Status on performance study of mixed nitride fuel pins of BREST reactor type von Zabudko, L.M., Grachev, A.F., Zherebtsov, A.A., Lachkanov, E.V., Mochalov, Yu.S., Skupov, M.V., Ivanov, Yu.A., Kryukov, F.N., Zvir, E.A.

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Impact of Thermal Tests Simulating Dry Storage of VVER-1000 Fuel on the Hydride Phase Morphology in Fuel Element Claddings von Mazaev, A. O., Kobylyansky, G. P., Zvir, E. A., Shishalova, G. V., Minduksheva, I. A.

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Results of Investigations of BREST-Type Reactor Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel, Irradiated in BOR-60 and BN-600 von Grachev, A. F., Zherebtsov, A. A., Zabud’ko, L. M., Zvir, E. A., Kryukov, F. N., Nikitin, O. N., Skupov, M. V., Ivanov, Yu. A., Porollo, S. I.

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Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding von Grachev, A. F., Zabud’ko, L. M., Ivanov, Yu. A., Skupov, M. V., Zvir, E. A., Kryukov, F. N., Nikitin, O. N., Marinenko, E. E., Porollo, S. I.

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Investigations of Mixed Uranium-Plutonium Nitride Fuel in Project Breakthrough von Grachev, A. F., Zabud’ko, L. M., Glushenkov, A. E., Ivanov, Yu. A., Kireev, G. A., Skupov, M. V., Gil’mutdinov, I. F., Grin’, P. I., Zvir, E. A., Kryukov, F. N., Nikitin, O. N.

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