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AbstractAbstract
[en] Investigations in the field of cosmic nuclear power engineering in the USSR were started in sixties, now they are realized through demonstration tests of nuclear power plants at Kosmos satellites. The advantages of thermoelectric space power generators i.e. minimal overall dimensions, possibility of power increase, provide their competibility at power up to hundreds of kW and 2-3 year srvice life with further improvement up to 5 years and more. Nuclear facilities, providing power supply for different cosmic systems - power, propulsion, combined ones - are under current development in the USSR. Further develolment of cosmic nuclear power engineering needs comprehensive researches, most effective in the case of international cooperation
Original Title
Yadernaya ehnergetika v kosmose
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Source
6. Symposium on cosmic nuclear energetic; Albuquerque, NM (USA); 10 Jan 1989
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Journal Article
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Conference
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DEVELOPED COUNTRIES, DIRECT ENERGY CONVERTERS, EUROPE, EXPERIMENTAL REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, KILOWATT POWER RANGE, MOBILE REACTORS, OPERATION, POWER PLANTS, POWER RANGE, POWER REACTORS, PROPULSION REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SATELLITES, SOLID HOMOGENEOUS REACTORS, SPACE POWER REACTORS
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AbstractAbstract
[en] Development of the world power industry in the 21st century is forecasted. It is noted that natural gas will be the dominating power source. Problems of safety of new generation reactors and the effect of nuclear power on the environment are discussed
[ru]
Прогнозируется развитие мировой энергетики в 21 веке. Отмечается, что доминирующим энергоносителем будет природный газ. Обсуждаются проблемы безопасности реакторов нового поколения и влияние атомной энергетики на окружающую средуOriginal Title
K atomnoj ehnergetike 21 veka cherez gazovyj most
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3 figs.
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AbstractAbstract
[en] Consideration is being given to the main factors (safety, sphere of application and fuel supply), dictating competitiveness of nuclear power at the world power market. Requirements of reactor safety are formulated on the basis of risk assessment including analysis of the maximum credible design basis reactor accidents. The social estimation is based on the condition of providing the minimal probability of occurrence of even one accident with dangerous radioactive effluents. The economical estimation derived from the condition that the damage from serious accident doesn't exceed several percent of the reduced power generation cost. It is shown that when determining possible scales of nuclear power development and requirements for reactors of a new generation allowance must be made for the structure of heat production both with respect to the type of energy-transfer medium (steam, hot water, high-temperature coolant) and to its temperature potential, as well as for the factor of registered capacity
Original Title
Bezopasnost' i ehffektivnost' yadernoj ehnergetiki - osnova v rabotakh nad reaktorami novogo pokoleniya
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Aleksandrov, A.P.; Ponomarev-Stepnoj, N.N.
20 years of nuclear power engineering. Nuclear power plant operating experience and prospects of nuclear power engineering1974
20 years of nuclear power engineering. Nuclear power plant operating experience and prospects of nuclear power engineering1974
AbstractAbstract
No abstract available
Original Title
Atomnaya ehnergetika i tekhnicheskij progress
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Source
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow; p. 3-23; 1974; Jubilee conference dedicated to the twentieth anniversary of nuclear power engineering; Obninsk, USSR; 25 Jun 1974
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Report
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Conference
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AbstractAbstract
[en] Different aspects of nuclear reactor performance improvement due to optimal distribution of heat release, fuel enrichment, fissile material concentration, moderator, absorber, coolant flow rate, fuel element arrangement in a heterogeneous reactor with variable pitch etc., both without burn-up effects and taking account of the fuel-cycle and fueling patterns, are considered. 16 refs.; 82 figs.; 12 tabs
Original Title
Profilirovanie yadernogo reaktora
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Source
1988; 240 p; Ehnergoatomizdat; Moscow (USSR)
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Book
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BURNABLE POISONS, COOLANTS, CRITICAL MASS, CRITICAL SIZE, DISTRIBUTION FUNCTIONS, EIGENFUNCTIONS, EIGENVALUES, FLOW RATE, FLUX DENSITY, HEAT FLUX, HIGH TEMPERATURE, LAPLACE TRANSFORMATION, LMFBR TYPE REACTORS, LWGR TYPE REACTORS, NEUTRON FLUX, OPTIMIZATION, POWER DENSITY, POWER DISTRIBUTION, REACTOR CORES, TEMPERATURE DISTRIBUTION, WWER TYPE REACTORS
BREEDER REACTORS, DISTRIBUTION, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUNCTIONS, GRAPHITE MODERATED REACTORS, INTEGRAL TRANSFORMATIONS, LIQUID METAL COOLED REACTORS, MATERIALS, NEUTRON ABSORBERS, NUCLEAR POISONS, POWER REACTORS, PWR TYPE REACTORS, RADIATION FLUX, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, SIZE, SPATIAL DISTRIBUTION, THERMAL REACTORS, TRANSFORMATIONS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
[en] Outlooks on nuclear power development in Russia are analyzed. Specifically, the following problems are considered: NPP safety, specific features of new generation NPP, small power nuclear plants, nuclear power structure, NPP decommissioning and competitiveness
Original Title
O perspektivakh razvitiya atomnoj ehnergetiki Rossii
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3 figs.
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AbstractAbstract
[en] Problems on further development of nuclear power in Russia are considered. Practical safety, economical efficiency and competitiveness with traditional thermal power plants are the determinative factors by choice of reactor types. Necessity for substantiation of perspective nuclear power structure is noted
Original Title
Perspektivy razvitiya yadernoj ehnergetiki v Rossii
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1 fig.
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AbstractAbstract
No abstract available
Original Title
Profilirovanie geterogennogo reaktora s nebol'shim chislom tvehlov
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Journal Article
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Progress Report
Journal
At. Energ. (USSR); v. 30(3); p. 303-304
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AbstractAbstract
[en] Methods for calculating the stress-strain state of fuel microparticles of high-temperature gas-cooled reactors, realized in the form of the FORTRAN complex program for the BEhSM-6 computer, are considered. Calculation results of the stress-strain states of different layers of fuel microparticle coatings versus the neutron fluence and fuel burnup are presented. The dependence of the maximum stress in a SiC layer on its thickness is obtained. The fuel microparticles investigated consist of a UO2 core, 500 μm in dia., buffer layer of pyrolytic carbon PyC, 70 μm thick, the first reinforcing layer of dense PyC, 60 μm thick, the second reinforcing layer of SiC, 40 μm thick, and the third one of dense PyC, 50 μm thick. The mathematical calculation model is based on the following assumptions: the core has the shape of a sphere and is surrounded with spherically-symmetric coatings; the internal coating of porous PyC does not bear mechanical loading and transfers all the stresses, directed square to its surface, directly to the force coating of dense PyC; elastic constants of coating materials are isotropic and do not change during irradiation; irradiation with fast neutrons causes anisotropic changes in PyC coating dimensions. To calculate stress-strain states of fuel microparticles the classical methods of elasticity theory are used. On the basis of the analysis of the data obtained a conclusion is made that destruction of PyC layers does not result in destruction of fuel microparticles on the whole. SiC layer is a main reinforcing laye. Reliable operation of fuel microparticles shouled be evaluated taking into account the strsses arising in a SiC layer under irradiation
Original Title
Metody rascheta napryazhenno-deformatsionnogo sostoyaniya mikrotvehlov VTGR i vybor ikh konstruktsii
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For English translation see the journal Soviet Journal of Nuclear Physics (USA).
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Journal Article
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Yadernaya Fizika; ISSN 0044-0027; ; v. 56(2); p. 77-81
Country of publication
ALGORITHMS, BESM COMPUTERS, BURNUP, COATED FUEL PARTICLES, COMPUTER CALCULATIONS, DENSITY, HTGR TYPE REACTORS, MATHEMATICAL MODELS, MODERATELY ENRICHED URANIUM, NEUTRON FLUENCE, NUCLEAR FUELS, POWER REACTORS, PROTECTIVE COATINGS, PYROLYTIC CARBON, RELIABILITY, SILICON CARBIDES, SPHERICAL CONFIGURATION, STRAINS, SWELLING, THICKNESS, URANIUM DIOXIDE
ACTINIDE COMPOUNDS, ACTINIDES, CARBIDES, CARBON, CARBON COMPOUNDS, CHALCOGENIDES, COATINGS, COMPUTERS, CONFIGURATION, DEFORMATION, DIMENSIONS, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM, FUEL PARTICLES, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, ISOTOPE ENRICHED MATERIALS, MATERIALS, METALS, NONMETALS, OXIDES, OXYGEN COMPOUNDS, PHYSICAL PROPERTIES, REACTOR MATERIALS, REACTORS, SILICON COMPOUNDS, URANIUM, URANIUM COMPOUNDS, URANIUM OXIDES
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Legasov, V.A.; Kotel'nikov, G.A.; Ponomarev-Stepnoj, N.N.
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii1975
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii1975
AbstractAbstract
[en] Results of comparative estimation of energy consumption in steel production with high-temperature gas-cooled reactor (HTGR) and water-cooled and water-moderated power reactor for the electrolysis method of reducing gas (hydrogen) production are given. It is shown that, according to the schemes adopted, the greatest energy consumption go into the hydrogen production (about 70% of energy in both cases). The energy costs in the steel production, the unit energy costs being equal for both installations, differ by 11% in favour of the high-temperature reactor. (author)
Original Title
Sravnitel'naya otsenka vozmozhnostej ispol'zovaniya vysokotemperaturnogo i nizkotemperaturnogo reaktorov dlya proizvodstva stali pri ehlektroliticheskom poluchenii vodoroda
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1975; 11 p; 14 refs.
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Report
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