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Anuschewski, P.; Lahann, H.-J.; Mertins, H.
Symposium on the safety of nuclear ships. Hamburg, 5-9 Dec 19771978
Symposium on the safety of nuclear ships. Hamburg, 5-9 Dec 19771978
AbstractAbstract
[en] Calculations have been performed for the thermal and mechanical design of the fuel elements of FDR-2. This had to be done in accordance with the German licensing authorities opinion about the maximum center temperature in the fuel, maximum plastic deformation in the cladding and sufficient margin with respect to fatigue fracture. This means that a detailed life history of the most critical fuel rods had to be considered. The main design criterium for the fuel rods is the full power cycling feasibility of the ship reactor core which avoids restrictions on the manoeuvrability of the ship. Furthermore the thermomechanical behavior of some fuel rods during the restart of the reactor after partial reloading of the core was studied. The fuel modeling code SATURN-LG has been used, which calculates quasistationary the thermomechanical state of light water reactor fuel rods as a function of the operating conditions. For two fuel rods the values of the most important physical quantities dependent on the reactor operating history will be presented and discussed. Some remarks about the underlying models and the uncertainties in the fuel rod behavior prediction will be made
Primary Subject
Source
p. 565-577; 1978; p. 565-577; OECD; Paris, France; Symposium on the safety of nuclear ships; Hamburg, Germany, F.R; 5 - 9 Dec 1977
Record Type
Book
Literature Type
Conference
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AbstractAbstract
[en] The description is given of a honeycomb grille of the kind comprising rings defining respective apertures to take nuclear fuel rods. It includes several tubular rings grouped together inside a surrounding belt and devices for positioning the fuel rods in the apertures
[fr]
On decrit une grille cellulaire du type comportant des viroles pour definir des ouvertures respectives destinees a des barreaux de combustible nucleaire, comprenant plusieurs viroles tubulaires groupees a l'interieur d'une bande environnante et des organes destines a positionner les barreaux de combustible dans les ouverturesOriginal Title
Grille cellulaire de positionnement de cartouches de combustible nucleaire
Primary Subject
Source
11 Jan 1978; 9 p; FR PATENT DOCUMENT 2377685/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 12 Jan 1977, UK.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Donck, H.A.; Masetti, W.R.
United Nuclear Corp., Elmsford, N.Y. (USA)1974
United Nuclear Corp., Elmsford, N.Y. (USA)1974
AbstractAbstract
No abstract available
Original Title
i.e. for fuel rods
Primary Subject
Source
17 Dec 1974; 18 p; CA PATENT DOCUMENT 959583; Available from Commissioner of Patents, Ottawa; Filed 23 Jul 1971. Priority USA 24 Jul 1970 (58,094). 6 claims, 6 figs. Available from Commissioner of Patents, Ottawa.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Ballard, A.S.; Cooper, R.G.; Davis, D.E.
General Atomic Co., San Diego, Calif. (USA)1976
General Atomic Co., San Diego, Calif. (USA)1976
AbstractAbstract
[en] A method of manufacturing a nuclear rod is described. It comprises only partially filling a mold cavity with nuclear fuel particles, closing the mold cavity and reducing the volume thereof such that the fuel particles substantially fill the mold cavity, injecting a fluid solidifiable binder into the particle-filled mold cavity to fill the interstices between the fuel particles. The volume of particle-filled mold cavity is reduced by applying pressure to the contents thereof via a movable portion of mold cavity, and solidifying binder in cavity to form a fuel rod
[fr]
On decrit une methode de fabrication d'une barre de combustible nucleaire. Cela comporte le remplissage partiel de la cavite d'un moule avec des particules de combustible nucleaire, la fermeture de la cavite du moule, et la reduction de son volume de facon que les particules de combustible remplissent substantiellement cette cavite, puis l'injection dans celle-ci d'un liant fluide solidifiable pour combler les interstices entre les particules de combustible. Le volume de la cavite du moule rempli de particules est reduit en appliquant une pression au contenu par une partie mobile de la cavite du moule, puis par solidification du liant dans la cavite afin de former une barre de combOriginal Title
Fabrication de barres de combustible nucleaire
Primary Subject
Source
8 Jun 1976; 10 p; FR PATENT DOCUMENT 2314562/E/; Available from Institut National de la Propriete Industrielle, Paris (France); Addition to the French patent document 7433451; priority claim: 10 Jun 1975, US.
Record Type
Patent
Country of publication
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Foussard, J.F.J.A.
Transnucleaire, 75 - Paris (France)1983
Transnucleaire, 75 - Paris (France)1983
AbstractAbstract
[en] The present invention allows to compact objects of important length and small transversal dimensions to put them in a reliable, repetitive and quick way into a container so that the section of the container taken by the transversal sections of the said objects is maximal. It applies more particularly to fuel rods handling and compaction to put them in a container (final storage, intermediate storage, transport,...). A plurality of guide tubes are set along a general vertical direction. The upper parts are set in coincidence with the initial disposition of the fuel rod bundle. The lower parts are placed according to the wished arrangment. The dimensions of the guide tubes allow the fuel rod to slip down with the aid of the gravity. The fuel rods are placed above the guide tubes, then, each rod is introduced by its lower end in the upper part of a guide tube of all the fuel rods slip down
[fr]
La presente invention permet de compacter des objects de grande longueur et de faibles dimensions transversales en vue de les disposer de facon fiable, repetitive et rapide dans un conteneur de sorte que la section de ce dernier occupee par les sections transversale desdits objets soit maximale. Elle s'applique tout particulierement, a la manipulation eau compactage de crayons combustibles en vue de leur mise en conteneur (stockage definitif, stockage intermediaire, transport,...). On agence une pluralite de tubes de guidage selon une direction generale verticale. Les extremites superieures sont disposees en concordance avec la disposition initiale de l'ensemble des crayons combustibles. Les extremites inferieures sont disposees suivant la disposition desiree. les dimensions des tubes de guidage permettent aux crayons combustibles de glisser avec l'aide de la pesanteur. Les crayons combustibles sont amenes au-dessus des tubes de guidage, puis on introduit chaque crayon par son extremite inferieure dans l'extremite superieure d'un tube de guidage et l'ensemble des crayons glissent vers le basOriginal Title
Procede, installation et dispositif pour le compactage d'objets oblongs et flexibles notamment des crayons de reacteurs nucleaire
Primary Subject
Source
9 Dec 1983; 7 Jun 1982; 18 p; FR PATENT DOCUMENT 2528218/A/; FR PATENT APPLICATION 8209859; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 7 Jun 1982
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kaminski, D.J.; Boyd, C.H.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1978
Westinghouse Electric Corp., Pittsburgh, PA (USA)1978
AbstractAbstract
[en] This invention relates to a supporting rack for nuclear fuel rods. It particularly concerns facilities for laterally supporting a storage rack of nuclear fuel under water. This nuclear fuel rack is placed in a containment with virtually vertical walls. It includes a certain number of cells each of which is dimensionally designed to take one fuel rod and is so placed that one side is practically parallel with one of the walls in question and at a certain distance from it. It also includes a structure for counteracting seismic movements
[fr]
La presente invention se rapporte a un casier de support pour barreaux de combustible nucleaire. Elle vise plus precisement des moyens pour supporter lateralement un casier de stockage de carburant nucleaire sous l'eau. Ce casier a combustible nucleaire est dispose dans une enceinte ayant des parois pratiquement verticales. Il comprend un certain nombre de cellules dont chacune est dimensionnee pour recevoir un barreau de combustible, et il est place de facon a avoir un cote pratiquement parallele a l'une des parois, a une certaine distance de celle-ci. Il comporte, en outre, une structure d'enrayage des mouvements sismiquesOriginal Title
Casier de support pour barreaux de combustible nucleaire
Primary Subject
Source
16 Mar 1978; 9 p; FR PATENT DOCUMENT 2384326/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 18 Mar 1977, US.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Ockert, C.E.
USAEC, Washington, D.C.1973
USAEC, Washington, D.C.1973
AbstractAbstract
No abstract available
Original Title
Keramisk brenselbrikett for kjernereaktorer
Primary Subject
Source
14 Jun 1973; 8 p; NO PATENT DOCUMENT 126647; Priority claim 18 Nov 1966 USA nr. 595.541.
Record Type
Patent
Country of publication
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Wyatt, B.S.; Feraday, M.A.
Atomic Energy of Canada Ltd., Ottawa, Ontario1972
Atomic Energy of Canada Ltd., Ottawa, Ontario1972
AbstractAbstract
No abstract available
Primary Subject
Source
1 Aug 1972; 13 p; CA PATENT DOCUMENT 906693; Available from Commissioner of Patents, Ottawa; Filed 22 Jul 1970. 13 claims, 3 figures. Available from Commissioner of Patents, Ottawa.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Georges, N.J.; Pennell, W.E.
Westinghouse Electric Corp., East Pittsburgh, Pa. (USA)1977
Westinghouse Electric Corp., East Pittsburgh, Pa. (USA)1977
AbstractAbstract
[en] The invention pertains to an improved spacer for fuel pins in long, rod-shaped fuel element clusters of nuclear reactors. This is achieved by altering the shape of one of the support studs which hold the fuel pins in the openings of the spacer grid. This way, higher loads can be taken up even in case of very small distances between rods. (RW)
[de]
Die Erfindung bezieht sich auf eine Verbesserung der Abstandshalterung fuer Brennstaebe in langen stabfoermigen Brennelementbuendeln von Kernreaktoren. Es handelt sich um eine Abaenderung der Form eines der Stuetznoppen, die die Brennstaebe jeweils in der Oeffnung des Haltegitters festlegen. Dadurch lassen sich auch bei sehr geringen Stababstaenden groessere Belastungen auffangen. (RW)Original Title
Abstandshalterung fuer Brennstaebe von Kernreaktoren
Primary Subject
Source
24 Nov 1977; 6 p; DE PATENT DOCUMENT 1944932/B/; Also available from Dt. Patentamt, Muenchen (FRG)
Record Type
Patent
Country of publication
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INIS VolumeINIS Volume
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McCulloch, R.W.
Oak Ridge National Lab., TN (USA)1981
Oak Ridge National Lab., TN (USA)1981
AbstractAbstract
[en] Separate abstracts are included for each of the papers presented concerning fuel rod simulator operation and performance; simulator design and evaluation; clad heated fuel rod simulators and fuel rod simulators for cladding investigations; fuel rod simulator components and inspection; and simulator analytical modeling. Ten papers have previously been input to the Energy Data Base
Primary Subject
Source
May 1981; 691 p; International symposium on fuel rod simulators-development and application; Gatlinburg, TN, USA; 22 - 24 Oct 1980; Available from NTIS., PC A99/MF A01
Record Type
Report
Literature Type
Conference
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