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AbstractAbstract
No abstract available
Primary Subject
Source
Biron, Andre (ed.); Ecole Polytechnique, Montreal, Quebec (Canada). Dept. de Genie Mecanique; p. 104-113; Jul 1974; Stress analysis of nuclear power plant components; Montreal, Quebec, Canada; 2 May 1974
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AbstractAbstract
[en] This paper addresses the effects of dynamic events induced by support motion on piping systems with snubbers having variable gap sizes. The investigation consists of 3 parts: (i) Mathematical examination of a linear 1 DOF mass-spring-snubber system with gap size zero or infinity. (ii) Numerical analysis of a piecewise linear 1 DOF mass-spring-snubber system with varying gap sizes, by means of a simple computer code. (iii) Numerical analysis of a realistic three-dimensional piping system with 3 snubbers, each having 4 different gap sizes, with the aid of a non-linear F.E. code. (orig.)
Primary Subject
Record Type
Journal Article
Journal
Nuclear Engineering and Design; ISSN 0029-5493;
; v. 67(2); p. 145-164

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Kamil, H.; Gantayat, A.; Attia, A.; Goulding, H.
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. F1983
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. F1983
AbstractAbstract
[en] The paper presents the results of an investigation on the development of methodologies for coupled water-hammer analyses. The study was conducted because the present analytical methods for calculation of loads on piping systems and supports resulting from water-hammer phenomena are overly conservative. This is mainly because the methods do not usually include interaction between the fluid and the piping and thus predict high loads on piping systems and supports. The objective of the investigation presented in this paper was to develop methodologies for coupled water-hammer analyses, including fluid-structure interaction effects, to be able to obtain realistic loads on piping systems and supports, resulting in production of more economical designs. (orig./RW)
Primary Subject
Source
Commission of the European Communities, Luxembourg; Argonne National Lab., IL (USA); 426 p; ISBN 0 444 86695 7;
; 1983; p. 275-281; North-Holland; Amsterdam (Netherlands); 7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7); Chicago, IL (USA); 22-26 Aug 1983

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Book
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Conference
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Jan, F.; Perry, R.F.; Rigamonti, G.F.
Structural mechanics in reactor technology. Transactions. IK-panel session papers1979
Structural mechanics in reactor technology. Transactions. IK-panel session papers1979
AbstractAbstract
No abstract available
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. 377; 1979; p. 377; North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-017; Short communication only.
Record Type
Book
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Conference
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Raymond, T.E.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1978
Westinghouse Electric Corp., Pittsburgh, PA (USA)1978
AbstractAbstract
[en] A storage rack for nuclear fuel assemblies comprising lower and upper bearers to support and hold fuel assemblies in their vertical position is described. The feature of this rack is the lower supporting device which comprises a pivoting base on which rests each fuel assembly, thereby enabling the fuel assembly not be subjected to any fatigue during storage
[fr]
On decrit un ratelier de magasinage d'assemblages combustibles nucleaires comprenant des dispositifs de support inferieur et superieur pour supporter et retenir des assemblages combustibles dans leur position verticale, caracterise par le fait que le dispositif de support inferieur comporte pour chaque assemblage combustible une base pivotante sur laquelle porte cet assemblage combustible pour permettre, de ce fait, le relachement de toute fatigue de cet assemblage combustible pendant le magasinageOriginal Title
Dispositif a base pivotante pour le magasinage de combustible nucleaire
Primary Subject
Source
27 Jan 1978; 10 p; FR PATENT DOCUMENT 2379883/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 2 Feb 1977, US.
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Plummer, S.J.
Picker International, Inc., Highland Heights, OH (USA)1990
Picker International, Inc., Highland Heights, OH (USA)1990
AbstractAbstract
[en] This patent describes a scanning nuclear camera apparatus. A camera head for converting radiation from a subject into output signals indicative thereof; a subject supporting top having a head end, a foot end, and first and second sides; a gantry means for supporting and selectively moving the camera head longitudinally along upper and lower surfaces of the top, and peripherally around a central portion and the head end of the top; and an undercarriage for supporting the top without interfering with the movement of the camera head and without interfering with reception by the camera head of radiation events emanating from the supported subject during the peripheral movement of the camera head
Secondary Subject
Source
24 Jul 1990; 20 Sep 1988; vp; US PATENT DOCUMENT 4,943,726/A/; Patent and Trademark Office, Box 9, Washington, DC 20232 (USA); ?: 20 Sep 1988
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Anthony, A.J.
Combustion Engineering, Inc., Windsor, CT (USA); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
Combustion Engineering, Inc., Windsor, CT (USA); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
AbstractAbstract
[en] For refuelling the reactor vessel closure head is opened and the annulus between reactor vessel and biological shield respectively reactor cavity is filled with water containing boric acid. In this way an additional shield against neutron and gamma radiation is formed. For support and sealing of the annulus there is used a ring to be mounted on the site and consisting of equal-sized ring segments being firmly and tightly braced with each other. At its lower side there is fastened one each U-shaped sealing ledge sewing as contact surface on the pressure vessel and the biological shield. Thex meet closely and thus form two circular sealing rings. They consist of plastics on the basis of polymethane and get into close contact with the ring segments of ferritic steel. On the ring segments there may also be put a protective sheet of polyethylene. (DG)
[de]
Beim BE-Wechsel wird der RDB-D geoeffnet und der Ringraum zwischen RDB und dem biologischen Schild bzw. der Reaktorkaverne mit Borsaeure enthaltendem Wasser geflutet. Es wird somit eine Zusatzabschirmung gegenueber Neutronen- und γ-Strahlung gebildet. Zur Abstuetzung und Abdichtung des Ringraumes dient ein vor Ort montierbarer Ring aus gleichgrossen Ringsegmenten, welche miteinander dicht und fest verspannt werden. An ihrer Unterseite befindet sich jeweils eine U-foermige Dichtleiste fuer die Auflage am Druckbehaelter und die Auflage am biologischen Schild. Sie stossen dicht aneinander und bilden somit zwei umlaufende Dichtringleisten. Sie bestehen aus Kunststoff auf Polyurethan-Basis und gehen mit den Ringsegmenten aus feritischem Stahl eine innige Verbindung ein. Auf die Ringsegmente kann ebenfalls eine Schutzfolie aus Polyaethylen aufgelegt sein. (DG)Original Title
Abschirmvorrichtung fuer einen Kernreaktor und Verfahren zur Herstellung eines Tragkoerpers fuer eine solche Vorrichtung
Primary Subject
Source
6 Apr 1978; 14 p; DE PATENT DOCUMENT 2743426/A/
Record Type
Patent
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Reference NumberReference Number
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Foerster, S.; Kleemann, M.
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)1977
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)1977
AbstractAbstract
[en] Plate-shaped heat exchanger matrices of high capacity are modified so that they can be used for great mass flows at high differential pressure and temperature, particularly in the gas cooled high temperature nuclear reactor. It is proposed that a large number of heat exchanger matrices connected in parallel should be inserted in a tubular housing, which has a polygonal end plate at one of the outside surfaces, which acts as a support. This carries a number of honeycomb shaped cells, which take the individual heat exchanger matrices. An advantageous configuration of the individual components of the arrangement is described. (UWI)
[de]
Plattenfoermige Waermetauschermatrizen hoher Leistungsfaehigkeit werden so modifiziert, den sie auch fuer grosse Massenstroeme bei hohen Druck- und Temperaturdifferenzen einzusetzen sind, insbesondere bei gasgekuehlten Hochtemperatur-Kernreaktoren. Es wird vorgeschlagen, eine groessere Zahl von parallelgeschalteten Waermetauschmatrizen in einem rohrfoermigen Gehaeuse einzusetzten, das an einer der Stimseiten eine polygone Endplatte aufweist, die zur Abstuetzung dient. Sie traegt eine Anzahl wabenfoermiger Zellen, die die einzelnen Waermetauschermatrizen aufnehmen. Vorteilhafte Ausgestaltung der einzelnen Komponenten der Vorrichtung ist beschrieben. (UWI)Original Title
Vorrichtung zur Abstuetzung fuer plattenfoermige Waermetauschermatrizen
Primary Subject
Source
18 May 1977; 23 p; DE PATENT DOCUMENT 2549052/A/; Also available from Dt. Patentamt, Muenchen (FRG); 7 figs.
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Patent
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INIS VolumeINIS Volume
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AbstractAbstract
[en] The proposal concerns the reinforcement of a cooling tower made of reinforced concrete, which has a dish-shaped supporting structure and has ribs running in the vertical direction. In order to reduce the cost for fitting the reinforcement, the dish-shaped supporting structure is made wholly or partly as an anisotropic dish. By this construction of the reinforcement (spatial grating with different thickness of beam reinforcement of vertical ribs and of the circular beams provided in the dish, site reinforcement of the areas between the beams) one achieves the anisotropy of the dish. The fixing of constructional steel mats as site reinforcement is advantageous. (UWI)
[de]
Der Vorschlag betrifft die Bewehrung eines Kuehlturms aus Stahlbeton der ein Schalentragwerk aufweist und in Meridianrichtung verlaufende Rippen besitzt. Um die Kosten fuer das Anbringen der Bewehrung herabzusetzten, wird das Schalentragwerk ganz oder teilweise als anisotrope Schale ausgebildet. Man erreicht, dass durch Ausbildung der Bewehrung (raeumlicher Balkenrost mit unterschiedlicher Staerke der Bewehrung der Balken, der Meridianrippen und der in der Schale vorgesehenen Ringbalken andererseits, Feldbewehrung der zwischen den Balken befindlichen Felder) die Anisotropie der Schale gebildet wird. Vorteilhaft ist das Anbringen von Baustahlmatten als Feldbewehrung. (UWI)Original Title
Kuehlturm
Primary Subject
Source
20 Oct 1977; 13 p; DE PATENT DOCUMENT 2614695/A/; Also available from Dt. Patentamt, Muenchen (FRG); 4 figs.
Record Type
Patent
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INIS VolumeINIS Volume
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Overview of numerical methods for predicting flow-induced vibration and wear of heat-exchanger tubes
Axisa, F.; Villard, B.; Antunes, J.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Inst. de Recherche Technologique et de Developpement Industriel (IRDI)1986
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Inst. de Recherche Technologique et de Developpement Industriel (IRDI)1986
AbstractAbstract
[en] Practical interest in performing predictive analysis of vibration and wear risks of industrial tube bundles, e.g. in nuclear reactor heat exchangers, subjected to cross flow is broadly recognized. A predictive analysis of an heat-exchanger design against severe vibration and wear has to cope with experimental data on FIV and fretting wear, together with the use of analytical and numerical methods for predicting linear and nonlinear tube response. This paper describes a general approcah of the problem currently under development at C.E.A. Attention is especially paid to some key aspects of the numerical techniques, namely, the modelisation of flow-induced forcing functions and the modelisation of impact and sliding at tube-support gaps. These topics are exemplified by numerical results related to some typical situations including the case of random vibration induced by flow turbulence and fluid-elastic vibration
Primary Subject
Source
Jul 1986; 20 p; International conference on computers in engineering, pressure vessels and piping; Chicago, IL (USA); 20-24 Jul 1986
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Report
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Conference
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