Modelling the alteration gel composition of simplified borosilicate glasses by precipitation of an ideal solid solution in equilibrium with the leachant

Munier, Isabelle; Crovisier, J. L.; Grambow, Bernd; Fritz, Bertrand; Clément, Alain

doi:10.1016/j.jnucmat.2003.08.033

Cited by 32 publications

(26 citation statements)

References 58 publications

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“…This concentration enables to be oversaturated with respect to chalcedony for all experimental conditions. A previous study showed that silicon concentration measured in solution is close to that of chalcedony [14]. The different experiments are listed in Table 2.…”

Section: Methodsmentioning

confidence: 78%

Solid state diffusion during nuclear glass residual alteration in solution

Chave¹,

Frugier²,

Ayral³

et al. 2007

Journal of Nuclear Materials

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Section: Methodsmentioning

confidence: 78%

Solid state diffusion during nuclear glass residual alteration in solution

Chave¹,

Frugier²,

Ayral³

et al. 2007

Journal of Nuclear Materials

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“…Element concentrations often are under the detection level and/or rarely reach concentrations encountered in the blanks. Despite pure water does not buffer the experiment and that pH can evolve during leaching [25,31], some pH analyses indicate a pH near pure water which is relevant with emission spectroscopy measurements. Considering flow rate and water volume in the container, it can be assumed that residence time is very low in the container (i.e.…”

Section: Leachate Chemistrymentioning

confidence: 98%

“…They revealed that glass dissolution rate strongly vary depending on factors such as pH [14,15], temperature [16,17], elements in solution (Zn [18]; Pb [19]; Fe [20], Si [15,21], Al [22,23], S/V ratio [24,25] flow rate [26][27][28] and glass composition [29][30][31][32].…”

Section: Introductionmentioning

confidence: 99%

Effect of Pb-rich and Fe-rich entities during alteration of a partially vitrified metallurgical waste

Seignez

Gauthier

Bulteel

et al. 2007

Journal of Hazardous Materials

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“…Glass specimens were prepared after the glass powder was ultrasonically cleaned in deionized water and allowed to dry at 90 0 C for 24 hours. The specific area and density of each specimen was determined by BET (Krypton) measurements [39]. These values are of obtained are in the order of 663cm 2 /g and 2.405 g/cm 3 , respectively.…”

Section: Obsidian Glassmentioning

confidence: 99%

“…Glass specimens of 100 -120 m size granule was prepared and ultrasonically cleaned in deionized water and allowed to dry at 90 0 C for 24 hours. The specific area and density of specimen was determined by BET (Krypton) measurements [39]. …”

Section: Waste Glassmentioning

confidence: 99%

Corrosion Mechanism in the Obsidian and its Comparison with the Nuclear Waste Glass for Long-Term Performance Assessment in the Geological Repository~!2009-08-04~!2009-10-08~!2010-03-16~!

Rani¹,

Shrivastava²,

Bajpai³

2010

TOCORRJ

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Present paper discusses experimental work on obsidian glass to understand corrosion mechanism at variable pressure temperature conditions. For comparison, Advanced Vitrification System, a nuclear waste glass was studied simultaneously under similar conditions. Owing to massive weight loss the glass samples were unable to sustain beyond 4 hour during the experiments. Corrosion experiments on both these glasses were performed under hydrothermal like conditions and observed that the changes in the experimental conditions have major control over the release of sodium and other ions from obsidian and nuclear waste glass, hence effecting corrosion mechanism. X-ray diffraction patterns of the residue obtained after the experiments on obsidian glass revealed appearance of neo-formed minerals, such as quartz, celadonite, halloysite, sodalite, heulandites and wairakite. High degree of corrosion and formation of amorphous residue observed in case of the experiments performed at 300 0 C over the granules of the nuclear waste glass. The back scattered electron images of the scanning electron microscope indicate distinctive microstructures, associated with the neo-formed minerals, and their formation is linked with the release of sodium, potassium and other ions, causing changes in the pH and conductivity of the leachate. In case of nuclear waste glass back scattered images of the scanning electron microscope indicates formation of multiple alteration layers and secondary alteration products. The surface of the pellet after the experiment shows phyllosilicate with numerous tiny spherules embedded within the structure. These experimental results when extrapolated suggest formation of amorphous silica, quartz and chalcedony as end members in case of obsidian glass whereas, formation of iron rich fayalite and greenalite can be observed in case of nuclear waste glass. The mechanism, conditions of formation of neo-formed minerals and their stability have been discussed in the paper.

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Modelling the alteration gel composition of simplified borosilicate glasses by precipitation of an ideal solid solution in equilibrium with the leachant

Cited by 32 publications

References 58 publications

Solid state diffusion during nuclear glass residual alteration in solution

Solid state diffusion during nuclear glass residual alteration in solution

Effect of Pb-rich and Fe-rich entities during alteration of a partially vitrified metallurgical waste

Corrosion Mechanism in the Obsidian and its Comparison with the Nuclear Waste Glass for Long-Term Performance Assessment in the Geological Repository~!2009-08-04~!2009-10-08~!2010-03-16~!

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