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Beyer, M.; Carl, H.; Langer, L.; Nowak, K.; Schumann, P.; Seidel, A.; Tolksdorf, P.; Zschau, J.
Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 19931994
Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 19931994
AbstractAbstract
[en] Short communication
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Source
Weiss, F.P. (ed.); Rindelhardt, U. (ed.); Forschungszentrum Rossendorf e.V. (FZR) (Germany). Inst. fuer Sicherheitsforschung; 118 p; Jun 1994; p. 52-57
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Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.-P.; Zschau, J.; Nowak, K.
Proceedings of the International topical meeting on VVER instrumentation and control1997
Proceedings of the International topical meeting on VVER instrumentation and control1997
AbstractAbstract
[en] As part of a programme of cooperation with Central and Eastern European states, a technical system has been established for the Zaporozhe nuclear power plant, which complements existing operational checking and monitoring facilities with modern means of information technology. It makes it possible to continuously monitor the state of the units in normal operation and in cases of anomalies or incidents. The parameters selected for monitoring are listed, and the system of automatic evaluation at the power plant site is described in detail. Test operation of the technical system started in late 1995 and the industrial testing phase in mid-1996. (A.K.)
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European Nuclear Society (International Organisation without Location); Czech Nuclear Society, Prague (Czech Republic); 361 p; Nov 1997; p. 105-112; International topical meeting on VVER instrumentation and control; Prague (Czech Republic); 21-24 Apr 1997; 4 figs., 1 tab., 4 refs.
Record Type
Report
Literature Type
Conference
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Krhounkova, J.
Ustav Jaderneho Vyzkumu a.s., Rez (Czech Republic)1995
Ustav Jaderneho Vyzkumu a.s., Rez (Czech Republic)1995
AbstractAbstract
[en] The results of calculation of the transient process due to failure of 2 out of the 4 main circulation pumps during reactor unit operation at full power were compared with observed data that emerged from a dynamic test. The calculation encompassed 350 s of the process. The largest differences in the reactor unit behavior concerned the secondary circuit parameters, due to the fact that the pressure in the secondary circuit affects the coolant pressure in the primary circuit. (M.D.). 30 figs., 5 refs
Original Title
Vypocet vypadku HCC pro zaporozskou JE. Srovnani s experimentem
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Source
Dec 1995; [44 p.]; Available from Ustav jaderneho vyzkumu Rez, a.s., 250 68 Rez, Czech Republic
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Report
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Numerical Data
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AbstractAbstract
[en] The IAEA Assessment of Safety Significant Events Team (ASSET) report presents the results of an ASSET team's assessment of their investigation of the effectiveness of the plant for prevention of incidents since 1990 at Zaporozhe nuclear power plant. The results, conclusions and suggestions presented herein reflect the views of the ASSET experts. They are provided for consideration by the responsible authorities in Ukraine. The ASSET team's views presented in this report are based on visits to the plant, on review of documentation made available by the operating organization and on discussions with utility personnel. The report is intended to enhance operational safety at Zaporozhe by proposing improvements to the policy for the prevention of incidents at the plant. The report includes, as a usual practice, the official response of the operating organization as well as of the regulatory body to the ASSET recommendations. Figs
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1994; 214 p; IAEA/NENS/ASSET--94/R/01; PROJECT UKR/9/004/6
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Report
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AbstractAbstract
[en] Technical and economic analysis of mounting the reactor buildings of NPPs with WWER-1000 reactors which are under construction is performed. Cutting of buildings into mounting elements of different size is considered. Mounting schemes of Zaporozhskaya, Kalininskaya, Balakovskaya and Tatarskaya NPPs are shown taking reactor building sealed zone, containment, socle part and building as examples
Original Title
Analiz metodov sooruzheniya reaktornykh otdelenij AEhS s reaktorami VVEhR-1000
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Journal Article
Journal
Ehnergeticheskoe Stroitel'stvo; CODEN ENSTA; (no.2); p. 9-18
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Beyer, M.; Carl, H.; Schumann, P.; Seidl, A.; Weiss, F.P.; Zschau, J.; Nowak, K.
Proceedings of the 2nd international symposium on safety and reliability systems of PWRs and VVERs1997
Proceedings of the 2nd international symposium on safety and reliability systems of PWRs and VVERs1997
AbstractAbstract
[en] A technical system to improve operational monitoring was designed and established in 1992 as a pilot project in the Zaporozhe nuclear power plant. The technical system complements the existing operational checking and monitoring facilities by including up-to-date information technology. The monitoring tasks are related to: general plant condition, barrier effectiveness, radioactivity inventories, release of radioactive substances into the air, immissions into buildings and surroundings, recording of meteorological conditions, release of radioactive substances into the water, adherence to monitoring-specific threshold values and plant condition in the event of anomaly or incident/accident. Based on the concept of protection aims and monitoring tasks, 49 different safety related operational parameters of the core and unit, 18 radiological parameters of the unit and the plant site, and 6 meteorological parameters are permanently and automatically monitored, recorded and evaluated. (M.D.)
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Source
Ceske jaderne forum, Prague (Czech Republic); Energovyzkum, Brno (Czech Republic); 353 p; 1997; p. 346-353; 2. international symposium on safety and reliability systems of PWRs and VVERs; Brno (Czech Republic); 26-30 May 1997; 4 figs., 4 refs., 1 tab.
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Miscellaneous
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Conference
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AbstractAbstract
[en] As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)
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Weiss, F.P.; Rindelhardt, U. (eds.); Forschungszentrum Rossendorf e.V. (FZR) (Germany). Inst. fuer Sicherheitsforschung; 192 p; Oct 1998; p. 117-122
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Miscellaneous
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Kozlov, V.; Brozova, A.; Zdarek, J.; Cipra, S.
6th International seminar on horizontal steam generators. Summaries of reports2004
6th International seminar on horizontal steam generators. Summaries of reports2004
AbstractAbstract
No abstract available
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Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Federal'noe Gosudarstvennoe Unitarnoe Predpriyatie Opytnoe Konstruktorskoe Byuro GIDROPRESS, Podol'sk, Moskovskaya Obl. (Russian Federation); 72 p; ISBN 5-94883-038-1; ; 2004; p. 21-25; 6. International seminar on horizontal steam generators; 6-j Mezhdunarodnyj seminar po gorizontal'nym parogeneratoram; Podol'sk, Moskovskaya Obl. (Russian Federation); 22-24 Mar 2004; 6 figs.; 1 tab.
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Book
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Conference
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AMINES, CHEMISTRY, DIMENSIONLESS NUMBERS, ENRICHED URANIUM REACTORS, ETHERS, HETEROCYCLIC COMPOUNDS, HYDRIDES, HYDROGEN COMPOUNDS, NITROGEN COMPOUNDS, NITROGEN HYDRIDES, NUCLEAR FACILITIES, ORGANIC COMPOUNDS, ORGANIC NITROGEN COMPOUNDS, ORGANIC OXYGEN COMPOUNDS, OXYGEN COMPOUNDS, POWER PLANTS, POWER REACTORS, PWR TYPE REACTORS, REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER, WATER COOLED REACTORS, WATER MODERATED REACTORS, WWER TYPE REACTORS
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Luchna, A.Je.; Lavrenchuk, A.I.; Sjednjev, V.A.; Vasil'chenko, V.M.; Dvojeglazov, O.M.; Medvedjev, V.Yi.; Pechera, Yu.M.
International Conference 'Current Problems in Nuclear Physics and Atomic Energy'. May 29 - Jun 03 2006. Book of Abstracts2006
International Conference 'Current Problems in Nuclear Physics and Atomic Energy'. May 29 - Jun 03 2006. Book of Abstracts2006
AbstractAbstract
No abstract available
Original Title
Sukhe skhovishche vyidprats'ovanogo yadernogo paliva Zaporyiz'koyi AES. Zabezpechennya bezpeki
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Source
Vyshnevskyi, I.M. (ed.); Yinstitut Yadernikh Doslyidzhen', NAN Ukrayini, Kyiv (Ukraine); Kiyivs'kij Natsyional'nij unyiversitet, Kyiv (Ukraine); Natsyional'na energogeneruyucha kompanyiya Ukrayini 'ENERGOATOM', Kyiv (Ukraine); 201 p; 2006; p. 158; International Conference 'Current Problems in Nuclear Physics and Atomic Energy'; Myizhnarodna konferentsiya 'Aktual'nyi problemi yadernoyi fyiziki ta atomnoyi energetiki'; Kyiv (Ukraine); 29 May - 3 Jun 2006
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Miscellaneous
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Conference
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ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, MANAGEMENT, MATERIALS, NUCLEAR FUELS, POWER REACTORS, PWR TYPE REACTORS, RADIOACTIVE WASTE MANAGEMENT, REACTOR MATERIALS, REACTORS, SAFETY, STORAGE, THERMAL REACTORS, WASTE MANAGEMENT, WASTE STORAGE, WATER COOLED REACTORS, WATER MODERATED REACTORS, WWER TYPE REACTORS
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Beyer, M.; Schumann, P.; Seidel, A.; Zschau, J.
Forschungszentrum Rossendorf e.V. (FZR) (Germany). Inst. fuer Sicherheitsforschung. Funding organisation: Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit, Bonn (Germany)1997
Forschungszentrum Rossendorf e.V. (FZR) (Germany). Inst. fuer Sicherheitsforschung. Funding organisation: Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit, Bonn (Germany)1997
AbstractAbstract
[en] In the paper a Technical System is described to improve the operational monitoring of a nuclear power plant equipped with the standardised VVER-1000/320 reactor type is described. A pilot project of this system in Zaporozhye NPP unit 5 has been started in 1992. The monitoring tasks are mainly directed to operational parameters but include in accordance to international experiences the radiological parameters as well as the meteorological. The monitoring concept based on protection objectives and related control tasks, the resulting selection of monitored parameters, the structure of the monitoring system, the automatic evaluation of the process and of components by comparison of the actual values of the selected parameters with monitor-specific limit values as well as the classification of the evaluation results into the information levels Notice, Warning and Alarm are explained. The operational testing period of the system has been started in summer 1996. (orig.)
[de]
Es wird ueber ein Technisches System zur verbesserten betrieblichen Ueberwachung eines KKW mit unifiziertem WWER-1000/320-Reaktor berichtet, mit dessen Pilotprojekt 1992 im ukrainischen KKW Saporoshje begonnen worden war. Die Ueberwachung ist schwerpunktmaessig auf betriebliche Parameter ausgerichtet, umfasst aber auch die international ueblichen radiologischen und meteorologischen Aufgaben. Das Ueberwachungskonzept auf der Basis von Schutzzielen und Kontrollaufgaben sowie die daraus folgende Auswahl der ueberwachten Parameter, die strukturelle Gestaltung des technischen Systems, die automatische Bewertung des Prozess- und Anlagenzustandes durch Vergleich der betrieblichen und radiologischen Parameter mit ueberwachungsspezifischen Grenzwerten sowie die Klassierung des Bewertungsergebnisses in die Informationsstufen Meldung, Warnung und Alarm werden erlaeutert. Der Testbetrieb des Systems unter industriellen Bedingungen hat im Sommer 1996 begonnen. (orig.)Original Title
Aufbau eines behoerdlichen Fernueberwachungssystems zur betrieblichen Ueberwachung des KKW Saporoshje (Block 5) - 3. Realisierungsstufe. Abschlussbericht. Textteil
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Mar 1997; 40 p; FOERDERKENNZEICHEN BMU INT 9226; Available from FIZ Karlsruhe
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