The structural role of Zr within alkali borosilicate glasses for nuclear waste immobilisation

2011 ◽  
Vol 357 (7) ◽  
pp. 1647-1656 ◽  
Author(s):  
A.J. Connelly ◽  
N.C. Hyatt ◽  
K.P. Travis ◽  
R.J. Hand ◽  
E.R. Maddrell ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glasses ◽  
Structural Role ◽  
Alkali Borosilicate Glasses

The Structural Role of Zn in Nuclear Waste Glasses

2011 ◽  
Vol 2 (4) ◽  
pp. 343-353 ◽  
Author(s):  
Nathan J. Cassingham ◽  
Martin C. Stennett ◽  
Paul A. Bingham ◽  
Neil C. Hyatt ◽  
Giuliana Aquilanti
Keyword(s):  
Nuclear Waste ◽  
Structural Role ◽  
Role Of Zn

Composition-Structure Relationships in Simplified Nuclear Waste Glasses: 1. Mixed Alkali Borosilicate Glasses

2010 ◽  
Vol 94 (1) ◽  
pp. 151-159 ◽  
Author(s):  
Andrew J. Connelly ◽  
Karl P. Travis ◽  
Russell J. Hand ◽  
Neil C. Hyatt ◽  
Ewan Maddrell
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glasses ◽  
Mixed Alkali ◽  
Composition Structure ◽  
Alkali Borosilicate Glasses

scholarly journals An Assessment of Initial Leaching Characteristics of Alkali-Borosilicate Glasses for Nuclear Waste Immobilization

Materials ◽  
2019 ◽  
Vol 12 (9) ◽  
pp. 1462 ◽  
Author(s):  
Osama Farid ◽  
Michael Ojovan ◽  
A. Massoud ◽  
R.O. Abdel Rahman
Keyword(s):  
Nuclear Waste ◽  
Temporal Change ◽  
Matrix Composition ◽  
Dissolution Process ◽  
Borosilicate Glasses ◽  
Leaching Characteristics ◽  
Waste Loading ◽  
Thermodynamic Instability ◽  
Fractional Release ◽  
Alkali Borosilicate Glasses

Initial leaching characteristics of simulated nuclear waste immobilized in three alkali- borosilicate glasses (ABS-waste) were studied. The effects of matrix composition on the containment performance and degradation resistance measures were evaluated. Normalized release rates are in conformance with data reported in the literature. High Li and Mg loadings lead to the highest initial de-polymerization of sample ABS-waste (17) and contributed to its thermodynamic instability. Ca stabilizes non-bridging oxygen (NBO) and reduces the thermodynamic instability of the modified matrix. An exponential temporal change in the alteration thickness was noted for samples ABS-waste (17) and Modified Alkali-Borosilicate (MABS)-waste (20), whereas a linear temporal change was noted for sample ABS-waste (25). Leaching processes that contribute to the fractional release of all studied elements within the initial stage of glass corrosion were quantified and the main controlling leach process for each element was identified. As the waste loading increases, the contribution of the dissolution process to the overall fractional release of structural elements decreases by 43.44, 5.05, 38.07, and 52.99% for Si, B, Na, and Li respectively, and the presence of modifiers reduces this contribution for all the studied metalloids. The dissolution process plays an important role in controlling the release of Li and Cs, and this role is reduced by increasing the waste loading.

scholarly journals Structural role of ZrO2 and its impact on properties of boroaluminosilicate nuclear waste glasses

2018 ◽  
Vol 2 (1) ◽  
Author(s):  
Xiaonan Lu ◽  
Lu Deng ◽  
Sebastien Kerisit ◽  
Jincheng Du
Keyword(s):  
Nuclear Waste ◽  
Structural Role

Role of Sulfate in Structural Modifications of Sodium Barium Borosilicate Glasses Developed for Nuclear Waste Immobilization

2008 ◽  
Vol 91 (12) ◽  
pp. 3903-3907 ◽  
Author(s):  
Raman K. Mishra ◽  
Kumaran V. Sudarsan ◽  
Pranesh Sengupta ◽  
Rajesh K. Vatsa ◽  
Avesh K. Tyagi ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glasses ◽  
Structural Modifications ◽  
Waste Immobilization ◽  
Nuclear Waste Immobilization

The Pyrochlore Line in the System CaO—ZrO2—TiO2: Implications on Synroc Phase Assemblages

1991 ◽  
Vol 257 ◽  
Author(s):  
M. Ondina Figueiredo ◽  
António Correia dos Santos ◽  
Carmen Parada Cortina ◽  
M. Joao Basto
Keyword(s):  
Phase Equilibria ◽  
Nuclear Waste ◽  
Tetragonal Phase ◽  
Structural Role ◽  
High Level Nuclear Waste ◽  
High Level

ABSTRACTResults of further studies on phase equilibria in system CaO—ZrO2—TiO2 along the “pyrochlore” line ( Ca Zrx Ti3-x 07 ) are reported concerning the possible substitution of cerium for either calcium or zirconium in nominal “Ca Zr2 Ti 07”. The dominant tetragonal phase in this composition was identified as calzirtite. The structural role of zirconium and its tendency towards 7—coordination environments are discussed. Possible implications on high—level nuclear waste immobilizers like SYNROC are brieflyconsidered.

scholarly journals Corrosion of ternary borosilicate glass in acidic solution studied in operando by fluid-cell Raman spectroscopy

2021 ◽  
Vol 5 (1) ◽  
Author(s):  
Christoph Lenting ◽  
Thorsten Geisler
Keyword(s):  
Raman Spectroscopy ◽  
Nuclear Waste ◽  
Numerical Models ◽  
Adsorbed Water ◽  
Corrosion Mechanism ◽  
Borosilicate Glasses ◽  
Long Term Storage ◽  
In Operando ◽  
High Level ◽  
Fluid Cell

AbstractFluid-cell Raman spectroscopy is a space and time-resolving application allowing in operando studies of dynamic processes during solution–solid interactions. A currently heavily debated example is the corrosion mechanism of borosilicate glasses, which are the favoured material for the immobilization of high-level nuclear waste. With an upgraded fluid-cell lid design made entirely from the glass sample itself, we present the polymerization of the surface alteration layer over time in an initially acidic environment, including the differentiation between pore and surface-adsorbed water within it. Our results support an interface-coupled dissolution-precipitation model, which opposes traditional ion-exchange models for the corrosion mechanism. A sound description of the corrosion mechanism is essential for reliable numerical models to predict the corrosion rate of nuclear waste glasses during long-term storage in a geological repository.

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