Please use this identifier to cite or link to this item: http://hdl.handle.net/10995/102317
Title: Research of oxygen-conducting ceramic materials for lithium chloride melt in reactors for pyrochemical processing of spent nuclear fuel
Authors: Valtseva, A. I.
Pershin, P. S.
Suzdaltsev, A. V.
Zaikov, Yu. P.
Issue Date: 2020
Publisher: IOP Publishing Ltd
Citation: Research of oxygen-conducting ceramic materials for lithium chloride melt in reactors for pyrochemical processing of spent nuclear fuel / A. I. Valtseva, P. S. Pershin, A. V. Suzdaltsev, et al. — DOI 10.1088/1742-6596/1683/3/032029 // Journal of Physics: Conference Series. — 2020. — Vol. 1683. — Iss. 3. — 032029.
Abstract: The behavior of potential ceramic materials (electrolytes conducting on oxygen ions) of electrochemical control devices of technological operations in oxide-halide melts was investigated. Based on the literature data and thermodynamic estimates for long-term tests in the LiCl, LiCl-Li2O and LiCl-Li2O-Li melts at a temperature of 650 ° C, mixtures of oxides ZrO2- Y2O3(YSZ), ZrO2-Sc2O3(ScSZ), ZrO2-CaO (CaSZ) and CeO2-Gd2O3(CGO) were selected. These melt under the studies are the most widely used in a number of high-temperature electrochemical processes of obtaining metals and alloys, as well as in the developed schemes of pyrochemical processing of nuclear fuel. The stability of the samples was determined by changes in mass, appearance, elemental analysis of the melt, as well as via the scanning electron microscopy. The best stability in LiCl-Li2O melts was shown by the samples of ZrO2-Y2O3with cubic and tetragonal structures and the samples of ZrO2-CaO. Based on the changes in the microstructure of the samples, it was concluded that the increase in the content of Li2O in the LiCl-Li2O melt accelerates the destruction of the sample mainly by the mechanism of dyeing, and the presence of lithium leads to loosening of the samples. © 2020 Institute of Physics Publishing. All rights reserved.
Keywords: CALCIUM OXIDE
CERIUM OXIDE
LITHIUM CHLORIDE
METALLURGY
NUCLEAR FUELS
OXYGEN
SCANNING ELECTRON MICROSCOPY
YTTRIA STABILIZED ZIRCONIA
YTTRIUM METALLOGRAPHY
ZIRCONIA
ELECTROCHEMICAL CONTROL
HIGH-TEMPERATURE ELECTROCHEMICAL
LITERATURE DATA
METALS AND ALLOYS
PYROCHEMICAL PROCESSING
SPENT NUCLEAR FUELS
TECHNOLOGICAL OPERATIONS
TETRAGONAL STRUCTURE
THERMAL ENGINEERING
URI: http://hdl.handle.net/10995/102317
Access: info:eu-repo/semantics/openAccess
SCOPUS ID: 85099537298
PURE ID: 20519096
c6629bd7-4f18-422b-a174-d8a909fe2297
ISSN: 17426588
DOI: 10.1088/1742-6596/1683/3/032029
Appears in Collections:Научные публикации, проиндексированные в SCOPUS и WoS CC

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