Application of Direct Numerical Simulation to Determine the Correlation Describing Friction Losses during the Transverse Flow of Fluid in Hexagonal Array Pin Bundles by Shvetsov, Yury E., Khomyakov, Yury S., Bayaskhalanov, Mikhail V., Dichina, Regina P.

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Studies on Influence of Sodium Void Reactivity Effect on the Concept of the Core and Safety of Advanced Fast Reactor by POPLAVSKY, Vladimir, MATVEEV, Vyacheslav, ELISEEV, Vladimir, KUZNETSOV, Igor, VOLKOV, Andrey, SHVETSOV, Yury, KHOMYAKOV, Yury, TSIBOULIA, Anatoly

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Studies on Influence of Sodium Void Reactivity Effect on the Concept of the Core and Safety of Advanced Fast Reactor by POPLAVSKY, Vladimir M., MATVEEV, Vyacheslav I., ELISEEV, Vladimir A., KUZNETSOV, Igor A., VOLKOV, Andrey V., SHVETSOV, Yury E., KHOMYAKOV, Yury S., TSIBOULIA, Anatoly M.

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Identification of the Sintering Mechanism of Oxide Nuclear Fuel through the Analysis of Experimental Pore Size Distributions by Devyatko, Yury N., Khomyakov, Oleg V., Tenishev, Andrey V., Matvenov, Maxim E., Shornikov, Dmitry P.

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Determination of Density and Pore Size Distribution in Uranium Dioxide Fuel Pellet by Image Analysis of its Cross-Sectional Structure by Devyatko, Yury N., Khomyakov, Oleg V., Tenishev, Andrey V., Mikhalchik, Vladimir V., Shornikov, Dmitry P.

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Determination of equilibrium fuel composition for fast reactor in closed fuel cycle by Ternovykha, Mikhail, Tikhomirov, Georgy, Khomyakov, Yury, Suslov, Igor

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