Mitenkov, F.M.; Antonovskij, G.M.; Belyaev, A.A.; Runov, B.I.; Smirnov, M.V.
Heavy liquid-metal coolants in the nuclear technologies. Collection of the conference reports in two volumes. Volume 11999
Heavy liquid-metal coolants in the nuclear technologies. Collection of the conference reports in two volumes. Volume 11999
AbstractAbstract
[en] One analyzes the records of design and operation of OK-550 reactor facility (RF) with lead-bismuth liquid-metal coolant to be incorporated in nuclear power facility of a naval ship. One describes efforts to design reactor, steam generator and turbopump of the primary circuit. One describes the efforts to update equipment on the basis of the test results and of the records of trial operation of a forerunner RF
[ru]
Анализируется опыт создания и эксплуатации оборудования реакторной установки (РУ) ОК-550 с жидкометаллическим теплоносителем свинец-висмут, предназначенной для использования в составе ядерной энергетической установки корабля ВМФ. Описываются разработки конструкций реактора, парогенератора и турбонасосного агрегата 1-го контура. Описана также доработка оборудования по результатам испытаний и опытной эксплуатации головной РУOriginal Title
Opyt sozdaniya i ehkspluatatsii RU OK-550
Primary Subject
Source
Gromov, B.F. (ed.); Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Fiziko-Ehnergeticheskij Inst. im. akademika A.I. Lejpunskogo, Obninsk (Russian Federation); 372 p; 1999; p. 84-87; Heavy liquid-metal coolants in the nuclear technologies; Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh; Obninsk (Russian Federation); 5-9 Oct 1998; Available from FSUE Atominform, Russian Federation, 127434, Moscow, Dmitrovskoe sh., 2. E-mail: mikhnev@ainf.ru; 1 ref.
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[en] The design of the VPBEhR-600 reactor plant consisting of the water cooled and moderated integrated reactor, in the vessel of which the core with control system working devices, direct-current steam generator assemblied of heat-exchanging sections, built-in pressure compensator, main circulation pumps flow sections and heat exchangers-consensers of emergency core cooling system are located, is described. The VPBEhR-600 engineering solutions give an opportunity to create nuclear power plant of a new generation with improved safety basing on technologies well mastered by Russian industry
Original Title
Reaktornaya ustanovka VPBEhR-600 dlya atomnykh stantsij novogo pokoleniya
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Journal Article
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Ehnergeticheskoe Stroitel'stvo; CODEN ENSTAC; (no.12); p. 31-35
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Mitenkov, F.M.; Antonovskij, G.M.; Belyaev, V.M.; Egorov, V.V.; Drozhkin, V.N.; Kurachenkov, A.V.; Panov, Yu.K.; Polunichev, V.I.; Runov, B.I.
From the first NPP in the World towards nuclear industry of the XXI century. Collection of theses of reports and information1999
From the first NPP in the World towards nuclear industry of the XXI century. Collection of theses of reports and information1999
AbstractAbstract
No abstract available
Original Title
Atomnye stantsii maloj moshchnosti - sochetanie shirokikh vozmozhnostej, povyshennoj bezopasnosti, nadezhnosti n ehkonomichnosti
Primary Subject
Source
Yadernoe Obshchestvo Rossii, Moscow (Russian Federation); 256 p; 1999; p. 169-170; 10. Annual conference of the Russian Nuclear Society. From the first NPP in the World towards nuclear industry of the XXI century; 10. Ezhegodnaya konferentsiya Yadernogo Obshchestva Rossii. Ot pervoj v mire AEhS k atomnoj ehnergetike XXI veka; Obninsk (Russian Federation); 28 Jun - 2 Jul 1999; Available from Atominform, Russian Fedaration, 127434, Moscow, P.O. Box 971. Fax: (095) 976-72-03. E-mail: mihn@ai.ru
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[en] Decription of basic design and schematic solutions of the VPBER-600 reactor are given. Technical basis and practical testing of the basis equipment are shown. Design principles of protection and localizing systems are presented. Safety concept based on the reactor inherant selfprotection and application of passive systems and device are formulated. The VPBER-600 reactor exceeds the best foreign facilities of the AP-600 type by the level of their safety
Original Title
Ehnergeticheskij reaktor povyshennoj bezopasnosti VPBEhR-600 dlya AS novogo pokoleniya
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Source
Nuclear technology tomorrow; 3. Ezhegodnaya nauchno-tekhnicheskaya konferentsiya yadernogo obshchestva 'Yadernye tekhnologii v zavtrashnem mire'; Sankt-Peterburg (Russian Federation); 14-18 Sep 1992
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Journal Article
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Antonovskij, G.M.; Kuznetsov, L.E.; Novikov, V.V.; Panov, Yu.K.; Runov, B.I.; Flerov, L.N.; Kovrizhnikov, V.M.; Kuznetsov, Yu.A.; Nikiporets
Physics of radiation damage and radiation materials technology1994
Physics of radiation damage and radiation materials technology1994
AbstractAbstract
[en] This installation has a series of safety barriers and can be used in electricity or heat producing plants. A description of its parameters and technical solutions is given
Original Title
Reaktornaya ustanovka passivnoj bezopasnosti VPBEh-600 dlya AS srednej moshchnosti novogo pokoleniya
Primary Subject
Source
Natsional'nyj Nauchnyj Tsentr, Kharkov (Ukraine). Khar'kovskij Fiziko-Tekhnicheskij Inst; Voprosy atomnoj nauki i tekhniki. Fizika radiatsionnykh povrezhdenij i radiatsionnoe materialovedenie; v. 2-3(62-63); 151 p; 1994; p. 42-49; ISSN 0134-5400;
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ACCIDENTS, CONTROL SYSTEMS, COOLING SYSTEMS, DESIGN BASIS ACCIDENTS, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, POWER PLANTS, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, REMOVAL, SAFETY, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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