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    Article

    Pum** Equipment for Nuclear Energy and the Non-Nuclear Market

    OKBM Afrikantov possesses unique experience in develo** different types of highly reliable pum** equipment. The pum** equipment developed at the enterprise possesses high safety and reliability metrics a...

    D. L. Zverev, A. V. Vasyaev, S. V. Babushkin, I. B. Korobov in Atomic Energy (2020)

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    Article

    Reactor Installations with Sodium-Cooled Fast Reactors for Two-Component Nuclear Energy

    The experience of origination and operation of BN-600, -800 and development of BN-1200 commercial power units of two-component nuclear energy are recounted. Substantiation is given for the engineering solution...

    S. V. Babushkin, B. A. Vasil’ev, A. V. Vasyaev, V. E. Vorontsov in Atomic Energy (2020)

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    Article

    Gen-IV Reactor Systems Criteria Implementation in BN-1200

    The design of the BN-1200 sodium-cooled fast reactor is analyzed from the standpoint of its compliance with the criteria fitting the promising Gen-IV reactor facilities. The basic technical solutions adopted i...

    Yu. M. Ashurko, A. V. Gulevich, D. A. Klinov, B. A. Vasil’ev in Atomic Energy (2019)

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    Article

    Similarity of high-temperature gas-cooled reactor technologies and designs in Russia and USA

    Historical information concerning the development of high-temperature gas-cooled reactors in the USA and Russia is presented. The reactor facilities MHTGR (USA), VG-400 (Russia), VGM (Russia), GT-MGR (Russia, ...

    N. N. Ponomarev-Stepnoi, N. G. Abrosimov, A. V. Vasyaev, M. E. Ganin in Atomic Energy (2010)

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    Article

    Development of a design for the GT-MHR energy conversion unit

    Since 1995, the General Atomics Company (USA) and OKBM have been jointly develo** a design for GT-MHR — a modular helium-cooled reactor and energy-conversion unit with a direct gas-turbine cycle. The reactor...

    V. I. Kostin, N. G. Kodochigov, S. E. Belov, A. V. Vasyaev, V. F. Golovko in Atomic Energy (2007)

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    Article

    Substantiation of the parameters and layout solutions for an energy conversion unit with a gas-turbine cycle in a nuclear power plant with HTGR

    Light is shed on questions concerning the application of a direct closed gas-turbine cycle for generating electricity in a nuclear power plant with HTGR. This makes it possible to use such reactor systems for ...

    A. V. Vasyaev, V. F. Golovko, I. V. Dmitrieva, N. G. Kodochigov in Atomic Energy (2005)

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    Article

    High-temperature gas-cooled reactors — energy source for industrial production of hydrogen

    High-temperature helium-cooled reactors are the best understood nuclear technology that can supply high-temperature heat for thermal processes for producing hydrogen. The GT-MGR reactor — an innovative interna...

    F. M. Mitenkov, N. G. Kodochigov, A. V. Vasyaev, V. F. Golovko in Atomic Energy (2004)