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AbstractAbstract
No abstract available
Original Title
Ob odnoj spektral'noj teoreme teorii zamedleniya
Primary Subject
Source
Yurova, L.N. (ed.); Moskovskij Inzhenerno-Fizicheskij Inst. (USSR); p. 28-34; 1973
Record Type
Report
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Country of publication
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Shishkov, L.K.
Draft report of a consultants meeting on core control and protection strategy of WWER-1000 reactors. Extrabudgetary programme on the safety of WWER-1000 NPPs1994
Draft report of a consultants meeting on core control and protection strategy of WWER-1000 reactors. Extrabudgetary programme on the safety of WWER-1000 NPPs1994
AbstractAbstract
[en] The author would like to address some aspects of assuring safe and reliable operation of WWER-1000 reactors. This reactor was designed according to deterministic assumptions, i.e. for a chosen configuration of the core and for a given fuel cycle they determined a totality of potential/design-basis/accidents and demonstrated that the accepted permissible limits for the breach of fuel rod integrity are not exceeded for these accidents in combination with a possible additional single failure of equipment. Here they also specified a group of core neutron-physical characteristics at which favourable progression of the above mentioned transients/accidents was 'assured'. It is natural that for the normal operation conditions the adopted totality of neutron-physical characteristics assures reliable operation of reactor facility. It should be noted that at the design stage the thermal-hydraulic calculations of transients were performed with a significant amount of conservatism which allowed to ensure large reactor, safety margin. We will come back to this point later, and now one should note that the regular fuel loading is chosen such that its neutron-physical characteristics meet the conditions specified in the design
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 431 p; 7 Dec 1994; p. 55-61; Consultants meeting on core control and protection strategy of WWER-1000 reactors; Vienna (Austria); 18-22 Apr 1994; 1 fig
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACCIDENTS, BARYONS, ELEMENTARY PARTICLES, ENRICHED URANIUM REACTORS, FERMIONS, FLUID MECHANICS, FUEL ELEMENTS, HADRONS, HYDRAULICS, MECHANICS, NUCLEONS, OPERATION, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, SAFETY, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
No abstract available
Original Title
Vybor optimal'nogo varianta metoda peremennykh napravlenij dlya rascheta dvumernykh modelej reaktorov
Primary Subject
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. 45(5); p. 384-385
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AbstractAbstract
[en] Analysis of the efficiency of different methods for solving heterogeneous equations of generalized perturbation theory used for determination of nuclear reactor critical parameters is conducted. An algorithm for solving these equations by means of two-layer Tschebyscheff extrapolation is developed. The problem of internal and external iteration coordination is considered. The rate of convergence of each method is analytically and numerically evaluated. High efficiency of the Tschebyscheff polynomial method use for solving heterogeneous equations of generalized perturbation theory is displayed
Original Title
O metodakh resheniya neodnorodnykh uravnenij obobshchennoj teorii vozmushchenij
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. 52(1); p. 52-56
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AbstractAbstract
[en] Reasons of essential divergences in computer and experimental values of efficiency of rod worth measurements at WWER are discussed. Influence of effects of neutron flux space distribution is considered as the most significant reason. The procedure is suggested that makes possible rule out the influence of space effects on the results of measurements of efficiency of rod worth measurements. Possibilities of the suggested procedure were illustrated by the examples of data processing of experiments at the WWER-440 and -1000 power blocks
[ru]
Обсуждаются причины существенных расхождений расчетных и экспериментальных значений эффективности органов регулирования, наблюдаемых во время пусковых экспериментов на ВВЭР. В качестве наиболее значимой причины рассматривается влияние эффектов пространственного распределения нейтронного потока. Предлагается методика, которая позволяет исключить влияние пространственных эффектов на результаты измерения эффективности органов регулирования. Возможности предлагаемой методики проиллюстрированы на примерах обработки результатаов эспериментов, проводившихся на энергоблоках с ВВЭР-440 и -1000Original Title
Izmerenie ehffektivnosti organov regulirovaniya VVEhR
Primary Subject
Source
7 refs., 4 figs., 2 tabs.
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Alekseev, P.N.; Bolobov, P.A.; Zaritskij, S.M.; Shishkov, L.K.
Collection of reports on computer programs and methods of physical computations of fast reactors. CMEA1975
Collection of reports on computer programs and methods of physical computations of fast reactors. CMEA1975
AbstractAbstract
[en] Different methods of two-dimensional fast reactor calculations are discussed. The main attention was paid to comparison of the method of top relaxation and the method of variable directions. The results of numerical experiments for comparison of speed of convergence of these methods in typical fast reactors calculations are given. (author)
Original Title
Raschet dvumernykh bystrykh reaktorov metodom peremennykh napravlenij i metodom verkhnej relaksatsii
Primary Subject
Source
Sovet Ehkonomicheskoj Vzaimopomoshchi, Moscow (USSR). Postoyanniya Komissiya po Ispol'zovaniyu Atomnoj Ehnergii v Mirnykh Tselyakh; p. 15-28; 1975; Meeting of specialists on methods and computer programs for physical calculations of fast reactors; Dimitrovgrad, USSR; 1 Jul 1974
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Dementiev, V.G.; Shishkov, L.K.; Tsyganov, S.V.
Proceedings of the fifteenth Symposium of Atomic Energy Research2005
Proceedings of the fifteenth Symposium of Atomic Energy Research2005
AbstractAbstract
[en] In the AER materials a great attention is given to the necessity of accounting for spatial effects of neutron flux redistribution in the WWER scram drop measurements. It has been emphasized that the said spatial effects manifest themselves the stronger the higher is the absolute value of negative reactivity inserted into the rector. It was proposed to determine the time dependence of the ratio of neutron density in the ion chamber's location to the neutron flux averaged over the reactor using the dynamic BIPR-8 KN or NOSTRA-type code. At the same time it is known that in the insertion of a high negative reactivity (scram drop) the above ratio of neutron fluxes will remain unchanged during the whole measurement period. This fact makes it possible to use steady-state BIPR-type codes for this ratio (Authors)
Primary Subject
Secondary Subject
Source
Vidovszky, I. (ed.); VUJE, Inc., 918 64 Trnava (Slovakia); KFKI Atomic Energy Research Institute, Reactor Analysis Laboratory, H-1525 Budapest 114, POB 49 (Hungary); NPP Dukovany, 675 50 Dukovany (Czech Republic); Institute State Scientific and Technical Center for Nuclear and Radiation Safety, 35-37 Radgospna street, 03142 Kyiv-142 (Ukraine); Kozloduy NPP plc, Kozloduy 3321 (Bulgaria); Jaslovske Bohunice NPP (Slovakia); Nuclear Research Institute Rez plc, CZ-250 68 Husinec-Rez, cp.130 (Czech Republic); ALTA Dukovany, NPP Dukovany, 675 50 Dukovany (Czech Republic); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest XI, Mueegyetem rkp. 9, 1111 (Hungary); International Atomic Energy Agency (IAEA), Wagramerstrasse 5, P.O.Box 100, A-1400 Vienna (Austria); 783 p; ISBN 963-372-632 8; ; Nov 2005; p. 311-317; 15. Atomic Energy Research Symposium on WWER Reactor Physics and Reactor Safety; Znojmo (Czech Republic); 3-7 Oct 2005; Also available from VUJE, Inc., Okruzna 5, 918 64 Trnava (SK); 4 figs., 1 tab., 4 refs.
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
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AbstractAbstract
[en] The paper discusses the influence of the reactor parameters limits for normal operation on the economical performance of WWER fuel cycles. It is shown for the typical WWER fuel cycles that decreasing the limits for the main power distribution parameters to 10% leads to decreasing the fuel components of the electricity cost price up to 4-5%. As the nowadays limitations are reached the dependence becomes weaker. (Authors)
Primary Subject
Source
Vidovszky, I. (Kiadja az MTA KFKI Atomenergia Kutatointezet, Budapest (Hungary)); Fortum Nuclear and Thermal (Finland); VTT Technical Research Centre of Finland (Finland); Lappeenranta University of Technology (Finland); The Aalto University School of Science and Technology (Finland); Paks NPP Ltd., Paks (Hungary); KFKI Atomic Energy Research Institute, Budapest (Hungary); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest (Hungary); Hungarian Atomic Energy Authority (Hungary); VUJE, Inc., Trnava (Slovakia); Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, Bratislava (Slovakia); Nuclear Regulatory Authority of the Slovak Republic (Slovakia); Nuclear Research Institute Rez plc, Husinec-Rez (Czech Republic); Skoda JS a.s., Plzen (Czech Republic); CEZ , Inc. (Czech Republic); University of Defence in Brno (Czech Republic); The University of West Bohemia Faculty of Applied Sciences (Czech Republic); Russian Research Center 'Kurchatov Institute', Moscow (Russian Federation); JSC OKB 'GIDROPRESS' (Russian Federation); JSC 'TVEL' (Russian Federation); Forschungszentrum Dresden- Rossendorf, Institute of Safety Research, Dresden (Germany); GRS mbH (Germany); Studsvik Scandpower GmbH (Germany); TUEV SUED Industrie Service, Energy and Technology (Germany); Gesellschaft fuer Anlagen - und Reaktorsicherheit (Germany); Studsvik Scandpower (Sweden); State Scientific and Technical Centre on Nuclear and Radiation Safety of Ukraine, Kyiv (Ukraine); Nuclear and Radiation Safety Centre (Armenia); Jiangsu Nuclear Power Corporation, Tianwan Nuclear Power Station (China); Jiangsu Nuclear Power Corporation (China); 790 p; ISBN 978-963-372-643-3 (OE); ; Oct 2010; p. 1-7; 20. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Hanasaari, Espoo (Finland); 20-24 Sep 2010; 1 fig.; 8 refs.
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
Report Number
Country of publication
COMPUTER CODES, CONTROL ROD WORTHS, DATA COVARIANCES, DESIGN, EFFICIENCY, EVALUATION, FUEL ASSEMBLIES, FUEL CYCLE, LIMITING VALUES, NUMERICAL DATA, POWER DISTRIBUTION, REACTOR CORES, REACTOR LATTICE PARAMETERS, REACTOR OPERATION, REACTOR SAFETY, REPROCESSING, SAFETY ANALYSIS, STATISTICAL MODELS, STATISTICS, WWER TYPE REACTORS
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AbstractAbstract
No abstract available
Original Title
Sravnenie chetyrekh iteratsionnykh metodov resheniya odnogruppovykh konechno-raznostnykh diffuzionnykh uravnenij dlya dvumernykh modelej bystrykh reaktorov
Primary Subject
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. 45(5); p. 386-387
Country of publication
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Gorodkov, S.S.; Shishkov, L.K.; Suhino-Homenko, E.A.
Proceedings of the twentieth symposium of atomic energy research2010
Proceedings of the twentieth symposium of atomic energy research2010
AbstractAbstract
[en] Presence of spacing grid in fuel assembly noticeably decreases local energy release due to small local change of uranium-water ratio. Condition of total energy release conservation leads to some increase in maximum of axial power distribution. With MCU Monte Carlo code these increase/decrease were calculated for some VVER-440 and VVER-1000 F As. Since geometry of spacing grid is very complicated, two different sensibly simplified models were proposed. Both gave close results. Local minimums turn out to be ∼5% lower than average and local maximums increase slightly more than 1%. (Authors)
Primary Subject
Source
Vidovszky, I. (Kiadja az MTA KFKI Atomenergia Kutatointezet, Budapest (Hungary)); Fortum Nuclear and Thermal (Finland); VTT Technical Research Centre of Finland (Finland); Lappeenranta University of Technology (Finland); The Aalto University School of Science and Technology (Finland); Paks NPP Ltd., Paks (Hungary); KFKI Atomic Energy Research Institute, Budapest (Hungary); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest (Hungary); Hungarian Atomic Energy Authority (Hungary); VUJE, Inc., Trnava (Slovakia); Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, Bratislava (Slovakia); Nuclear Regulatory Authority of the Slovak Republic (Slovakia); Nuclear Research Institute Rez plc, Husinec-Rez (Czech Republic); Skoda JS a.s., Plzen (Czech Republic); CEZ , Inc. (Czech Republic); University of Defence in Brno (Czech Republic); The University of West Bohemia Faculty of Applied Sciences (Czech Republic); Russian Research Center 'Kurchatov Institute', Moscow (Russian Federation); JSC OKB 'GIDROPRESS' (Russian Federation); JSC 'TVEL' (Russian Federation); Forschungszentrum Dresden- Rossendorf, Institute of Safety Research, Dresden (Germany); GRS mbH (Germany); Studsvik Scandpower GmbH (Germany); TUEV SUED Industrie Service, Energy and Technology (Germany); Gesellschaft fuer Anlagen - und Reaktorsicherheit (Germany); Studsvik Scandpower (Sweden); State Scientific and Technical Centre on Nuclear and Radiation Safety of Ukraine, Kyiv (Ukraine); Nuclear and Radiation Safety Centre (Armenia); Jiangsu Nuclear Power Corporation, Tianwan Nuclear Power Station (China); Jiangsu Nuclear Power Corporation (China); 790 p; ISBN 978-963-372-643-3 (OE); ; Oct 2010; p. 1-5; 20. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Hanasaari, Espoo (Finland); 20-24 Sep 2010; 3 figs.; 3 tabs.; 1 ref.
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
Report Number
Country of publication
CALCULATION METHODS, DATA, ELECTRODES, ELECTROMAGNETIC RADIATION, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, INFORMATION, IONIZING RADIATIONS, MATERIALS, METALS, NUCLEAR FUELS, POWER REACTORS, PWR TYPE REACTORS, RADIATIONS, REACTOR MATERIALS, REACTORS, THERMAL REACTORS, TRANSITION ELEMENTS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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