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AbstractAbstract
[en] The construction of the Marcoule nuclear center in the Rhone Valley was a part of the industrial development of this region. A large hydraulic power plant and two facilities for metal electrochemical processing were already operating in this country. The nuclear center and the Cogema nuclear plants allowed 3800 employments. This good social impact added to many operation years without accident and a good communication policy with school and media make that there is no nuclear controversy in this area
[fr]
La decision de creer, pour la premiere fois en province, un centre atomique, se placait dans le contexte de la politique nationale d'amenagement du territoire , dont le but etait de compenser les desequilibres economique et demographique croissants par l'implantation d'industries. La construction de Marcoule s'est realisee a une periode ou, au plan national, l'idee que le progres economique et social resulterait necessairement du developpement des sciences et des techniques, etait une idee dominante disposant d'un tres grand consensus. Un bon accueil initial, d'une population essentiellement rurale et un sentiment favorable a Marcoule qui s'est maintenu et renforce, une creation realisee dans un contexte national et local favorable a l'industrie nucleaire au cas present, et une excellente acceptation du developpement de Marcoule qui s'est toujours manifeste comme un partenaire economique regional, une population de travailleurs exceptionnellement integree et fidelisee a la region et au nucleaire, une image de Marcoule tres specifique qui l'a quelque peu preserve des effets immediats du debat nucleaire, un capital de confiance acquis au long de nombreuses annees sans incident majeur et marquee par l'approfondissement, au quotidien et sur le terrain, de rapports de bons voisinages, tels sont les facteurs qui expliquent a ce jour la bonne acceptation du nucleaire dans la region d'implantation de MarcouleOriginal Title
Retraitement et opinion publique. Analyse de 30 ans de relations entre l'usine de Marcoule et son environnement
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Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; 391 p; 1987; p. 1121-1129; 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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AbstractAbstract
[en] This study has for object to bring to the fore the contributions and the limits of the impact evaluation of a nuclear facility functioning, when it is based on the measures realized in environment. The study has been made at the Cogema request and was applied to the nuclear site of Marcoule. The whole dose received by an inhabitant of Codolet is estimated to 900 micro sievert by year. The contribution of the functioning of the facility at the individual dose estimated is comprised between 5 and 23 micro sievert by year, depending on whether we take into account the measures inferior to the detection limits. (N.C.)
Original Title
Contribution methodologique a l'evaluation de l'impact dosimetrique du fonctionnement du site de Marcoule
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Societe Francaise de Radioprotection, 75 - Paris (France); 313 p; 1999; p. 186; 2. national congress of radiation protection; 2. congres national de radioprotection; Angers (France); 2-4 Jun 1999
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Miscellaneous
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Bourgogne, J.L.
Optimization of the workers radiation protection in the electro nuclear, industrial and medical fields1998
Optimization of the workers radiation protection in the electro nuclear, industrial and medical fields1998
AbstractAbstract
[en] In the case of Cogema/Marcoule, the constant decrease of radiation doses is attributed to three factors: technical with a surveillance system and doses optimization, relational with the promotion of confidence in teams of radiation protection services as an acceptation factor of radiation protection techniques and psychological with an evolution of minds towards the ALARA approach. (N.C.)
Original Title
Facteurs techniques et humains dans la reduction et l'optimisation des doses a Cogema/Marcoule
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Source
Societe Francaise de Radioprotection, 75 - Paris (France); 278 p; 1998; p. 72-76; Days of French Society of Radiation Protection(S.F.R.P.). Optimization of workers radiation protection in the electro nuclear, industrial and medical fields; Journees Societe Francaise de Radioprotection (S.F.R.P.). Optimisation de la radioprotection des travailleurs dans le domaines electronucleaire, industriel et medical; La Rochelle (France); 9-10 Jun 1998
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Miscellaneous
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AbstractAbstract
[en] At this culmination of 15 years devoted to the design, construction,starting of this new plant and to refined of the many technical, financial and commercial aspects of this major project, I would like to take this opportunity to make three observations: after two years of operations UP3 is performing well; UP 3 opens up new horizons in the field of spent fuel management and UP 3 brings reprocessing into the age of industrial maturity and provides confirmation to the worldwide nuclear power industry that there is an industrially proven solution for spent fuel management
Original Title
UP3 nouvelle installation de retraitement a La Hague
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Journal Article
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AbstractAbstract
[en] Occupational exposure in the French fuel reprocessing plants of La Hague and Marcoule cannot be studied without recalling the potential risks associated with reprocessing activities characterized by a large variety and evolutivity due to both the fuel and the nature of the mechanical and chemical processes or other up- or downstream activities. The results of occupational exposure in both plants and its evolution during the last twelve years are examined: annual mean doses for workers employed in four sensitive sectors and exposure of all the workers. The evolution of the results, favourable as a whole, is analysed. As a conclusion, the guiding principles gained from experience, which will allow to further reduce occupational exposure from reprocessing are stated
[fr]
L'exposition professionnelle dans les usines de retraitement francaises de La Hague et de Marcoule ne peut etre abordee sans rappeler les risques potentiels associes aux activites de retraitement caracterisees par une grande diversite et une evolutivite liees au combustible et a la nature des operations mecaniques et chimiques qui se deroulent au cours des diverses phases du procede, ou lors des diverses activites situees en amont ou en aval du procede. Les resultats concernant l'exposition professionnelle dans les deux usines et son evolution au cours des douze dernieres annees sont examines: doses moyennes annuelles des agents travaillant dans quatre secteurs sensibles et exposition de l'ensemble des travailleurs. L'evolution, dans l'ensemble favorable, de ces resultats est brievement analysee. En conclusion, sont evoques les principes directeurs qui se sont degages de l'experience et qui permettront de reduire encore, dans les futures usines, l'exposition professionnelle due au retraitementOriginal Title
Exposition professionnelle dans les usines de retraitement
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French - Italian meeting on occupational exposures: methodological aspects and practical experiences; Nice (France); 29-31 Jan 1986
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Journal Article
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Mimaud, Robert; Malet, Georges; Ollivier, Francis; Fabre, J.-C.; Valois, Philippe; Desgranges, Patrick; Anfossi, Gilbert; Gentizon, Michel; Serpollet, Roger.
Compagnie Generale de Matieres Nucleaires (COGEMA), 92 - Chatillon (France)1977
Compagnie Generale de Matieres Nucleaires (COGEMA), 92 - Chatillon (France)1977
AbstractAbstract
[en] The U.P.2 plant, built at La Hague Center is intended mainly for the reprocessing of spent fuels coming from (as metal) graphite-gas reactors and (as oxide) light-water, heavy-water and breeder reactors. In each of the five large nuclear units the digital processing of measurements was dealt with until 1974 by CAE 3030 data processors. During the period 1974-1975 a modern industrial computer system was set up. This system, equipped with T 2000/20 material from the Telemecanique company, consists of five measurement acquisition devices (for a total of 1500 lines processed) and two central processing units (CPU). The connection of these two PCU (Hardware and Software) enables an automatic connection of the system either on the first CPU or on the second one. The system covers, at present, data processing, threshold monitoring, alarm systems, display devices, periodical listing, and specific calculations concerning the process (balances etc), and at a later stage, an automatic control of certain units of the Process
[fr]
L'usine U.P.2, installee au Centre de La Hague a pour mission essentielle le retraitement des combustibles irradies provenant (sous forme metallique) de la filiere graphite-gaz, et (sous forme oxyde) des filieres eau ordinaire, eau lourde, surgenerateurs. Dans chacune des cinq grandes unites nucleaires, le traitement numerique des mesures etait assure jusqu'en 1974 par des processeurs CAE 3030. Dans la periode 1974-75, un systeme moderne d'Informatique Industrielle a ete mis en service. Ce systeme, dote de materiels T 2000/20 de la societe Telemecanique se compose de: cinq chaines de mesure (pour un total de 1500 voies traitees), et deux unites centrales. Le couplage Materiel et Logiciel de ces deux unites permet le passage en Automatique de l'une a l'autre. Le systeme assure, actuellement, le traitement des mesures, surveillances de seuils, alarmes, asservissements, sorties visualisation et journaux, les calculs specifiques relatifs au Procede (bilan, etc), et dans une deuxieme phase, la conduite automatique de certaines unites du ProcedeOriginal Title
Installation d'un systeme d'informatique sur le centre de La Hague
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Jan 1977; 54 p
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Report
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Devillers, C.; Dubois, G.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1987
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1987
AbstractAbstract
[en] In this document the authors show the main guiding lines on which is based the safety of the new reprocessing plant of La Hague. They are: - the objectives: to limit the impacts on workers and environment - the methods: safety analysis based on the checking and evaluation of significant risks. - the means: to make a safety plant by the use of quality assurance in the conception and in the plant construction
[fr]
L'extension du complexe industriel de La Hague, autorisee par decrets du 12 mai 1981, comprend: - la construction de l'usine UP3, en chantier depuis 1982, qui aura une capacite annuelle de 800 tonnes de combustible PWR, - l'extension de l'usine UP2 a une capacite annuelle de 800 tonnes de combustible PWR, - la construction d'une nouvelle station de traitement d'effluents liquides: STE 3. L'experience d'exploitation des usines UP1 (Marcoule) et UP2-400 (La Hague) a ete mise a profit pour definir les dispositions de surete a retenir dans les nouveaux ateliers en cours de construction. En parallele, les methodes d'analyse de surete se sont structurees et affinees. Le present document propose d'exposer les trois grandes lignes directrices sur lesquelles repose la surete des nouvelles installations de retraitement: - les buts: limiter l'impact sur le personnel et sur l'environnement tout en etant compatible avec les imperatifs de disponibilite, - les methodes: l'analyse de surete, fondee sur le recensement et l'evaluation des risques significatifs, - les moyens: la mise en place d'un systeme d'obtention de la qualite couvrant les activites de conception et de realisation permettant d'assurer une installation conforme aux exigences de sureteOriginal Title
La surete des nouvelles usines de retraitement de La Hague
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Sep 1987; 8 p; Conference on nuclear fuel reprocessing and waste management (RECOD 87); Paris (France); 23-28 Aug 1987
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AbstractAbstract
[en] The principles of the fission product vitrification process developed in France are exposed. The Marcoule vitrification facilities are described (glass vitrification and storage)
[fr]
On expose le principe du procede de vitrification des produits de fission mis au point en France et decrit les installations construites a Marcoule pour la mise en oeuvre de ce procede (atelier de vitrification et stockage des verres)Original Title
L'atelier de vitrification continue des produits de fission de Marcoule
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Journal Article
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Revue Generale Nucleaire; (no.4); p. 302-306
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AbstractAbstract
[en] The paper explains, through an example, the continuous improvement of the working methods and performance of the equipment. The facility selected is the high activity oxide facility of the La Hague reprocessing plant designed to handle 400 tons of spent fuels per year
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Source
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; 492 p; 1987; p. 171-184; 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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Leudet, A.; Hugelmann, D.; Fournier, W.; Dalverny, G.
CEA Centre d'Etudes de la Vallee du Rhone, 30 - Marcoule (France). Dept. des Procedes de Retraitement1991
CEA Centre d'Etudes de la Vallee du Rhone, 30 - Marcoule (France). Dept. des Procedes de Retraitement1991
AbstractAbstract
[en] The UP3 plant start up has been achieved in two successive steps. The first one, from November 89 to April 90, involved all the facilities but T1, the head-end facility. During that period, shearing, dissolution and the first cycle extraction operations were performed in UP2 plant. 100 tons of fuel have been reprocessed that way. The second step began in August 1990, with the T1 facility start-up and the reprocessing of the resulting active solutions in the rest of the plant. This second phase involving the entire UP3 plant continued until the end of January 1991. At that time, 160 tons of fuel have been completely treated in UP3 plant
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1991; 7 p; 3. International Conference on Nuclear Fuel Reprocessing and Waste Management; Sendai (Japan); 14-18 Apr 1991
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