Electric melting of nuclear waste glasses State of the art

Chapman, C.C.; Pope, James Gray; Barnes, S.M.

doi:10.1016/0022-3093(86)90781-7

Cited by 21 publications

(6 citation statements)

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“…The key trialled and/or implemented vitrification technologies for radioactive waste immobilisation [1][2][3][34][35][36][37][38] consist of induction melters (e.g. UK, France and India) and Joule heated ceramic melters (e.g.…”

Section: Vitrification Melter Technologies and Processing Parametersmentioning

confidence: 99%

Corrosion of glass contact refractories for the vitrification of radioactive wastes: a review

Bingham

Connelly

Hyatt

et al. 2011

International Materials Reviews

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A key consideration for all radioactive waste vitrification technologies is the physical and chemical integrity of the melting vessel. Most melting vessels require refractory liners that can safely withstand the high-temperature, highly corrosive environment, contain molten waste mixtures during melting and provide robust and reproducible service lifetimes. In this review article the key glass contact refractory materials used in radioactive waste vitrification melters, their properties, their applications and the mechanisms by which they become corroded during service are reviewed.

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Section: Vitrification Melter Technologies and Processing Parametersmentioning

confidence: 99%

Corrosion of glass contact refractories for the vitrification of radioactive wastes: a review

Bingham

Connelly

Hyatt

et al. 2011

International Materials Reviews

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“…Since 1973, more than 200,000 kg (440,000 lb) of simulated and actual waste glasses containing simulated high-level radioactive wastes have been produced at PNL-in the development of JHCM technology. Vitrification research at PNL has covered a wide range of waste stream compositions for both commercial and defense nuclear reactor operations (Chapman, Pope, and Barnes 1986). Waste streams vitrified in existing developmental melters include high fission product nitric acid wastes and alkaline sludges containing refractory materials (e.g., high iron, chromium, alumina, zirconium, and zeolite concentrations).…”

Section: Joule-heated Ceramic Melter Technologymentioning

confidence: 99%

Vitrification technologies for Weldon Spring raffinate sludges and contaminated soils - Phase 2 Report: Screening of Alternatives

Koegler¹,

Nakaoka²,

Farnsworth³

et al. 1989

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This program was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor Battelle Memorial Institute, nor any or their employees, makes .1ny warranty, expressed or implied, or assumes any legal IWlillty or responsibility for the accurK)', completeness, or usefulness of any information, appuatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government of any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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“…The high-level radioactive liquid waste (HLLW) generated from spent fuels in the reprocessing facilities is immobilized into the borosilicate glass by using the Joule heated ceramic melter (JHCM) because of its high thermal efficiency and safety [ 1 , 2 ]. However, the existence of platinum group metals (PGMs) in the radwaste limited the advantages of the JHCM method for HLLW vitrification.…”

Section: Introductionmentioning

confidence: 99%

The Removal of Platinum Group Metals, Cs, Se, and Te from Nuclear Waste Glass Using Liquid Sb Extraction and Phase Separation Methods

Zhang

et al. 2020

Materials

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Recovery of platinum group metals (PGMs: Pd, Ru, Rh), Cs, Se, and Te from molten borosilicate glass containing simulated high level radwaste through the combination of liquid metal extraction and phase separation method under reductive heat-treatment was studied. In this process, the PGMs were extracted in recovered liquid metal phase, where Sb and Bi metals were used as the collecting metals. Meanwhile, Cs, Se, and Te were enriched in the phase separated potassium-rich materials on glass surface, which were extracted by water. The type of liquid metals had profound influence on the extraction behaviors of PGMs and other fission products from the glass melt. As a result, except the near extraction efficiency of Pd, Sb showed higher affinity for Ru and Rh than Bi metal. The higher phase separation efficiency of potassium-rich materials led to the higher extraction efficiencies of Cs, Se, and Te in liquid Sb extraction than Bi. Among the examined conditions, using liquid Sb extraction, the Pd, Ru, and Rh extraction efficiencies were 78.6%, 62.1% and 100% in liquid Sb metal phase, and 93.76% of Cs, 60.4% of Se, and 23.65% of Te in leachate were obtained.

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Electric melting of nuclear waste glasses State of the art

Cited by 21 publications

References 0 publications

Corrosion of glass contact refractories for the vitrification of radioactive wastes: a review

Corrosion of glass contact refractories for the vitrification of radioactive wastes: a review

Vitrification technologies for Weldon Spring raffinate sludges and contaminated soils - Phase 2 Report: Screening of Alternatives

The Removal of Platinum Group Metals, Cs, Se, and Te from Nuclear Waste Glass Using Liquid Sb Extraction and Phase Separation Methods

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