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Calixte, Olivier; Garnier, Thomas
The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)2012
The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)2012
AbstractAbstract
[en] The APM 214 facility (Marcoule Pilot Workshop) owns blind cells which were used in various chemical processing operations. They are now at the end of their working lives and D and D operations have been planned. Due to the high level of radiation these operations must be partially carried out using remote-controlled equipment. The CEA has entrusted ONECTRA to define the best way to dismantle the blind cells with remote-controlled operations. The first step started with an inventory of the main physical characteristics, constraints, nature of remote operations to perform and imagining the machines necessary to complete the tasks at hand. A further step has seen the designing of these specialized machines. (authors)
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2012; 4 p; American Society of Mechanical Engineers - ASME; New York (United States); ICEM2011: 14. international conference on Environmental Remediation and Radioactive Waste Management; Reims (France); 25-29 Sep 2011; Country of input: France
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AbstractAbstract
[en] CEA is challenged by the dismantling of some of its nuclear installations because of their diversity (research reactors, accelerators, irradiators, hot cells, tanks,...) but also by the fact that some installations have been modified, more or less strongly, over their operating life and that these modifications have not been well documented. Furthermore dismantling activities can last a few decades for some installations and the issue of knowledge preserving appears. The dismantling of the Plutonium plant of Marcoule is presented as an example of these challenges. A digital mock-up of the plant has been made in order to reduce the number of real mock-ups to be built. Virtual reality has been used to define dismantling procedures and train workers. (A.C.)
Original Title
La simulation numerique au service du demantelement
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Journal Article
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AbstractAbstract
No abstract available
Original Title
Recherche du cout minimal lors de la definition d'une installation de filtration d'air a tres haute efficacite
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Source
Jarry, H. (ed.); Societe Francaise de Radioprotection, 92 - Montrouge (France); p. 401-418; 1974; Societe Francaise de Radioprotection; Montrouge, France; 7. International congress of the French Society for Radioprotection; Versailles, France; 28 May 1974
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Book
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Guay, P.; Roux, J.P.; Streiff, G.; Hancok, H.
CEA Etablissement de la Vallee du Rhone, 30 - Bagnols-sur-Ceze (France)1990
CEA Etablissement de la Vallee du Rhone, 30 - Bagnols-sur-Ceze (France)1990
AbstractAbstract
[en] The Marcoule Pilot Facility (APM) is used to test reprocessing methods and equipment under actual operating conditions with spent fuel at semi-industrial throughput rates and during demonstration runs of significant duration. In addition to the general objective of continuous long-term operation, the facility is also used for radioactive testing and qualification of specific process equipment items for planned or future reprocessing plants. This pilot function covers not only process operations but also other areas including remote manipulation. A remote manipulation system using an MA23 M electronic telemanipulator will be submitted to qualification testing in this way under actual operating conditions exposed to high irradiation levels together with numerous mechanical devices
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1990; 5 p; European Nuclear Conference '90; Lyon (France); 23-28 Sep 1990
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Report
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Conference
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AbstractAbstract
[en] This Order fixes the annual authorized limits and procedures for the transfer from Atalante to the Cogema establishment also at Marcoule of the low-level liquid effluents for treatment. It also specifies the measures for their control and surveillance. (NEA)
Original Title
Arrete du 24 juillet 1992 relatif a l'autorisation de rejet d'effluents radioactifs liquides par l'installation nucleaire de base, denommee Atalante, du centre d'etudes nucleaires de la vallee du Rhone sur le site nucleaire de Marcoule
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22 Aug 1992; 1 p; Published in the Journal Official de la Republique francaise.
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Miscellaneous
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Legislative Material
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AbstractAbstract
[en] This Order fixes the annual authorized limits and procedures for radioactive effluent releases from Atalante. It also specifies the measures for their control and surveillance. (NEA)
Original Title
Arrete du 24 juillet 1992 relatif a l'autorisation de rejet d'effluents radioactifs gazeux par l'installation nucleaire de base, denommee Atalante, du centre d'etudes nucleaires de la vallee du Rhone sur le site nucleaire de Marcoule
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29 Aug 1992; 1 p; Published in the Journal Officiel de la Republique francaise.
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Miscellaneous
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Legislative Material
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AbstractAbstract
[en] A drying colloidal gel has been developed to clean contaminated surfaces in order to reduce the volume of radioactive effluents. This gel makes the stage of surface rinsing useless, only an aspiration through a vacuum cleaner is necessary. This technique generates a few grams of solid effluents per square meter of decontaminated area and has been adapted to stainless steel surface. Further developments will concern the surface decontamination of porous materials and of the inside lining of complex duct systems through the use of gels and foams. (A.C.)
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Suface contaminees: rien ne sert de rincer, il faut aspirer a point
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Journal Article
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CEA Technologies (Gif-sur-Yvette); ISSN 1166-7648; ; (no.79); p. 4
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AbstractAbstract
No abstract available
Original Title
Pratique de la radioprotection sur le centre de Marcoule
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Conference on radioprotection; Marcoule, France; 21 Apr 1971
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Journal Article
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Conference
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Rayonnements Ionisants, Techniques de Mesures et de Protection; (no.3); p. 20-41
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AbstractAbstract
[en] The ATALANTE facility, located on the MARCOULE Research Centre, received the authorization for radioactive operations in december 1992. A significant part of the laboratories sheltered by this facility is dedicated to the R and D on the management of various types of high level activity wastes, resulting from the reprocessing of fuel elements. Better separation of long lived elements and re-use of separated elements, reduction in volumes and conditioning of wastes...Besides accordance with the latest safety design rules (RFS), the particular restraints fixed to the design team were the followings: (i) To take into account the operational feed back from existing laboratories. (ii) To allow adaptation to future, not yet known, R and D needs. (iii) To allow multiple and independent research works, without interference risks with regard to safety and operational restraints. (iv) To provide equipments allowing the treatment of all the wastes generated by the facility - in order to meet the requirements set by ANDRA for long term disposal, or by MARCOULE liquid effluent treatment station (STEL). The aim of this paper is to describe how these objectives have been achieved, from the conceptual point of view. (authors). 5 figs
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Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France); 464 p; 1993; p. 234-243; Societe Francaise d'Energie Nucleaire; Paris (France); SAFEWASTE 93: International Conference on Safe Management and Disposal of Nuclear Waste; Avignon (France); 13-18 Jun 1993
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Book
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AbstractAbstract
[en] Plutonium analysis on entry solutions and exit products are the basis of the mass balance in a reprocessing plant. In the Marcoule laboratory the entry mass is determined by plutonium concentration and solutions volume; the exit products are determined by plutonium content of the final products
[fr]
Les analyses de plutonium effectuees au Laboratoire sur les solutions d'entree et sur les produits de sortie, sont a la base du calcul de l'ecart de bilan sur les matieres nucleaires de base de l'Etablissement de Marcoule. Il y a lieu de distinguer: la determination de la masse d'entree ME qui necessite la mesure precise de la concentration du plutonium < Pu> contenu dans les cuves de dissolution, et qui, multipliee par le volume de solution de dissolution mis en jeu, permet de remonter a ME: ME = < Pu>. Volume, la determination de la masse de sortie MS obtenue a partir de l'analyse de la teneur en plutonium dans les produits finis, nitrate et oxyde de plutonium. C'est a partir de ces deux donnees qu'est etabli l'ecart de bilan E des matieres nucleaires de base d'une usine de retraitement. Il peut se mettre sous la forme: E = ME - (MS + Pertes) - (ECf-ECi) avec ECi = En Cours initial et ECf = En Cours final. Les mesures du Laboratoire interviennent donc sur ME et sur MSOriginal Title
Les analyses de bilan au laboratoire de Marcoule
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Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; 479 p; 1987; p. 971-973; Societe Francaise d'Energie Nucleaire; Paris (France); International Conference on nuclear fuel reprocessing and waste management; Paris (France); 23-27 Aug 1987
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Book
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Conference
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