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AbstractAbstract
[en] Quality assurance for ensuring the requisite quality of primary system components includes object-related and system-related measures. The object-related measures include assessment of the fabrication engineering preconditions, checking the documentation relating to design, ordering and fabrication, and supervision of the important fabrication steps and of testing. This work is carried out by independent experts and inspectors and by the KWU. The system-related quality assurance is aimed at creating the organisational preconditions for faultless fabrication, taking also into account the time schedules and costs. This work is carried out by the KWU. (orig.)
[de]
Zur Sicherstellung der Qualitaet von Primaerkomponenten werden objektbezogene und systembezogene Massnahmen durchgefuehrt. Die objektbezogenen Massnahmen beinhalten neben einer Begutachtung der fertigungstechnischen Voraussetzungen eine Ueberpruefung der Unterlagen fuer die Konstruktion, Bestellung und Fertigung sowie eine Ueberwachung wichtiger Fertigungsschritte und die Durchfuehrung der Pruefungen. Diese Arbeiten werden von den technischen Ueberwachungsvereinen und der KWU durchgefuehrt. Die systembezogenen Massnahmen der Qualitaetssicherung sollen die organisatorischen Voraussetzungen fuer die Durchfuehrung der Fertigung unter Beruecksichtigung von Terminen und Kosten schaffen. Diese Massnahmen werden von der KWU durchgefuehrt. (orig.)Original Title
Qualitaetssicherung bei der Herstellung von Primaerkomponenten
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Kerntechnik; v. 18(4); p. 164-167
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INIS VolumeINIS Volume
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Paiva, I.P.V.
Semi-annual report of Nuclear Technology and Development Center (CDTN) - July to December 19881989
Semi-annual report of Nuclear Technology and Development Center (CDTN) - July to December 19881989
AbstractAbstract
[en] The main activities developed during the year of 1988 are described. (E.G.)
[pt]
Descrevem-se as atividades desenvolvidas no periodo de 01.01.88 a 31.12.88 no programa de testes de componentes do CDTN. (E.G.)Original Title
Relatorio anual do programa testes de componentes - 1988
Primary Subject
Source
Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); 353 p; 1989; p. 133-148; DETR--277-88
Record Type
Report
Literature Type
Progress Report
Report Number
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LanguageLanguage
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Raczynski, Wladyslaw.
Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)1981
Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)1981
AbstractAbstract
[en] A centrifugal pump for moving a fluid such as the coolant fluid of a nuclear reactor is described. It comprises a volute made up of an enclosure with openings for the inlet and outlet of the fluid, a removable suction pipe fixed on the volute on a level with the fluid inlet opening and directed towards its interior, a rotor located inside the volute fixed on a shaft passing through an opening provided in the volute wall as well as an annular diffuser having as circular symmetry axis the rotation axis of the rotor, arranged around the rotor inside the volute and fixed on the suction pipe at one of its ends. The examination and maintenance operations of the internal components of the pump can be carried out with suitable testing appliances introduced through the opening through which the rotor passes
[fr]
On decrit une pompe centrifuge pour la mise en circulation d'un fluide, tel que le fluide de refroidissement d'un reacteur nucleaire, comportant une volute constituee par une enceinte ayant des ouvertures pour l'entree et la sortie du fluide, un conduit d'aspiration demontable fixe sur la volute au niveau de l'ouverture d'entree du fluide et dirige vers l'interieur de celle-ci, un rotor dispose a l'interieur de la volute fixe sur un arbre passant par une ouverture prevue dans la paroi de la volute ainsi qu'un diffuseur annulaire ayant pour axe de symetrie de revolution l'axe de rotation du rotor, dispose autour du rotor a l'interieur de la volute et fixe sur le conduit d'aspiration a l'une de ses extremites, les operations d'examen et d'entretien des organes internes de la pompe, pouvant etre effectuees a l'aide d'appareils de controle appropries introduits par l'ouverture de passage du rotorOriginal Title
Pompe centrifuge a diffuseur demontable
Primary Subject
Source
24 Dec 1981; 13 p; FR PATENT DOCUMENT 2485114/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
Record Type
Patent
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Whenever the stress analysis for some secondary pipes is not necessary, it is desirable to uncouple the main system from these secondary pipes. The uncoupling, however, is only allowable on the basis of some acceptability criteria defined in terms of mass and frequency ratios of the main system to the secondary system. At the request of the authorities, it often becomes necessary, at a later date, to also investigate the secondary pipes. The important reduction of costs, the elimination of the effect of ill-conditioning that are more serious in large systems with large differences in the stiffnesses of the elements, the exceeding of the program or computer capacity can be arguments for a separate stress analysis of the secondary uncoupled system. For the stress analysis of the secondary uncoupled system, it is generally not possible to neglect the influence of the main system. This paper presents a method to separately perform the stress analysis of the secondary uncoupled piping systems from the main system already calculated. (orig.)
Primary Subject
Source
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; Commission of the European Communities, Brussels (Belgium); 332 p; ISBN 0 444 86259 5;
; 1981; vp; North-Holland Publishing Co; Amsterdam, Netherlands; 6. international conference on structural mechanics in reactor technology; Paris, France; 17 - 21 Aug 1981

Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Buchner, K.H.; Jakusch, H.; Souresny, H.
Vitkovicke Zelezarny Klementa Gottwalda, Ostrava (Czechoslovakia)1975
Vitkovicke Zelezarny Klementa Gottwalda, Ostrava (Czechoslovakia)1975
AbstractAbstract
[en] The demands are presented on the material properties of tubes used for building reactors and manufacturing equipment of nuclear power plants. These materials are subjected to long-term straining, to neutron flux which affects their physical, chemical and mechanical properties. The composition of the coolant and minute admixtures in it affect the corrosion of the tubes and released hydrogen causes embrittlement. Sodium reacts with certain alloying components. Certain types of austenitic steels, alloys and cladding materials for thermal reactors are given. The most frequently used are Zircalloy 2 and 4. The regulations are given issued by builder of reactors for manufacturers of tubes, for testing, cleaning, packing, etc. A brief description is also given of the manufacture of tubes by extrusion by Schoeller and Bleckmann. (Oy)
Original Title
Trubky pro stavbu reaktoru
Primary Subject
Secondary Subject
Source
1975; 17 p; P--50/75; Available from Vitkovicke zelezarny Klementa Gottwalda, Ostrava, Czechoslovakia; Translated from Berg- Huettenmaenn. Monatsh. (1972) v. 117(5) p. 181-190.
Record Type
Miscellaneous
Report Number
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Reference NumberReference Number
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AbstractAbstract
[en] In the design of nuclear power stations all stresses on the pressure-bearing enclosure in respect of their effect on component strength and integrity are investigated. In addition, local and global monitoring during operation is carried out, in order to detect also those stresses which have been hitherto unknown or are caused by malfunctions of components. In this way a realistic assessment of the condition of the pressure-bearing enclosure is possible and any irregularities which can imply malfunctions of components or physical effects not hitherto known can be detected early. (orig.)
[de]
Bei der Auslegung von Kernkraftwerken werden alle Belastungen der druckfuehrenden Umschliessung hinsichtlich ihrer Auswirkungen auf Bauteilfestigkeit und Integritaet untersucht. Zusaetzlich wird eine betriebsbegleitende lokale und globale Ueberwachung durchgefuehrt, um auch Belastungen zu erfassen, die bisher nicht bekannt waren oder durch Fehlfunktionen von Bauteilen verursacht werden. Dadurch ist eine realistische Beurteilung des Zustandes der druckfuehrenden Umschliessung moeglich, etwaige Unregelmaessigkeiten, die auf Fehlfunktionen von Bauteilen bzw. auf bisher nicht bekannte physikalische Effekte schliessen lassen, werden fruehzeitig erkannt. (orig.)Original Title
Betriebsbegleitende Bauteilueberwachung in Kernkraftwerken
Primary Subject
Record Type
Journal Article
Journal
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AbstractAbstract
[en] A gland is proposed of the valve spindle designed for radioactive or otherwise harmful media, such as in nuclear power plant primary circuits. The gland is installed in the valve cover and consists of a primary and a secondary part and of a gland case partitioning the gland space into two chambers. The bottom face of the gland case is provided with a double-sided collar for controlling the elements of the bottom primary gland while the top face is provided with a removable flange. (M.S.)
Original Title
Ucpavka vretena armatury
Primary Subject
Source
15 Mar 1979; 4 p; CS PATENT DOCUMENT 177797/B/
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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AbstractAbstract
[en] A hydrostatic radial pump is described characterized by the fact that part of the medium off-taken from delivery is used as a lubricating medium. Two additional bodies are placed alongside a hydrostatic bearing with coils in between them and the pump shaft; the coils have an opposite pitch. The feed channel for the hydrostatic bearing pocket is linked to delivery. The coil outlets are connected to the pump suction unit. Two rotating coils placed alongside the hydrostatic bearing will considerably simplify the communication channel design and reduce the dependence on the pump shaft deflections. The addition of another rotating coil in the close vicinity of the pump shaft or directly on the shaft further increases the efficiency. The bearing can be used in designing vertical circulating pumps for the cooling circuits of nuclear reactors. (J.B.)
Original Title
Hydrostaticke radialni lozisko odstrediveho cerpadla
Primary Subject
Source
15 Aug 1976; 3 p; CS PATENT DOCUMENT 164155/B/
Record Type
Patent
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AbstractAbstract
[en] The regulation, issued by the National Board of Technical Surveillance, concerns pressure components of pressurized water reactors, water treatment plants within nuclear power stations, and devices for measuring and controlling pressure, temperature, and level of filling. It specifies licensing and permission, revision and inspection, and transitional regulations and will enter into force on 1 January 1988
Original Title
Anordnung ueber die Nomenklatur ueberwachungspflichtiger drucktechnischer Anlagenteile fuer Kernkraftwerke mit Druckwasserreaktoren vom 6. Mai 1987
Primary Subject
Secondary Subject
Record Type
Journal Article
Literature Type
Legislative Material
Journal
Gesetzblatt der Deutschen Demokratischen Republik. Teil 1; ISSN 0138-1644;
; CODEN GDDTD; (no.16); p. 185-186

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AbstractAbstract
[en] The inner diameter of the pump body connecting branch is provided with a bevelled surface shoulder while the outer diameter of the lid is provided in its bottom part with a bevelled surface recess. A sealing ring is inserted between the lid and the connecting branch. The connecting branch of the pump body is provided with a slot housing a segment ring. The lid is provided with a shim preventing the segment ring radial movement. The sealing ring has a triangular or a rectangular cross section. (J.P.)
Original Title
Spojeni vika a telesa cerpadla, zejmena cirkulacniho cerpadla pro primarni okruhy jadernych energetickych systemu
Primary Subject
Source
15 Jul 1976; 6 p; CS PATENT DOCUMENT 163994/B/
Record Type
Patent
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