Search Results - "Novoselov, I. Yu"

Electrochemical treatment of irradiated nuclear graphite by Bespala, E.V., Antonenko, M.V., Chubreev, D.O., Leonov, A.V., Novoselov, I. Yu, Pavlenko, A.P., Kotov, V.N.

“…The paper is dedicated to the issues of accumulation of irradiated reactor graphite and possible options for handling it. There are described the advantages of…”
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Dynamics of temperature fields during Wigner energy release in bulk graphite irradiated at low temperature by Pavliuk, A.O., Kotlyarevsky, S.G., Bespala, E.V., Novoselov, I. Yu

“…This paper is concerned with determination of parameters associated with release of the energy accumulated in irradiated graphite. These parameters define the…”
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Plasma-Chemical Synthesis and Investigation of Nano-Size Oxide Compositions Simulating Uranium-Thorium Dispersion Nuclear Fuel by Shamanin, I. V., Karengin, A. G., Karengin, A. A., Novoselov, I. Yu

“…A promising direction of advancement in nuclear energy is the use of uranium-thorium dispersion nuclear fuel, which consists of fissile metal (uranium,…”
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Analysis of the Causes of Irregular 36Cl Radionuclide Distribution in Irradiated Nuclear Graphite by Bespala, E. V., Pavlyuk, A. O., Kotlyarevskiy, S. G., Novoselov, I. Yu

“…— The article is dedicated to analyzing the concentration processes of the long-lived 36 Cl radionuclide in irradiated graphite of uranium-graphite nuclear…”
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Plasma-Chemical Synthesis of Nanostructured Oxide Compounds for Accident Tolerant Fuel by Karengin, A. G., Karengin, A. A., Kuznetsov, S. Yu, Novoselov, I. Yu, Tikhonov, A. E., Golovkov, N. I.

“…The use of the accident tolerant fuel is one of promising development trends of nuclear power. This fuel contains metal oxides uniformly distributed in the…”
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Heat Treatment of Irradiated Graphite in an Oxidizing Atmosphere by Bespala, E. V., Pavlyuk, A. O., Kotlyarevskii, S. G., Novoselov, I. Yu, Bespala, Yu. R.

“…It was demonstrated that thermal treatment and decontamination methods can be used for the processing of irradiated nuclear graphite. Special features of the…”
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Study of evaporating the irradiated graphite in equilibrium low-temperature plasma by Bespala, E. V., Novoselov, I. Yu, Pavlyuk, A. O., Kotlyarevskiy, S. G.

“…The paper describes a problem of accumulation of irradiated graphite due to operation of uranium-graphite nuclear reactors. The main noncarbon contaminants…”
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Investigation of Plasma-Chemical Synthesis of Complex Oxide Compositions for Dispersed Uranium-Plutonium Mixed Fuel by Shamanin, I. V., Karengin, A. G., Karengin, A. A., Novoselov, I. Yu, Rastorguev, V. I.

“…The central problems of using ceramic nuclear fuel fabricated from uranium dioxide enriched in uranium-235 are low thermal conductivity, high disposal costs,…”
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Study of irradiated graphite-bakelite paste by Bespala, E.V., Antonenko, M.V., Bespala, Yu.R., Kotov, V.N., Novoselov, I.Yu

“…•The study of irradiated graphite-bakelite paste from a uranium-graphite reactor was carried out for the first time.•The radionuclide composition and the rate…”
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Heat and Mass Transfer in Cesium Evaporation from Graphite Surface in Argon by Bespala, E. V., Myshkin, V. F., Pavlyuk, A. O., Novoselov, I. Yu

“…The aim of the present work is mathematical modeling of the heat and mass transfer of 137 Cs under the action of low-temperature equilibrium plasma flow on…”
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