Vitrification of sulfate- and chloride-containing radioactive waste in an electric furnace

Sobolev, I. A.; Lifanov, F. A.; Stefanovskii, S. V.; Kobelev, A. P.; Zakharenkov, V. N.; Musatov, N. D.; Krylova, N. V.

doi:10.1007/bf00676565

Cited by 4 publications

(2 citation statements)

References 2 publications

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“…Vitrification is primarily used for HLW immobilisation, but it recently showed potential for ILW immobilisation as well. 80,81 In this process, glass frit is melted with nuclear waste, and at the end of the vitrification process, radionuclides are chemically immobilized within the glass network. 2 Problematic elements for the vitrification process include I, Xe, Kr, Cs, and especially Tc, because they are volatile at high temperatures.…”

Section: Vitrificationmentioning

confidence: 99%

Nuclear Waste Management

Cetina

2024

Kem. ind. (Online)

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Nuclear energy production generates nuclear waste. Nuclear and radioactive waste, especially high level waste (HLW) and intermediate level waste (ILW), require special long-term safe management solutions. One part of the solution involves recycling through reprocessing of spent nuclear fuel. Recycling reduces the volume of nuclear waste and allows for the reuse of some of its components. This can be achieved through methods such as adsorption, ion exchange, coagulation, flotation, filtration, chemical precipitation, reverse osmosis, and solvent extraction, like the PUREX process. Another possible future solution involves partitioning and transmutation technology, which can reduce the production of nuclear waste. The best long-term solution is the immobilisation of HLW and ILW in a solid matrix. Materials used for this purpose include glasses, cements, bitumen, geopolymers, concrete, and ceramics as a promising material. While cementation is still the most commonly used immobilisation method due to its low cost and simplicity, vitrification is a more permanent long-term solution. Deep geological disposal in combination with vitrification and a robust multi-barrier system is considered the most acceptable solution for safe nuclear waste isolation. This review provides insight into the mostly commonly used and promising immobilisation materials, as well as the most effective methods and technologies currently in use and under development for the management of HLW and ILW in nuclear waste management.

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Section: Vitrificationmentioning

confidence: 99%

Nuclear Waste Management

Cetina

2024

Kem. ind. (Online)

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“…Consequently, glass gall (the "yellow phase"), which is often observed in a ceramic melter [9] where the layer of calcination products is stable and the temperature on the surface is much lower than in the interior volume of the melt, is not formed on the surface of the glass mass in a cold crucible, at least, at the sulfate and chloride concentrations indicated above.…”

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confidence: 96%

Vitrification of a surrogate for high-level wastes from the Savannah River plant (USA) on a cold-crucible bench facility

Kobelev¹,

Stefanovskii²,

Zakharenko³

et al. 2007

At Energy

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Two experiments on the vitrification of a surrogate for the wastes from the Savannah River plant (USA) have been performed on a cold-crucible (inner diameter 216 mm) induction-melting bench facility at the Moscow Scientific and Industrial Association Radon (1.76 MHz, 60 kW). To obtain borosilicate glasses with two compositions containing 45 mass % oxides of the wastes (computed) a slurry with moisture content about 60 mass % and a mixture of reagents as the glass-forming additives gave a mass velocity of the slip 8 kg/h on average, glass output about 2 kg/h, and specific glass product rate about 47 kg/(m 2 ⋅h). The specific energy consumption was 20 kW⋅h/kg. It was shown that the mass velocity of the slip can be increased to 18 kg/h. Switching to glass-forming additives consisting of the special borosilicate frit-200 and -320 and lowering the water content in the slurry to 25-30 mass % increases the productivity of the process by 15-35%. The specific glass production rate reaches 100 kg/(m 2 ⋅h). The glasses produced contained a small quantity of a magnetitic spinel phase.Vitrification is now the best developed method of solidifying liquid radioactive wastes, especially high-level wastes. High-level wastes are vitrified commercially in metal induction melters at the average frequency (10-50 kHz) or joule-heated ceramic melters. One of the new methods being developed most intensively in France and our country is induction melting in a cold crucible at frequencies above 300 kHz, for example, in the Moscow Scientific and Industrial Association Radon facility for vitrifying medium-level wastes at 1760 kHz. This technology is of interest because it has certain advantages, such as a higher specific capacity and no contact between the melt and the refractories and electrodes, which increases the life span and operational reliability of the melter and allows much smaller dimensions thereby facilitating disassembly and removal after the melter is removed from operation [1,2].The experiments described in the present paper on the vitrification of surrogates of high-level wastes from one of the facilities of the US Department of Energy were performed within the framework of a signed contract. The objective of the present paper is to estimate the technological parameters of cold-crucible induction melting of a charge containing a surrogate of one form of high-level wastes (SB2) from the Savannah River facility and to determine the structure and properties of the glasses in order to compare them with those obtained in the USA using a ceramic melter.

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Transport of a passive scalar across a protective wall-jet in a pipe. Part I: Data acquisition

Tesař¹

2011

Chemical Engineering Research and Design

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Vitrification of sulfate- and chloride-containing radioactive waste in an electric furnace

Cited by 4 publications

References 2 publications

Nuclear Waste Management

Nuclear Waste Management

Vitrification of a surrogate for high-level wastes from the Savannah River plant (USA) on a cold-crucible bench facility

Transport of a passive scalar across a protective wall-jet in a pipe. Part I: Data acquisition

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