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AbstractAbstract
[en] Role of nuclear power in power engineering and fuel-power system of the country in the whole is discussed. Economic advantages of NPP's as compared with thermal power plants for district heating (TPP) are grounded. Advisability of combined production of thermal and electric power at TPP as compared with separate heat generation at NPP for district heating and electric power generation at NPP is reported. Data on perspectives of development of nuclear engineering in the light of ''Main directions of economic and social development of the USSR in 1981-1985 and up to 1990'' are presented. It is concluded that nuclear power introduction into national economy would bring important technical, economic and social consequences. Large-scale NPP construction would result in radical revision of the industry structure in the whole fuel-power system including output and transport on the base of modern technology and recent scientific-technical achievements providing essential economic and national economic effect essentially higher labour productivity in fuel power branches of industry. Besides, nuclear engineering creates conditions for better preservation of environment, reduction of expenditures for power and fuel transport, bringing industry centres nearer to centres of energy consumption as well as pre-conditions for removing threat of the so-called ''power hunger''
[ru]
Original Title
Rol' atomnoj ehnergii v ehnergeticheskom komplekse strany
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Secondary Subject
Source
For English translation see the journal Soviet Journal of Atomic Energy (USA).
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Journal Article
Journal
Atomnaya Ehnergiya; ISSN 0004-7163; ; v. 50(6); p. 371-376
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AbstractAbstract
[en] The cost situation for a series of system variants is investigated to determine an optimum operational order for the fissile material circuit. The most important parameters here are the investment costs and the running costs. The results of the investigation show that industries producing and reprocessing fuel elements must be centrally ordered and have command over considerable production capacities even in the individual constructional stages. (UA)
[de]
Zur Bestimmung einer optimalen Anordnung der Betriebe fuer den Spaltstoffkreislauf wird die Kostensituation fuer eine Reihe von Anordnungsvarianten untersucht. Die wichtigsten Parameter sind dabei die Investitionskosten und die laufenden Kosten. Als Ergebnis der Untersuchung zeigt sich, dass die Betriebe zur Herstellung un Wiederaufbereitung der Brennelemente zentral angeordnet sein muessen und bereits in den einzelnen Ausbaustufen ueber betraechtliche Produktionskapazitaeten verfuegen muessen. (UA)Original Title
Bewertung der Zweckmaessigkeit einer Leistungskonzentration der spaltstoffverarbeitenden Industrie in der fortschreitenden Kernenergiewirtschaft
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Source
Translated from Russian, Ocenka celesoobraznosti konzentracii moscnostej toplivoobrabatyvajuscej promyslennosti razvivajuscejsja jadernoj energetiki, published in Atomnaja Energija, v. 44(4) Apr 1978, p. 306-310.
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Journal Article
Journal
Archiv fuer Energiewirtschaft; v. 32(11); p. 884-892
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AbstractAbstract
[en] Two mathematical models are described for two parts of the nuclear power station, the reactor part (thermal energy generation) and the thermal power part (conversion of heat into electrical power). The saturated steam and hot steam reactors are treated as variants, for each of which one optimum was produced by the model. With the rising trend for nuclear fuel prices, the hot steam variant is preferable because of the higher efficiency. (UA)
[de]
Es werden zwei mathematische Modelle fuer zwei Teilbereiche des Kernkraftwerkes beschrieben, den Reaktorabschnitt (Waermeenergieerzeugung) und den Waermekraftabschnitt (Umwandlung der Waerme in elektrischen Strom). Als Varianten werden der Sattdampf- und der Heissdampf-Reaktor behandelt, fuer die sich im Modell je ein Optimum ergeben. Bei steigender Tendenz der Kernbrennstoffpreise ist wegen des hoeheren Wirkungsgrades die Heissdampfvariante vorzuziehen. (UA)Original Title
Volloptimierung eines mit Wasser-Graphitreaktoren ausgeruesteten Kernkraftwerkes
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Translated from Russian: Kompleksnaja optimizacija AES s vodografitovymi raktorami. Also publ. in At. Ehnerg., Aug 1978, v. 45(2) p. 91-98.
Record Type
Journal Article
Journal
Archiv fuer Energiewirtschaft; v. 32(12); p. 976-986
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AbstractAbstract
[en] Results are presented of technical and economical analysis of advisability of constructing combined Nuclear Power and Heating Plants (NPHP) assuring the possibility of their location near the areas of heat power consumption in case of observing a given degree of radiation safety for population and personnel. Specific features determining the choice of turbine-driven units for such plants are analyzed. Conditions of competiveness of a specialized NPHP with alternative power units, NPHP based on the WWER-1000 reactor and district heating plants (NDHP), are determined. Analysis of design specifications of NPHP with two VK-500 reactor units and structures of capital investments in such a plant reveal that an increase in the total capital investments in the NPHP would not exceed 2% with account of the difference in costs for grid heaters and a corresponding change in dimensions of operation rooms as well as changes in costs of heat removal system (within one site) at the TK turbine replacement by the T turbine
Original Title
Tekhniko-ehkonomicheskie predposylki sozdaniya spetsializirovannykh ATEhTs
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Secondary Subject
Source
For English translation see the journal Soviet Journal of Atomic Energy (USA).
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Journal Article
Journal
Atomnaya Ehnergiya; ISSN 0004-7163; ; V.55(1); p. 14-18
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Baturov, B.B.; Chernyaev, V.A.; Galaktionov, I.V.; Makarov, V.E.; Radchenko, S.V.
Operating experience of nuclear plants and the future development of nuclear power production1974
Operating experience of nuclear plants and the future development of nuclear power production1974
AbstractAbstract
No abstract available
Original Title
Atomnye teploehlektrotsentrali i atomnye kotel'nye. Tekhnicheskaya vozmozhnost' i ehkonomicheskaya tselesoobraznost'
Primary Subject
Source
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow; p. 22-41; 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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Dollezhal', N.A.; Aleshchenkov, P.I.; Baturov, B.B.; Mityaev, Yu.I.
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
Nekotorye igoti i perspektivy yadernogo peregreva para v kanal'nykh reaktorakh
Primary Subject
Source
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow; p. 149-170; 1974; Jubilee conference dedicated to the twentieth anniversary of nuclear power engineering; Obninsk, USSR; 25 Jun 1974
Record Type
Report
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Conference
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Baturov, B.B.; Zvereva, G.A.; Mityaev, Yu.I.; Mikhan, V.I.
International Atomic Energy Agency, Vienna (Austria)1977
International Atomic Energy Agency, Vienna (Austria)1977
AbstractAbstract
[en] Experience gained from prolonged operation of superheating channel of Beloyarsk nuclear power station has convincingly proved engineering feasibility of efficient nuclear superheat. The problems of ensuring both the necessary relation between the power for evaporation and for steam superheating and the safety of channel transfer from water to steam cooling in channel-type reactors are solved relatively easy. Channels in operation with steam outlet temperature up to 5650C have proved great operational reliability at the burnup up to 35 kg/t and with normal service life of six-seven years. These results allow counting on good economics of the nuclear power station in spite of relatively great quantity of steel and neutron absorbing contact materials of fuel composition. The use of superheating channels with fuel rods in which the quantity of steel per unit mass of uranium is reduced and the contact material is eliminated allows improving operating and economic characteristics of channel-type reactor by implementing nuclear superheating of steam in it. The report sums up the results of the Beloyarsk nuclear power station operation and examines the prospects of nuclear superheat on the example of the large modular reactor RBM-KP. The project of this type of reactor has fully solved the problems of this trend in nuclear power engineering which is important from a viewpoint of uranium save and essential reduction of heat removal
[ru]
Original Title
Yadernyj peretrev para. Itogi i perspektivy na sovremennom ehtape
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Source
1977; 12 p; International conference on nuclear power and its fuel cycles; Salzburg, Austria; 2 - 13 May 1977; 8.0.-.T.1./10 1 table, 5 figs. Also available in English.
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Report
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Conference
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AbstractAbstract
[en] The operating experience of the Beloyarsk NPP (BNPP) is reported, and prospects for nuclear steam superheating are shortly discussed taking as an example the RBMKP-2400 reactor (calculated steam parameters: 450 deg C and 65 kg/cm2). Characteristic features of the LWGR type reactors are surveyed. The reactors are the most promising to obtain superheated steam of high quality (510-540 deg C, 90 kg/cm2). Lifetime of the both BNPP reactors (100 MWe and 200 MWe respectively) has totalled 21 reactor-years at efficiency approximately 37-38%, capacity factor approximately 62-77% and availability factor approximately 75-91%. The BNPP reactors have proved the feasibility of commercial nuclear steam superheating, adequate reliability, safety and economic attractiveness. It is noted that the reactors with nuclear steam superheating can be economically run at off-peak loads, serve for industrial or district heating purposes and exert far less thermal impact on the environment
Original Title
Yadernyj peregrev para, itogi i perspektivy na sovremennom ehtape
Primary Subject
Source
For English translation see the journal Sov. J. At. Energy.
Record Type
Journal Article
Journal
Atomnaya Ehnergiya; v. 44(2); p. 126-131
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AbstractAbstract
No abstract available
Original Title
Ispytaniya tsirkonievykh paroperegrevatel'nykh kanalov v reaktore pervogo bloka Beloyarskoj AEhS im. I.V. Kurchatova
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Source
Letter-to-the-editor; for English translation see the journal Soviet Journal of Atomic Energy (USA).
Record Type
Journal Article
Journal
Atomnaya Ehnergiya; ISSN 0004-7163; ; v. 46(1); p. 55-56
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AbstractAbstract
[en] A calculation model of the fuel component of the electric energy cost price with regard for the cost of NPP fuel charging is proposed. The method is based on the principle of transfer of the fuel cost to the supplied electric energy proportional to its burnup and to the registration of the fuel charging residual cost as a normative period of justification of capital investments into the national economy. An example of calculation of the fuel component of the electric energy cost price and circulating funds of the NPP is given
Original Title
Uchet stoimosti toplivnoj zagruzki v sebestoimosti ehlektroehnergii AEhS
Primary 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. 47(4); p. 237-241
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