Filters
Results 1 - 10 of 11
Results 1 - 10 of 11.
Search took: 0.025 seconds
| Sort by: date | relevance |
[en] Reactor facilities for advanced nuclear floating thermoelectric power plants and ships are discussed in the report. When developing a reactor facility, a system analysis and optimization of all the components of the power plants with small reactors has been done
[ru]
Реакторные установки для перспективных атомных плавучих теплоэлектростанций и судов представлены в докладе. При разработке реакторной установки проведен системный анализ и оптимизация всех его составляющихSource
Sarkisov, A.A. (ed.); Inst. Problem Bezopasnogo Razvitiya Atomnoj Ehnergetiki Rossijskoj Akademii Nauk, Moscow (Russian Federation); 387 p; ISBN 978-5-906324-04-7; 
; 2015; p. 104-113; 4 figs.; this article was presented at the international conference «Small-sized nuclear power plants: the current direction of nuclear power development» (Moscow, 3-5 Dec 2013)
; 2015; p. 104-113; 4 figs.; this article was presented at the international conference «Small-sized nuclear power plants: the current direction of nuclear power development» (Moscow, 3-5 Dec 2013)
[en] The concept of WBER reactor facilities of block type for regional power production is considered, it is based on combination of technologies of transport nuclear steam generating plants with solutions developed in civil nuclear power industry for core and fuel cycle. Design, technological and operational characteristics of WBER-600 reactor, confirmed by referentiality on the base of ship facilities and WWER fuel, are aimed at ensuring competitive technical-and-economic characteristics of midsize NPP (safety, reliability, maneuverability, flexibility in application, duration and cost of construction, operating cost values). The achieved midsize NPP characteristics allow to consider them as a promising direction of nuclear energy use in addition to the high-power NPP power units
[ru]
Рассмотрена концепция реакторных установок ВБЭР блочного типа для региональной энергетики, которая основана на сочетании технологий транспортных атомных паропроизводящих установок с отработанными в гражданской атомной энергетике решениями по активной зоне и топливному циклу. Конструктивные, технологические и эксплуатационные характеристики реакторной установки ВБЭР-600, подтвержденные референтностью на базе судовых установок и топлива ВВЭР, направлены на обеспечение конкурентоспособных технико-экономических показателей АЭС средней мощности (безопасность, надежность, маневренность, удобство эксплуатации, продолжительность и стоимость сооружения, величина эксплуатационных затрат). Достигнутые проектные показатели АЭС средней мощности позволяют их рассматривать как перспективное направление использования ядерной энергии в дополнение к энергоблокам АЭС большой мощностиSource
Rosehnergoatom (Ehlektroehnergeticheskij Divizion Rosatoma), Moscow (Russian Federation); 800 p; ISBN 978-5-88777-038-3; ; 2016; p. 673-677; 10. International scientific-technical conference ''Safety, efficiency and economics of nuclear energy''; Desyataya Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya «Bezopasnost', ehffektivnost' i ehkonomika atomnoj ehnergetiki»; Moscow (Russian Federation); 25-27 May 2016; 5 figs., 1 tab.
; 2016; p. 673-677; 10. International scientific-technical conference ''Safety, efficiency and economics of nuclear energy''; Desyataya Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya «Bezopasnost', ehffektivnost' i ehkonomika atomnoj ehnergetiki»; Moscow (Russian Federation); 25-27 May 2016; 5 figs., 1 tab.
No abstract available
Source
Aktsionernoe Obshchestvo Ordena Lenina Nauchno-Issledovatel'skij i Konstruktorskij Inst. Ehnergotekhniki imeni N.A. Dollezhalya, Moscow (Russian Federation); 292 p; ISBN 978-5-98706-105-3; ; 2016; p. 162, 162-163; Innovative designs and technologies of nuclear power. 4. International scientific and technical conference; Innovatsionnye proekty i tekhnologii yadernoj ehnergetiki. IV Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya; Moscow (Russian Federation); 27-30 Sep 2016
; 2016; p. 162, 162-163; Innovative designs and technologies of nuclear power. 4. International scientific and technical conference; Innovatsionnye proekty i tekhnologii yadernoj ehnergetiki. IV Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya; Moscow (Russian Federation); 27-30 Sep 2016
No abstract available
Source
Trufanov, A.A.; Sorokin, A.P. (eds.); Predpriyatie Goskorporatsii Rosatom AO Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo, Obninsk (Russian Federation); 274 p; ISBN 978-5-906512-70-3; ; 2015; p. 53; Thermal physics of new generation reactors (Thermal physics-2015); Teplofizika reaktorov novogo pokoleniya (Teplofizika-2015); Obninsk (Russian Federation); 6-9 Oct 2015
; 2015; p. 53; Thermal physics of new generation reactors (Thermal physics-2015); Teplofizika reaktorov novogo pokoleniya (Teplofizika-2015); Obninsk (Russian Federation); 6-9 Oct 2015
[en] The report analyzes the prospects for the development of energy sources with small and medium-sized reactors, which have been studied and developed for the last fifteen years. The authors give a picture of all reactors of this type, developed both in Russia and abroad
[ru]
В докладе анализируются перспективы развития энергоисточников с реакторами малой и средней мощности, которые исследуются и разрабатываются последние пятнадцать лет. Авторы дают картину всех реакторов этого типа, разрабатываемых как в России, так и за рубежомSource
Sarkisov, A.A. (ed.); Inst. Problem Bezopasnogo Razvitiya Atomnoj Ehnergetiki Rossijskoj Akademii Nauk, Moscow (Russian Federation); 387 p; ISBN 978-5-906324-04-7; ; 2015; p. 36-49; 10 refs., 2 figs., 3 tabs.; this article was presented at the international conference «Small-sized nuclear power plants: the current direction of nuclear power development» (Moscow, 3-5 Dec 2013)
; 2015; p. 36-49; 10 refs., 2 figs., 3 tabs.; this article was presented at the international conference «Small-sized nuclear power plants: the current direction of nuclear power development» (Moscow, 3-5 Dec 2013)
No abstract available
Source
Aktsionernoe Obshchestvo Ordena Lenina Nauchno-Issledovatel'skij i Konstruktorskij Inst. Ehnergotekhniki imeni N.A. Dollezhalya, Moscow (Russian Federation); 292 p; ISBN 978-5-98706-105-3; ; 2016; p. 175, 175-176; Innovative designs and technologies of nuclear power. 4. International scientific and technical conference; Innovatsionnye proekty i tekhnologii yadernoj ehnergetiki. IV Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya; Moscow (Russian Federation); 27-30 Sep 2016
; 2016; p. 175, 175-176; Innovative designs and technologies of nuclear power. 4. International scientific and technical conference; Innovatsionnye proekty i tekhnologii yadernoj ehnergetiki. IV Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya; Moscow (Russian Federation); 27-30 Sep 2016
No abstract available
Source
Aktsionernoe Obshchestvo Ordena Lenina Nauchno-Issledovatel'skij i Konstruktorskij Inst. Ehnergotekhniki imeni N.A. Dollezhalya, Moscow (Russian Federation); 292 p; ISBN 978-5-98706-105-3; ; 2016; p. 163-164, 164; Innovative designs and technologies of nuclear power. 4. International scientific and technical conference; Innovatsionnye proekty i tekhnologii yadernoj ehnergetiki. IV Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya; Moscow (Russian Federation); 27-30 Sep 2016
; 2016; p. 163-164, 164; Innovative designs and technologies of nuclear power. 4. International scientific and technical conference; Innovatsionnye proekty i tekhnologii yadernoj ehnergetiki. IV Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya; Moscow (Russian Federation); 27-30 Sep 2016
[en] A floating nuclear desalination complex with two barges, one for ABV type reactor plant, with twin reactor 2 x 6 MW(e), and one for reverse osmosis desalination plant, was described. The principal specifications of the ABV type reactor plant and desalination barge were given. The ABV type reactor has a traditional two-circuit layout using an integral type reactor vessel with all mode natural convection of primary coolant. The desalted water cost was estimated to be around US $0.86 per cubic meter. R and D work has been performed and preparations for commercial production are under way. (author)
Source
International Atomic Energy Agency, Vienna (Austria); 103 p; ISSN 1011-4289; ; May 1997; p. 23-28; Technical committee meeting on floating nuclear energy plants for seawater desalination; Obninsk (Russian Federation); 29-31 May 1995
; May 1997; p. 23-28; Technical committee meeting on floating nuclear energy plants for seawater desalination; Obninsk (Russian Federation); 29-31 May 1995
[en] Several independent active and passive safety systems are employed in the design of integral WCR in order to provide together with the reactor inherent safety features realization of the emergency heat removal function: active primary coolant clean-up system transmitting heat to the tertiary and then to the forth circuit; passive emergency heat removal through steam generator to the atmosphere; reactor cavity flooding system providing heat transfer from the reactor vessel to the reactor metal-water shielding tank; high and low pressure make-up system using water from the special storage tank. Operation of the systems under LOCAs and accidents with normal heat removal systems failure is considered in the paper. Special emphasis is done to the description of systems characteristics, systems interaction and modes of operation which are influenced by the reactor integral design. (author)
Source
International Atomic Energy Agency, Vienna (Austria); 243 p; ISSN 1011-4289; ; Nov 1997; p. 161-170; Technical committee meeting on integral design concepts of advanced water cooled reactors; Obninsk (Russian Federation); 9-12 Oct 1995; 6 figs, 1 tab.
; Nov 1997; p. 161-170; Technical committee meeting on integral design concepts of advanced water cooled reactors; Obninsk (Russian Federation); 9-12 Oct 1995; 6 figs, 1 tab.
| 1 | 2 | Next |