Degradation of high-level waste glass under simulated repository conditions

Pan, Yiming; Jain, V.K.; Pensado, Osvaldo

doi:10.1016/s0022-3093(02)01955-5

Cited by 10 publications

(12 citation statements)

References 8 publications

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“…6a), the value of which is ~25% higher than that of ISG(+PTFE) corroded under similar conditions. The observation of B plateauing is consistent with the findings of Pan et al 20 , who corroded model nuclear waste glasses in highly acidic FeCl toward glass corrosion. However, it is probable that the data point for B corresponding to ISG(+PTFE) at 365 days (Fig.…”

Section: Solution Analysessupporting

confidence: 91%

“…However, conditions for crevice corrosion like tight crevices was not mimicked in that study, so their result is likely associated with the uniform corrosion of SS. Pan et al 20 investigated the effect of aqueous Fe 2+ and Fe 3+ (from FeCl 2 and FeCl 3 , respectively) on model waste glasses and reported an increase of up to 50× in the corrosion rate of glass due to the enhanced acidity. Although the testing environment was a surrogate for a crevice due to the Fe cation hydrolysis and resulting low pH, they did not consider mass transport effects.…”

Section: Introductionmentioning

confidence: 99%

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Long-term interactive corrosion between International Simple Glass and stainless steel

Mohanty

Guo²,

Kaya³

et al. 2022

npj Mater Degrad

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The interactive corrosion between stainless steel 316 (SS) and International Simple Glass (ISG) has been studied for 12 months. The samples were placed in intimate contact to create crevice corrosion conditions on SS in a 0.6 M NaCl solution with and without 142 ppm dissolved silica species enriched in 29Si. Corrosion on SS was observed with large pits located close to the crevice mouth at the end of 1 year in 0.6 M NaCl solution. The SS corrosion was also associated with the dissolution of nearby glass in a highly localized manner. When the leaching solution was saturated with silica species, the corrosion rate of SS was suppressed. However, the presence of SS enhances ISG dissolution in both conditions. The implications of the observed phenomena on the long-term storage of nuclear waste are discussed.

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Section: Solution Analysessupporting

confidence: 91%

Section: Introductionmentioning

confidence: 99%

Long-term interactive corrosion between International Simple Glass and stainless steel

Mohanty

Guo²,

Kaya³

et al. 2022

npj Mater Degrad

View full text Add to dashboard Cite

show abstract

“…The effect of Fe and Fe oxide/oxyhydroxide on the corrosion of nuclear waste glass has been investigated by several studies [9][10][11][12][13][14][15] . The first work was published by McVay et al 9 , who altered PNL 76-68 borosilicate glass and carbon steel together at 90°C in various aerated solutions, including deionized water, tuff groundwater, and basalt groundwater.…”

Section: Introductionmentioning

confidence: 99%

Near-field corrosion interactions between glass and corrosion resistant alloys

et al. 2020

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This study explores the corrosion interactions between model nuclear waste glass materials and corrosion resistant alloys, under accelerated conditions that simulate the near field of a nuclear waste repository. The interactions between the corrosion of stainless steel (SS) 316, alloy G30, or alloy 625, and international simple glass or soda-lime silica glass are systematically studied. The dissimilar materials were exposed in close proximity to each other in different electrolytes at 90°C. After exposure, the glass surface exposed near metals showed different regimes of corrosion, with distinct surface morphologies and chemistries that were likely affected by the local environment created by the localized corrosion of metals. Surface and solution analyses showed that the corrosion rate of glass was enhanced by the presence of metals. Infrared spectroscopy data suggested the local build-up of stresses in the contact area of glass, which may lead to the mechanical instability of the glass alteration layer. On the other hand, the effect of glass on metal corrosion is strongly dependent on the leaching solution. In electrolytes containing abundant aggressive anions such as Cl − , glass seems to suppress the localized corrosion of SS by the precipitation of a Si-rich surface film that protects the SS substrate from solutions. However, in less aggressive electrolytes, the corrosion rate of SS was increased by the presence of glass corrosion products. Overall, our study showed that the hidden and localized damage on glass in contact with metals may enhance the release rate of glass components compared to typical uniform glass corrosion.

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“…The atomic-and molecular-scale understanding of the interactions between Fe 3 + /Fe 2+ ions and glass in aqueous environments should also be explored, which is feasible through the development of models based on density functional theory and molecular dynamics. Since the effect of Fe 3+ /Fe 2+ ions on glass corrosion is self-accelerated in nature due to the high tendency to hydrolyze and these cations also exist in some nuclear waste glasses (e.g., SRL and WVDP glasses) as structure components 73 , it is important to investigate how these metal cations released from the glass substrate impact glass corrosion. Additionally, given the importance of localized corrosion of metallic containers, it is crucial to explore whether localized corrosion of CS or CRAs could occur in a real-world anoxic repository (e.g., in a radiation field 30 ) and any subsequent influence on the alteration of glass or crystalline ceramics present nearby.…”

Section: Summary and Perspectivesmentioning

confidence: 99%

Review of corrosion interactions between different materials relevant to disposal of high-level nuclear waste

2020

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This review covers the corrosion interactions between different materials that are relevant to the disposal of high-level nuclear waste, in particular the waste forms and containers. The materials of interest are borosilicate glass, crystalline ceramics, metal alloys, and any corrosion products that might form. The available data show that these interactions depend on the structure, chemistry, thermodynamic history, and proximity of the materials in contact, as well as the environmental attributes, such as temperature, solution chemistry, and radiation. Several key mechanisms that govern these interactions are highlighted. Scientific gaps and open questions are summarized and discussed.

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Degradation of high-level waste glass under simulated repository conditions

Cited by 10 publications

References 8 publications

Long-term interactive corrosion between International Simple Glass and stainless steel

Long-term interactive corrosion between International Simple Glass and stainless steel

Near-field corrosion interactions between glass and corrosion resistant alloys

Review of corrosion interactions between different materials relevant to disposal of high-level nuclear waste

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