SON68 nuclear glass dissolution kinetics: Current state of knowledge and basis of the new GRAAL model

Frugier, Pierre; Gin, Stéṕhane; Minet, Y.; Chave, Tony; Bonin, Bernard; Godon, N.; Lartigue, Jean-Éric; Jollivet, Patrick; Ayral, A.; Windt, Laurent de; Santarini, G.

doi:10.1016/j.jnucmat.2008.06.044

Cited by 328 publications

(375 citation statements)

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“…The test with SON68 at pH 9 [4] did not show a clear deviation from the first-order rate law, but it cannot be excluded that the resulting forward rate was also to some extent decreased by Si resorption. It nevertheless fits with the forward rate equation found in [16], so the possible bias is probably small. Table III also presents the results from the experiments carried out in YCWCa (pH 13.5).…”

Section: Resultssupporting

confidence: 53%

Determination of the Forward Dissolution Rate for International Simple Glass in Alkaline Solutions

2017

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The International Simple Glass (ISG) is considered as reference benchmark glass and is used in the frame of an international collaboration for the study of the dissolution mechanisms of high-level vitrified nuclear waste. In this work the forward dissolution rate of the ISG was determined in different alkaline solutions, as a simulation of the disposal conditions foreseen by the Belgian concept for geological disposal of vitrified waste. The determination of the forward dissolution rate was done by measuring the Si released from the glass in solution in tests performed at 30 °C in four different KOH solutions with pH varying from 9 to 14 and in artificial cementitious water at pH 13.5. The forward dissolution rates determined for the ISG in high pH solutions are in good agreement with the results obtained for a lower pH range. The rates obtained in this study, moreover, were compared with the rates measured in the same conditions for SON68 glass from a previous work. The values obtained for the two glasses are comparable in artificial cementitious water and in KOH at moderately alkaline pH. At higher pH, ISG glass shows a lower forward dissolution rate with respect to SON68 (0.20 g·m -2 ·d for ISG and 0.35 g·m -2 d for SON68 at pH 14).

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Section: Resultssupporting

confidence: 53%

Determination of the Forward Dissolution Rate for International Simple Glass in Alkaline Solutions

2017

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“…The GLAMOR project (Van Iseghem et al 2006;Van Iseghem et al 2007) was a concerted effort to evaluate the primary evolving processes of glass degradation and to compare the capabilities of two specific models to represent those multiple processes using a selected set of experimental data from the literature. A number of more recent studies have extended glass degradation modeling from the end point of the GLAMOR project using the GRAAL model applied to SON68 nuclear glass (Frugier et al 2008;Frugier et al 2009) and explicitly evaluating coupled processes in the alteration of Roman glass (Verney-Carron et al 2010). In these cases, the details of choosing parameter values for input to the model of these coupled processes emphasizes the facility of an integrated framework for evaluating experiments and analogs.…”

Section: Current Understanding and Gap Identificationmentioning

confidence: 99%

“…In the GRAAL model (Frugier et al 2008;Frugier et al 2009), the concept of the passivating reactive interphase (PRI) is developed ( Figure 3-5); the PRI is essentially most of the gel layer and secondary phase layers that develop on the glass surface. The compositional profiles change rapidly just outside the surface of the glass (Figure 3-5 (Figure 3-6).…”

Section: Current Understanding and Gap Identificationmentioning

confidence: 99%

“…In the boxes below the schematic, the layers are listed with the primary formation mechanisms of these likely amorphous phases and the gross characteristics of each layer. (after Frugier et al 2008). Experimental studies of mineral dissolution kinetics (e.g., Hamilton et al 2001;Hellmann and Tisserand 2006;Yang and Steefel 2008;Pierce et al 2010) and of the related process of glass degradation (e.g., Strachan and Croak 2000;Advocet et al 2001;Wolf-Boenisch et al 2004;Pierce et al 2006;Cailleteau et al 2008) have provided data to show that there is a complex coupled feedback process that changes glass degradation from simple far-from equilibrium dissolution kinetics at the start to slower degradation controlled in part by diffusion processes in gel and secondary phase layer(s) in which the reaction solution has a modified composition near the surface (i.e., the reactive interface) of fresh glass (see Grambow 2006;Van Iseghem et al 2007).…”

Section: Current Understanding and Gap Identificationmentioning

confidence: 99%

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Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.

Criscenti¹,

Sassani²,

Argüello³

et al. 2011

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This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements.Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologicchemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.iv ACKNOWLEDGEMENTS

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“…Introducing a boron/alkali diffusion coefficient, the BRAG model describes boron/alkali diffusion in the diffusion layer as well (Aertsens, 2007). Recently, the Glass Reactivity with Allowance for the Alteration Layer (GRAAL) model (Frugier et al, 2009(Frugier et al, , 2008 has been proposed, which is dependent on the composition and the passivating nature of the gel layer, called the passivating reactive interphase (PRI). The GRAAL model considers that water diffusion in the passivating reaction zone (the gel formed under saturation conditions) is a rate-limiting step in the overall glass dissolution kinetics.…”

Section: Glass Passivationmentioning

confidence: 99%

Mathematical Formulation Requirements and Specifications for the Process Models

Steefel¹,

Moulton²,

Pau³

et al. 2010

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SON68 nuclear glass dissolution kinetics: Current state of knowledge and basis of the new GRAAL model

Cited by 328 publications

References 40 publications

Determination of the Forward Dissolution Rate for International Simple Glass in Alkaline Solutions

Determination of the Forward Dissolution Rate for International Simple Glass in Alkaline Solutions

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.

Mathematical Formulation Requirements and Specifications for the Process Models

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