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Silberstein, A.
Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)1982
Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)1982
AbstractAbstract
[en] FRAGEMA has developed most types of inspection equipments to work on irradiated fuel assemblies and on single fuel rods during reactor outages with an efficiency compatible with the utilities operating priorities. In order to illustrate this statement, two specific examples of inspection equipments are shortly described: the on-site removable fuel rod assembly examination stand, and the fuel assembly multiple examination device. FRAGEMA has developed techniques for the identifiction of the leaking fuel rods in the fuel assembly and the tooling necessary to perform the replacement of the faulted element. These examples of methods, techniques and equipments described and the experience accumulated through their use allow FRAGEMA to qualify for offering the supply of the corresponding software, hardware or both whenever an accurate understanding of the fuel behaviour is necessary and whenever direct intervention on the assembly and associated components is necessary due to safety, operating or economical reasons
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Sep 1982; 8 p; 8. Annual meeting of the Spanish Nuclear Society; Santander (Spain); 20-22 Sep 1982
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Report
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Conference
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Campbell, J.W.; Todd, J.L.
Sandia Labs., Albuquerque, N.Mex. (USA)1975
Sandia Labs., Albuquerque, N.Mex. (USA)1975
AbstractAbstract
[en] The design of a prototype safeguards instrument for determining the number of irradiated fuel assemblies leaving an on-power refueled reactor is described. Design details include radiation detection techniques, data processing and display, unattended operation capabilities and data security methods. Development and operating history of the bundle counter is reported. (U.S.)
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1975; 8 p; American Nuclear Society meeting; New Orleans, Louisiana, USA; 8 Jun 1975; CONF-750607--21
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Blomeke, J.O.; Nichols, J.P.; Salmon, R.
Oak Ridge National Lab., Tenn. (USA)1974
Oak Ridge National Lab., Tenn. (USA)1974
AbstractAbstract
No abstract available
Primary Subject
Source
1974; 23 p; 4. international symposium on packaging and transportation of radioactive materials; Miami Beach, Florida, USA; 22 Sep 1974
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Report
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Akbari, F.; Welland, M.J.; Lewis, B.J.; Thompson, W.T.
Ninth international conference on CANDU fuel, 'fuelling a clean future'2005
Ninth international conference on CANDU fuel, 'fuelling a clean future'2005
AbstractAbstract
[en] It is well known that the oxidation of a defected fuel element by steam gives rise to an increase in O/U ratio with a consequent lowering of the incipient melting temperature. Concurrently, the hyperstoichiometry reduces the thermal conductivity thereby raising the centerline fuel pellet temperature for a fixed linear power. The development of fission products soluble in the UO2 phase or, more important, the deliberate introduction of additive oxides in advanced CANDU fuel bundle designs further affects and generally lowers the incipient melting temperature. For these reasons, the modeling of the molten (hyperstoichiometric) UO2 phase containing several solute oxides (ZrO2, Ln2O3 and AnO2) is advancing in the expectation of developing a moving boundary heat and mass transfer model aimed at better defining the limits of safe operating practice as burnup advances. The paper describes how the molten phase stability model is constructed. The redistribution of components across the solid-liquid interface that attends the onset of melting of a non-stoichiometric UO2 containing several solutes will be discussed. The issues of how to introduce boundary conditions into heat transfer calculations consistent with the requirements of the Phase Rule will be addressed. The Stefan problem of a moving boundary associated with the solid/liquid interface sets this treatment apart from conventional heat and mass transfer problems. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); 152 Megabytes; ISBN 0-919784-84-4;
; 2005; [14 p.]; 9. International conference on CANDU fuel, 'fuelling a clean future'. Proceedings; Belleville, Ontario (Canada); 18-21 Sep 2005; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); Paper A3004; 24 refs., 10 figs.

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Miscellaneous
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Schaaf, W.
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)1987
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)1987
AbstractAbstract
[en] The loading pond for loading and unloading a transport container for the fuel element of a PWR has a separate area. In this area, the decontamination of the surface of the transport container by means of jets and flushing liquid can be carried out. The part basin equipped for cooling and decontamination is devided by means of a flexible wall made of plastic plates and a boron insert between the transport container lid and a surrounding edge in the loading basin. (DG)
[de]
Das Ladebecken zum Be- und Entladen eines Transportbehaelters fuer die BE eines DWR besitzt einen abgetrennten Bereich. In diesem Bereich lassen sich Dekontaminationen der Oberflaeche des Transportbehaelters mittels Spritzduesen und Spuelfluessigkeit durchfuehren. Das zur Kuehlung und Dekontaminierung aufgeruestete Teilbecken ist mittels einer flexiblen Wand aus Kunststoffplatten und Bormaterialeinlage zwischen dem Tranportbehaelterdeckel und einem umlaufenden Rand im Ladebecken abgeteilt. (DG)Original Title
Wassergefuelltes Ladebecken einer kerntechnischen Anlage
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Secondary Subject
Source
7 May 1987; 23 Aug 1977; 4 p; DE PATENT DOCUMENT 2737990/C2/; ?: 23 Aug 1977
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Patent
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AbstractAbstract
[en] The service range covers technical and shipment implications in the transport of fresh and spent fuel elements. The paper discusses the transport volume, the number of transports required and the transport cost resulting for the NPPs. (DG)
[de]
Die Dienstleistungs-Palette umfasst die Darstellung der technischen und speditionellen Schwergewichte beim Transport frischer und bestrahlter BE. Sie wird um Hinweise auf das Transportvolumen, die Zahl der erforderlichen Transporte und die dabei den KKW entstehenden Transportkosten ergaenzt. (DG)Original Title
Der Transport frischer und abgebrannter Brennelemente
Primary Subject
Source
Bauer, K.G. (comp.); Deutsches Atomforum e.V., Bonn (Germany, F.R.); 416 p; ISBN 3-922798-27-6;
; Dec 1986; p. 224-237; Trade conference and exhibition of Deutsches Atomforum e.V.: High serve - services for nuclear engineering; Fachtagung und Ausstellung des Deutschen Atomforums e.V.: High Serve - Service fuer die Kerntechnik; Bonn (Germany, F.R.); 22-23 Oct 1986; Available from Deutsches Atomforum e.V., Bonn (Germany, F.R.)

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AbstractAbstract
[en] A core for a nuclear reactor of high specific power output is provided with an arrangement of fuel bundles in which at least some bundles incorporate tubular pencil elements mounted between end plates, having coolant flow restricting means secured to the bundle to control the balance of coolant flow between external flow along the outsides of the pencils and internal coolant flow within the hollow pencils. 4 claims, 6 drawing figures
Original Title
Patent
Primary Subject
Source
2 Mar 1976; 4 p; US PATENT DOCUMENT 3,941,654
Record Type
Patent
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Barbalat, R.; Bayon, G.; Laporte, A.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1983
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1983
AbstractAbstract
[en] The neutron radiography installations of Saclay using collimated neutron sources from reactors for non-destructive testing of nuclear fuels and components of the nuclear industry are described. The first installation in a pool for experimental devices before, during and after irradiation near the core allowing imaging of highly radioactive materials. The second, a dry installation, is used for monitoring active fuel elements. The last is used for inactive materials coming from industry
[fr]
Pour repondre aux besoins d'examens non destructifs de combustibles et de composants exprimes par l'industrie nucleaire, les Services des Piles de Saclay se sont equipes de 3 installations de neutronographie dont les caracteristiques de conception et d'utilisation sont decrites. Une installation immergee en piscine pour le controle des dispositifs experimentaux avant, pendant et apres irradiation aupres du coeur permet la prise de cliches de pieces fortement radioactives. La seconde installation a sec est utilisee pour le controle de combustible actifs a l'aide de films en nitrate de cellulose. La troisieme installation effectue les controles sur materiel inactif en provenance de l'industrieOriginal Title
La neutronographie appliquee aux controles non destructifs d'elements combustibles avant et apres irradiation
Primary Subject
Source
Dec 1983; 5 p; 6. International conference on non-destructive evaluation in the nuclear industry; Zurich (Switzerland); 27 Nov - 2 Dec 1983
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AbstractAbstract
[en] It is stated that one type of fuel element assembly used in a sdoium cooled fast reactor comprises a hexagonal bundle of slender fuel elements enclosed by a casing, termed a 'wrapper'. The fuel elements are each helically wrapped with wire to brace them apart and prevent bowing and vibration and to ensure efficient cooling. The width of the gap between the fuel bundles and the 'wrapper' is mainly governed by the height of the wire wraps of the outer fuel elements, and the edge channels resulting from the wire wraps of the same size tend to cause overcoolinf of the outer elements. Allowance may be necessary for differential growth under irradiation. The transverse growth of the fuel bundle is greater than between the ends of the bundle and is greater than the 'wrapper'. The resuling bundle to 'wrapper' gap which must be allowed involves a coolant flow path that is much less restrictive than that over the inner elements of the bundle, so that the outer elements are greatly overcooled and the mean outlet temperature of coolant from the assembly is reduced. Furthermore the fuel elements can vibrate in the clearance and suffer damage. An expedient that has been adopted to reduce overcooling of the outer elements is to insert a 'filler' in the form of a ribbed plate within the gap, thereby reducing the cross-sectional area of the coolant flow path. In the arrangement described at least one collapsible filler is located within the gap, the filler being longitudinally convoluted to follow the transverse contour of the bundle. This substantially eliminates vibration of the bundle and restricts the cross-sectional area of the gap. The filler can collapse during irradiation to accommodate differential irradiation growth of bundle and 'wrapper'. A preferred construction of collapsible filler comprises two spaced membranes forming a longitudinally convoluted envelope, one membrane being slit and deformed to provide leaf springs that react on the wrapper. (U.K.)
Primary Subject
Source
30 Jul 1975; 3 p; GB PATENT DOCUMENT 1401308/B/
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Patent
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AbstractAbstract
No abstract available
Primary Subject
Source
ANS annual meeting; Atlanta, GA, USA; 3 - 8 Jun 1979; CONF-790602--(SUMM.); Published in summary form only.
Record Type
Journal Article
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Conference
Journal
Transactions of the American Nuclear Society; ISSN 0003-018X;
; v. 32 p. 600-601

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