Recommendations for calculating the rate of irradiation-induced creep of oxide fuel when analyzing fuel-element serviceability von Malygin, V. B., Naboichenko, K. V., Shapovalov, A. S., Bibilashvili, Yu. K.

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Recommendations for calculating the thermal creep properties of uranium dioxide when analyzing fuel-element serviceability von Malygin, V. B., Naboichenko, K. V., Shapovalov, A. S., Bibilashvili, Yu. K.

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Recommendations for calculating the characteristics of thermal creep of mixed uranium–plutonium oxide fuel when analyzing fuel-element serviceability von Malygin, V. B., Naboichenko, K. V., Shapovalov, A. S., Bibilashvili, Yu. K.

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Study of VVER fuel with dopant additives von Novikov, V. V., Bibilashvili, Yu. K., Mikheev, E. N., Grachev, A. F., Kalygin, V. V., Ovchinnikov, V. A., Kobylyanskii, G. P.

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Simulational testing of materials von Baranov, V. M., Kudryavtsev, E. M., Bibilashvili, Yu. K.

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Experimental investigation of the deformation behavior of claddings of Zr-1% Nb alloy in the presence of iodine at elevated temperatures von BIBILASHVILI, Yu. K, MEDVEDEV, A. V, SOTNIKOV, A. S, SOKOLOV, N. B, STEKACHEV, Yu. V, ANDREEVA-ANDRIEVSKAYA, L. N

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Fatigue testing of materials under extremal conditions by acoustic method von Baranov, V. M., Bibilashvili, Yu. K., Karasevich, V. A., Sarychev, G. A.

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Simulation of Heat Emission from Fuel Element Cladding with Rapid Energy Input von Antonova, L I, Afanas'eva, E Yu, Drobyazko, S V, Evdokimov, I A, Kurchatov, S Yu, Likhanskii, V V, Senatorov, Yu M, Khoruzhii, O V, Bibilashvili, Yu K, Nechaeva, O A

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Tubes of Dispersion-Hardened Powder Steel Kh13M2T for the Nuclear Power Industry von Suslov, A G, Barskaya, R A, Medvedeva, E A, Bibilashvili, Yu K

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The initiation of cracks in cladding tubes of Zr-1%Nb alloy under stress corrosion cracking conditions von Bibilashvili, Yu. K., Dolgov, Yu. N., Novikov, V. V., Glazkov, A. G.

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Investigation of the growth rate of cracks in shells made of the alloy Zr-1%Nb under conditions of iodine corrosion cracking under stress von Bibilashvili, Yu. K., Dolgov, Yu. N., Nesterov, B. I., Novikov, V. V.

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Experience with uranium-erbium fuel at the Ignalinsk Atimic Power Plant von Shevaldin, V N, Negrivoda, G P, Vorontsov, BA, Robom'ko, A V, Burlakov, E V, Krayushkin, A V, Fedosov, A M, Tishkin, YuA, Novikov, V G, Panyushkin, A K, Kupalov-Yaropolk, AI, Nikolaev, V A, Bibilashvili, YuK, Yamnikov, V S

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Thermophysical means for nondestructive investigation of the airtightness and gas parameters in reactor fuel elements von Pastushin, V. V., Novikov, A. Yu, Zelenchuk, A. V., Bibilashvili, Yu. K.

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Acoustic method for investigating the parameters of gas in reactor fuel elements von Pastushin, V. V., Bibilashvili, Yu. K., Sharapa, A. I.

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Iodine diffusion in the alpha phase of Zr-1% Nb alloy von Gladkov, V. P., Petrov, V. I., Svetlov, A. V., Smirnov, E. A., Tenishev, V. I., Bibilashvili, Yu. K., Novikov, V. V.

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Influence of irradiation on KISCC of Zr–1%Nb claddings von Bibilashvili, Yu.K, Medvedev, A.V, Nesterov, B.I, Novikov, V.V, Golovanov, V.N, Eremin, S.G, Yurtchenko, A.D

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Flow-area blockage of fuel assemblies of a water-moderated, water-cooled power reactor in a loss-of-coolant accident von Solyanyi, V. I., Andreeva-Andrievskaya, L. N., Bibilashvili, Yu. K., Salatov, A. V., Tonkov, V. Yu

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In-reactor study of the friction characteristics of reactor materials von Shchavelin, V. M., Kostochka, A. V., Kuznetsov, A. A., Golovnin, I. S., Bibilashvili, Yu. K.

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Homogeneity in zirconium fuel-pin cladding von Anufriev, B. F., Baranov, V. M., Bibilashvili, Yu. K., Golovnin, I. S., Isaenkova, M. G., Kalyadin, A. Yu, Perlovich, Yu. A., Tonkov, V. Yu

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Effects of irradiation on the elastoplastic deformation of Zr+1%Nb fuel pin cladding von Matushkin, V. A., Medvedev, A. A., Miloserdin, Yu. V., Semenov, B. D., Bibilashvili, Yu. K., Golovnin, I. S.

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