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AbstractAbstract
[en] To assist the loading of nuclear reactor fuel elements in a reactor core, positioning blocks with a pyramidal upper face charged to guide the fuel element leg are placed on the lower core plate. A carrier equipped with means of controlled displacement permits movement of the blocks over the lower core plate
[fr]
Pour faciliter le chargement des elements combustibles dans un reacteur nucleaire, on place sur la plaque inferieure du coeur des paves positionneurs dont la face superieure pyramidale assure un guidage du pied de l'element lors de sa descente. Le positionnement des paves est assure par un porteur qui se deplace sur la plaque inferieure du coeur, en transportant les pavesOriginal Title
Outil d'aide au chargement d'elements combustibles d'un reacteur nucleaire
Primary Subject
Source
12 Apr 1991; 11 Oct 1989; 29 p; FR PATENT DOCUMENT 2652942/A/; FR PATENT APPLICATION 8913282; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 11 Oct 1989
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Lopez Perez, B.
Junta de Energia Nuclear, Madrid (Spain)1981
Junta de Energia Nuclear, Madrid (Spain)1981
AbstractAbstract
[en] An overview on the radioactive waste management generated in the nuclear fuel cycle, with regard to the state of the available technology is given. The quantity of the different wastes that will be produced is estimated and the conditioning methods applicable to each type of waste are described, taking into account the main properties of the solid matrixes. Next step of the solidified waste management is the disposal in order to obtain its isolation from the biosphere. That can be achived applying different concepts, from which some trends are described, with special emphasis in burial in geological formations. The barriers strategy to avoid releases of radioactive isotopes to the biosphere is explain. Some not technological aspects which may have influence on the waste management are commented. (author)
Original Title
Los residuos radiactivos
Primary Subject
Record Type
Journal Article
Journal
Energia Nuclear (Madrid); ISSN 0013-7324; 
; v. 25(132); p. 297-311
; v. 25(132); p. 297-311
Country of publication
HIGH-LEVEL RADIOACTIVE WASTES, INTERMEDIATE-LEVEL RADIOACTIVE, LOW-LEVEL RADIOACTIVE WASTES, MARINE DISPOSAL, RADIOACTIVE EFFLUENTS, RADIOACTIVE WASTE DISPOSAL, RADIOACTIVE WASTE FACILITIES, RADIOACTIVE WASTE PROCESSING, RADIOACTIVE WASTE STORAGE, SALT DEPOSITS, UNDERGROUND DISPOSAL, UNDERGROUND STORAGE
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Lopez Perez, B.
Junta de Energia Nuclear, Madrid (Spain)
Glasses and glass-ceramics for nuclear waste management1987
Junta de Energia Nuclear, Madrid (Spain)
Glasses and glass-ceramics for nuclear waste management1987
AbstractAbstract
[en] The transformations involved in the nuclear fuels during the burn-up at the power nuclear reactors for burn-up levels of 33.000 MWd/th are considered. Graphs and data on the radioactivity variation with the cooling time and heat power of the irradiated fuel are presented. Likewise, the cycle of the fuel in light water reactors is presented and the alternatives for the nuclear waste management are discussed. A brief description of the management of the spent fuel as a high level nuclear waste is shown, explaining the reprocessing and giving data about the fission products and their radioactivities, which must be considered on the vitrification processes. On the final storage of the nuclear waste into depth geological burials, both alternatives are coincident. The countries supporting the reprocessing are indicated and the Spanish programm defined in the Plan Energetico Nacional (PEN) is shortly reviewed. (author) 8 figs., 4 tabs
Primary Subject
Source
Rincon Lopez, J.M. (ed.); Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Madrid (Spain); Instituto de Ceramica y Vidrio, Madrid (Spain); 212 p; 1987; p. 1-18; Seminar on the use of glasses and glass-ceramics for nuclear waste management; Madrid (Spain); 21-22 May 1985
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, INFORMATION, ISOTOPES, LEVELS, MANAGEMENT, MATERIALS, NUCLEAR FUELS, POWER REACTORS, RADIOACTIVE MATERIALS, RADIOACTIVE WASTES, REACTOR MATERIALS, REACTORS, STORAGE, THERMAL REACTORS, WASTE MANAGEMENT, WASTE PROCESSING, WASTE STORAGE, WASTES, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A general reference is given of the work carried out by the Working Group 6 of INFCE, that was created for the study of the Spent Fuel Management, as these spent fuels still contain fissionable material and sources of it. The objectives were: To review current experience for storage and transport of spent fuel. To investigate alternative storage approaches. To evaluate present and future spent fuel management requirements
Primary Subject
Source
Anon; p. vp; 1980; p. vp; Atomic Industrial Forum, Inc; Bethesda, MD; Fuel cycle conference; New Orleans, LA, USA; 15 - 18 Apr 1980
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Perez, B.; Batisse, J.P.
Electricite de France (EDF), 75 - Paris (France)1994
Electricite de France (EDF), 75 - Paris (France)1994
AbstractAbstract
[en] The lighting device is retractable under the action of appliances working in the swimming pool or thanks to various impacts. Each arm is assembled pivoting around a vertical axis. Return means as spring allow to bring back in a balanced angular position the arm carrying a headlight in a determined angular position after the arm and the headlight having been spread from this position in an intentional or fortuitous way. Application to lighting devices for nuclear reactor swimming pools. (Author). 4 figs., 3 refs
Original Title
Dispositif d'eclairage orientable et escamotable pour une piscine contenant des matieres radioactives
Primary Subject
Secondary Subject
Source
30 Dec 1994; 23 Jun 1993; 12 p; FR PATENT DOCUMENT 2706983/A/; FR PATENT APPLICATION 9307622; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 23 Jun 1993
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Schlewitz, Y.; Perez, B.
Electricite de France, 75 - Paris (France)1988
Electricite de France, 75 - Paris (France)1988
AbstractAbstract
[en] This tool for loading fuel assemblies in a PWR has a guide with an outlet centred on the core plate and an inlet offset from it. This tool puts the deformed fuel assembly in coincidence with the centering pins of the core support plate
[fr]
Outil d'aide au chargement des assemblages combustibles d'un reacteur nucleaire a eau. Le reacteur comporte une structure rigide sur laquelle des assemblages combustibles sont disposes cote a cote pour former le coeur du reacteur. La structure comporte des pions de centrage destines a cooperer avec des trous correspondants formes dans une piece d'extremite inferieure et des assemblages, ces pions de centrage etant repartis selon un reseau regulier afin d'assigner une position relative precise des assemblages les uns par rapport aux autres. L'outil comporte des moyens de guidage comportant une entree decalee selon au moins une direction XX, YY du reseau des assemblages et une sortie centree par rapport a cette direction XX, YY, de maniere qu'un assemblage a mettre en place, dont l'extremite inferieure se presente decalee par rapport a sa position theorique a l'entree des moyens de guidage soit amenee par ces moyens de guidage en coincidence avec les pions de centrage de la plaque de support de coeur a la sortie de ces moyens de guidageOriginal Title
Outil d'aide au chargement des assemblages combustibles d'un reacteur nucleaire a eau pressurisee 1300 MW
Primary Subject
Source
21 Oct 1988; 15 Apr 1987; 28 p; FR PATENT DOCUMENT 2614128/A/; FR PATENT APPLICATION 8705381; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 15 Apr 1987
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Lopez Perez, B.; Martinez Martinez, A.
Junta de Energia Nuclear, Madrid (Spain)
Junta de Energia Nuclear, Madrid (Spain)
AbstractAbstract
[en] The results of operating a pilot plant for the treatment of liquid radioactive waste originating from the MTR fuel reprocessing facility constructed at the Juan Vigon National Nuclear Research Center (CNEN) in Madrid are reported. The pilot plant is being adapted in order to provide general services for the Center. A description of the storage of solid radioactive waste at Sierra Albarrana (Cordoba) is included
Primary Subject
Source
nd; 17 p; IAEA symposium on the management of radioactive waste; Vienna, Austria; 22 - 26 Mar 1976; Translation of SM--207/90 CONF-760310--21.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Camacho-Perez, B.; Poggi-Varaldo, H. M.
The Third International Meeting on Environmental Biotechnology and Engineering. 21-25 September 2008. Palma de Mallorca. Spain2009
The Third International Meeting on Environmental Biotechnology and Engineering. 21-25 September 2008. Palma de Mallorca. Spain2009
AbstractAbstract
[en] Lindane of γ-hexachloro-cyclohexane (γHCH) is a chlorinated insecticide widely used in developing countries, particularly in Mexico, in spite of its banning in first world countries. negative impacts of lindane on the environment and human health have been reported worldwide. (Author)
Primary Subject
Source
350 p; ISBN 978-84-692-4948-2; ; 2009; p. 290; Graficas Terrasa; Islas Baleares (Spain); 3. International Meeting on Environmental Biotechnology and Engineering; Palma de Mallorca (Spain); 21-25 Sep 2008
; 2009; p. 290; Graficas Terrasa; Islas Baleares (Spain); 3. International Meeting on Environmental Biotechnology and Engineering; Palma de Mallorca (Spain); 21-25 Sep 2008
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Record Type
Journal Article
Journal
Science; v. 175(4029); p. 1481-1483
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In AC regime, the peak current, Ip, in a superconducting tape can surpass the critical current, Ic, so that the circuit is superconducting only part of the time and normal the rest. Up to the limit Ip=Ic, the losses in the tape are the typical AC superconducting losses. But for Ip>Ic part of the losses are from the Joule heat in the normal tape resistance. Analysis of the plot of loss per cycle against peak current gives Ic as the point of change of the trend
Source
International cryogenic materials conference: Topical conference on the voltage-current relation in technical superconductors; Enschede (Netherlands); 25-28 May 2003; S0921453403015120; Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Literature Type
Conference
Journal
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