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Barry, R.F.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1980
Westinghouse Electric Corp., Pittsburgh, PA (USA)1980
AbstractAbstract
[en] The invention refers to the process monitoring which requires a high standard of efficiency and reliability. It particularly concerns the monitoring of the vital processes of the nuclear reactor system for generating electric energy. Apart from the nuclear reactor, such reactor systems include auxiliary appliances such as steam generators, pressurizing systems, feed water heaters, turbines, etc. The invention applies totally to the monitoring of nuclear reactor systems and, with a view to facilitating the understanding of this invention by dealing with the concrete monitoring difficulties, this submission is, to a large extent, restricted to the monitoring difficulties of the operating processes of nuclear reactor systems
[fr]
L'invention concerne le controle de processus qui demandent un standard eleve de rendement et de fiabilite. Elle concerne particulierement le controle des processus vitaux des systemes a reacteur nucleaire destines a la production d'energie electrique. De tels systemes a reacteur comportent, en addition a un reacteur nucleaire, des appareils auxiliaires tels que des generateurs de vapeur, des dispositifs de mise sous pression, des rechauffeurs d'eau d'alimentation, des turbines, etc. L'invention s'applique totalement au controle des systemes a reacteur nucleaire et, dans l'interet de faciliter la comprehension de cette invention en traitant les difficultes concretes de controle, la presente demande est, dans une large mesure, limitee aux difficultes de controle des processus de fonctionnement de systemes a reacteur nucleaireOriginal Title
Appareil pour le controle du fonctionnement d'une installation a reacteur nucleaire
Primary Subject
Source
12 Sep 1980; 42 p; FR PATENT DOCUMENT 2449325/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 14 Feb 1979, US.
Record Type
Patent
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AbstractAbstract
[en] By the use of a procedure for on-site testing of nuclear reactor instruments it should be possible to judge their ability to guarantee the reactor safety and availability at the moment of divergence or during operation. Such a procedure must therefore be created as a work implement for the quick and reliable installation of electronic devices necessary for nuclear reactor control and supervision. A standard document is proposed for this purpose, allowing a ''test programme'' to be set up before the equipment is installed on the site
[fr]
L'utilisation d'une procedure d'essais sur le site de l'instrumentation des reacteurs nucleaires doit permettre d'apprecier l'aptitude du material a assurer la securite et la disponibilite du reacteur au moment de la divergence et en cours d'exploitation. Il est donc necessaire de creer cette procedure, afin de posseder un outil efficace permettant la mise en service rapide et sure des ensembles electroniques necessaires au controle des reacteurs nucleaires. Pour atteindre ce but, on propose un document type permettant d'elaborer avant l'installation du material sur le site un ''programme d'essais''Original Title
Material electronique nucleaire pour tableau de commande et de controle. Guide de procedures pour les essais sur le site de l'instrumentation des reacteurs nucleaires
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Source
Oct 1975; 28 p; CEA-S-MCH-MENT--9
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Report
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AbstractAbstract
No abstract available
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Journal Article
Journal
Electronics Letters; v. 11(13); p. 269-270
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AbstractAbstract
No abstract available
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Source
20. nuclear science symposium and 5. nuclear power systems symposium; San Francisco, CA; 14 Nov 1973
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Journal Article
Literature Type
Conference
Journal
IEEE (Inst. Elec. Electron. Eng.), Trans. Nucl. Sci; v. NS-21(1); p. 964-970
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Brabenec, J.
Tesla, Premysleni (Czechoslovakia). Vyzkumny Ustav Pristroju Jaderne Techniky1971
Tesla, Premysleni (Czechoslovakia). Vyzkumny Ustav Pristroju Jaderne Techniky1971
AbstractAbstract
No abstract available
Original Title
Vyzkum a vyvoj pristroju pro system rizeni jadernych reaktoru
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Source
Apr 1971; 6 p
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Report
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AbstractAbstract
[en] Many technical solutions have been proposed for controlling the neutron flux in a reactor, among them, controlling by means of channels filled with neutron absorbers in various states of aggregation. The present paper considers the possibility of employing channels filled with layered structures of neutron-transparent and neutron-absorbing substances whose content is determined by the constant of a two-phase equilibrium reaction which is temperature-dependent. 12 refs
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Journal Article
Journal
Soviet Atomic Energy; v. 48(3); p. 217-219
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Gemin, Yves.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France)1975
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France)1975
AbstractAbstract
[en] The attention of manufacturers of control and monitoring materials is attracted on the possible improvements to be effected in control board reading using a more rational arrangement of monitoring stations
[fr]
On attire l'attention des constructeurs de materiels de controle et de surveillance sur les possibilites d'ameliorer la lecture des tableaux par une disposition plus rationnelle des postes de surveillanceOriginal Title
Etude d'une disposition plus fonctionnelle des tableaux d'une salle de controle d'un reacteur nucleaire
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Source
Feb 1975; 6 p; 5. Annual meeting of the European Society of Nuclear Methods in Agriculture (ESNA); Bucharest, Romania; 19 Sep 1974
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Report
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Conference
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Valentine, T.E.; Mihalczo, J.T.
Oak Ridge National Lab., TN (United States). Funding organisation: USDOE, Washington, DC (United States)1996
Oak Ridge National Lab., TN (United States). Funding organisation: USDOE, Washington, DC (United States)1996
AbstractAbstract
[en] One primary concern for design of safety systems for reactors is the time response of external detectors to changes in the core. This paper describes a way to estimate the time delay between the core power production and the external detector response using Monte Carlo calculations and suggests a technique to measure the time delay. The Monte Carlo code KENO-NR was used to determine the time delay between the core power production and the external detector response for a conceptual design of the Advanced Neutron Source (ANS) reactor. The Monte Carlo estimated time delay was determined to be about 10 ms for this conceptual design of the ANS reactor
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1996; 8 p; PHYSOR 96: international conference on the physics of reactors; Mito (Japan); 16-20 Sep 1996; CONTRACT AC05-96OR22464; Also available from OSTI as DE96013779; NTIS; US Govt. Printing Office Dep
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Report
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Tzafestas, S.G.
Democritos Nuclear Research Center, Athens (Greece)1983
Democritos Nuclear Research Center, Athens (Greece)1983
AbstractAbstract
[en] This report presents a review of the basic techniques developed over the recent years for the optimum supervision and detection/location of failures in dynamic technological systems such as nuclear reactors, aircrafts, etc. Regarding the optimum supervision problem the following policies are considered: optimum selection of supervision frequency, optimum supervision policies, optimum selection of sequential tests, and finally the effect of supervision capability upon the system availability. Regarding the optimum detection/location/identification of failures the following techniques are briefly presented: majority technique, failure sensitive filter technique, generalized maximum likelihood technique, output estimation error technique, dynamic redundancy technique with Luenberger observer, and finally jump processes technique. Some examples and comments on open problems for further research are also presented. (author)
Original Title
Tehnikes beltistes epiblepses kai anihneuses blabon tehnologikon sustematon - Mia genike anaskopese; A general review
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Source
Dec 1983; 39 p; Also available from Library, Democritus NRC
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Report
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Gouffon, A.; Lecocq, J.M.
Nuclear energy maturity. Communications of the I. European nuclear conference. Paris, 21-25 April 19751975
Nuclear energy maturity. Communications of the I. European nuclear conference. Paris, 21-25 April 19751975
AbstractAbstract
[en] Among other Westinghouse three-loop plants, the Tihange plant has the highest linear power density. Severe control systems have thus been developed. The reactivity control system, power distribution control and axial power distribution monitoring system are described
[fr]
Parmi les autres reacteurs Westinghouse a trois boucles, la centrale de Tihange a la plus forte puissance lineique moyenne. Des systemes de controle severe ont donc du etre developpes: systeme de controle de reactivite, controle de distribution de puissance, et le systeme de controle de la distribution de puissance axiale (APDMS)Original Title
Le controle de la puissance de la centrale de Tihange
Primary Subject
Source
Lehoulier, J.; Mantega, M. (eds.); American Nuclear Society, Hinsdale, Ill.; Societe Europeenne d'Energie Nucleaire, Petit-Lancy (Switzerland); p. 70-71; 1975; Societe Francaise de l'Energie Nucleaire; Clamart, France; 1. European nuclear conference; Paris, France; 21 Apr 1975
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Book
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Conference
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