Scientific and technical problems of CNFC in two-component NPE and their solution in "Proryv" project von Rachkov, V I, Adamov, E O

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Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation von Adamov, E. O., Kaplienko, A. V., Orlov, V. V., Smirnov, V. S., Lopatkin, A. V., Lemekhov, V. V., Moiseev, A. V.

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REMOVED: RBMK plants in the Soviet and Russian nuclear power industry von Adamov, E.O.

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New Technological Platform for the National Nuclear Energy Strategy Development von Adamov, E. O., Rachkov, V. I.

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On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy von Adamov, E. O., Ivanov, V. K., Mochalov, Yu. S., Rachkov, V. I., Shadrin, A. Yu, Khomyakov, Yu. S., Lachkanov, E. V., Orlov, A. I.

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Spent Nuclear Fuel Reprocessing and Nuclear Materials Recycling in Two-Component Nuclear Energy von Adamov, E. O., Mochalov, Yu. S., Rachkov, V. I., Khomyakov, Yu. S., Shadrin, A. Yu, Kascheev, V. A., Khaperskaya, A. V.

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Role of NPPs in the Russian Electricity Industry Taking into Account Carbon Emissions Limits von Adamov, E. O., Tolstoukhov, D. A., Panov, S. A., Veselov, F. V., Khorshev, A. A., Solyanik, A. I.

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Key Outcomes of Comprehensive Computational and Experimental Validation of Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel for the BN-1200 and Brest Reactors von Adamov, E. O., Grachev, A. F., Zabudko, L. M., Lachkanov, E. V., Mochalov, Yu. S., Belyaeva, A. V., Kryukov, F. N., Ivanov, Yu. A., Skupov, M. V., Marinenko, E. E., Porollo, S. I.

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Development of Fuel Pin with Uranium-Plutonium Nitride Fuel and Liquid-Metal Sublayer von Adamov, E. O., Zabud’ko, L. M., Mochalov, Yu. S., Rachkov, V. I., Khomyakov, Yu. S., Kryukov, F. N., Skupov, M. V.

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Service Life Restoration Technology for RBMK: Design, Implementation, and Assimilation Experience von Adamov, E. O., Dragunov, Yu. G., Slobodchikov, A. V., Mikhailov, M. N., Petrov, A. A., Ukharov, S. G., Burlakov, E. V., Asmolov, V. G., Chernikov, O. G., Bystrikov, A. A., Kudryavtsev, K. G., Lozhnikov, I. N., Kharakhnin, S. N.

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Comparison of the technical and economic parameters of different variants of the nuclear fuel cycle reactors of the nuclear power plants von Adamov, E. O., Rachkov, V. I., Tolstoukhov, D. A., Panov, S. A.

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Conceptual framework of a strategy for the development of nuclear power in Russia to 2100 von Adamov, E. O., Dzhalavyan, A. V., Lopatkin, A. V., Molokanov, N. A., Muravyov, E. V., Orlov, V. V., Kal’akin, S. G., Rachkov, V. I., Troyanov, V. M., Avrorin, E. N., Ivanov, V. B., Aleksakhin, R. M.

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In memory of Viktor Nikitovich Mikhailov von Avrorin, E.N., Adamov, E.O., Voloshin, N.P., Ilkaev, R.I., Kokoshin, A.A., Neznamov, Vasilii P., Pertsev, S.F., Rumyantsev, Aleksandr Yu, Rykovanov, G.N., Ryabev, Lev D.

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Self-consistent model of nuclear power and nuclear fuel cycle von Adamov, E.O, Ganev, I.Kh, Lopatkin, A.V, Orlov, V.V, Smirnov, V.S

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Prospects and problems using vanadium alloys as a structural material of the first wall and blanket of fusion reactors von Votinov, S.N., Solonin, M.I., Kazennov, Yu.I., Kondratjev, V.P., Nikulin, A.D., Tebus, V.N., Adamov, E.O., Bougaenko, S.E., Strebkov, Yu.S., Sidorenkov, A.V., Ivanov, V.B., Kazakov, V.A., Evtikhin, V.A., Lyublinski, I.E., Trojanov, V.M., Rusanov, A.E., Chernov, V.M., Birgevoj, G.A.

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Inherently safe pool-type reactor as a generator of low-grade heat for district heating, air conditioning and salt water desalination von Adamov, E.O., Cherkashov, Yu.M., Romenkov, A.A., Mikhan, V.I., Semenikhin, V.I.

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The raw material and waste activity balance in the projected nuclear power of Russia von Adamov, E.O., Ganev, I.Kh, Lopatkin, A.V., Muratov, V.G., Orlov, V.V.

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Channel reactors: Status and prospects von Adamov, E. O.

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Status and prospects for pressure-tube water-cooled graphite-moderated reactors von Adamov, E.O., Grozdov, I.I., Petrov, A.A., Cherkashov, Yu.M., Burlakov, E.V., Kramerov, A.Ya

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Perspective channel-type reactor with enhanced safety von Adamov, E.O., Grozdov, I.I., Kuznetsov, S.P., Petrov, A.A., Rozhdestvensky, M.I., Cherkashov, Yu.M.

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