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Rineysky, A.A.; Kamaev, A.A.
Proceedings of the international topical meeting on safety of next generation power reactors1988
Proceedings of the international topical meeting on safety of next generation power reactors1988
AbstractAbstract
[en] The creation of next generation advanced nuclear reactor designs is impossible without operational and technological experience of those in operation now. Safety and economics are the key problems for both currently under development and perspective designs. This paper presents information on the operational experience of the first large-scale nuclear power plant (NPP) with the BN-600 fast reactor and on the influence of this operational experience upon the solution of safety problems of NPPs being currently designed
Primary Subject
Source
Anon; 933 p; ISBN 89448-1460-0;
; 1988; p. 732-741; American Nuclear Society; La Grange Park, IL (USA); American Nuclear Society topical meeting on the safety of next generation power reactors; Seattle, WA (USA); 1-5 May 1988; CONF-880506--; American Nuclear Society, 555 North Kensington Ave., La Grange Park, IL 60525 (USA)

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Book
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AbstractAbstract
[en] The development of self-protected nuclear reactors (having intrinsic safety properties) is considered a new approach to the solution of the safety problem. Attempts are being made to achieve self-protectedness by using known physical laws such as natural coolant circulation; the thermal expansion of fuel, the lattices of the discharge chamber, and the absorption rods; the Doppler effect; and gravity. Reactor shutdown and shutdown-cooling systems designed with these passive principles in mind can be made absolutely reliable. Given such systems, one faces the task of ensuring the survivability of the reactor in design accidents and in accidents that go beyond this framework and that involve the simultaneous failure of active protective systems and the regular cooling system. Work to develop a self-protected reactor is in the initial stage. At present, ways of solving this problem completely for medium- and high-power reactors are not entirely clear. It is apparent that we still have not found optimal solutions with respect to the design of fuel subassemblies and the core as a whole, to the type of fuel, and to other reactor parameters that would ensure maximum sensitivity of 'critical' geometry to coolant output temperature and heating. This problem will be solved in stages (beginning with an enhanced-safety reactor) with the ultimate goal of building an extremely or absolutely safe reactor. In the first stage, in the selection of hydraulic characteristics, the task is set of designing a core and a reactor which is the topic of this paper
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Cover-to-cover Translation of Atomnaya Energy (USSR).
Record Type
Journal Article
Literature Type
Translation
Journal
Country of publication
BREEDING RATIO, BURNUP, CONTROL ELEMENTS, DESIGN, FAST REACTORS, FUEL ASSEMBLIES, GRAVITATION, HEAT EXCHANGERS, HETEROGENEOUS REACTOR CORES, HYDRODYNAMICS, LIQUID METALS, NATURAL CONVECTION, PLUTONIUM 239, PLUTONIUM 241, PRIMARY COOLANT CIRCUITS, PUMPS, REACTIVITY, REACTOR ACCIDENTS, REACTOR CORES, REACTOR SAFETY, SHIELDS, SHUTDOWN, SODIUM, SPECIFICATIONS, SPONTANEOUS FISSION RADIOISOTO
ACCIDENTS, ACTINIDE NUCLEI, ALKALI METALS, ALPHA DECAY RADIOISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CONVECTION, CONVERSION RATIO, COOLING SYSTEMS, ELEMENTS, ENERGY TRANSFER, EPITHERMAL REACTORS, EQUIPMENT, EVEN-ODD NUCLEI, FLUID MECHANICS, FLUIDS, HEAT TRANSFER, HEAVY NUCLEI, ISOTOPES, LIQUIDS, MECHANICS, METALS, NUCLEI, PLUTONIUM ISOTOPES, RADIOISOTOPES, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SAFETY, YEARS LIVING RADIOISOTOPES
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Rinejskij, A.A.; Kamaev, A.A.; Yarovitsin, V.V.
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst1980
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst1980
AbstractAbstract
[en] Comparative evaluation methods for fast reactor NPP with different parameters of the steam cycle are discussed. The comparative evaluation methods at Nsub(cl)=const and Nsub(therm)=const powers are compared. It is shown that in the first case the parameters lesser than in the second case are optimal. It is proposed to compare versions at similar restrictions on the reactor sizes, core and other equipment parameters, which are restricted. The proposed method is illustrated by comparison of low, average and high parameters for a fast reactor at 1500-1600 MW power. The economical estimations show that under considered conditions the version with moderate parameters of the steam cycle 140 atm, 495 deg C (after the steam generator) is the optimum one
[ru]
Original Title
O metodakh sopostavleniya variantov AEhS s razlichnymi parametrami parosilovogo tsikla
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Secondary Subject
Source
1980; 10 p; 3 refs.; 1 tab.
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Report
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Bagdasarov, Yu.E.; Kuzneyjov, I.A.; Kamaev, A.A.
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
Kontseptsiya estestvennoj bezopasnosti ehnergobloka s reaktorom na bystrykh nejtronakh s natrievym yeplonositelem
Primary Subject
Source
Yadernoe Obshchestvo Rossii, Moscow (Russian Federation); 256 p; 1999; p. 30-31; 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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Miscellaneous
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AbstractAbstract
[en] Fast Neutron Plutonium Storage Reactor (FNPSR) concept is presented. Technological and physical problems of plutonium storage reactor development on the basis of design solutions used in BN-1600M and BN-800 type reactor plants are considered. (author)
Secondary Subject
Source
Japan Atomic Energy Research Inst., Tokyo (Japan); Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan); 673 p; Sep 1996; p. D/31-D/40; PHYSOR96: international conference on the physics of reactors 1996; Mito (Japan); 16-20 Sep 1996; Available from Atomic Energy Society of Japan
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
BREEDER REACTORS, EASTERN EUROPE, EPITHERMAL REACTORS, EUROPE, FBR TYPE REACTORS, FUEL CYCLE, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MEASURING INSTRUMENTS, NEUTRON DETECTORS, NUCLEAR FACILITIES, POWER PLANTS, POWER REACTORS, RADIATION DETECTORS, REACTORS, SELF-POWERED DETECTORS, SODIUM COOLED REACTORS, THERMAL POWER PLANTS
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AbstractAbstract
[en] Possible ways of decreasing fuel costs for power fast reactors with sodium coolant of the first generation at the initial stage of their commissioning in the presence of Pu reserve accumulated during thermal reactor operation have been considered. Investigations have been performed under the conditions of insufficient assimilation and effectiveness of technologies of fuel element production and fast reactor fuel regeneration. The low intensive fast reactor with a decreased blanket thickness Which may be realized in the framework of the traditional variant of the power fast reactor core has been considered as the most perspective variant of such reactors. A conclusion has been drawn that the observed increase of reactor critical loading and insignificant decrease of the breading ratio of the fuel will slightly effect the nuclear power economics because they will be compensated by decreasing of costs on fuel element production and fuel regeneration
Original Title
Ehkonomiya zatrat na toplivo na nachal'nom ehtape vvoda bystrykh reaktorov
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Secondary Subject
Source
For English translation see the journal Soviet Journal of Atomic Energy (USA).
Record Type
Journal Article
Journal
Atomnaya Ehnergiya; ISSN 0004-7163;
; v. 55(2); p. 77-80

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Bagdasarov, Yu.E.; Kuznetsov, I.A.; Kamaev, A.A.
Heavy liquid-metal coolants in the nuclear technologies. Collection of reports of the conference in two volumes. Volume 21999
Heavy liquid-metal coolants in the nuclear technologies. Collection of reports of the conference in two volumes. Volume 21999
AbstractAbstract
[en] The consequences of using sodium, lead and lead-bismuth in fast reactors are analyzed from the viewpoint of the following aspects: the reactor physics and thermohydraulics, the reactor achievable parameters and of the unit as a whole; the effect of the coolant peculiarities on the design solutions by the reactor core elements and the facility as a whole; the expected reliability characteristics of the NPP under normal mode of operation; the NPP safety aspects by using this coolant; the NPP expected economical characteristics
[ru]
Анализируются последствия использования натрия, свинца и свинца-висмута в быстрых реакторах с точки зрения следующих аспектов: физика и теплогидравлика реактора, достижимые параметры реактора и блока в целом; влияние особенностей теплоносителя на конструктивные решения по элементам активной зоны и установки в целом; ожидаемые надежностные характеристики ЯЭУ в режиме нормальной эксплуатации; аспекты безопасности ЯЭУ при использовании данного теплоносителя и ожидаемые экономические характеристики ЯЭУOriginal Title
Sravnenie natriya i tyazhelogo teplonositelya kak okhlazhdayushchej sredy dlya bystrogo reaktora
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); 824 p; 1999; p. 482-495; 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; 4 tabs.
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Poplavskij, V.M.; Bagdasarov, Yu.E.; Kamaev, A.A.; Tsikunov, A.G.; Zybin, V.A.; Ivanenko, V.N.
Fast nuclear reactors. Russian scientific and engineering forum. Theses of reports2003
Fast nuclear reactors. Russian scientific and engineering forum. Theses of reports2003
AbstractAbstract
No abstract available
Original Title
K voprosu ob opasnosti goreniya natrievogo teplonositelya
Primary Subject
Source
Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Fiziko-Ehnergeticheskij Inst. im. A.I. Lejpunskogo, Obninsk (Russian Federation); 80 p; 2003; p. 24-25; Nuclear power engineering with fast reactors; Yadernye ehnergeticheskie tekhnologii s reaktorami na bystrykh nejtronakh; Obninsk (Russian Federation); 9-10 Dec 2003; Available from the Federal State Unitary Enterprise TSNIIATOMINFORM, Russian Federation, 127434, Moscow Dmitrovskoe sh., 2
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Miscellaneous
Literature Type
Conference
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ACCIDENTS, ALKALI METALS, BREEDER REACTORS, COOLING SYSTEMS, DESIGN BASIS ACCIDENTS, ELEMENTS, ENERGY SYSTEMS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, METALS, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SODIUM COOLED REACTORS
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Poplavskij, V.M.; Tsibulya, A.M.; Kamaev, A.A.
Fast nuclear reactors. Russian scientific and engineering forum. Theses of reports2003
Fast nuclear reactors. Russian scientific and engineering forum. Theses of reports2003
AbstractAbstract
No abstract available
Original Title
Perspektivnyj natrievyj bystryj reaktor BN-1800, udovletvoryayushchij trebovaniyam k atomnij ehnergetike XXI veka
Primary Subject
Source
Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Fiziko-Ehnergeticheskij Inst. im. A.I. Lejpunskogo, Obninsk (Russian Federation); 80 p; 2003; p. 47-48; Nuclear power engineering with fast reactors; Yadernye ehnergeticheskie tekhnologii s reaktorami na bystrykh nejtronakh; Obninsk (Russian Federation); 9-10 Dec 2003; Available from the Federal State Unitary Enterprise TSNIIATOMINFORM, Russian Federation, 127434, Moscow Dmitrovskoe sh., 2
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Poplavskij, V.M.; Bagdasarov, Yu.E.; Kamaev, A.A.; Tsikunov, A.G.; Bakuta, N.N.; Zybin, V.A.; Ivanenko, V.N.
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
Ob istinnoj i mnimoj potentsial'noj opasnosti natrievogo teplonositelya bystrogo reaktora
Primary Subject
Source
Yadernoe Obshchestvo Rossii, Moscow (Russian Federation); 256 p; 1999; p. 57; 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
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ACCIDENTS, ALKALI METALS, BREEDER REACTORS, CHEMICAL REACTIONS, COOLING SYSTEMS, DESIGN BASIS ACCIDENTS, ELEMENTS, ENERGY SYSTEMS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HAZARDS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, METALS, OXIDATION, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SAFETY, SODIUM COOLED REACTORS, THERMOCHEMICAL PROCESSES
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