Chemical engineering problems of radioactive waste fixation by vitrification

Taylor, Rebecca

doi:10.1016/0009-2509(85)80001-4

Cited by 19 publications

(5 citation statements)

References 30 publications

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“…Bibler et al (30) compared measured and predicted concentrations of technetium-99 ( 99 Tc) and 137 Cs in glass produced from a Savannah River tank waste and found that 31% of the 99 Tc and 4% of the 137 Cs were vaporized during vitrification. Taylor (31) performed a detailed analysis of ruthenium and cesium volatility during several vitrification processes, with the greatest release occurring during calcination. He reported that 137 Cs volatilities commonly range around 1%, although values as high as 13% have been measured.…”

Section: Introductionmentioning

confidence: 99%

High-Temperature Sorption of Cesium and Strontium on Dispersed Kaolinite Powders

Yoo

Shinagawa

Wood

et al. 2005

Environ. Sci. Technol.

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Sorption of cesium and strontium on kaolinite powders was investigated as a means to minimize the emissions of these metals during certain high-temperature processes currently being developed to isolate and dispose of radiological and mixed wastes. In this work, nonradioactive aqueous cesium acetate or strontium acetate was atomized down the center of a natural gas flame supported on a variable-swirl burner in a refractory-lined laboratory-scale combustion facility. Kaolinite powder was injected at a postflame location in the combustor. Cesium readily vaporized in the high-temperature regions of the combustor, but was reactively scavenged onto dispersed kaolinite. Global sorption mechanisms of cesium vapor on kaolinite were quantified, and are related to those available in the literature for sodium and lead. Both metal adsorption and substrate deactivation steps are important, so there is an optimum temperature, between 1400 and 1500 K, at which maximum sorption occurs. The presence of chlorine inhibits cesium sorption. In contrast to cesium, and in the absence of chlorine, strontium was only partially vaporized and was, therefore, only partially scavengeable. The strontium data did not allow quantification of global kinetic mechanisms of interaction, although equilibrium arguments provided insight into the effects of chlorine on strontium sorption. These results have implications for the use of sorbents to control cesium and strontium emissions during high-temperature waste processing including incineration and vitrification.

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Section: Introductionmentioning

confidence: 99%

High-Temperature Sorption of Cesium and Strontium on Dispersed Kaolinite Powders

Yoo

Shinagawa

Wood

et al. 2005

Environ. Sci. Technol.

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“…Hydrodynamic and van der Waals forces were estimated through the relations provided by Allain et al [35]. The hydrodynamic force was calculated as 𝐹 𝐻 = 𝜂 𝑓 𝛾Ṙ 2 , where 𝜂 𝑓 is the viscosity of the continuous phase, 𝛾̇ is the shear rate and 𝑅 is the aggregate radius. For the van der Waals potential, the relation 𝐹 𝑣𝑑𝑊 = ᴧ𝑎 12ℎ 2 , was considered, where ᴧ is the Hamaker constant, 𝑎 is the particle radius and ℎ is the mean distance between the particles.…”

Section: Force Balance and Aggregation Mechanismsmentioning

confidence: 99%

“…The melter crucible can be heated by conduction (hot crucible), indirect induction (cold crucible), or in a Liquid Fed Ceramic Melter with electrodes. The nuclear glass is then poured into metal containers and stored in shafts while awaiting future storage in a deep geological repository [1], [2].…”

Section: Introductionmentioning

confidence: 99%

Influence of platinum group metal particle aggregation on the rheological behavior of a glass melt

Machado

Pereira

Neyret

et al. 2022

Journal of Nuclear Materials

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“…Vitrification is the established technology to immobilize HLW into a glass waste form that possesses the requisite chemical durability and radiation stability for long-term storage and disposal [23][24][25][26][27][28]. Vitrification was selected for HLW treatment at WVDP, SRS, and the Hanford Site, [1,2,4,5].…”

Section: Introductionmentioning

confidence: 99%

Glass-contact refractory of the nuclear waste vitrification melters in the United States: a review of corrosion data and melter life

Jin

Hall

Vienna

et al. 2023

International Materials Reviews

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The performance of the refractory lining in glass melters used for nuclear waste vitrification is critical to the melter reliability for long-term continuous operation. Monofrax® K-3, a high Cr 2 O 3 fused cast refractory material, has been widely used to build the liners of nuclear waste glass melters in the United States. Corrosion behaviour of Monofrax® K-3 refractory has been evaluated based on crucible-scale testing, inspection of the refractory components following scaled melter testing, and inspections of the Defense Waste Processing Facility (DWPF) melter refractory after service. The literature generally consists of empirical models based on short-term testing to describe refractory corrosion dependence on glass composition. Corrosion data from tests with longer testing times, at various temperatures, in the presence of molten salts, and with different redox reactions in the plenum atmosphere exist, may be insufficient to provide accurate refractory service life estimates. Additionally, the corrosion data collected under actual and scaled melter operating conditions are limited. Recommendations to achieve more direct correlation between the laboratory refractory corrosion data predictions and the observed melter service life are discussed to allow for more accurate predictions of the useful life of melter refractory linings.

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Chemical engineering problems of radioactive waste fixation by vitrification

Cited by 19 publications

References 30 publications

High-Temperature Sorption of Cesium and Strontium on Dispersed Kaolinite Powders

High-Temperature Sorption of Cesium and Strontium on Dispersed Kaolinite Powders

Influence of platinum group metal particle aggregation on the rheological behavior of a glass melt

Glass-contact refractory of the nuclear waste vitrification melters in the United States: a review of corrosion data and melter life

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