Behavior of the Fuel Elements of Floating Power-Generating Units Under Irradiation by Kulakov, G. V., Vatulin, A. V., Ershov, S. A., Konovalov, Yu. V., Morozov, A. V., Sorokin, V. I., Fedotov, V. V., Shishin, V. Yu, Ovchinnikov, V. A., Shel’dyakov, A. A.

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Analysis of the Effect of the Stress-Strain State of Irradiated Zirconium-Alloy Fuel-Element Cladding on Hydride Orientation by Kulakov, G. V., Vatulin, A. V., Konovalov, Yu. V., Kosaurov, A. A., Peregud, M. M., Korotchenko, E. A., Shishin, V. Yu, Shel’dyakov, A. A.

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High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding by Kulakov, G. V., Konovalov, Yu. V., Vatulin, A. V., Kosaurov, A. A., Shishin, V. Yu, Shel’dyakov, A. A., Romanov, A. I., Morozov, O. A., Samoilov, O. B.

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Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation by Kulakov, G. V., Konovalov, Yu. V., Kosaurov, A. A., Peregud, M. M., Nikulina, A. B., Shishin, V. Yu, Ovchinnikov, V. A., Shel’dyakov, A. A.

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Testing of Dispersion Type Fuel Rods with a Heat-Proof Meat with Controlled Porosity for Small Nuclear Power Plants by Savchenko, A. M., Konovalov, Yu. V., Kulakov, G. V., Maranchak, S. V., Ershov, S. A., Mainikov, E. V., Kozlov, A. V., Shishin, V. Yu, Sheldyakov, A. A., Yakovlev, V. V.

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Peculiarities of Application of the Gas Extraction Method for Determination of Hydrogen Content in Samples of Irradiated Zirconium Materials by Shishalova, G. V., Kobylyansky, G. P., Sheldyakov, A. A., Shishin, V. Yu, Novikov, A. M.

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COMPARATIVE ANALYSIS OF STRUCTURAL CHANGES IN U-MO DISPERSED FUEL OF FULL-SIZE FUEL ELEMENTS AND MINI-RODS IRRADIATED IN THE MIR REACTOR by IZHUTOV, ALEKSEY. L., IAKOVLEV, VALERIY. V., NOVOSELOV, ANDREY. E., STARKOV, VLADIMIR. A., SHELDYAKOV, ALEKSEY. A., SHISHIN, VALERIY. YU, KOSENKOV, VLADIMIR. M., VATULIN, ALEKSANDR. V., DOBRIKOVA, IRINA. V., SUPRUN, VLADIMIR. B., KULAKOV, GENNADIY. V.

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