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Starr, J.A.; Steinert, L.A.
General Electric Co., Schenectady, NY (USA)1981
General Electric Co., Schenectady, NY (USA)1981
AbstractAbstract
[en] The present invention treats, in a general way, the leaktightness devices used for passages between pools, and in particular, the fixed leaktight joints used for the contiguous pools of nuclear facilities. These pools are employed for the storage and maintenance of irradiated components. Components are immersed in water or other liquids in these pools so as to assure protection from radiation and the cooling of the components. These pools are often connected to one another by a series of passages, which may either be closed or which may allow the transfer of irradiated components under water
[fr]
La presente invention concerne, de maniere generale, des dispositifs d'etancheite pour passages entre piscines et, plus particulierement, des joints etanches amovibles pour utilisation entre piscines contigues dans une installation nucleaire. Ces piscines sont utilisees pour le stockage et l'entretien des composants irradies. Dans ces piscines, les composants sont immerges dans l'eau ou d'autres liquides assurant une protection contre les rayonnements et leur refroidissement. Ces piscines sont souvent reliees entre elles au moyen d'une serie de passages qui peuvent etre fermes ou qui peuvent permettre le transfert sous l'eau des composants irradiesOriginal Title
Dispositif d'etancheite pour passage entre piscines d'installations nucleaires
Primary Subject
Source
27 Feb 1981; 15 p; FR PATENT DOCUMENT 2463969/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 20 Aug 1979, US.
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Patent
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AbstractAbstract
[en] Irradiated nuclear fuel has been stored in water pools at essentially all nuclear reactors, beginning with the earliest plants in 1943. Fuel from water-cooled power reactors is clad either with Zircaloy or with stainless steel. Zircaloy-clad fuel has been stored US pools since 1959. Some experimental stainless-steel-clad fuel was stored for 12 yr in the US before reprocessing. Canadian Zircaloy-clad fuel has been stored since 1962. There has been no evidence that the fuel has degraded during pool storage, based principally on visual observations and radiation monitoring of pool air and water. However, several fuel rods have been subjected to metallographic examination after pool exposures up to 11 yr, also with no evidence that the fuel cladding has degraded in the pool. Canadian fuel stored up to 10 yr was returned to a reactor and performed well. Favorable storage experience also has been indicated for other countries with fuel residence times of 5 to 10 yr. The pool storage environment is high-purity water at 5.3 to 7.5 pH, except for pools for pressurized water reactors, which utilize boric acid pool chemistry at 4.5 to 6.0 pH. Pool water temperatures generally range between 20 and 500C. The favorable storage experience, demonstrated technology, successful handling of fuel with reactor-induced defects, benign storage environments, and corrosion-resistant materials offer sufficient bases to proceed with expanded storage capacities and extended fuel storage until questions regarding fuel reprocessing and final storage of nuclear wastes have been resolved. Some surveillance is justified to detect degradation if it becomes significat. Surveillance programs are already under way in several countries. 1 figure, 6 tables
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Nuclear Technology; ISSN 0029-5450;
; v. 43(2); p. 165-173

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Krieger, F.
Noell (G.) und Co., Wuerzburg (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
Noell (G.) und Co., Wuerzburg (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
AbstractAbstract
[en] It is proposed to fix the plates (made of sintered boron) used for radiation shielding for chambers which are used for storing spent nuclear fuel elements, with the help of a double sheet on the outside of the chambers. Areas which are to take the plates are divided by reinforcements running longitudinally and transversely. (UWI)
[de]
Es wird vorgeschlagen, die zur Strahlenabschirmung eingesetzten Platten (aus gesintertem Bor) fuer Kammern, die zur Aufbewahrung verbrauchter Kernbrennelemente dienen, mit Hilfe einer Doppelfolie auf den Kammeraussenwaenden zu befestigen. Durch laengs und quer laufende Sicken werden Felder abgeteilt, die die Platten aufnehmen sollen. (UWI)Original Title
Kammer zur Aufnahme eines gebrauchten Brennelements aus Kernkraftwerken
Primary Subject
Source
2 Mar 1978; 6 p; DE PATENT DOCUMENT 2638922/A/
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Patent
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AbstractAbstract
[en] The storage frame consists of a bottom plate and plates placed edgewise and parallel to one another on it. The plates are made corrugated so that long cut-outs for accommodating the fuel elements are formed. The corrugations from alternating shafts and seams, where to improve the stability, the plates are rigidly connected to each other at the seams. The plates themselves are made of high quality steel or boron steel. (DG)
[de]
Das Lagergestellt besteht aus einer Bodenplatte und darauf hochkant und parallel zueinander verlaufenden Platten. Die Platten sind wellenfoermig ausgebildet, so dass langgestreckte Ausnehmungen fuer die Aufnahme der BE entstehen. Die Wellungen bilden abwechselnd Schaechte und Nahtstellen, wobei zur Verbesserung der Stabilitaet die Platten an den Nahtstellen miteinander starr verbunden sind. Die Platten selbst sind aus Edelstahl oder Borstahl gefertigt. (DG)Original Title
Einrichtung zum Lagern von Kernreaktorbrennelementen
Primary Subject
Source
12 Apr 1984; 11 Nov 1982; 12 p; DE PATENT DOCUMENT 8231745/U1/; Available from Deutsches Patentamt, Muenchen (Germany, F.R.); ?: 11 Nov 1982
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Patent
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AbstractAbstract
[en] Whatever the alternative selected for the 'back end' of the nuclear fuel cycle, from reprocessing to final disposal in a geological repository, the electrical power utilities throughout the world have to solve the problem of interim fuel storage. The ideal storage facility, both for the reactor and for a centralized installation, must be 'safe' and as 'compact' as possible. Underwater storage is currently the most proven technology. It represents the most widely used solution on the industrial scale, and is of interest for its adaptability to high-density storage
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Journal Article
Journal
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AbstractAbstract
No abstract available
Original Title
Pembangunan Kolam Bahan Api Nuklear Terpakai
Primary Subject
Source
2019; 23 p; NTC 2019: Nuclear Technical Convention 2019; Bangi (Malaysia); 22-24 Oct 2019; Available in Malaysian Nuclear Agency Document Delivery Center; Oral presentation
Record Type
Miscellaneous
Literature Type
Conference
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Wade, E.E.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1977
Westinghouse Electric Corp., Pittsburgh, PA (USA)1977
AbstractAbstract
[en] This invention relates to sodium cooled fast breeder reactors. It particularly concerns facilities for the transfer of fuel assemblies between the reactor core and a fuel transfer area. The installation is simple in construction and enables a relatively small vessel to be used. In greater detail, the invention includes a vessel with a head, fuel assemblies housed in this vessel, and an inlet and outlet for the coolant covering these fuel assemblies. The reactor has a fuel transfer area in communication with this vessel and gear inside the vessel for the transfer of these fuel assemblies. These facilities are borne by the vessel head and serve to transfer the fuel assemblies from the vessel to the transfer area; whilst leaving the fuel assemblies completely immersed in a continuous mass of coolant. A passageway is provided between the vessel and this transfer area for the fuel assemblies. Facilities are provided for closing off this passageway so that the inside of the reactor vessel may be isolated as desired from this fuel transfer area whilst the reactor is operating
[fr]
La presente invention se rapporte aux reacteurs surregenerateurs refroidis au sodium. Elle vise, plus specialement, une installation assurant le transfert d'assemblages combustibles entre le coeur du reacteur et une zone de transfert de combustible. L'installation est de construction simple et permet d'utiliser une cuve relativement petite. De facon plus precise, l'invention comprend une cuve munie d'une tete, des assemblages combustibles loges dans cette cuve, une entree et une sortie pour un fluide de refroidissement entourant ces assemblages combustibles. Le reacteur presente une zone de transfert de combustible en communication avec cette cuve, et des moyens interieurs a la cuve pour le transfert des assemblages combustibles. Ces moyens sont portes par ladite tete de la cuve et servent a transporter les assemblages combustibles de la cuve jusqu'a la zone de transfert, en laissant les assemblages combustibles completement immerges dans une masse continue de fluide de refroidissement. Un passage pour les assemblages combustibles est prevu entre la cuve et cette zone de transfert. Des moyens d'isolement adaptes permettent de bloquer ledit passage de maniere que l'on puisse, a volonte, isoler de cette zone de transfert de combustible, l'interieur de la cuve du reacteur, en cours de marche du reacteurOriginal Title
Installation de transfert de combustible pour reacteurs nucleaires
Primary Subject
Source
18 Feb 1977; 14 p; FR PATENT DOCUMENT 2341920/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 23 Feb 1976, US.
Record Type
Patent
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King, F.D.
Proceedings of the NEA seminar on the storage of spent fuel elements. Madrid, 20-23 June 19781978
Proceedings of the NEA seminar on the storage of spent fuel elements. Madrid, 20-23 June 19781978
AbstractAbstract
[en] Bases were developed for the conceptual design of a water basin to store 5000 MT of irradiated light water reactor fuel. The basin, which could be operational by 1983, is designed to receive over 2000 MT per year of spent fuel and to provide interim storage of U.S. and some foreign fuel in support of U.S. policy of receiving and taking title to spent fuel rather than reprocessing this fuel. The bases for various design decisions are discussed
Primary Subject
Secondary Subject
Source
Anon; p. 211-219; ISBN 92-64-01840-9;
; 1978; p. 211-219; OECD; Paris, France; Seminar on the storage of spent fuel elements; Madrid, Spain; 20 - 23 Jun 1978

Record Type
Book
Literature Type
Conference
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Related RecordRelated Record
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Beam to support plane elements such as the inner metal sheets of a nuclear reactor deactivation pond
Aubert, F.
Electricite de France, 75 - Paris1986
Electricite de France, 75 - Paris1986
AbstractAbstract
[en] The present invention proposes a beam forming a plane bearing surface for the inner metal sheet of a pond while providing a channel allowing the introduction of a radiography apparatus after the beam has been incorporated in the concrete and, an efficiency drainage of leaking fluids from the welding joint between the sheets that this beam has to support
[fr]
La presente invention a pour but de fournir une poutre delimitant une surface d'appui plate pour les toles du revetement interieur d'une piscine tout en menageant un canal permettant l'introduction d'un appareil de radiographie apres que la poutre ait ete incorporee dans le beton et qui soit susceptible de permettre un drainage efficace des liquides de fuite provenant du cordon de soudure qui joint les toles que cette poutre est destinee a supporterOriginal Title
Poutre destinee a supporter des elements plans tels que notamment des toles de revetement interieur d'une piscine de desactivation d'une centrale nucleaire
Primary Subject
Source
25 Jul 1986; 21 Jan 1985; 17 p; FR PATENT DOCUMENT 2576344/A/; FR PATENT APPLICATION 8500792; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 21 Jan 1985
Record Type
Patent
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Schabert, H.P.; Weber, R.; Schwabe, I.
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
AbstractAbstract
[en] A stable fixing of a storage rack in a fuel element pond equipped with metal cladding can be achieved, according to the invention, by dividing the support into two parts. A peg is connected (e.g. by welding) to the metal cladding, above which a supporting bolt is inverted when the storage rack is inserted, whose edge is opened up to form a hood and which surrounds the peg with little play. It should be at a smaller distance from the metal cladding than the diameter of the peg. (UWI) 891 HP
[de]
Eine stabile Befestigung eines Lagergestells in einem mit metallischer Auskleidung versehenen Lagerbecken fuer Brennelemente laesst sich erfindungsgemaess dadurch erreichen, dass man die Abstuetzung zweiteilt. Mit der Metallauskleidung ist ein Zapfen verbunden, (z.B. verschweisst) ueber den beim Einsetzen des Lagergestells ein Stuetzbolzen gestuelpt wird, dessen Rand haubenartig erweitert ist und den Zapfen mit einem kleinen Spiel umfasst. Er soll dabei von der Metallauskleidung um weniger als den Durchmesser des Zapfens entfernt sein. (UWI)Original Title
Abstuetzung fuer ein Brennelement-Lagergestell
Primary Subject
Source
2 Mar 1978; 11 p; DE PATENT DOCUMENT 2637879/A/
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Patent
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