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    Article

    Experimental Investigations of the Coolant Flow in the Fuel Assembly of the Fissile Core of the Reactor of a Small Nuclear Power Plant

    The results are presented of experimental investigations of the coolant flow in a bundle of fuel elements of a fuel assembly of a RITM-type reactor of a small nuclear power plant. The goal of this work is to i...

    S. M. Dmitriev, A. A. Dobrov, D. V. Doronkov in Journal of Engineering Physics and Thermop… (2022)

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    Article

    Investigation of Coolant Flow in an RITM-Reactor Fuel Cassette

    The results of coolant flow investigations of a fuel rod bundle of an RITM-reactor fuel cassette for a small nuclear power plant are reported. The purpose of this work is to investigate the redistribution of t...

    S. M. Dmitriev, V. I. Polunichev, A. E. Khrobostov, D. N. Solntsev in Atomic Energy (2021)

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    Article

    Reactor Installations for Nuclear Icebreakers: Origination Experience and Current Status

    OKBM Afrikantov has been develo** power installations for the icebreaker fleet for more than 60 years. The first generation of reactor installations is represented by the OK-150 loop-type installation for th...

    D. L. Zverev, Yu. P. Fadeev, A. N. Pakhomov, V. Yu. Galitskikh in Atomic Energy (2020)

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    Article

    The World’s First Floating NPP: Origination and Direction of Future Development

    The main stages of the origination (in our country) of the world’s first floating nuclear thermal power plant based on the floating power-generating unit Akademik Lomonosov with two icebreaker-type reactor ins...

    V. M. Belyaev, M. A. Bol’shukhin, A. N. Pakhomov, A. M. Khizbullin in Atomic Energy (2020)

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    Article

    Nuclear Power Plants for the Icebreaker Fleet and Power Generation in the Arctic Region: Development Experience and Future Prospects

    The technical characteristics of a power series of reactor installations developed at Afrikantov OKBM are presented. The technical qualities making facilities equipped with modern ship reactor installations co...

    D. L. Zverev, Yu. P. Fadeev, A. N. Pakhomov, V. I. Polunichev in Atomic Energy (2019)

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    Article

    Conceptual Design of Small NPP with RITM-200 Reactor

    A small ground-based nuclear power plant with two RITM-200 reactors is examined. The plant is intended for electric and thermal energy production and desalination of water. The general layout of the site, arra...

    V. V. Petrunin, Yu. P. Fadeev, A. N. Pakhomov, K. B. Veshnyakov in Atomic Energy (2019)

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    Article

    RITM-200: new-generation reactor for a new nuclear icebreaker

    The main technical solutions incorporated in the design of the RITM-200 reactor for a new-generation nuclear icebreaker are presented. Its special feature is an extended service life compared with icebreakers ...

    D. L. Zverev, A. N. Pakhomov, V. I. Polunichev, K. B. Veshnyakov in Atomic Energy (2013)

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    Service life extension and safety enhancement of ship reactors

    The results of operation and the present state of the nuclear icebreaker fleet are presented. The fundamentals of service life extension of reactors on nuclear icebreakers are presented. The complex of researc...

    V. V. Petrunin, Yu. P. Fadeev, V. A. Panov, A. N. Pakhomov in Atomic Energy (2013)

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    Article

    Analysis of questions concerning the nonproliferation of fissile materials for low-and medium-capacity nuclear power systems

    The principles used in the design of low- and medium-power nuclear power systems to decrease the proliferation risk for nuclear materials as well as the results of a comparative analysis of GT-MGR, KLT-40, ABV...

    V. V. Petrunin, V. I. Polunichev, Yu. P. Sukharev, V. I. Alekseev in Atomic Energy (2008)

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    Article

    Floating power-generating unit with a KLT-40S reactor system for desalinating sea water

    It is concluded on the basis of predictions of the growth in demand for fresh water that nuclear desalination has promise. The world status of and experience in nuclear desalination are reviewed. The requireme...

    V. I. Kostin, Yu. K. Panov, V. I. Polunichev, I. E. Shamanin in Atomic Energy (2007)

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    Article

    Development and investigation of the regulator of the passive heat-removal system for the Kudankulam nuclear power plant (India)

    A system for passive removal of the residual heat released in VVÉR-1000 with a heat-removal regulator in the form of an air damper operating passively is described. The main results of the computational and ex...

    V. I. Polunichev, G. P. Shumailov, P. A. Gorbunov, M. M. Grigor’ev in Atomic Energy (2007)

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    Article

    Reactor systems in nuclear-powered ships — present status, service life extension, and prospects

    The main results of the operation of nuclear-powered ships (icebreakers) and their reactor systems are presented. Information about the operating time of the ship reactors and the results of operating individu...

    V. I. Kostin, Yu. K. Panov, V. I. Polunichev, O. A. Yakovlev in Atomic Energy (2007)

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    Article

    Prospects for Using Nuclear Power Systems in Commercial Ships in Northern Russia

    The experience gained over many years of operating nuclear-powered ice breakers in conquering the northern sea route is described. The conditions which must be met for year-round navigation of cargo ships in t...

    F. M. Mitenkov, O. A. Yakovlev, V. I. Polunichev, Yu. K. Panov in Atomic Energy (2003)

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    Article

    Experience in Building and Operating Reactor Systems for Civilian Ships

    The steps taken in our country to develop reactor systems for several generations for ships for the nuclear-powered civilian fleet, starting with the icebreaker “Lenin,” are described. The characteristics of t...

    V. I. Makarov, B. G. Pologikh, N. S. Khlopkin, F. M. Mitenkov in Atomic Energy (2000)

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    Article

    Gas-transfer kinetics and regulation of the gas content of coolant in the first loop of a water-cooled-water-moderated reactor

    V. I. Polunichev, N. Ya. Spir'yanov in Atomic Energy (1992)