Vitrification Testing and Demonstration for the Hanford Waste Treatment and Immobilization Plant

Perez, J.M.; Barnes, Steven; Kelly, Susan E.; Petkus, L.L.; Morrey, E.V.

doi:10.1002/9781118408438.ch1

Cited by 3 publications

(3 citation statements)

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“…More than 200 000 m 3 of nuclear waste will be vitrified at the Hanford Site over the coming decades . Understanding melter feed rheology is a key component for an enhanced mathematical model that estimates the melter waste-processing rates and guides strategies for efficient operations in the WTP that will significantly shorten the life cycle of the cleanup process at the Hanford Site.…”

Section: Implication For Nuclear Waste Vitrificationmentioning

confidence: 99%

Effect of Bubbles and Silica Dissolution on Melter Feed Rheology during Conversion to Glass

Marcial

Chun

Hrma

et al. 2014

Environ. Sci. Technol.

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Nuclear-waste melter feeds are slurry mixtures of wastes with glass-forming and glass-modifying additives (unless prefabricated frits are used), which are converted to molten glass in a continuous electrical glass-melting furnace. The feeds gradually become continuous glass-forming melts. Initially, the melts contain dissolving refractory feed constituents that are suspended together with numerous gas bubbles. Eventually, the bubbles escape, and the melts homogenize and equilibrate. Knowledge of various physicochemical properties of the reacting melter feed is crucial for understanding the feed-to-glass conversion that occurs during melting. We studied the melter feed viscosity during heating and correlated it with the volume fractions of dissolving quartz (SiO2) particles and the gas phase. The measurements were performed with a rotating spindle rheometer on the melter feed heated at 5 K/min, starting at several different temperatures. The effects of undissolved quartz particles, gas bubbles, and compositional inhomogeneity on the melter feed viscosity were determined by fitting a linear relationship between the logarithm of viscosity and the volume fractions of suspended phases.

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Section: Implication For Nuclear Waste Vitrificationmentioning

confidence: 99%

Effect of Bubbles and Silica Dissolution on Melter Feed Rheology during Conversion to Glass

Marcial

Chun

Hrma

et al. 2014

Environ. Sci. Technol.

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“…Joule-heated, slurry-fed ceramic melters are in use at SRS and will be used at Hanford to produce borosilicate glass waste forms. [1][2] Over 16 million liters of waste have been treated and vitrified, producing more than 6,800 metric tons of glass at the Defense Waste Processing Facility (DWPF) at SRS since its startup in 1996. The tank waste at Hanford Site are planned to be separated into a low-volume, high-level waste (HLW) fraction and a high-volume lowactivity waste (LAW) fraction through pretreatment processes.…”

Section: Introductionmentioning

confidence: 99%

Glass Property Models, Constraints, and Formulation Approaches for Vitrification of High-Level Nuclear Wastes at the US Hanford Site

Kim¹

2015

J. Korean Ceram. Soc

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Current plans for legacy nuclear wastes stored in underground tanks at the U.S. Department of Energy's Hanford Site in Washington are that they will be separated into high-level waste and low-activity waste fractions that will be vitrified separately. Formulating optimized glass compositions that maximize the waste loading in glass is critical for successful and economical treatment and immobilization of these nuclear wastes. Glass property-composition models have been developed and applied to formulate glass compositions for various objectives for the past several decades. Property models with associated uncertainties combined with composition and property constraints have been used to develop preliminary glass formulation algorithms designed for vitrification process control and waste-form qualification at the planned waste vitrification plant. This paper provides an overview of the current status of glass property-composition models, constraints applicable to Hanford waste vitrification, and glass formulation approaches that have been developed for vitrification of hazardous and highly radioactive wastes stored at the Hanford Site.

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“…Long term storage in underground repositories after vitrification [1] is one method and the second involves partition of long-lived isotopes and transmutation (P&T) [2] or immobilisation of those isotopes that cannot be transmutated. Intermediate level waste can be disposed of in surface repositories, provided the longlived isotopes are removed.…”

Section: Introductionmentioning

confidence: 99%

Perfluorinated phenols as extraction agents for Cs⁺ and Sr²⁺

Baker¹,

Ogilvie

Richards

2010

Radiochimica Acta

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The extraction efficiency of some perfluorinated phenols for the removal of Cs + and Sr 2+ from aqueous solutions is reported. The perfluorinated phenols C 6 F 5 OH and 2,3,5,6-C 6 F 4 HOH have been shown to extract 90 Sr 2+ or Cs + from aqueous solutions into a 100 : 1 mixture of toluene and pyridine in reasonable efficiencies, using radio-tracer and ICP-OES techniques. Additionally uranium, 59 Fe 3+ {as a model for Pu(IV)} and Eu 3+ {as a model for Am(III)} were investigated, with only iron not being successfully extracted.

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Vitrification Testing and Demonstration for the Hanford Waste Treatment and Immobilization Plant

Cited by 3 publications

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Effect of Bubbles and Silica Dissolution on Melter Feed Rheology during Conversion to Glass

Effect of Bubbles and Silica Dissolution on Melter Feed Rheology during Conversion to Glass

Glass Property Models, Constraints, and Formulation Approaches for Vitrification of High-Level Nuclear Wastes at the US Hanford Site

Perfluorinated phenols as extraction agents for Cs⁺ and Sr²⁺

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Vitrification Testing and Demonstration for the Hanford Waste Treatment and Immobilization Plant

Cited by 3 publications

References 0 publications

Effect of Bubbles and Silica Dissolution on Melter Feed Rheology during Conversion to Glass

Effect of Bubbles and Silica Dissolution on Melter Feed Rheology during Conversion to Glass

Glass Property Models, Constraints, and Formulation Approaches for Vitrification of High-Level Nuclear Wastes at the US Hanford Site

Perfluorinated phenols as extraction agents for Cs+ and Sr2+

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Product

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Perfluorinated phenols as extraction agents for Cs⁺ and Sr²⁺