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AbstractAbstract
No abstract available
Original Title
Procede d'enregistrement en code binaire et de lecture d'un numero d'identification sur une piece metallique et appareil correspondant
Primary Subject
Source
06 Aug 1971; 12 p; FR PATENT DOCUMENT 2148859/D/; Available from INPI, Paris; Available from Institut National de la Propriete Industrielle, Paris (France).
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A description is given of a nuclear fuel element for use in a nuclear reactor which is provided with a high strength sheath to limit the effects of forces acting internally and externally on the element when in service within a reactor
Original Title
Patent
Primary Subject
Source
23 Dec 1975; 4 p; US PATENT DOCUMENT 3,928,130
Record Type
Patent
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Aubry, Michel; Deletre, Gerard.
CEA, 75 - Paris (France)
CEA, 75 - Paris (France)
AbstractAbstract
No abstract available
Original Title
Dispositif d'etancheite pour element combustible
Primary Subject
Source
13 Apr 1970; 5 p; FR PATENT DOCUMENT 2,085,350; French patent appl. 70.13172.
Record Type
Patent
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 28 p. 328-329
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Rosenbaum, H.S.; Davies, J.H.
General Electric Co., Schenectady, NY (USA)
General Electric Co., Schenectady, NY (USA)
AbstractAbstract
[en] A process is described for manufacturing a composite elongated cladding tube for containing a nuclear fuel and forming a reactor fuel element. In a method recommended by the invention, the composite cladding tube includes a zirconium alloy tube and a shield-coat of metal zirconium metallurgically bonded to the internal surface of the tube. Among the zirconium alloys suitable for the tube are Zircaloy-2 or Zircaloy-4. Zircaloy-2 contains by weight around 1.5% tin, 0.12% iron, 0.09% chromium, 0.05% nickel, the balance being zirconium. Zircaloy-4 contains less nickel than Zircaloy-2 but slightly more iron. In either case, the alloy contains other ingredients than zirconium in a quantity above 5000 parts per million. The shield-coat which can represent around 1 to 30% of the composite cladding thickness, is made of metal zirconium, with a limited level of impurities from a highly pure or practically pure zirconium containing under 500 ppm impurities to an impurity level of up to 5000 ppm but preferably with an impurity level under around 4200 ppm
[fr]
On presente un procede de fabrication d'un tube de gainage composite de forme allongee destine a contenir du combustible nucleaire et a former un element combustible pour reacteur. Dans une realisation recommandee de l'invention le tube de gainage composite comporte un tube en un alliage de zirconium et une couche-ecran de zirconium metallique liee metallurgiquement a la surface interieure du tube. Parmi les alliages de zirconium convenant pour le tube, on peut citer le Zircaloy-2 ou le Zircaloy-4. Le Zircaloy-2 contient, sur une base ponderale, environ 1,5% d'etain, 0,12% de fer, 0,09% de chrome, 0,05% de nickel, le reste etant du zirconium. Le Zircaloy-4 contient moins de nickel que le Zircaloy-2, mais contient legerement plus de fer. Dans l'un ou l'autre cas, l'alliage contient des constituants autres que le zirconium, en une quantite superieure a 5000 parties par million. La couche-ecran, qui peut representer d'environ 1 a environ 30% de l'epaisseur de la gaine composite, est faite de zirconium metallique, de teneur en impuretes limitee allant d'un zirconium de purete elevee ou pratiquement pur renfermant moins de 500 ppm d'impuretes a une teneur en impuretes allant jusqu'a 5000 ppm mais de preference ayant une teneur en impuretes inferieure a environ 4200 ppmOriginal Title
Procede de fabrication de tube de gainage pour element de combustible nucleaire et tube ainsi obtenu
Primary Subject
Source
2 Jan 1981; 13 p; FR PATENT DOCUMENT 2458876/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 4 Jun 1979, US.
Record Type
Patent
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The corrosion speed of aluminium plaques by loss of weight with changing PH values anal temperatures in aqueous solutions is analyzed. The study is undertaken by simulating working conditions (pH anal temperature) to which the aluminium vains of the burnable components of the RP-10 reactor are submitted
Original Title
Corrosion de componentes de aluminio en el reactor RP-10
Primary Subject
Record Type
Journal Article
Journal
Informe Nuclear; v.2(1); p. 38-41
Country of publication
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In the operation of nuclear reactors employing sintered fuel tablets sheathed in zirconium alloy sheaths it has been found that, during irradiation, cadmium is released from the fuel and migrates outwardly to the inner surface of the sheath, where it can create an embrittlement phenomenon, resulting in sheath failure due to stress corrosion cracking. In accordance with the present disclosure copper is provided as a barrier or partial barrier between the fuel and the sheath inner surface, to facilitate the formation of a stable copper-cadmium alloy during the irradiation life of the fuel, to thereby impede the formation of a concentration of cadmium or active compounds thereof on the sheath inner surface. (auth)
Primary Subject
Source
17 Jun 1980; 5 p; CA PATENT DOCUMENT 1079873/A/; Available from Micromedia Ltd., 165 Hotel de Ville, Hull, Quebec, Canada J8X 3X2
Record Type
Patent
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Gaertner, M.; Kaspar, G.; Senski, G.; Reymann, A.; Wilhelm, H.
Structural mechanics in reactor technology. Transactions. Vol. C
Structural mechanics in reactor technology. Transactions. Vol. C
AbstractAbstract
[en] An irradiation program has been started in the test reactor FRG-2 to study the in-pile creep behaviour of zirconium alloy cladding tubes. In test capsules, specimens of 10.75 mm OD and 200 mm length are irradiated at temperatures from 300 to 4000C, at a fast flux (E > 1 MeV) of approx. 3 x 1013cm-2s-1 and at tensile and compressive hoop stresses from 70 to 120 N/mm2. Irradiation periods up to 3,000 and 6,000 h are planned. The cladding tube temperatures are controlled by a forced helium flow in a closed capsule circuit and are nearly constant in time with a very small local gradient. The diametrical creep deformation is determined by measuring the diameter of the tube specimens in Hot Cells at regular intervals. This paper presents the results of short-time (approx. 600 h) precursor experiments at temperatures of approx. 4000C and cladding hoop stresses of 100 and 120 N/mm2. The specimen material was Zircaloy-4 and ZrNb3Sn1. (orig.)
Primary Subject
Secondary 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. C3/5 (1-8); ISBN 0444 85359 6; 
; 1979; p. C3/5 (1-8); 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--79-321-090
; 1979; p. C3/5 (1-8); 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--79-321-090
Record Type
Book
Literature Type
Conference
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Jabsen, F.S.
Babcock and Wilcox Co., New York (USA)
Babcock and Wilcox Co., New York (USA)
AbstractAbstract
[en] An invention is described whereby end fittings are formed from lattices of mutually perpendicular plates. At the plate intersections, sockets are secured to the end fittings in a manner that permits the longitudinal axes of each of the sockets to align with the respective lines of intersection of the plates. The sockets all protrude above one of the surfaces of the end fitting. Further, a detent is formed in the proturding sides of each of the sockets. Annular grooves are formed in each of the ends of the fuel rods that are to be mounted between the end fittings. The socket detents protrude into the respective annular grooves, thus engaging the grooves and retaining the fuel rods and end fittings in one integral structure. (auth)
Primary Subject
Source
13 May 1980; 10 p; CA PATENT DOCUMENT 1077626/A/; Available from Micromedia Ltd., 165 Hotel de Ville, Hull, Quebec, Canada J8X 3X2
Record Type
Patent
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Boyko, E.S.; Campbell, Joseph; Wiggins, R.J.
Westinghouse Electric Corp., Pittsburgh, Pa. (USA)
Westinghouse Electric Corp., Pittsburgh, Pa. (USA)
AbstractAbstract
No abstract available
Original Title
specifically, sealing end plugs
Primary Subject
Source
3 Dec 1974; 14 p; CA PATENT DOCUMENT 958821; Available from Commissioner of Patents, Ottawa; Filed 19 Oct 1971. Priority USA 8 Dec 1970 (96,153). 8 claims, 5 figs. Available from Commissioner of Patents, Ottawa.
Record Type
Patent
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
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