaCl₂ and ∼10⁻³ M SiO₂(aq). The experimental solutions were reacted with synthetic uranophane and analyzed periodically over 10 weeks. Interpretation of the aqueous solution data permitted extraction of a solubility constant for the uranophane dissolution reaction and standard state Gibbs free energy of formation for uranophane ( kJ mol⁻¹).     

Uranium-rich opal from the Nopal I uranium deposit, Peña Blanca, Mexico: Evidence for the uptake and retardation of radionuclides

The Nopal I uranium deposit of the Sierra Peña Blanca, Mexico, has been the focus of numerous studies because of its economic importance and its use as a natural analog for nuclear-waste disposal in volcanic tuff. Secondary uranyl minerals such as uranophane, Ca[(UO₂)(SiO₃OH)]₂(H₂O)₅, and weeksite, (K,Na)₂[(UO₂)₂(Si₅O₁₃)](H₂O)₃, occur in the vadose zone of the deposit and are overgrown by silica glaze. These glazes consist mainly of opal A, which contains small particles of uraninite, UO₂, and weeksite. Close to a fault between brecciated volcanic rocks and welded tuff, a greenish silica glaze coats the altered breccia. Yellow silica glazes from the center of the breccia pipe and from the high-grade pile coat uranyl-silicates, predominantly uranophane and weeksite. All silica glazes are strongly zoned with respect to U and Ca, and the distribution of these elements indicates curved features and spherical particles inside the coatings. The concentrations of U and Ca correlate in the different zones and both elements inversely correlate with the concentration of Si. Zones within the silica glazes contain U and Ca in a 1:1 ratio with maximum concentrations of 0.08 and 0.15 at.% for the greenish and yellow glazes, respectively, suggesting trapping of either Ca₁U₁-aqueous species or -particles in the colloidal silica. X-ray photoelectron spectroscopy (XPS), Fourier-transform infra-red spectroscopy (FTIR), and oxygen-isotope ratios measured by secondary-ion mass spectrometry (SIMS) indicate higher U⁶⁺/U⁴⁺ ratios, higher proportions of Si-OH groups and lower δ¹⁸O values for the greenish silica glaze than for the yellow silica glaze. These differences in composition reflect increasing brecciation, porosity, and permeability from the center of the breccia pipe (yellow silica glaze) toward the fault (green silica glaze), where the seepage of meteoric water and Eh are higher.     

Crystal chemistry of selenates with mineral-like structures. VI. Hydrogen bonds in the crystal structure of [(H5O2)(H3O)(H2O)][(UO2)(SeO4)2]

The crystal structure of a new compound, [(H₅O₂)(H₃O)(H₂O)][(UO₂)(SeO₄)₂] (monoclinic, P2₁/n a = 8.3105(15), b = 11.0799(14), c = 13.227(2) Å, β = 103.880(13)°, V = 1182.4(3) ų), has been solved by direct methods and refined to R ₁ = 0.036. The structure is based on [(UO₂)(SeO₄)₂]^2? sheet complexes formed by corner-shared UO₇ pentagonal bipyramids and SeO₄ tetrahedrons. The sheets are parallel to the ( $ \bar 1 The crystal structure of a new compound, [(H₅O₂)(H₃O)(H₂O)][(UO₂)(SeO₄)₂] (monoclinic, P2₁/n a = 8.3105(15), b = 11.0799(14), c = 13.227(2) ?, β = 103.880(13)°, V = 1182.4(3) ?³), has been solved by direct methods and refined to R ₁ = 0.036. The structure is based on [(UO₂)(SeO₄)₂]²⁻ sheet complexes formed by corner-shared UO₇ pentagonal bipyramids and SeO₄ tetrahedrons. The sheets are parallel to the (01) plane. Oxonium ions and water molecules forming [(H₃O)·(H₂O)·(H₅O₂)]²⁺ complexes are interlayer. Among minerals, the existence of (H₅O₂)⁺ has been unambiguously confirmed only in rhomboclase, (H₅O₂)⁺[Fe₂(SO₄)₂(H₂O)₂]. Original Russian Text ? S.V. Krivovichev, 2008, published in Zapiski Rossiiskogo Mineralogicheskogo Obshchestva, 2008, No. 2, pp. 123–130.     

The crystal structure of meta-uranocircite II,Ba(UO2)2(PO4)2·6H2O

Summary The crystal structure of meta-uranocircite II, Ba(UO₂)₂(PO₄)₂·6H₂O, has been determined with a synthetic crystal using three-dimensional X-ray techniques.R=0.071 andR _w =0.064 were obtained for 1743 observed reflections. Ba(UO₂)₂(PO₄)₂·6H₂O is monoclinic, space groupP112₁/a, a=9.789,b=9.822,c=16.868 Å, =89.95° andZ=4. The structure consists of slightly corrugated UO₂PO₄ layers parallel (001). The layers are connected by Ba atoms and H₂O molecules. Uranium exhibits a (2+4)-coordination with mean U-O bond lengths of 1.78 Å for the uranyl oxygens and 2.28 Å for the phosphate oxygens. The average P-O bond length is 1.52 Å. Barium is coordinated by two uranyl oxygens. two phosphate oxygens and five water molecules. The Ba–O bond lengths vary from 2.74 to 3.11 Å. Two of the six water molecules of the formula are not bonded to barium.

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Die Kristallstruktur des Meta-Uranocircits II, Ba(UO₂)₂(PO₄)₂·6H₂O

Zusammenfassung Die Kristallstruktur des Meta-Uranocircits II, Ba(UO₂)₂(PO₄)₂·6H₂O, wurde anhand eines künstlichen Kristalls mit dreidimensionalen Röntgendaten bearbeitet und für 1743 Reflexe aufR=0,071 undR _w =0,064 verfeinert. Ba(UO₂)₂(PO₄)₂·6H₂O kristallisiert monoklin in der RaumgruppeP112₁/a, a=9,789,b=9,882,c=16,868 Å, =89,95° und einem Zellinhalt von vier Formeleinheiten. Die Struktur besteht aus schwach gewellten UO₂PO₄-Schichten parallel (001), die durch Ba-Atome und H₂O-Moleküle miteinander verknüpft sind. Uran besitzt oktaedrische (2+4)-Koordination mit mittleren U-O-Abständen von 1,78 Å für die Uranylsauerstoffatome und 2,28 Å für die Phosphatsauerstoffatome. Die P-O-Abstände der Phosphattetraeder messen im Mittel 1.52 Å. Barium ist von je zwei Uranyl- und Phosphatsauerstoffatomen sowie von fünf Wassermolekülen koordiniert. Die Ba-O-Abstände betragen 2,74–3,11 Å. Von den sechs H₂O-Molekülen der Formel sind zwei nicht an Barium gebunden.

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Crystal chemistry of selenates with mineral-like structures: V. Crystal structures of (H3O)2[(UO2)(SeO4)2(H2O)](H2O)2 and (H3O)2[(UO2)(SeO4)2(H2O)](H2O), new compounds with rhomboclase and goldichite topology

The crystal structures of two new compounds (H₃O)₂[(UO₂)(SeO₄)₂(H₂O)](H₂O)₂ (1, orthorhombic, Pnma, a = 14.0328(18), b = 11.6412(13), c = 8.2146(13) Å, V = 134.9(3) ų) and (H₃O)₂[(UO₂)(SeO₄)₂(H₂O)](H₂O) (2, monoclinic, P2₁/c, a = 7.8670(12), b = 7.5357(7), c = 21.386(3) Å, β = 101.484(12)°, V = 1242.5(3) ų) have been solved by direct methods and refined to R ₁ = 0.076 and 0.080, respectively. The structures of both compounds contain sheet complexes [(UO₂)(SeO₄)₂]^2? formed by cornershared [(UO₂)O₄(H₂O)] bipyramids and SeO₄ tetrahedrons. The sheets are parallel to the (100) plane in structure 1 and to (?102) in structure 2. The [(UO₂)(SeO₄)₂(H₂O)]^2? layers are linked by hydrogen bonds via interlayer groups H₂O and H₃O⁺. The sheet topologies in structures 1 and 2 are different and correspond to the topologies of octahedral and tetrahedral complexes in rhomboclase (H₂O₂)⁺[Fe(SO₄)₂(H₂O)₂] and goldichite K[Fe(SO₄)₂(H₂O)₂](H₂O)₂, respectively.     

Transformation of synthetic U3O8 into different uranium oxide hydrates

Summary Referring to the natural formation of secondary uranium minerals, the primary transformation of U₃O₈ into schoepite has been investigated. The transformation is realized in a continuous system with O₂, CO₂ and H₂O. At 100°C schoepite III, UO₃ · zH₂O (z 1), is formed (a = 14.12; b = 16.83; c = 15.22 Å) with a density of 4.460 g/cm³. At 25°C a mixture of schoepite II (UO₃ · yH₂O, 1 < y < 2; a = 13.99; b = 16.72; c = 14.73 Å) and schoepite I (UO₃ · xH₂O, x 2; a = 14.33; b = 16.79; c = 14.73 Å) is obatined. From thermogravimetric analysis the activation energy of dehydration for schoepite III is determined as 49(3) · 10³ J/mole.

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Umwandlung von synthetischem U₃O₈ in verschiedene Uranoxidhydrate

Zusammenfassung In Hinblick auf die natürliche Bildung sekundärer Uranminerale wurde die primäre Umwandlung von U₃O₈ in Schoepit untersucht. Die Umwandlung wurde in einem kontinuierlichen System mit O₂, CO₂ und H₂O bewerkstelligt. Bei 100°C bildet sich Schoepit III (UO₃ · zH₂O, z 1; a = 14.12, b = 16.83, c = 15.22 Å; Dichte: 4.460 g/cm³). Bei 25°C wird eine Mischung von Schoepit II (UO₃ · yH₂O, 1 < y < 2; a = 13.99, b = 16.72, c = 14.73 Å) und Schoepit I (UO₃ · xH₂O, x 2; a = 14.33, b = 16.79, c = 14.73 Å) erhalten. Aus der thermogravimetrischen Analyse wurde die Aktivierungsenergie der Dehydratation von Schoepit III mit 49(3) · 10³ J/mole berechnet.

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Who wishes to dedicate the paper to the memory of his father, Hendrik Vochten.

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The effect of calcium on aqueous uranium(VI) speciation and adsorption to ferrihydrite and quartz

Recent studies of uranium(VI) geochemistry have focused on the potentially important role of the aqueous species, CaUO₂(CO₃)₃²⁻ and Ca₂UO₂(CO₃)₃⁰(aq), on inhibition of microbial reduction and uranium(VI) aqueous speciation in contaminated groundwater. However, to our knowledge, there have been no direct studies of the effects of these species on U(VI) adsorption by mineral phases. The sorption of U(VI) on quartz and ferrihydrite was investigated in NaNO₃ solutions equilibrated with either ambient air (430 ppm CO₂) or 2% CO₂ in the presence of 0, 1.8, or 8.9 mM Ca²⁺. Under conditions where the Ca₂UO₂(CO₃)₃⁰(aq) species predominates U(VI) aqueous speciation, the presence of Ca in solution lowered U(VI) adsorption on quartz from 77% in the absence of Ca to 42% and 10% at Ca concentrations of 1.8 and 8.9 mM, respectively. U(VI) adsorption to ferrihydrite decreased from 83% in the absence of Ca to 57% in the presence of 1.8 mM Ca. Surface complexation model predictions that included the formation constant for aqueous Ca₂UO₂(CO₃)₃⁰(aq) accurately simulated the effect of Ca²⁺ on U(VI) sorption onto quartz and ferrihydrite within the thermodynamic uncertainty of the stability constant value. This study confirms that Ca²⁺ can have a significant impact on the aqueous speciation of U(VI), and consequently, on the sorption and mobility of U(VI) in aquifers.     

The crystal structure of Liebigite,Ca2UO2(CO3)3·∼11H2O

Summary The crystal structure of liebigite, previously only incompletely known from a short note, has been determined from X-ray 4-circle diffractometer data and refined toR=0.030 for 3005 observed reflections. Liebigite from Joachimsthal, Böhmen, was used. It was found to crystallize in the polar orthorhombic space groupBba2–C _2v ¹⁷ witha=16.699(3),b=17.557(3),c=13.697(3) Å,V=4016 ų and a cell content of 8 Ca₂UO₂(CO₃)₃·11H₂O. The structure contains UO₂(CO₃)₃ units which are linked by two kinds of CaO₄(H₂O)₄ polyhedra and one kind of CaO₃(H₂O)₄ polyhedron to form puckered Ca₂UO₂(CO₃)₃·8H₂O layers parallel to (010). These layers are interconnected only by hydrogen bonds, both directly as well as via three additional interlayer H₂O molecules, two of which show positional disorder.

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Die Kristallstruktur des Liebigits, Ca₂UO₂(CO₃)₃·11H₂O

Zusammenfassung Die Kristallstruktur des Minerals Liebigit, die bis jetzt nur unzureichend bekannt war, wurde mit Röntgen-Vierkreisdiffraktometer-Daten bestimmt und für 3005 beobachtete Reflexe aufR=0,030 verfeinert. Der untersuchte, von Joachimsthal, Böhmen, stammende Liebigit kristallisiert in der polaren rhombischen RaumgruppeBba2–C _2v ¹⁷ mita=16,699(3),b=17,557(3),c=13,697(3) Å,V=4016 ų und einem Zellinhalt von 8 Ca₂UO₂(CO₃)₃·11H₂O. Die Struktur enthält UO₂(CO₃)₃-Gruppen, die durch zwei Arten von CaO₄(H₂O)₄-Polyedern und eine Art von CaO₃(H₂O)₄-Polyedern zu buckeligen Ca₂UO₂(CO₃)₃·8H₂O-Schichten parallel (010) verknüpft sind. Diese Schichten sind nur durch Wasserstoffbrücken verbunden, und zwar sowohl direkt als auch mittels dreier zusätzlicher freier Wassermoleküle, von denen zwei eine Lagenfehlordnung aufweisen.

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The dissolution of synthetic Na-boltwoodite in sodium carbonate solutions

Uranyl silicates such as uranophane and Na-boltwoodite appear to control the solubility of uranium in certain contaminated sediments at the US Department of Energy Hanford site [Liu, C., Zachara, J.M., Qafoku, O., McKinley, J.P., Heald, S.M., Wang, Z. 2004. Dissolution of uranyl microprecipitates in subsurface sediments at Hanford Site, USA. Geochim. Cosmochim. Acta68, 4519-4537.]. Consequently, the solubility of synthetic Na-boltwoodite, Na(UO₂)(SiO₃OH) · 1.5H₂O, was determined over a wide range of bicarbonate concentrations, from circumneutral to alkaline pH, that are representative of porewater and groundwater compositions at the Hanford site and calcareous environments generally. Experiments were open to air. Results show that Na-boltwoodite dissolution was nearly congruent and its solubility and dissolution kinetics increased with increasing bicarbonate concentration and pH. A consistent set of solubility constants were determined from circumneutral pH (0 added bicarbonate) to alkaline pH (50 mM added bicarbonate). Average or 5.85 ± 0.0.26; using the Pitzer ion-interaction model or Davies equation, respectively. These values are close to the one determined by [Nguyen, S.N., Silva, R.J., Weed, H.C., Andrews, Jr., J.E., 1992. Standard Gibbs free energies of formation at the temperature 303.15 K of four uranyl silicates: soddyite, uranophane, sodium boltwoodite, and sodium weeksite. J. Chem. Thermodynamics24, 359-376.] under very different conditions (pH 4.5, Ar atmosphere).     

The crystal structure of walpurgite, (UO2)Bi4O4(AsO4)2·2H2O

Summary The crystal structure of walpurgite has been determined from three-dimensional X-ray single crystal data and has been refined toR=0.041 for 1381 independent reflections using a crystal from Schneeberg, Sachsen. Walpurgite crystallizes triclinic, space group , witha=7.135 (2),b=10.426 (4),c=5.494 (1) Å, =101 47 (2), =110.82 (2), =88.20 (2)^o andV-374 A³. Cell content and chemical formula are (UO₂)Bi₄O₄(AsO₄)₂·2H₂O, which is one H₂O less than previously known. The structure consists of complex layers Bi₄O₄(AsO₄)₂·2H₂O extending parallel to (010). Each layer is built up from a network of bismuth and oxygen atoms, to both sides of which AsO₄ groups and water molecules are attached. (UO₂)O₄ octahedra link the layers parallel tob via the AsO₄ groups and thus simultaneously from UO₂(AsO₄)₂ chains parallel toc. The two independent Bi atoms are trivalent and form pronounced one-sided BiO polyhedra: 4–5 oxygens are at distances of 2.11–2.48 Å, 4 additional oxygens are at distances of 2.63–3.35 Å.

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Die Kristallstruktur des Walpurgins, (UO₂)Bi₄O₄(AsO₄)₂·2H₂O

Zusammenfassung Die Kristallstruktur des Walpurgins wurde anhand eines Kristalls von Schneeberg, Sachsen, mit dreidimensionalen Röntgen-Einkristalldaten bestimmt und für 1381 Reflexe aufR=0,041 verfeinert. Walpurgin kristallisiert triklin, Raumgruppe ,a=7,135 (2),b=10,426 (4),c=5,494 (1) Å, =101,47 (2), =110,82 (2), =88,20 (2)^o undV=374 ų. Zellinhalt und chemische Formel lauten (UO₂)Bi₄O₄(AsO₄)₂·2H₂O, das ist um ein H₂O-Molekül weniger als bislang bekannt. Die Struktur enthält kompliziert gebaute Bi₄O₄(AsO₄)₂·2H₂O-Schichten, die sich parallel (010) erstrecken. Jede Schicht besteht aus einem Netz von Wismut- und Sauerstoffatomen, an das zu beiden Seiten AsO₄-Gruppen und H₂O-Moleküle anknüpfen. (UO₂)O₄-Oktaeder verbinden die Schichten über die AsO₄-Gruppen parallel zub und bilden so gleichzeitig (UO₂)(AsO₄)₂-Ketten parallel zuc aus. Die zwei unabhängigen, dreiwertigen Wismutatome des Walpurgins sind von 4–5 Sauerstoffatomen in Abständen von 2,11–2,48Å einseitig koordiniert und darüber hinaus noch von vier weiteren Sauerstoffatomen in Abständen von 2,63–3,35 Å umgeben.

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With 4 Figures     

Experimental determination of uranium (IV) speciation in HF solutions at 500°C and 1000 bar

Uraninite solubility in HF solutions (0.0001–0.5 m) was experimentally studied at 500°C, 1000 bar, and hydrogen fugacity corresponding to the Ni/NiO buffer. It was shown that the predominant U(IV) species in aqueous solution are U(OH)₄⁰, U(OH)₃F⁰, and U(OH)₂ F₂⁰. Using the results of uraninite solubility measurement, the Gibbs free energies of the uranium (IV) species were calculated at 500°C and 1000 bar (kJ/mol): −986.55 for UO₂(aq), −1712.42 for U(OH)₃F⁰, −1755.53 for U(OH)₂F₂⁰, and the equilibrium constants of the uraninite solubility in water and HF solutions were estimated: UO₂(κ) = UO₂(aq), which is similar to UO₂(cr) + 2H₂O = U(OH)₄⁰, pK₀ = 6.64; UO₂(cr) + HF⁰ + H₂O = U(OH)₃F⁰, K₁ = 0.0513; UO₂(cr) + 2HF⁰ = U(OH)₂F₂⁰K₂ = 7.00 × 10⁻⁴. Approximate values K₃ = 5.75 × 10⁻³ and K₄ = 6.7 × 10⁻² were obtained for equilibria UO₂(cr) + 4HF⁰ =UF₄⁰ + 2H₂O and UO₂(cr) + 4HF = UF₄⁰ + 2H₂O. Maximum observed in the uranium concentration curve as a function of HF concentration can be explained by the decrease (to < 1) of activity coefficient ratio of HF⁰ to U(OH)₃F⁰ with increasing HF concentrations.     

Die Kristallstruktur des Johannits,Cu(UO2)2(OH)2(SO4)2·8H2O

Zusammenfassung Die Kristallstruktur des Johannits wurde anhand eines verzwillingten Kristalls von Joachimsthal, Böhmen, mit dreidimensionalen Röntgendaten bestimmt und für 2005 unabhängige Reflexe aufR=0,039 verfeinert. Johannit kristallisiert triklin, RaumgruppeP1, mita=8,903 (2),b=9,499 (2),c=6,812 (2) Å, =109,87 (1) =112,01 (1), =100,40 (1)° undV=469,9 ų. Chemische Formel und Zellinhalt lauten Cu(UO₂)₂(OH)₂(SO₄)₂·8H₂O, das ist um zwei H₂O-Moleküle mehr als bisher angenommen. In der Struktur sind pentagonal dipyramidale (UO₂)(OH)₂O₃-Polyeder paarweise über eine von zwei OH-Gruppen gebildete Kante zu Doppelpolyedern und diese wiederum durch SO₄-Gruppen zu (UO₂)₂(OH)₂(SO₄)₂-Schichten parallel (100) verknüpft. Die Schichten sind parallel über gestreckte Cu(H₂O)₄O₂-Oktaeder und Wassermoleküle miteinander verbunden. Folgende Bindungslängen wurden gefunden: U–O=1,78 Å (2x) und 2,34–2,39 Å (5x); Cu–O=1,97 Å (4x) und 2,40 Å (2x); =1,47 Å; O–O in Wasserstoffbrücken 2,71–2,91 Å (8x) und 3,30 Å.

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The crystal structure of johannite, Cu(UO₂)₂(OH)₂(SO₄)₂·8H₂O

Summary The crystal structure of johannite has been determined from threedimensional X-ray data measured on a twinned crystal from Joachimsthal, Böhmen, and has been refined toR=0.039 for 2005 independent reflections. Johannite crystallizes triclinic, space groupP1, witha=8.903 (2),b=9.499 (2),c=6.812 (2) Å, =109.87(1), =112.01(1), =100.40 (1)° andV=469.9 ų. Chemical formula and cell content are Cu(UO₂)₂(OH)₂(SO₄)₂·8H₂O, by two H₂O molecules more than previously assumed. Pairs of pentagonal dipyramidal (UO₂) (OH)₂O₃ polyhedra form double polyhedra by edgesharing via two OH groups. The double polyhedra are linked by the SO₄ tetrahedra to form layers (UO₂)₂(OH)₂(SO₄)₂ parallel zu (100). These layers are interconnected parallel toa by elongated Cu(H₂O)₄O₂ octahedra and water molecules. Following bond lengths have been observed: U–O=1.78 Å (2x) and 2.34–2.39 Å (5x); Cu–O=1.97 Å (4x) and 2.40 Å (2x); =1.47 Å; O–O for hydrogen bonds 2.71–2.91 Å (8x) and 3.30 Å.

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Mit 2 Abbildungen     

On the space group of threadgoldite

Summary It is shown that the crystal structure of the autunite group mineral threadgoldite, Al(UO₂)₂(PO₄)₂(OH)·8H₂O, recently determined byPiret et al. (1979) in the acentric space groupCc, can be better described and refined in the centrosymmetric space groupC2/c. The bond distances thus obtained are more reasonable than the previous ones.

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Zur Raumgruppe des Minerals Threadgoldit

Zusammenfassung Es wird gezeigt, daß die Kristallstruktur des Uranglimmer-Minerals Threadgoldit, Al(UO₂)₂(PO₄)₂(OH)·8H₂O, die kürzlich vonPiret et al. (1979) unter Verwendung der nichtzentrosymmetrischen RaumgruppeCc bestimmt wurde, besser in der zentrosymmetrischen RaumgruppeC2/c zu beschreiben und verfeinern ist. Die so erhaltenen Bindungslängen sind kristallchemisch plausibler als die zuvor gefundenen Werte.

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With 1 Figure     

Surface complexation of U(VI) on goethite (α-FeOOH)

Sorption of U(VI) to goethite is a fundamental control on the mobility of uranium in soil and groundwater. Here, we investigated the sorption of U on goethite using EXAFS spectroscopy, batch sorption experiments and DFT calculations of the energetics and structures of possible surface complexes. Based on EXAFS spectra, it has previously been proposed that U(VI), as the uranyl cation , sorbs to Fe oxide hydroxide phases by forming a bidentate edge-sharing (E2) surface complex, >Fe(OH)₂UO₂(H₂O)_n. Here, we argue that this complex alone cannot account for the sorption capacity of goethite (α-FeOOH). Moreover, we show that all of the EXAFS signal attributed to the E2 complex can be accounted for by multiple scattering. We propose that the dominant surface complex in CO₂-free systems is a bidentate corner-sharing (C2) complex, (>FeOH)₂UO₂(H₂O)₃ which can form on the dominant {101} surface. However, in the presence of CO₂, we find an enhancement of UO₂ sorption at low pH and attribute this to a (>FeO)CO₂UO₂ ternary complex. With increasing pH, U(VI) desorbs by the formation of aqueous carbonate and hydroxyl complexes. However, this desorption is preceded by the formation of a second ternary surface complex (>FeOH)₂UO₂CO₃. The three proposed surface complexes, (>FeOH)₂UO₂(H₂O)₃, >FeOCO₂UO₂, and (>FeOH)₂UO₂CO₃ are consistent with EXAFS spectra. Using these complexes, we developed a surface complexation model for U on goethite with a 1-pK model for surface protonation, an extended Stern model for surface electrostatics and inclusion of all known UO₂-OH-CO₃ aqueous complexes in the current thermodynamic database. The model gives an excellent fit to our sorption experiments done in both ambient and reduced CO₂ environments at surface loadings of 0.02-2.0 wt% U.     

Crystallization of sodium sulfate phases in porous materials: The phase diagram Na2SO4-H2O and the generation of stress

Mechanical disintegration by crystal growth of salts in pores is generally considered as an important mechanism of rock breakdown both on Earth and on Mars. Crystal growth is also a major cause of damage in porous building materials. Sodium sulfate is the most widely used salt in accelerated weathering tests of natural rocks and building materials. This paper provides an updated phase diagram of the Na₂SO₄-H₂O system based on a careful review of the available thermodynamic data of aqueous sodium sulfate and the crystalline phases. The phase diagram includes both the stable phases thenardite, Na₂SO₄(V), and mirabilite, Na₂SO₄·10H₂O, and, the metastable phases Na₂SO₄(III) and Na₂SO₄·7H₂O. The phase diagram is used to discuss the crystallization pathways and the crystallization pressures generated by these solids in common laboratory weathering experiments and under field conditions. New crystallization experiments carried out at different temperatures are presented. A dilatometric technique is used to study the mechanical response of sandstone samples in typical wetting-drying experiments as in the standard salt crystallization test. Additional experiments with continuous immersion and evaporation were carried out with the same type of sandstone. Both, the theoretical treatment and the results of the crystallization experiments confirm that the crystallization of mirabilite from highly supersaturated solutions is the most important cause of damage of sodium sulfate in porous materials.