Tests of Models of BREST-OD-300 Reactor Fuel Elements in an Autonomous Lead-Cooled Channel of a BOR-60 Reactor von Kordyukov, A G, Leonov, V N, Pikalov, A A, Sila-Novitskii, A G, Filin, AI, Brovko, V V, Efimov, V N, Korol'kov, A S, Stynda, YuE, Yurchenko, AD, Kostyukov, YuA, Rogozkin, B D, Ryzhov, A A, Ivanov, K D, Martynov, P N, Orlov, YuI, Pevchikh, YuM, Troyanov, V M

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In-reactor investigations of the creep of structural materials von BUL'KANOV, M. G, KRUGLOV, A. S, PEVCHIKH, YU. M, TROYARNOV, V. M

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Radiation creep in 09Kh16N15M3B steel at stresses exceeding the elastic limit von Kruglov, A. S., Bykov, V. N., Pevchikh, Yu. M.

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Creep in 09Kh16N15M3B steel at 623?823 K in a reactor von Kruglov, A. S., Bykov, V. N., Pevchikh, Yu. M., Yurin, O. G., Bul'kanov, M. G.

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Equipment ?VAIR? for mechanical tests on materials in a nuclear reactor von Moseev, V. I., Bul'kanov, M. G., Kruglov, A. S., Pevchikh, Yu. M., Fazkullin, V. A.

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Stress dependence of radiation-induced creep in 09Kh16N15M3B steel at 470 C von Kruglov, A. S., Bykov, V. N., Bul'kanov, M. G., Dmitriev, V. D., Pevchikh, Yu. M., Yurin, O. G.

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Investigation of radiation creep of steel 09Kh16N15M3B in the BR-10 reactor von Kruglov, A. S., Bul'kanov, M. G., Bykov, V. N., Pevchikh, Yu. M.

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Tests of models of BREST-OD-300 reactor fuel elements in an autonomous lead-cooled channel of a BOR-60 reactor von KORDYUKOV, A. G, LEONOV, V. N, KOSTYUKOV, Yu. A, ROGOZKIN, B. D, RYZHOV, A. A, IVANOV, K. D, MARTYNOV, P. N, ORLOV, Yu. I, PEVCHIKH, Yu. M, TROYANOV, V. M, PIKALOV, A. A, SILA-NOVITSKII, A. G, FILIN, A. I, BROVKO, V. V, EFIMOV, V. N, KOROL'KOV, A. S, STYNDA, Yu. E, YURCHENKO, A. D

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