The Effects of Waste Loading on the Durability of Nuclear Waste Glasses

2008 ◽  
pp. 439-445
Author(s):  
Greg Darby ◽  
David E. Clark ◽  
George G. Wicks
Keyword(s):  
Nuclear Waste ◽  
Waste Loading

An Electrodeless Melter for Vitrification of Nuclear Waste

1996 ◽  
Vol 465 ◽  
Author(s):  
J. P. Freidberg ◽  
A. J. Shajii ◽  
K. W. Wenzel ◽  
J. R. Lierzer
Keyword(s):  
High Temperature ◽  
Radioactive Waste ◽  
Nuclear Waste ◽  
Thermal Analyses ◽  
Iron Core ◽  
Leaching Rate ◽  
One Dimensional ◽  
High Silica ◽  
Waste Loading

ABSTRACTThis paper describes a new concept for a high-temperature, electrodeless melter for vitrifying radioactive wastes. Based on the principles of induction heating, it circumvents a number of difficulties associated with existing technology. The melter can operate at higher temperatures (1500–2000°C vs 1150°C), allowing for a higher quality, more durable glass which reduces the long-term leaching rate. Higher processing temperatures also enable conversion from borosilicate to high-silica glass which can accommodate 2 to 3 times as much radioactive waste, potentially halving the ultimate required long-term disposal space. Finally, with high temperatures, conversion of nuclear waste into ceramics can also be considered. This too leads to higher waste loading and the reduction of repository space. The melter is toroidal, linked by an iron core transformer that allows efficient electrical operation even at 60 Hz. One-dimensional electrical and thermal analyses are presented.

Corrigendum to “The dissolution rates of simulated UK Magnox – ThORP blend nuclear waste glass as a function of pH, temperature and waste loading” [Miner. Mag. 79, (2015) 1529–1542]

2018 ◽  
Vol 82 (4) ◽  
pp. 939-942 ◽  
Author(s):  
Claire. L. Corkhill ◽  
Adam J. Fisher ◽  
Denis M. Strachan ◽  
Russell J. Hand ◽  
Neil C. Hyatt
Keyword(s):  
Nuclear Waste ◽  
Intrinsic Rate ◽  
Data Fitting ◽  
Waste Glass ◽  
Dissolution Rates ◽  
Nuclear Waste Glass ◽  
Corrected Data ◽  
Waste Loading ◽  
Fitting In ◽  
Intrinsic Rate Constant

AbstractWe revise the data fitting in our original paper [The dissolution rates of simulated UK Magnox - ThORP blend nuclear waste glass as a function of pH, temperature and waste loading, Miner. Mag.79 (2015) 1529–1542]. The intrinsic rate constant data were calculated incorrectly, the corrected data are presented herein. To support the corrected analysis we have also taken the opportunity to report some additional 90°C data. The conclusions of the original paper remain sound.

The dissolution of simulant UK Ca/Zn-modified nuclear waste glass: the effect of increased waste loading

MRS Advances ◽  
2021 ◽  
Author(s):  
Adam J. Fisher ◽  
Mike T. Harrison ◽  
Neil C. Hyatt ◽  
Russell J. Hand ◽  
Claire L. Corkhill
Keyword(s):  
Nuclear Waste ◽  
Waste Glass ◽  
Nuclear Waste Glass ◽  
Waste Loading

The effect of mixed modifiers on nuclear waste glass processing, leaching, and Raman spectra

1998 ◽  
Vol 13 (1) ◽  
pp. 8-15 ◽  
Author(s):  
S. V. Raman
Keyword(s):  
Raman Spectra ◽  
Nuclear Waste ◽  
Initial Increase ◽  
Borosilicate Glasses ◽  
Leach Rate ◽  
Mixed Alkali ◽  
Glass Processing ◽  
Nuclear Waste Glass ◽  
Mixed Alkali Effect ◽  
Waste Loading

Borosilicate glasses with different waste loadings were prepared by ambient melting, quenching, and annealing. Some melt compositions partially crystallize to durable phases of zircon and forsterite. The coexisting liquid quenches to glass and endures the leach tests. The waste loading dependent leach rate trends of these glasses are reminiscent of the mixed alkali effect. Raman spectra suggest initial increase in durability with increases in the depolymerization of silicate species. Fluorine and hydroxyl ions also contribute to depolymerization. Tetraborate and metaborate rings are identified in the Raman spectra. The durability is enhanced when tetraborate bands are more intense than the metaborate bands.

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.

Long-Term Thermomechanical and Thermohydrological Factors Controlling the Optimal Design of a Nuclear Waste Repository

1982 ◽  
Vol 15 ◽  
Author(s):  
J. S. Y. Wang ◽  
D. C. Mangold ◽  
C. F. Tsang
Keyword(s):  
Optimal Design ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Horizontal Gradient ◽  
Major Mechanism ◽  
Surface Uplift ◽  
Generic Modeling ◽  
Waste Repository ◽  
Waste Loading

ABSTRACTSurface uplift and buoyancy flow are two of the major long-term, far-field perturbations to the geologic formations around a nuclear waste repository. The allowable surface uplift has been accepted in the literature as a criterion limiting the repository waste loading density. It has also been recognized in generic modeling studies that the buoyancy distortion of the ambient groundwater flow around a repository is a major mechanism for radionuclide transport. However, the buoyancy considerations have yet to be quantified for the purpose of optimal design of a radioactive waste repository. We suggest the possibility of using the buoyancy gradient when compared with the ambient regional (horizontal) gradient as a measurable thermohydrologic factor that controls the design of waste loading. This study indicates that the buoyancy gradient could in some cases become the main controlling factor. To decrease the buoyancy effects, much lower values of waste loading density should be considered in the design of the waste repository.

The Effect of Waste Loading on the Characteristics of Borosilicate SRS SB4 Waste Glasses

2009 ◽  
Author(s):  
Sergey Stefanovsky ◽  
Alexander Kobelev ◽  
Vladimir Lebedev ◽  
Michael Polkanov ◽  
Dmitriy Suntsov ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Spinel Structure ◽  
Glass Ceramics ◽  
Chemical Durability ◽  
X Ray Diffraction ◽  
X Ray ◽  
Infra Red ◽  
Inner Diameter ◽  
Waste Loading ◽  
High Concentrations

The glasses containing surrogate of Sludge Batch 4 (SB4) waste with high concentrations of aluminum and ferrous oxides within the waste loading (WL) range of ∼50 to 70 wt.% produced in alumina crucibles in a resistive furnace and in a 236 mm inner diameter cold crucible were examined by X-ray diffraction, electron microscopy and infra-red spectroscopy. At relatively low WLs (50 to 60 w.%) the products remain predominantly vitreous with minor crystalline spinel structure phase corresponding in chemical composition to trevorite-magnetite solid solution. At higher WLs (>60 wt.%) amount of crystalline phases increased significantly and a nepheline phase was observed. The products with WL of 65 to 70 wt.% were spinel/nepheline glass-ceramics. The glass with 60 wt.% WL slowly cooled in accordance with the canister centerline cooling (CCC) conditions contained minor nepheline. Occurrence of nepheline reduces the chemical durability of nuclear waste glasses.

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