Search Results - "MARANCHAK, S. V"
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Fuel cycles with advanced dispersion fuel elements of high uranium density
Published in Atomic energy (New York, N.Y.) (01-07-2023)“…The paper considers the possibility of replacing container fuel elements of thermal reactors with uranium dioxide or mixed oxide uranium-plutonium fuel with…”
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Testing of Dispersion Type Fuel Rods with a Heat-Proof Meat with Controlled Porosity for Small Nuclear Power Plants
Published in Atomic energy (New York, N.Y.) (01-04-2022)“…The results of development work on dispersion type fuel rods, whose meat, containing granules of a uranium-molybdenum alloy in a matrix of special zirconium…”
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Zirconium alloys matrix as innovative material for composite fuel
Published in Progress in nuclear energy (New series) (01-05-2012)“…A novel class of zirconium alloys is suggested as fuel matrix. They are “deep” ternary or quaternary eutectics having relatively low melting point i.e. from…”
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Inert matrix fuel with low melting point zirconium brazing alloys
Published in Journal of nuclear materials (30-06-2006)“…Several versions of inert matrix fuel (IMF) using low melting point zirconium brazing alloys are suggested to improve their utilisation. The alloys are…”
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Inert matrix fuel with low melting point zirconium brazing alloys : Nuclear Materials
Published in Journal of nuclear materials (2006)Get full text
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