Dissolution mechanism of the SON68 reference nuclear waste glass: New data in dynamic system in silica saturation conditions

Neeway, James J.; Abdelouas, A.; Grambow, Bernd; Schumacher, Stéphan

doi:10.1016/j.jnucmat.2011.05.027

Cited by 62 publications

(34 citation statements)

References 22 publications

(22 reference statements)

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“…Based on these experimental observations, Grambow and Muller [13] proposed the GM2001 model in which silicon diffusion in the gel was supplemented with a water diffusion term. Further improvements have been made in the versions GM2003 and GM2004(list possibly not exhaustive, more advanced versions may exist) [19,58,59].…”

Section: A C C E P T E D Accepted Manuscriptmentioning

confidence: 99%

“…Gin [65]found that the formation and evolution of a dense layer during glass dissolution can significantly affect the inter-diffusion process. Even models based on chemical affinity acknowledge this(GLASSOL model [45][46][47], and GM models [13,19,58,59]). …”

Section: Diffusion Barrier Concept and Modelsmentioning

confidence: 99%

“…At present, more and more researchers realise that it is too simple to regard the control mechanisms of rate drop or residual rate as one single mechanism, the control mechanism can be a combination of the two [12,58,59]. Sometimes chemical affinity can be dominating [27,68], sometimes the protective properties of the gel dominating [51][52][53], and sometimes the rate can be controlled by both mechanisms [59], depending on the glass composition and the leaching conditions. It is essential to find a way to combine the two providing a model with comprehensive application to general glass dissolution.…”

Section: Summary Of Rate Drop Mechanismsmentioning

confidence: 99%

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A mechanistic model for long-term nuclear waste glass dissolution integrating chemical affinity and interfacial diffusion barrier

Jivkov

et al. 2017

Journal of Nuclear Materials

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Abstract:Understanding the alteration of nuclear waste glass in geological repository conditions is critical element of the analysis of repository retention function. Experimental observations of glass alterations provide a general agreement on the following regimes: inter-diffusion, hydrolysis process, rate drop, residual rate and, under very particular conditions, resumption of alteration. Of these, the mechanisms controlling the rate drop and the residual rate remain a subject of dispute. This paper offers a critical review of the two most competitive models related to these regimes: affinity-limited dissolution and diffusion barrier. The limitations of these models are highlighted by comparison of their predictions with available experimental evidence. Based on the comprehensive discussion of the existing models, a new mechanistic model is proposed as a combination of the chemical affinity and diffusion barrier concepts. It is demonstrated how the model can explain experimental phenomena and data, for which the existing models are shown to be not fully adequate.Key words: nuclear waste glasses, long-term dissolution, mechanisms, modelling IntroductionRadioactivity wastes are generated at all stages of the nuclear fuel cycle, including the decommissioning of nuclear facilities, as well as from military applications. Of particular concern for the storage/disposal of radioactivity wastes are those containing long-lived radionuclides [1].The current plan ( countries such as Belgium, Finland , Sweden , France etc.)for long-term management of such wastes is to store them in deep, stable and lowpermeable geological formations [2].The storage design is based on the so-called multi-barrier concept, where several barriers prevent for a period of time, or slow down the release and migration of radionuclides through the geosphere [3,4].Within this concept, hazardous nuclides are immobilized into solidified bodies. The wasteform selection is difficult, since durability is not the sole criterion [5]. Currently, vitrification is regarded as the best solution for immobilizing radionuclides. This technology has been progressively developed over the last half-century, has matured and has become industrially robust.Data collected to date suggest that glass waste forms offer the advantages that they can accommodate a wide range of waste streams, are resistant to radiation damage, and are relatively inert to both chemical and thermal perturbations [6].The use of natural and archeological analogues supported further the durability argument of glass as waste forms [7][8][9][10][11]. Except for the alumino-phosphate glass used in Russia, the borosilicate glass has been universally selected by all other nations [12].In order to make scientifically-underpinned safety cases, the long-term behaviour of glassy wasteforms requires further understanding and assessment. Half-lives of some radionuclides extend to millions of years, requiring isolation for geological periods, while the period of investigation possible in the field and the la...

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Section: A C C E P T E D Accepted Manuscriptmentioning

confidence: 99%

Section: Diffusion Barrier Concept and Modelsmentioning

confidence: 99%

Section: Summary Of Rate Drop Mechanismsmentioning

confidence: 99%

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A mechanistic model for long-term nuclear waste glass dissolution integrating chemical affinity and interfacial diffusion barrier

Jivkov

et al. 2017

Journal of Nuclear Materials

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“…The components, preparation, and leaching procedure of the SON68 glass have been described elsewhere [20,27]. In brief, it was made by batching carbonates and oxides of the various metals, melting in a furnace, and quenching on a stainless steel plate.…”

Section: Materials and Sample Preparationmentioning

confidence: 99%

“…A leached simulated borosilicate nuclear waste glass(SON68), a La 0.93 Sr 0.07 CrO 3 thin film on a SrTiO 3 substrate, and a SrTiO 3 /SrCrO 3 bilayer film on a SrTiO 3 substrate were selected as model systems for our study because of their fundamental and practical importance [16][17][18][19][20][21][22][23][24][25][26].…”

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confidence: 99%

Argon Cluster Sputtering Source for ToF-SIMS Depth Profiling of Insulating Materials: High Sputter Rate and Accurate Interfacial Information

Wang

Liu

Zhao

et al. 2015

J. Am. Soc. Mass Spectrom.

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Abstract. The use of an argon cluster ion sputtering source has been demonstrated to perform superiorly relative to traditional oxygen and cesium ion sputtering sources for ToF-SIMS depth profiling of insulating materials. The superior performance has been attributed to effective alleviation of surface charging. A simulated nuclear waste glass (SON68) and layered hole-perovskite oxide thin films were selected as model systems because of their fundamental and practical significance. Our results show that high sputter rates and accurate interfacial information can be achieved simultaneously for argon cluster sputtering, whereas this is not the case for cesium and oxygen sputtering. Therefore, the implementation of an argon cluster sputtering source can significantly improve the analysis efficiency of insulating materials and, thus, can expand its applications to the study of glass corrosion, perovskite oxide thin film characterization, and many other systems of interest.

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Simulations of Glass–Water Interactions

Rimsza

Mahadevan

Deng

et al. 2022

Atomistic Simulations of Glasses

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Dissolution mechanism of the SON68 reference nuclear waste glass: New data in dynamic system in silica saturation conditions

Cited by 62 publications

References 22 publications

A mechanistic model for long-term nuclear waste glass dissolution integrating chemical affinity and interfacial diffusion barrier

A mechanistic model for long-term nuclear waste glass dissolution integrating chemical affinity and interfacial diffusion barrier

Argon Cluster Sputtering Source for ToF-SIMS Depth Profiling of Insulating Materials: High Sputter Rate and Accurate Interfacial Information

Simulations of Glass–Water Interactions

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