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Barabach, Boris; Deltour, Philippe.
CEA, 75 - Paris (France)1976
CEA, 75 - Paris (France)1976
AbstractAbstract
[en] This invention concerns a system for enabling a nuclear reactor core to be loaded whilst avoiding the errors in positioning them and, in particular, their introduction into the core in conditions likely to bring about nuclear excursions. It applies particularly to the case of an experimental reactor of the pool type. The system in question includes an upper deflecting grille with side openings, fitted above the core and parallel to the lower grille support, for introducing control members on a level with their position. A central aperture enables the fuel elements to be passed in one by one. The passage through this central aperture is prevented by pivoting bolts retracting under the effect of the actuating gear carried by the control members, so that the loading of any fuel element by axial entry into the central aperture then by transverse displacement in order to place it between two adjacent control members, cannot take place until all the control members have been introduced beforehand in the core
[fr]
La presente invention est relative a un dispositif permettant de proceder au chargement du coeur d'un reacteur nucleaire par des elements combustibles, en evitant les erreurs de positionnement de ces elements et notamment leur introduction dans le coeur dans des conditions susceptibles d'entrainer des risques d'excursions nucleaires. Elle s'applique plus particulierement dans le cas d'un reacteur experimental du type piscine. Le dispositif considere comporte, monte au-dessus du coeur et parallelement a la grille de support inferieure, une grille superieure de detrompage, comprenant des ouvertures laterales pour l'introduction, au droit de leurs emplacements dans le coeur, des elements de controle. Une ouverture centrale permet l'engagement un a un des elements combustibles. Le passage a travers cette ouverture centrale est empeche par des verrous pivotants s'effacant sous l'effet de moyens d'actionnement portes par les elements de controle de telle sorte que le chargement d'un element combustible quelconque par engagement axial dans l'ouverture centrale puis par deplacement transversal pour mise en place entre deux elements de controle adjacents, ne puisse s'effectuer qu'une fois tous les elements de controle prealablement introduits dans le coeurOriginal Title
Dispositif pour eliminer les erreurs de chargement dans un reacteur nucleaire; pool type reactors
Primary Subject
Source
28 Oct 1976; 15 p; FR PATENT DOCUMENT 2369657/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The design is described of the vessels and components of a multi-pool experimental reactor working with a variable reactor level. The reactor is composed of separated vessels which are placed in shafts in the external shielding block whose upper surface forms the technological foundation. Horizontal openings and vertical channels are formed in the block walls. One of the vessels is fitted with experimental channels, fuel elements and control elements. The shielding bushings of the tangential channel with the shielding plug and of the radial channel with a shielding closure reach as far as the outer shielding block. A common shaft for the reactor vessel and experimental vessel is formed in this block. The radioactive fuel element storage room is in the bottom part of the experimental vessel. (Z.S.). 2 figs
Original Title
Vicebazenovy experimentalni reaktor
Primary Subject
Source
25 Nov 1991; 6 Dec 1989; 5 p; CZ PATENT DOCUMENT 275475/B6/; CZ PATENT APPLICATION PV 6901-89.N; Application date: 6 Dec 1989
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Bartzis, J.G.
Democritos Nuclear Research Center, Athens (Greece)1983
Democritos Nuclear Research Center, Athens (Greece)1983
AbstractAbstract
[en] In open pool research and test reactors it is essential to demonstrate, in the case of loss of the tank water under accident conditions, that the ambient air is capable of keeping the temperature level below the melting point. This work is part of an effort to build capability of predicting fuel temperature in the air-cooled core of the Greek Research Reactor-1 (GRR-1) or similar ones. To this purpose a 3-D computer program named ThEAP-I is under development. Temperature calculations are performed taking into consideration important factors such as external and internal natural convection, heat radiation, grid plate effect, interrupted daily and weekly reactor working schedule, number of fuel cycles for a particular fuel element, etc. In the present work the overall problem of modelling, as well as certain applications are presented and discussed. (author)
Primary Subject
Source
Nov 1983; 48 p; Also available from Library, Democritus NRC
Record Type
Report
Report Number
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AbstractAbstract
[en] A computer programme has been developed to calculate the loss of coolant accident at the top part of the fuel rod, for a pool type reactor. The following heat transfer modes are considered in the computer code: 1) forced convection in the transition regimes, 2) forced turbulent convection, 3) forced laminar convection, 4) natural convection in water, 5) natural convection in rectangular cells, 6) natural convection in air in partially closed channels, 7) laminar convection in steam, 8) thermal radiation between two parallel plates within the steam, 9) nucleate boiling in standing liquid
Original Title
Programa de compute para el calcule del accidente de perdida del refrigerante de un reactor nuclear del tipo piscina
Primary Subject
Record Type
Journal Article
Journal
Informe Nuclear; v. 1(1); p. 41-54
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Bregeon, Louis; Dupuy, Gerard; Lerouge, Bernard; Schwartz, J.-P.
CEA, 75 - Paris (France)1974
CEA, 75 - Paris (France)1974
AbstractAbstract
[en] The pool type process heat nuclear reactor described includes a generally cylindrical vertical vessel filled with a cooland and with an open upper part. The containment is divided into two upper and lower sections by a horizontal partition. The lower part houses the reactor core, at least one heat exchanger and at least one venturi placed vertically, the neck of which is located near the bottom of the containment. The lower part includes facilities for moving part of the core coolant to the exchanger then from the exchanger to the venturi and last from the venturi to the core intake. The reactor also includes at least one duct passing through the horizontal partition and opening at its upper end in the top part and at its lower end in at least one hole provided in the wall of the venturi or venturis at neck level
[fr]
On presente un reacteur nucleaire calogene du type piscine. Il comprend une enceinte de forme generale cylindrique d'axe vertical remplie d'un liquide de refroidissement et ouverte a sa partie superieure. L'enceinte est separee en deux regions, respectivement superieure et inferieure, par une paroi horizontale. La region inferieure contient le coeur du reacteur, au moins un echangeur de chaleur et au moins un venturi a axe vertical dont le col est situe au voisinage du fond de l'enceinte. La zone inferieure comporte des moyens pour faire circuler une partie du fluide de refroidissement du coeur vers l'echangeur, puis de l'echangeur vers le venturi et enfin du venturi vers l'entree du coeur. Le reacteur comporte en outre au moins une conduite traversant la paroi horizontale et debouchant a son extremite superieure dans la region superieure et a son extremite inferieure dans au moins un orifice menage dans la paroi du ou des venturis au niveau du colOriginal Title
Reacteur nucleaire calogene du type piscine
Primary Subject
Source
30 Aug 1974; 10 p; FR PATENT DOCUMENT 2283523/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] The primary objective of the balance-of-plant technical effort during Phase A Extension was to perform design work for a 1000 MWe (gross) pool type LMFBR to obtain an integrated plant design with emphasis of pool related structures and systems that differ from a loop type LMFBR or are of special concern. This report describes the general arrangement of major structures and equipment that are supported on a common foundation mat and the containment auxiliary systems that are unique or essential for the pool concept. Installation of major pool components during construction and containment design features that permit removal of major pool-related equipment are also described
Primary Subject
Source
Aug 1978; 260 p; Available from NTIS., PC A12/MF A01
Record Type
Report
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AbstractAbstract
No abstract available
Primary Subject
Source
Transactions of the American Nuclear Society 1976 annual meeting; Toronto, Canada; 13 Jun 1976; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 23 p. 480
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Acquier, B.; Berhault, M.
Bignier-Schmid-Laurent (BSL), 94 - Ivry-sur-Seine (France)1987
Bignier-Schmid-Laurent (BSL), 94 - Ivry-sur-Seine (France)1987
AbstractAbstract
[en] The invention is concerned with a control process of the sealing of an assembly of elements, for instance between elements constituting the inner coating of a liquid vessel. Metallic pieces are positioned facing the liquid side of the assembly, such a welded line between two elements; they are welded on each side on the assembly. Some existing vessels can be modified in that way to make a control. All the closed spaces, this got following the invention, can be related between them so as to have an overall control
[fr]
L'invention concerne un procede de controle de l'etancheite d'un assemblage, par exemple entre des elements constituant le revetement interieur d'un recipient de liquide. Selon l'invention, on prevoit de rapporter cote liquide en regard de l'assemblage tel qu'une ligne de soudure entre deux elements tels que des toles, un profil metallique lui-meme fixe sur les elements par des soudures de part et d'autre de l'assemblage. On realise ainsi un espace ferme dans lequel peut etre introduit un fluide pour verifier l'etancheite des soudures. On peut ainsi avantageusement modifier des recipients existants pour pouvoir effectuer le controle selon l'invention. Dans une realisation particuliere, tous les espaces fermes au regard des assemblages d'une structure donnee peuvent etre relies entre eux pour pouvoir effectuer un controle global. Application au controle d'etancheite des revetements internes de piscines de centrales nucleairesOriginal Title
Procede de controle d'etancheite et application aux piscines de centrales nucleaires
Primary Subject
Source
20 Mar 1987; 19 Sep 1985; 10 p; FR PATENT DOCUMENT 2587486/A/; FR PATENT APPLICATION 8519933; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 19 Sep 1985
Record Type
Patent
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Reaktor-Institut Wuerenlingen (EIR)
Primary Subject
Record Type
Journal Article
Journal
Technica (Basel); v. 23(20); p. 1741-1744
Country of publication
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Puychevrier, Jean
CEA, 75 - Paris (France)1977
CEA, 75 - Paris (France)1977
AbstractAbstract
[en] The description is given of a pool reactor for performing experiments, comprising inside a water filled pool a core composed of a number of vertical fuel elements arranged in two orthogonal X and Y directions, an experimentation system filling a part of the upper face of the core and gear for handling the fuel elements. This invention particularly concerns a machine for loading and unloading fuel elements into and from the core of the reactor used for experiments under irradiation
[fr]
On decrit une pile piscine pour effectuer des experimentations comprenant a l'interieur d'une piscine remplie d'eau un coeur constitue par une pluralite d'elements combustibles verticaux disposes selon deux directions orthogonales X et Y, un ensemble d'experimentation occupant une partie de la face superieure du coeur et un dispositif de manutention des elements combustibles. La presente invention concerne plus particulierement une machine de chargement et de dechargement des elements combustibles du coeur de la pile piscine servant a des experimentations sous irradiationsOriginal Title
Pile piscine pour experimentations munie d'une machine de manutention
Primary Subject
Source
9 Sep 1977; 13 p; FR PATENT DOCUMENT 2402926/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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