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Sample records for du reacteur nucleaire

  1. Nuclear reactor (1960); Reacteurs nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Maillard, M.L. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Leo, M.B. [Electricite de France (EDF), 75 - Paris (France)

    1960-07-01

    The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author) [French] Les premiers reacteurs industriels plutonigenes francais G1 - G2 - G3 du Centre de Marcoule comportent une installation de recuperation d'energie. La production d'electricite de G1 ne compense pas l'energie depensee par ailleurs pour le fonctionnement de l'ensemble, par contre, G2 et G3 doivent fournir chacun une puissance de 25 a 30 MW au reseau national d'Electricite de France. Cette puissance est modeste, mais l'experience acquise grace a ces reacteurs est tres grande et c'est grace a elle qu'il nous sera possible de mettre en exploitation les reacteurs energetiques EDF1 - EDF2 - EDF3. Le memoire decrit comment, avant tout demarrage du reacteur, les essais effectues, en particulier ceux concernant l'installation de recuperation d'energie et le caisson, ont permis d'abreger la phase de montee en puissance. (auteur)

  2. Improvement of Sodium Neutronic Nuclear Data for the Computation of Generation IV Reactors; Contribution a l'amelioration des donnees nucleaires neutroniques du sodium pour le calcul des reacteurs de generation IV

    Energy Technology Data Exchange (ETDEWEB)

    Archier, P.

    2011-09-14

    de ces incertitudes provient des donnees nucleaires et, dans le cas des RNR-Na, des donnees nucleaires du sodium, qui presentent des differences significatives entre les bibliotheques internationales (JEFF-3.1.1, ENDF/B-VII.0, JENDL-4.0). L'objectif de cette these est d'ameliorer la connaissance sur les donnees nucleaires du sodium afin de mieux calculer les parametres neutroniques des RNR-Na et fournir des incertitudes fiables. Apres un etat des lieux des presentes donnees du {sup 23}Na, l'impact des differences est quantifie notamment sur les effets en reactivite de vidange du sodium, calcules avec des outils neutroniques deterministe et stochastique. Les resultats montrent qu'il est necessaire de reevaluer entierement les donnees nucleaires du sodium. Plusieurs developpements ont ete effectues dans le code d'evaluation Conrad, pour integrer de nouveaux modeles de reactions nucleaires et leurs parametres ainsi que pour permettre de proceder a des ajustements avec des mesures integrales. Suite a ces developpements, l'analyse des donnees differentielles et la propagation des incertitudes experimentales avec Conrad ont ete realisees. Le domaine des resonances resolues a ete etendu a 2 MeV et le domaine du continuum debute directement au-dela de cette energie. Une nouvelle evaluation du {sup 23}Na et les matrices de covariances multigroupes associees ont ete generees pour de futurs calculs d'incertitudes. La derniere partie de la these se focalise sur le retour des experiences integrales de vidange du sodium, par des methodes d'assimilation de donnees integrales, afin de reduire les incertitudes sur les sections efficaces du sodium. Ce document se clot sur des calculs d'incertitudes pour des RNR-Na de type industriel, qui montrent une meilleure prediction de leurs parametres neutroniques avec la nouvelle evaluation

  3. The Pegase reactor loops; Les boucles du reacteur Pegase

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    NONE

    1968-07-01

    After 4 years operation, experimentation and maintenance of the gas loops built especially for the nuclear fuel testing reactor Pegase, it appears desirable not only to gather together in a single document the essential characteristics and particularities of these devices and of their associated equipment, but also to give the reasons for the technical modifications and the way in which they were carried out; this is done here by the persons themselves who were responsible, day after day, for operating these loops. This essentially practically experience thus complements the careful research and preliminary testing carried out on these loops or on their prototypes. It should be of interest to those who deal with problems concerned with the design or operation of irradiation loops in experimental reactors or of similar equipment. (authors) [French] Apres 4 annees de fonctionnement, d'experimentation et d'entretien sur les boucles a gaz, construites specialement pour le reacteur d'essai des combustibles nucleaires Pegase, il a paru souhaitable non seulement de rassembler dans un meme document les caracteristiques et les particularites essentielles de ces dispositifs et des appareillages qui leur sont associes, mais aussi d'y preciser les raisons et les modalites des mises au point techniques, apportees par ceux qui, jour apres jour pendant cette periode, ont eu la charge de mettre en oeuvre ces boucles. Cette experience essentiellement pratique complete donc les etudes minutieuses et les essais preliminaires de ces boucles ou de leurs prototypes. Elle doit etre de quelque interet pour ceux qui sont confrontes aux problemes de conception ou d'exploitation de boucles d'irradiation dans des reacteurs experimentaux ou des dispositifs analogues. (auteurs)

  4. Some fundamental aspects of boiling in nuclear reactors; Quelques aspects fondamentaux de l'ebullition dans les reacteurs nucleaires

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    Mondin, H.; Lavigne, P.; Semeria, R. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    oscillation, the conditions of burnout are compared with those obtained under steady conditions. The burn-out flux following uniform 'stopped' heating has been studied in a channel containing still water. The flux shows a maximum as a function of unsaturation. The influence of the geometry and the nature of the metal was investigated. 4 - Output Oscillations: Using a low pressure (8 atm) loop, the influence of various parameters on the periods of output oscillations in a boiling channel on the thresholds at which they appear, was studied. Some new aspects of this complex phenomena were observed and are reported. (authors) [French] On indique les principaux resultats obtenus a Grenoble depuis quatre ans dans le domaine des mecanismes de l'ebullition et des phenomenes connexes dans les reacteurs nucleaires. 1 - OBSERVATION DE L'EBULLITION: Par photographie et cinematographie ultrarapide (8000 images par seconde maximum) on a observe l'ebullition en vase ou en canal jusqu'a 140 kg/cm{sup 2}. On a denombre les populations de germes (sites) generateurs de bulles et obtenu une correlation donnant leur nombre par unite de surface en fonction du flux thermique et de la pression. Le diametre des bulles se detachant de la paroi a ete etudie jusqu'a 140 kg/cm{sup 2}. On a mis en evidence trois types de bulles: - Les bulles en equilibre dont le diametre suit la formule de Fritz et Ende, - Les bulles d'ebullition dont le diametre diminue rapidement avec la pression (1/100 mm a 140 kg/cm{sup 2}), - Les coalescences apparaissant en liquide sature au-dessus de 15 W/cm{sup 2} et dont la proportion est independante de la pression. Par visualisation en strioscopie on observe les mouvements du film thermique associes a l'amorcage des germes, au depart et a la condensation des bulles; les mecanismes responsables de l'excellent transfert de chaleur ont pu ainsi etre precises. 2 - PERTES DE PRESSION EN ECOULEMENT DIPHASE: On a etabli un modele de

  5. Cross-correlation of two detectors in a nuclear reactor; Intercorrelation de deux detecteurs dans un reacteur nucleaire

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    Dalfes, A.; Beliard, L.; Cazemajou, J.; Froelicher, B. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    Auto and cross-correlation functions of signals given by neutron detectors situated in a subcritical nuclear reactor are determined by a numerical method. Values of the prompt neutrons decay constant obtained by means of the autocorrelation function of each detector and the cross-correlation function of the two detectors are compared to the reference value given by a classical pulsed neutrons measurement. Agreement between results seems to be satisfactory. (authors) [French] Les fonctions d'autocorrelation et d'intercorrelation des signaux issus de deux detecteurs de neutrons places dans un reacteur nucleaire sous critique sont determinees par une methode numerique. On compare les valeurs de la constante de decroissance des neutrons prompts donnees par les fonctions d'autocorrelation de chaque detecteur et la fonction d'intercorrelation des deux detecteurs au resultat de reference fourni par une manipulation dite de 'neutrons pulses'. L'accord entre les resultats parait satisfaisant. (auteurs)

  6. Determination of local boiling in light water reactors by correlation of the neutron noise; Determination de l'ebullition locale dans les reacteurs a eau legere par correlation du bruit neutronique

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    Zwingelstein, G. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    The power limit of swimming-pool type reactors depends on the phenomenon of the appearance of burn-out. In order to determine this limit we have attempted to detect the local boiling which usually occurs before the burn out. Local boiling has been simulated by an electrically heated plate placed in the core of the reactor Siloette. The study of local boiling, which is based on the properties of the correlation functions for the neutron noise of detectors placed in the core, shows that a privileged frequency occurs in the power spectrum of the noise. It is intended in the future to determine the influence of various parameters on this characteristic frequency. (author) [French] La limitation de la puissance des reacteurs nucleaires de type piscine est due au phenomene d'apparition de 'burn out'. Pour determiner cette limitation, nous nous sommes proposes dans ce rapport de detecter l'ebullition locale qui apparait generalement avant le 'burn out'. L'ebullition locale a ete simulee par une plaque chauffee electriquement et placee dans le coeur du reacteur SILOETTE. L'etude de l'ebullition locale, qui est basee sur les proprietes des fonctions de correlation du bruit neutronique de detecteurs places clans le coeur, fait apparaitre une frequence privilegiee dans le spectre de puissance du bruit. On envisage dans l'avenir, de determiner l'influence des divers parametres sur cette frequence caracteristique. (auteur)

  7. Description of methods for making activation detectors for use in nuclear reactors; Description des procedes de fabrication des detecteurs d'activation utilises dans les reacteurs nucleaires

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    Barbalat, R.; Le Coguie, R.; Leger, P.; Salon, L.; Thierry, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    A brief description of methods currently used for making activation detectors, thin films and various deposits used in nuclear reactors. The thicknesses required vary from about a few tenths of a micron to a few tenths of a millimeter. Different techniques are used for fixing the large variety of elements: rolling, moulding, painting, electrolysis, vacuum deposition, thin films, wires, enamels, protective linings, etc. (authors) [French] Expose succinct des procedes actuellement mis en oeuvre pour la realisation des detecteurs d'activation, feuilles minces et depots divers utilises dans les reacteurs nucleaires. La gamme des epaisseurs necessaires s'etendant approximativement des dixiemes de micrometre aux dixiemes de millimetre. La diversite des elements a fixer justifiant les techniques differentes selon les cas: laminage, moulage, peinture, electrolyse, depot sous vide, couches minces, fils, emaux, revetements protecteurs, etc. (auteurs)

  8. The nuclear power stations of the French atomic energy programme (1960); Les centrales nucleaires de puissance du programme francais (1960)

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    Leduc, C. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Roux, J.P. [Electricite de France (EDF), 75 - Paris (France)

    1960-07-01

    After recalling the entry of nuclear energy into energy production in France, the paper emphasizes the evolution of techniques applied in the designing of French nuclear power plants and describes the means employed for reducing costs per kWh of EDF2 and EDF3 compared with EDF1: the electric power per ton of uranium varies from 493 kW/t for EDF1 to 970 kW/t for EDF3. For this purpose the thermal power and electric power of units are changed respectively from 290 MWt for EDF1 to 1200 or 1600 MWt for EDF3 and from 28 to 250 MW. The results are obtained by an improvement in neutronic characteristics, developments in nuclear fuel technology, and simplification of the system of charging the reactor, whose means of maintenance are increased; the EDF2 heat-exchangers have been so designed as to increase the unit power of the elements, which will attain 9 MWt, as against 3 for EDF1. For EDF3 an advance project forecasts a thermodynamic layout with only one pressure stage. The paper ends with a description of the burst-slug detection systems, and an appendix gives a detailed comparative table of EDF1, EDF2 and EDF3 plant characteristics. (author) [French] Apres avoir rappele l'integration de l'energie nucleaire parmi les moyens de production de l'energie en France, les auteurs se penchent surtout sur l'evolution des techniques appliquees dans l'equipement des centrales nucleaires francaises et decrivent les moyens mis en oeuvre pour reduire les prix de revient du kWh d'EDF2 et d'EDF3 par rapport a EDF1: la puissance electrique par tonne d'uranium varie de 493 kW/t pour EDF1 a 970 kW/t pour EDF3. C'est dans ce but que les puissances thermiques et la puissance unitaire des groupes turbo-alternateurs passent respectivement de 290 MWt pour EDF1 a 1200 ou 1600 MWt pour EDF3 et de 82 a 250 MW. Les resultats sont obtenus par une amelioration des caracteristiques neutroniques, des progres realises sur la technologie des elements

  9. The use and evolution of the CEA research reactors; Utilisation et evolution des reacteurs de recherche du C.E.A

    Energy Technology Data Exchange (ETDEWEB)

    Rossillon, F.; Chauvez, C. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    retracent brievement l'histoire de ces reacteurs en montrant ce qu'a ete jusqu'a present leur utilisation, et comment certaines modifications ont permis de les adapter a l'evolution des programmes. Ils precisent egalement les raisons qui ont conduit a l'elaboration du projet de la nouvelle pile OSIRIS, La pile ZOE, la plus ancienne du CEA, est en service au Centre de Fontenay-aux-Roses depuis 1948. Elle est principalement utilisee pour les mesures de section efficace d'absorption du graphite, et pour diverses irradiations de courte duree ne necessitant que des flux peu eleves. La Pile EL2, en service depuis 1952, a permis les premieres etudes liees au refroidissement par gaz. Elle a ete tres utilisee pour la production des radioisotopes et pour de nombreuses experiences de physique, de metallurgie et de physico-chimie - le vieillissement de certaines parties du reacteur a conduit a decider l'arret prochain de cette installation. La Pile EL. 3 a ete tres utilisee pour les experiences de physique et pour l'etude des combustibles. L'adoption d'une nouvelle structure pour le coeur (solution 'Cristal de neige') va permettre d'accroitre considerablement les possibilites de la pile pour les irradiations en neutrons rapides. La pile TRITON-I, piscine de 2 MW, est surtout utilisee pour les irradiations en neutrons rapides et en gamma. Certaines modifications, actuellement en cours, permettront d'accroitre la puissance du reacteur jusqu'a 4 ou 5 MW. Dans un compartiment voisin de TRITON-I est implantee la Pile TRITON-II, de meme structure generale, mais dont la puissance maximum est de 100 kW. TRITON-II est utilisee exclusivement pour les etudes de protections. MELUSINE, pile piscine de 2 MW est en fonctionnement au Centre d'Etudes Nucleaires de Grenoble depuis 1959. Elle a permis l'execution d'un programme important concernant surtout la physique du solide, l'etude fondamentale de

  10. CO{sub 2} direct cycles suitable for AGR type reactors; Cycles directs de gaz carbonique applicables aux reacteurs du genre AGR

    Energy Technology Data Exchange (ETDEWEB)

    Maillet, E. [Commissariat a l' Energie Atomique. Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1967-10-01

    The perspectives given by the gas turbines under pressure, to build simple nuclear power plants and acieving significantly high yield, are specified. The CO{sub 2} is characterised by by good efficiency under moderate temperature (500 to 750 Celsius degrees), compactness and the simpleness of machines and the safe exploitation (supply, storage, relief cooling, thermosyphon). The revision of thermal properties of the CO{sub 2} and loss elements show that several direct cycles would fit in particular to the AGR type reactors. Cycles that would diverge a little from classical models and able to lead to power and heat generation can lead by simple means to the best results. Several satisfying solutions present for the starting up, the power regulation and the stopping. The nuclear power plant components and the functioning safety are equally considered in the present report. The conclusions stimulate the studies and realizations of carbon dioxide gas turbines in when approprite. [French] Les perspectives offertes par la turbine a gaz sous pression, pour construire des centrales nucleaires simples et de rendement progressivement eleve, se precisent actuellement. le CO{sub 2} se distingue par sa bonne efficacite a temperature moderee (500 a 750 degres celsius), la compacite et la simplicite des machines, et la surete qu'il apporte a l'exploitation ( approvisionnement, stockage, refroidissement de secours, thermosiphon). La revision des proprietes thermophysiques du CO{sub 2} et des elements de pertes montre que divers cycles directs conviendraient en particulier aux reacteurs agr ou derives. Des cycles s'ecartant peu des modeles classiques, et se pretant ulterieurement a la production simultanee d'electricite et de chaleur, peuvent conduire par des moyens simples aux meilleurs resultats d'ensemble. Plusieurs solutions satisfaisantes se presentent pour le demarrage, le reglage de la puissance et l'arret. Les composants de la centrale et la

  11. A mathematical model for cost of maritime transport. Application to competitiveness of nuclear vessels; Modele mathematique du cout de transport maritime application a la competitivite du navire nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Dorval, C. [Commissariat a l' Energie Atomique, 75 - Paris (France)

    1966-05-01

    In studying the competitiveness of a nuclear merchant vessel, economic assessments in terms of figures were discarded in favor of a simplified model, which gives a clearer idea of the mechanism of the comparison between alternative vessels and the particular influence of each parameter. An expression is formulated for the unit cost per ton carried over a given distance as a function of the variables (speed and deadweight tonnage) and is used to determine the optima for conventional and nuclear vessels. To represent the freight market involved in the optimization studies, and thus in the competitiveness computation, two cases are taken into account: the tonnage to be carried annually is limited, and the tonnage to be carried annually is not limited. In both cases the optima are calculated and compared for a conventional and a nuclear vessel. Competitiveness curves are plotted as a function of the ratios of nuclear and conventional fuel costs and nuclear and conventional marginal power costs. These curves express the limiting values of the above two ratios for which the transport costs of the nuclear and conventional vessels are equal. The competitiveness curves vary considerably according to the hypothesis adopted for the freight market and the limit of tonnage carried annually. (author) [French] Pour etudier la competitivite du navire marchand nucleaire, plutot que de nous livrer a des evaluations economiques chiffrees, discutables dans l'etat actuel des etudes, nous utilisons un modele simplifie permettant de mieux saisir le mecanisme de la comparaison des navires et l'influence particuliere de chaque parametre. Nous etablissons une expression du cout unitaire de la tonne transportee sur un parcours donne en fonction des variables vitesse et port en lourd. Et nous l'utilisons pour determiner les optima des navires classiques et nucleaires. Pour representer le marche du fret qui intervient dans les etudes d'optimisation, et donc dans la

  12. Chemical elimination of alumina in suspension in nuclear reactors heavy water; Elimination de l'alumine en suspension dans l'eau lourde des reacteurs nucleaires par voie chimique

    Energy Technology Data Exchange (ETDEWEB)

    Ledoux, A. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-02-01

    Corrosion of aluminium in contact with moderating water in nuclear reactor leads to the formation of an alumina hydrosol which can have an adverse effect on the operation of the reactor. Several physical methods have been used in an attempt to counteract this effect. The method proposed here consists in the elimination of the aluminium by dissolution and subsequent fixation in the ionic form on mixed-bed ion-exchange resin. In order to do this, the parameters and the values of these parameters most favorable to the dissolution process have been determined. If the moderator is heavy water, the deuterated acid can be prepared by converting a solution in heavy water to a salt of the acid using a deuterated cationic resin. (author) [French] La corrosion de l'aluminium au contact de l'eau moderatrice des reacteurs nucleaires, donne lieu a la formation d'un hydrosol d'alumine nuisible au bon fonctionnement des reacteurs. Plusieurs methodes physiques ont ete mises en oeuvre pour pallier ces inconvenients. On propose ici d'eliminer l'alumine par solubilisation pour la fixer ensuite sous forme ionique par des resines echangeuses d'ions, en lit melange. A cette fin on determine les parametres et leurs grandeurs favorables a cette solubilisation. Si le moderateur est de l'eau lourde la preparation d'acide deutere peut etre effectuee par passage d'une solution en eau lourde a un sel de l'acide sur resine cationique deuteree.

  13. Experimental study of the hydrodynamic instabilities occurring in boiling-water reactors; Etude experimentale des instabilites hydrodynamiques survenant dans les reacteurs nucleaires a ebullition

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    Fabreca, S. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-10-01

    The subjects is an experimental out-of pile loop study of the hydrodynamic oscillations occurring in boiling-water reactors. The study was carried out at atmospheric pressure and at pressure of about 8 atmospheres, in channels heated electrically by a constant and uniform specified current. In the test at 8 atmospheres the channel was a round tube of approximately 6 mm interior diameter. At 1 atmosphere a ring-section channel was used, 10 * 20 mm in diameter, with an inner heating tube and an outer tube of pyrex. It was possible to operate with natural convection and also with forced convection with test-channel by-pass. The study consists of 3 parts: 1. Preliminary determination of the laws governing pressure-drop during boiling. 2. Determination of the fronts at which oscillation appears, within a wide range of the parameters involved. 3. A descriptive study of the oscillations and measurement of the periods. The report gives the oscillation fronts with natural and forced convection for various values of the singular pressure drop at the channel inlet and for various riser lengths. The results are presented in non-dimensional form, which is available, in first approximation, for all geometric scales and for all fluids. Besides the following points were observed: - the wall (nature and thickness) can be an important factor ; - oscillation can occur in a horizontal channel. (author) [French] II a ete effectue une etude experimentale, en boucle hors-pile, des oscillations hydrodynamiques survenant dans les reacteurs a ebullition. L'etude a ete effectuee a la pression atmospherique et a une pression voisine de 8 atmospheres dans des canaux chauffes electriquement a puissance imposee constante et uniforme. Dans les essais a 8 atmospheres le canal etait un tube circulaire de diametre interieur 6 mm environ. A 1 atmosphere le canal etait de section annulaire 10 * 20 mm avec un tube interieur chauffant et un tube exterieur en pyrex. Le fonctionnement etait possible

  14. Micro manometer and pitot tube for measuring the velocity distribution in a natural convection water stream between two vertical parallel plates (1961); Micromano metre et tube de pitot destines a l'exploration du profil de vitesse dans un ecoulement d'eau de convection naturelle entre deux plaques verticales paralleles (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Santon, L.; Vernier, Ph. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1961-07-01

    For heat transfer studies in certain cases of cooling in swimming-pool type nuclear reactors, a knowledge of the distribution of the velocities between two heating elements is of prime importance. A Pitot tube and a micro-manometer have been developed for making these measurements on an experimental model. (authors) [French] Pour l'etude du transfert de chaleur dans certains cas de refroidissement des reacteurs nucleaires du type piscine, la connaissance de la repartition des vitesses entre deux elements chauffants est primordiale. On a mis au point un tube de Pitot et un micromanometre pour effectuer ces mesures sur une maquette experimentale. (auteurs)

  15. G2 - G3 inventive properties, the first french nuclear plants; Caracteristiques generales et aspects originaux des reacteurs G2 et G3

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    Pascal; Horowitz; Bussac; Joatton; De Lagge de Meux; Martin [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    This paper points out the inventive properties of the frenchctors G2 and G3. These are dual purpose reactors, i.e. designed for the production of both plutonium and energy (30 electrical MW); in this respect, they can be considered as the start point of the french electrical energy produced from nuclear fuel. The following points are specially discussed in this paper: the choice of the prestressed concrete pressure vessel, the horizontal arrangement of the channels, the interest of neutron flux flattening, the advantages of the charging and discharging device working during pile operation. (author)Fren. [French] Les caracteres originaux des reacteurs fran is G2 et G3 sont decrits dans ce rapport. Ce sont des reacteurs a double fin, plutonigenes et aussi producteurs d'energie (30 MW electriques); ils constituent a ce titre le point de depart de la production fran ise d'electricite d'origine nucleaire. Sont discutes, en particulier, dans ce rapport: le choix du caisson en beton precontraint pour tenir la pression, la disposition horizontale des canaux, l'interet de l'aplatissement du flux neutronique, les avantages de l'appareil permettant le chargement et le dechargement du combustible sans arreter la pile. (auteur)

  16. Processing Th C{sub 2} - UC{sub 2} fuel extracted from high temperature reactors HTGCR; Etude du traitement des combustibles Th C{sub 2} - UC{sub 2} issus de reacteurs a haute temperature

    Energy Technology Data Exchange (ETDEWEB)

    Derrien, C.; Lessart, P.; Pianezza, E.; Verry, C.; Villain, G. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    The object of this investigation is solubilisation head-end (from crushing and grinding phase to non included first purification phase) of pulverulent ({sup 233}U/{sup 232}Th)C{sub 2} (200 - 500 microns diameter) contained in a graphite matrix extracted from a 4.10{sup 13} n.cm{sup -2}.s{sup -1} thermalized neutrons average flux with an irradiation of 80000 MWjT{sup -1} HTGCR reactor. After having succinctly described different bibliographic processes we have chosen the burn - leach of reactor fuel and graphite matrix containing it. The technology of burner is original in nuclear field and still more by utilizing ultra-sounds to intensify burning reaction and to minimize the weight of unburnables. The mixture of ThO{sub 2}, U{sub 3}O{sub 8}, and fission products oxides is solubilized by boiling HNO{sub 3} 13 M + HF 0.05 M. This process is profit-learning in a thorium recuperation and reprocessing point of view. In the contrary-case it would be interesting to consider a dry-process which would permit to separate solid ThF{sub 4} from gaseous UF{sub 6}. (authors) [French] Cette etude a pour objet le traitement initial de mise en solution ou 'head-end' (allant de la phase broyag-concassage a la phase de premiere purification exclue) d'un combustible ({sup 233}U/{sup 232}Th)C{sub 2} pulverulent (de 200 a 500 {mu} de diametre) contenu dans une matrice de graphite issu d'un reacteur HTGCR surgenerateur a neutrons thermiques de flux moyen 4. l0{sup 13} n.cm{sup -2}.s{sup -1} et taux d'irradiation 80000 MWjT{sup -1}. Apres exposition succincte des differents procedes bibliographiques decrits, nous avons finalement choisi le traitement par combustion-attaque ('Burn-Leach') du combustible et de la matrice etanche graphite qui le contient. La technologie du bruleur est originale dans le domaine nucleaire d'autant qu'elle utilise les ultra-sons pour ameliorer le rendement de la reaction de combustion et reduire au minimum le poids

  17. Two further years of operation of the reactor G1 (july 1958 - july 1960); Deux nouvelles annees de fonctionnement du reacteur G1. (juillet 1958 - Juillet 1960)

    Energy Technology Data Exchange (ETDEWEB)

    Mathot, P.; Bauzit, J.; Cante, R.; Hebrard, L. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    observations ont pu etre faites sur l'empilement de graphite, en meme temps qu'etait accru le nombre de points de mesure des temperatures des gaines du combustible. - Du 25 septembre 1959 au 9 decembre 1959: preparation et execution du deuxieme recuit. A l'issue du recuit, le reseau de thorium a ete modifie et des thermocouples supplementaires donnant la temperature de la masse du graphite ont ete mis en place. Un appareillage permettant la mesure du flux radial a ete realise. - Du 9 decembre 1959 a juillet 1960: campagne de fonctionnement continu, avec le minimum d'arrets. Les resultats d'experience sont regroupes, independamment de toute chronologie sous trois grandes rubriques qui president a la vie du reacteur: - Fonctionnement continu, - Dechargements, - Recuits du reacteur. (auteur)

  18. Measurement and regulation of the level of a homogeneous plutonium reactor; Mesure et regulation du niveau d'un reacteur homogene au plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Berger, F.; Bertrand, J

    1958-12-01

    Reactivity depends strongly on disturbances of the level of the plutonium solution In the homogeneous reactor. Proserpine has a small cylindrical core, 250 mm diameter, and 10 liters volume. With a view to reducing the dangers due to corrosion and contamination, the solution level in the core is raised by pneumatic pressure. The level is stabilized by means of a regulating system. During critical experiments the variations of the level are less than one hundredth part of a millimeter. (author) [French] Les variations du niveau de la solution de plutonium dans le reacteur homogene Proserpine ont une grosse influence sur la reactivite, car le coeur est petit (10 litres de solution dans un cylindre de diametre 250 mm). En vue de reduire les dangers dus a la corrosion et a la contamination, la commande du volume liquide est pneumatique. Nous avons realise la stabilite du niveau par une regulation qui, dans les essais en regime critique, limite les variations du plan liquide a une fraction de centieme de millimetre. (auteur)

  19. Some aspects of the nuclear fission process; Quelques aspects du processus de fission nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Netter, F. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    In the following report one can find first a short general view on the present situation of our knowledge concerning the nuclear fission process, namely on the nucleus going through the saddle-point. Then there are some aspects connected with the excitation energy of the fissioning nucleus. The measurements made at Saclay on the fast neutron fission cross-section of U{sup 233}, U{sup 235}, Pu{sup 239}, U{sup 238} are described at the beginning of this work. It appears that for U{sup 233} there is some characteristic shape modulation of the cross-section curve, in relation with the collective excited state of the deformed nucleus at the saddle-point. Good evidence of this is also given by the study of the relative fission rate with emission of long-range particles; it appears also that this ternary fission rate does not change substantially for neutron between thermal energy and 2 MeV, but that is very lower for the compound nucleus U{sup 239} than for even-even compound nuclei. At the end there are some experiments on the strong 4,5 MeV gamma-ray originated by slow neutron absorption in U{sup 235}. Time-of-flight device is used to establish that this 4,5 MeV gamma-ray seems mostly connected with radiative capture. (author) [French] Le present travail debute par un apercu de l'etat actuel de nos connaissances sur le processus de fission nucleaire, notamment sur le passage par le point-seuil. Puis sont evoques des aspects lies au niveau d'energie d'excitation auquel est porte le noyau qui subit la fission. Les mesures de sections efficaces de fission induite dans {sup 233}U, {sup 235}U, {sup 239}Pu et {sup 238}U par des neutrons rapides effectuees a Saclay sont decrites en premier lieu; elles font apparaitre pour {sup 233}U une ondulation caracteristique du role des etats collectifs d'excitation du noyau deforme au point-seuil. Des experiences sur la fission avec emission de particules de long parcours confirment cet aspect tout en demontrant que

  20. Preliminary studies leading to a conceptual design of a 1000 MWe fast neutron reactor; Etudes preliminaires conduisant a un concept de reacteur a neutrons rapides de 1000 MWe

    Energy Technology Data Exchange (ETDEWEB)

    Vendryes, G.; Zaleski, C.P. [Association Euratom-CEA Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    projets de reacteurs futurs. - Il presente un concept de reacteur a neutrons rapides de 1000 MWe, pour la realisation duquel aucune impossibilite technologique de realisation n'apparait. - Il indique que le comportement dynamique appatait satisfaisant, bien que le coefficient de reactivite isotherme du au sodium soit positif. - Il essaie de situer le developpement des reacteurs a neutrons rapides dans le cadre de l'expansion de l'energie nucleaire. L'approvisionnement en matieres fissiles ne semble pas devoir freiner en France le developpement des reacteurs a neutrons rapides. Celui - ci dependra essentiellement a moyen terme de leur competitivite economique. (auteurs)

  1. Conformity of nuclear construction codes with the requirements of the French order dated December 12, 2005 related to nuclear pressure equipment; Conformite des codes de construction nucleaires avec les exigences de l'arrete du 12 decembre 2005 relatif aux equipements sous pression nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Grandemange, J.M.; Renaut, P. [Areva-NP, Tour AREVA, 92084 - Paris La Defense cedex, (France); Paris, D. [EDF-Ceidre 2 rue Ampere - 93206 SAINT-DENIS Cedex (France); Faidy, C. [EDF-Septen 12/14, Avenue Dutrievoz 69628 Villeurbanne Cedex (France)

    2007-07-01

    The French Decree dated December 13, 1999 transposing the Pressure Equipment Directive (PED) has replaced the fundamental texts on which up to now the regulation for pressure equipment important for the safety of nuclear reactors was also founded. By a Ministerial Order - called 'ESPN Order' - dated December 12, 2005, a new regulation has been issued for nuclear pressure equipment. This text makes reference to the Decree transposing the PED while completing these provisions by supplementary requirements having the objective to provide a very high level of integrity guarantee for equipments which are the most important for safety, and to cover the prevention of radioactive release risks. These regulatory evolutions are presented in the Plenary Session of the ESOPE conference. Referencing the Decree and thus the PED, and including specific provisions, the Ministerial Order implies that the Manufacturers update their documents and, if necessary, their prescriptions in the following two domains: - that of the conformity of Codes and Standards used, generally inspired from the ASME Code Section III, with the essential safety requirements of the PED, - that of the respect of the complementary provisions brought by the ESPN Order. This paper presents the more significant conclusions of this work and the resulting amendments of the RCC-M Code, introduced by the 2007 addendum to that Code. The analysis will lead to specify the same type of complementary requirements to Code when a manufacturer wishes to use the German KTA Rules or the ASME Code Section III. (authors) [French] Le decret du 13 decembre 1999 transposant la directive europeenne (DESP) relative aux equipements sous pression a remplace les textes fondamentaux sur lesquels se fondait egalement jusque la la reglementation des appareils a pression importants pour la surete des reacteurs nucleaires. Par arrete - dit 'arrete ESPN' - du 12 decembre 2005, une nouvelle reglementation a ete dictee. Ce

  2. Construction of the core of the 'heavy water-gas' reactor EL 4; Structures du coeur du reacteur 'eau- lourde-gaz EL 4'

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, J.L.; Foulquier, H.; Thome, P. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    problem of thermal insulation around a zirconium alloy liner tube. The neutron absorption equivalent is about 1, 1 mm of Al, and the mean loss around 2 p. 100 of the thermal power of the reactor. The methods proposed have proved practicable as a result of important research and developments on automatic remote control for all the operations which make up the sequences of mounting, demounting and repairing of the construction components. In particular the possibilities opened up by the new techniques of welding tubes from the inside have been extended to other problems connected with the assembling of a reactor. (authors) [French] Le coeur de ce reacteur est constitue par une cuve contenant l'eau lourde, cuve traversee d'une serie de tubes de force dans lesquels circule le gaz caloporteur sous pression de 60 at. Les specifications de depart qui ont joue un role important dans la conception de ces structures concernent des aspects de securite de fonctionnement (chargement du combustible par les deux faces du reacteur, remplacement des structures sur les deux faces du reacteur), des necessites neutroniques (absorption des structures minimum, pas du reseau, diametre des tubes de force) et des considerations thermiques (temperature de sortie 500 C). Ces specifications ont entraine une disposition horizontale des tubes de force et des problemes d'encombrement tres delicats qui ont elimine (pour les dimensions d'EL 4) toute possibilite de recourir a des compensateurs de dilatation sur les tubes de force. II s'ensuit un dessin de cuve semi-rigide dans lequel les tubes de force contribuent pour une part importante a la resistance mecanique de l'ensemble en jouant le role de tirant, d'ou des contraintes elevees sur les jonctions et tubes de force (et le choix des alliages de zirconium). Les structures comprennent le tube de force, les jonctions, l'isolement thermique et le tube de guidage. On expose brievement les moyens d'essais mis en

  3. Economic aspects of electricity and industrial heat generating reactors; Aspect economique des reacteurs produisant de l'electricite et de la chaleur industrielle

    Energy Technology Data Exchange (ETDEWEB)

    Gaussens, J.; Moulle, N.; Dutheil, F. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Aldebert, J. [Institut National des Sciences et Techniques Nucleaires (INSTN), CEA Saclay, 91 - Gif sur Yvette (France)

    1964-07-01

    combustibles et des investissements specifiques nucleaires et classiques. Ces conditions de rentabilite conduisent a admettre pour les reacteurs ainsi utilises certaines caracteristiques techniques et economiques hors desquelles la competition est improbable. On situe, d'autre part, ces resultats par rapport au marche potentiel de la vapeur et de l'electricite et on est ainsi conduit a examiner certaines utilisations de la chaleur des centrales mixtes telles que l'alimentation de complexes industriels, de divers types de chauffage urbain ou du dessalement des eaux de mer. (auteurs)

  4. Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

    Energy Technology Data Exchange (ETDEWEB)

    Lacour, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P. [S.E.M. Hispano-Suiza, 92 - Colombes (France)

    1964-07-01

    In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines

  5. Nuclear study of Melusine; Etude nucleaire de Melusine

    Energy Technology Data Exchange (ETDEWEB)

    Cherot, J. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    In this report are reviewed - with respect to starting of experiments - the main nuclear characteristics of a 20 per cent enriched uranium lattice, with light water as moderator and reflector. The reactor is to operate at 1 MW. 1) Study of various critical masses. 2) Control. Effectiveness of cadmium. Control rods and of a stainless steel regulating rod. 3) Study of the effect on reactivity of disturbances in the core center. 4) Study of xenon and samarium poisoning. 5) Temperature factor. 6) Heat exchanges in a fuel element. (author) [French] On etudie, dans ce rapport, les principales proprietes nucleaires d'un reseau a uranium enrichi (20 pour cent), dont le moderateur et le reflecteur sont l'eau legere en vue des experiences de demarrage. Ce reacteur devra fonctionner a 1 MW. 1) Etude de diverses masses critiques. 2) Controle. Efficacite des barres de controle en cadmium et d'une barre de reglage en acier inoxydable. 3) Etude de l'effet sur la reactivite de perturbation au centre du coeur. 4) Etude de l'empoisonnement xenon et samarium. 5) Coefficient de temperature. 6) Echanges thermiques dans un element. (auteur)

  6. Laser-induced mobilization of dust produced during fusion reactors operation; Mise en suspension par laser de poussieres generees lors du fonctionnement des reacteurs de fusion

    Energy Technology Data Exchange (ETDEWEB)

    Vatry, A.

    2010-11-16

    During tokamak operation, plasma-wall interactions lead to material erosion process and dusts production. These dusts are mainly composed by carbon and tungsten, with sizes ranging from 10 nm to 100 {mu}m. For safety reasons and to guarantee an optimum reactor functioning, the dusts have to be kept in reasonable quantity. The dusts mobilization is a first step to collect them, and the laser is a promising technique for this application. To optimize the cleaning, physical mechanisms responsible for dust ejection induced by laser have been identified. Some particles, such as aggregates, are directly ablated by the laser. The metal droplets are ejected intact by an electrostatic force, induced by the photoelectrons. We also characterized the particles ejection to choose an appropriate collection device. (author) [French] Lors du fonctionnement d'une machine de fusion, les interactions plasma-parois conduisent a des processus d'erosion des materiaux et a la production de particules. Ces poussieres sont principalement composees de carbone et de tungstene. Pour des raisons de surete et afin de garantir un fonctionnement optimum du reacteur, il est important de garder en quantite raisonnable les poussieres dont la taille varie entre 10 nm et 100 {mu}m. La mise en suspension de ces poussieres est une etape preliminaire a leur recuperation, et le laser est une technique prometteuse pour cette application. Afin d'optimiser le nettoyage, les mecanismes physiques a l'origine de l'ejection induite par laser de ces poussieres ont ete identifies. Les agregats sont directement ablates par le laser et les gouttelettes metalliques sont ejectees intactes par une force electrostatique induite par les photoelectrons. Nous avons egalement caracterise l'ejection des particules pour choisir un systeme de recuperation adapte

  7. Handbook for the calculation of reactor protections; Formulaire sur le calcul de la protection des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-07-01

    This note constitutes the first edition of a Handbook for the calculation of reactor protections. This handbook makes it possible to calculate simply the different neutron and gamma fluxes and consequently, to fix the minimum quantities of materials necessary under general safety conditions both for the personnel and for the installations. It contains a certain amount of nuclear data, calculation methods, and constants corresponding to the present state of our knowledge. (authors) [French] Cette note constitue la premiere edition du 'Formulaire sur le calcul de la protection des reacteurs'. Ce formulaire permet de calculer de facon simple les difterents flux de neutrons et de gamma et, par suite, de fixer les quantites minima de materiaux a utiliser pour que les conditions generales de securite soient respectees, tant pour le personnel que pour les installations. Il contient un certain nombre de donnees nucleaires, de methodes de calcul et de constantes correspondant a l'etat actuel de nos connaissances. (auteurs)

  8. Production of nuclear graphite in France; Production de graphite nucleaire en France

    Energy Technology Data Exchange (ETDEWEB)

    Legendre, P.; Mondet, L. [Societe Pechiney, 74 - Chedde (France); Arragon, Ph.; Cornuault, P.; Gueron, J.; Hering, H. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The graphite intended for the construction of the reactors is obtained by the usual process: confection of a cake from coke of oil and tar, cooked (in a electric oven) then the product of cook is graphitized, also by electric heating. The use of the air transportation and the control of conditions cooking and graphitization have permitted to increase the nuclear graphite production as well as to better control their physical and mechanical properties and to reduce to the minimum the unwanted stains. (M.B.) [French] Le graphite destine a la construction des reacteurs est obtenu par le procede usuel: confection d'une pate a partir de coke de petrole et de brai, cuisson de cette pate (au four electrique) puis graphitation du produit cuit, egalement par chauffage electrique. L'usage du transport pneumatique et le controle des conditions cuisson et de graphitation ont permit d'augmenter la production de graphite nucleaire ainsi que de mieux controler ses proprietes physiques et mecaniques et de reduire au minimum les souillures accidentelles. (M.B.)

  9. Relationship between the nuclear resonance of cobalt metal and its ferromagnetic properties; Relations entre la resonance nucleaire du cobalt metallique et ses proprietes ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

    Aubrun, J.N. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-05-15

    resulte du couplage intense existant entre les noyaux et les electrons porteurs du magnetisme. Ces derniers excitent les noyaux et, dans les parois de Bloch, les soumettent a un champ radio-frequence bien plus intense que le champ RF applique. Les parametres de la resonance se determinent alors a partir du mouvement des parois, et dependent donc des constantes ferromagnetiques. La theorie permet de prevoir quantitativement certains effets particuliers, notamment par action d'un champ magnetique continu ou de la temperature. L'etude expeimentale a porte sur des poudres de cobalt et est en bon accord avec la theorie. Toutefois il faut tenir compte de l'effet de peau et reviser la theorie en consequence. Ceci permet d'expliquer certaines divergences observees, ainsi que l'influence de la taille des grains et celle du champ magnetique sur la forme de raie. Des renseignements originaux ont ete obtenus sur certaines proprietes purement ferromagnetiques du cobalt, en etudiant l'effet d'un champ magnetique et cette methode a pu etre appliquee a d'autres corps ferromagnetiques. En raison du caractere particulier de cette resonance nucleaire, qui se produit en l'absence de champ directeur et possede une importante largeur de raie, des spectrographes de type nouveau ont ete realises qui ont rendu possible des mesures precises de la forme de raie. La faible intensite des signaux obtenus dans certains cas a conduit a la mise au point d'une methode originale d'extraction dont la theorie et les applications pratiques sont donnees ici. L'ensemble de ces experiences fait apparaitre la resonance nucleaire comme un puissant moyen d'etude du ferromagnetique permettant de deceler des phenomenes microscopiques difficilement accessibles par les methodes classiques. (auteur)

  10. Research on nuclear energy in the fields of fuel cycle, PWR reactors and LMFBR reactors; Recherche sur l`energie nucleaire dans les domaines du cycle du combustible des reacteurs a eau legere et des reacteurs a neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Barre, B.; Camarcat, N.

    1995-12-31

    In this article we present the CEA research programs to improve the safety of the next generation of reactors, to manage the Plutonium and the wastes of the fuel cycle end and to ameliorate the competitiveness. 6 refs.

  11. Is it possible to recycle nuclear wastes? Costs, risks and stakes of the plutonium industry; Peut-on recycler les dechets nucleaires? Couts, risques et enjeux de l'industrie du plutonium

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on the chain reaction from uranium to plutonium, the difference between reprocessing (which does not reduce waste volumes but multiply waste types) and recycling, the high risks associated with plutonium transport, La Hague as the most dangerous nuclear site in France, reprocessing as the alibi for the French nuclear industry, Areva as an expert in propaganda, reprocessing as an absurd world strategy, plutonium as a fuel for proliferation, the myth of unlimited energy with the breeder reactors, and so on

  12. A fly-wheel drive with controlled-torque clutch for a reactors cooling circuit pumps; Entrainement des pompes du circuit de refrigeration d'un reacteur par volant a embrayage sous couple controle

    Energy Technology Data Exchange (ETDEWEB)

    Riettini, A. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-10-15

    After a theoretical study on the slowing down of a centrifugal pump, the motion equations have been checked by means of experimental tests. In order to have important slowing down times (which is the case of the cooling pumps of a research reactor) it is necessary to add a fly-wheel. To prevent troubles when starting, a block pump-fly-wheel with clutch under controlled torque was developed. It is so possible to start the fly-wheel progressively without increasing too much power of the driving motor. (author) [French] Apres une etude theorique sur le mouvement de ralentissement d'une pompe centrifuge, les equations du mouvement ont ete verifiees par des essais pratiques. Pour obtenir des temps de ralentissement importants (cas des pompes de refrigeration d'un reacteur de recherche) il est necessaire d'y adjoindre un volant d'inertie. Pour eviter les inconvenients au demarrage, on a etudie un ensemble pompe-volant avec embrayage sous couple controle. Cette solution permet de lancer progressivement le volant sans augmentation appreciable de la puissance du moteur d'entrainement. (auteur)

  13. Differential measurement of the earth's magnetic field by nuclear magnetic resonance; Mesure differentielle du champ magnetique terrestre par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Robach, F. [Commissariat a l' Energie Atomique, 38 - Grenoble (France). Centre d' Etudes Nucleaires

    1967-07-01

    MNR transducers using proton dynamic polarisation allows to convert into a phase measurement any variation of the earth magnetic field. There exist several versions of the instrument corresponding to various models of MNR transducers, which the author analyses in detail, devoting an important place to influence of their alignment with respect to the earth's magnetic field. The sensibility obtained is of one hundredth of a gamma over a bandwidth of (0-0,1 Hz). - This instrument is designed for measuring field gradients in airborne magnetic surveying, for detecting nearly magnetic anomalies, and for distinguishing between nearly and distant magnetic phenomena. (author) [French] L'emploi de capteurs, bases sur la resonance magnetique nucleaire des protons en presence de polarisation dynamique, permet de traduire une difference de champ magnetique terrestre en une mesure de phase. L'appareil existe sous plusieurs versions avec des capteurs de modeles differents dont l'auteur fait une analyse detaillee en accordant une part importante a l'influence de l'orientation des capteurs par rapport au champ magnetique terrestre. La sensibilite est de 1/100 {gamma} pour une bande passante de (0 - 0,1 Hz). Cet appareil s'applique a la mesure du gradient en prospection magnetique aeroportee, a la detection d'anomalies magnetiques proches, a la differentiation d'effets magnetiques proches et lointains. (auteur)

  14. On needs for particular isotopes with future advanced nuclear reactors; Quelques besoins en isotopes particuliers pour les reacteurs nucleaires avances du futur

    Energy Technology Data Exchange (ETDEWEB)

    Asou, M.; Porta, J. [CEA Centre d`Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d`Etudes des Reacteurs

    1994-12-31

    This paper is concerned with two essential points with innovative approaches for nuclear reactors: utilization of {sup 15}N in uranium nitride fuels in order to avoid carbon 14 generation; utilization of rare earths, and especially gadolinium, for the control of the potential reactivity in the core in the case of a cycle lengthening from 12 to 18 months, and in the case of a water reactor operating without soluble boron. 1 tab., 17 refs.

  15. Production and validation of nuclear data for reactor and fuel cycle applications; Production et validation des donnees nucleaires pour les applications reacteurs et cycle du combustible

    Energy Technology Data Exchange (ETDEWEB)

    Trakas, C. [Framatome ANP GmbH NBTT, Erlangen (Germany); Verwaerde, D. [Electricite de France EDF, 75 - Paris (France); Toubon, H. [Cogema, 78 - Velizy Villacoublay (France)] [and others

    2002-07-01

    The aim of this technical meeting is the improvement of the existing nuclear data and the production of new data of interest for the upstream and downstream of the fuel cycle (enrichment, fabrication, management, storage, transport, reprocessing), for the industrial reactors, the research reactors and the new reactor concepts (criticality, dimensioning, exploitation), for the instrumentation systems (external and internal sensors), the radioprotection, the residual power, the structures (neutron bombardment effect on vessels, rods etc..), and for the activation of steel structures (Fr, Ni, Co). The expected result is the collection of more reliable and accurate data in a wider spectrum of energies and temperatures thanks to more precise computer codes and measurement techniques. This document brings together the communications presented at this meeting and dealing with: the process of production and validation of nuclear data; the measurement facilities and the big international programs; the users needs and the industrial priorities; the basic nuclear data (BND) needs at Cogema; the expression and evaluation of BND; the evaluation work: the efficient cross-sections; the processing of data and the creation of activation libraries; from the integral measurement to the qualification and the feedback on nuclear data. (J.S.)

  16. Etude de l'influence du champ magnetique dans une section d'essais thermohydraulique d'un canal de reacteur nucleaire CANDU 6

    Science.gov (United States)

    Landry-Lavoie, Renaud

    This memoir deals with the effects of the magnetic fields present in a thermal hydraulic test section of the Canadian nuclear industry. This test section is used to determine the thermal hydraulic conditions that can lead to critical heat flux in a channel of a CANDU 6 nuclear reactor. To perform their series of experiments the STERN Company used strong electric currents to heat the simulation bundles with a thermal power similar to the one found in a channel of a CANDU reactor. The materials constituting the simulation channel and its supports are of ferromagnetic nature. The strong magnetic field generated by the bundles implies that they are subjected to a magnetostatic force due to the magnetization of the ferromagnetic materials. The nuclear industry wants to know if these efforts, combined with the force of gravity, are sufficient to maintain the bundles in place in the simulation channel. The question also arises whether or not the magnetic field present in the channel can affect the parameters of boiling heat transfer. To determine the magnetic field distribution in the simulation channel, we had recourse to the magnetostatic image method and the integral method of calculation of magnetization. The results of the calculations show that the magnetostatic forces exerted by the ferromagnetic elements of the test section are inferior in magnitude to the one estimated by the STERN laboratorie. We used the mechanistic model of Sullivan et al. (1964) to evaluate the possible influence of the magnetic fields on the departure diameter of the vapor bubbles. The deviation in the frequency of bubble emission was evaluated by using the correlations of Zuber et al. (1959) and Cole (1960). By introducing a magnetostatic force in the boiling model and in the correlations, we demonstrated that the magnetic field present in the STERN test section has a negligible effect on the bubble departure diameter and their emission frequency. We conclude that the conditions in the test section are consistent with those prevailing in the channel of a CANDU 6 reactor.

  17. Contribution to the optimization of the coupling of nuclear reactors to desalination processes; Contribution a l'optimisation du couplage des reacteurs nucleaires aux procedes de dessalement

    Energy Technology Data Exchange (ETDEWEB)

    Dardour, S

    2007-04-15

    This work deals with modelling, simulation and optimization of the coupling between nuclear reactors (PWR, modular high temperature reactors) and desalination processes (multiple effect distillation, reverse osmosis). The reactors considered in this study are PWR (Pressurized Water Reactor) and GTMHR (Gas Turbine Modular Helium Reactor). The desalination processes retained are MED (Multi Effect Distillation) and SWRO (Sea Water Reverse Osmosis). A software tool: EXCELEES of thermodynamic modelling of coupled systems, based on the Engineering Algebraic Equation Solver has been developed. Models of energy conversion systems and of membrane desalination processes and distillation have been developed. Based on the first and second principles of thermodynamics, these models have allowed to determine the optimal running point of the coupled systems. The thermodynamic analysis has been completed by a first economic evaluation. Based on the use of the DEEP software of the IAEA, this evaluation has confirmed the interest to use these types of reactors for desalination. A modelling tool of thermal processes of desalination in dynamic condition has been developed too. This tool has been applied to the study of the dynamics of an existing plant and has given satisfying results. A first safety checking has been at last carried out. The transients able to jeopardize the integrated system have been identified. Several measures aiming at consolidate the safety have been proposed. (O.M.)

  18. Factors and uncertainties in the profitability of using nuclear energy in desalination of water; Facteurs et incertitudes de la rentabilite du recours a l'energie nucleaire dans le dessalement des eaux

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L.; Lievre, P. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-07-01

    coefficients de transmission, les durees de vie des materiels, selon le choix des materiaux, l'evolution des prix, la forme des fonctions de prix et les taux d'interet) et aux contraintes. Dans une deuxieme partie, on etudie et on discute les incertitudes liees, a la methode d'optimisation utilisee et au critere de choix retenu. On montre ainsi qu'il est extremement difficile dans la plupart des cas de conclure sans nuances a la competitivite ou, a l'inverse, a la non competitivite du recours a l'energie nucleaire dans le dessalement des eaux et qu'un grand nombre d'aspects doivent etre soigneusement examines. (auteur)

  19. Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR); Developpement du design d'un assemblage de controle et analyse dynamique des reacteurs a neutrons rapides de quatrieme generation refroidis au gaz

    Energy Technology Data Exchange (ETDEWEB)

    Girardin, G.

    2009-07-09

    was paid to have each individual fuel sub-assembly and CA represented, in order to allow the analysis of local deformations of the 3D distributions of power and safety related parameters, such as the coolant, cladding and fuel temperatures. The validation of the coupled full core models was performed against reference ERANOS-VARIANT calculations. (author) [French] Le travail de recherche a ete mene dans le contexte du RNR-G de reference a 2400 MWth. Le but principal a ete de developper et de qualifier le design de l'assemblage de controle et le schema d'implantation correspondant a ce systeme. Le travail a ete realise en trois phases successives et complementaires: (1) la validation des outils neutroniques, (2) le developpement du design de l'assemblage de controle et les etudes statiques correspondantes, (3) les etudes du comportement dynamique du coeur durant des transitoires hypothetiques lies aux assemblages de controle. Pendant la premiere phase de la these, le reseau test de reference de PROTEUS utilise dans ces experiences, a ete reinterprete avec ERANOS et la bibliotheque nucleaire ajustee ERALIB1. De maniere complementaire, des calculs de references ont ete realises avec le code de Monte Carlo MCNPX, visant a verifier les resultats deterministes, et a analyser la sensibilite des resultats aux differentes modernes librairies. Pour les taux de reactions principaux, la nouvelle analyse du reseau de reference GCFR-PROTEUS donne generalement des resultats en bon accord - dans l'incertitude experimentale 1{sigma} - avec les resultats experimentaux, ainsi qu'avec les simulations de Monte Carlo. L'utilisation d'ERANOS-2.0/ERALIB1 comme outil neutronique de reference a ainsi pu etre demontree pour l'analyse du RNR-G. Dans une seconde phase de cette recherche, le design de l'assemblage de controle (AC) du GFR a ete developpe, base sur des calculs a caractere iteratif, neutroniques et thermo-hydrauliques. En premier, des

  20. The origin of cholesterol in chyle demonstrated by nuclear indicator methods; Origines du cholesterol du chyle mises en evidence par la methode des indicateurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Vyas, M

    1962-07-01

    In order to obtain information about the mechanism of the intestinal absorption of cholesterol, rats having a lymphatic abdominal fistula are used. The animals receive either 4-{sup 14}C- cholesterol subcutaneously or orally, or the 1-{sup 14}C acetate. The study of the specific radio-activities of the cholesterol in chyle, in serum, in the lining, and in the intestinal contents makes it possible to define the roles played by the transfer cholesterol from the serum, by the cholesterol synthesised intestinally, and by the absorption cholesterol, in the formations of the lymph and of the chylomicrons. A new theory is proposed for the mechanism of cholesterol absorption. (author) [French] Pour obtenir des renseignements concernant le mecanisme de l'absorption intestinale du cholesterol, on utilise des rats porteurs d'une fistule lymphatique abdominale. Les animaux recoivent soit du cholesterol 4-{sup 14}C par voie sous-cutanee ou par voie orale, soit de l'acetate 1-{sup 14}C. L'etude des radioactivites specifiques du cholesterol du chyle, du serum, de la paroi et du contenu intestinal permet de preciser les roles joues par le cholesterol de transfert d'origine serique, par le cholesterol de synthese intestinale et par le cholesterol d'absorption, dans la formation de la lymphe et des chylomicrons. Une theorie nouvelle concernant le mecanisme de l'absorption du cholesterol est proposee. (auteur)

  1. The fast breeder reactor Rapsodie (1962); Le reacteur rapide surregenerateur rapsodie (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Vautrey, L.; Zaleski, C.P. [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1962-07-01

    In this report, the authors describe the Rapsodie project, the French fast breeder reactor, as it stands at construction actual start-up. The paper provides informations about: the principal neutronic and thermal characteristics, the reactor and its cooling circuits, the main handling devices of radioactive or contaminated assemblies, the principles and means governing reactor operation, the purposes and locations of miscellaneous buildings. Rapsodie is expected to be critical by 1964. (authors) [French] Dans ce rapport, les auteurs font le point du projet RAPSODIE (reacteur francais surregenerateur a neutrons rapides), au moment du debut effectif de sa construction. On y trouvera decrits: les principales caracteristiques neutroniques et thermiques, le bloc pile et les circuits de refroidissement, les principaux moyens de manutention des ensembles actifs ou contamines, les principes et les moyens qui regissent la conduite du reacteur, les fonctions et l'implantation des divers batiments. La divergence de RAPSODIE est prevue pour 1964. (auteurs)

  2. Ultrasonic testing of canning tubes in stainless steel of the EL 4 reactor; Controle par ultrasons des tubes de gaine en acier inoxydable du reacteur EL 4

    Energy Technology Data Exchange (ETDEWEB)

    Prot, A.; Monnier, P. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    From all the methods possible for controlling thin cans the one chosen, for numerous reasons, vas that making use of ultrasonic techniques. A method has been developed which should make it possible to carry out a rapid and efficient industrial control of canning tubes, The reasons for the choice of the ultrasonic method are given in detail, together with the principles of the method and the actual control parameters. In the present state of our research, it should be possible to control at least 50 000 tubes a year. Improvements brought about in the details of the control technique itself should make it possible to increase this rate considerably. (authors) [French] Parmi toutes les methodes possibles de controle des gaines minces, le procede retenu pour de multiples raisons a ete celui faisant appel a la technique des ultrasons. Une methode a ete mise au point qui doit permettre un controle industriel rapide et efficace des tubes de gaine. Sont exposes en detail, les raisons du choix de la methode par ultrasons, les principes de cette methode et les parametres du controle proprement dit. Dans l'etat actuel de nos etudes la cadence devrait permettre le controle de 50000 tubes par an au minimum. Des ameliorations de detail portant sur la technique de controle elle-meme, doivent permettre d'accelerer tres notablement cette cadence. (auteurs)

  3. New reactor concepts; Nieuwe rectorconcepten - nouveaux reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A

    1998-11-01

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost.

  4. Physics of nuclear reactors; La physique des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Marguet, S. [Ecole Nationale Superieure de Risques Industriels de Bourges, 18 (France); Institut de Transfert de Technologie d' EDF, 92 - Clamart (France)

    2011-07-01

    This manual covers all the aspects of the science of neutron transport in nuclear reactors and can be used with great advantage by students, engineers or even reactor experts. It is composed of 18 chapters: 1) basis of nuclear physics, 2) the interactions of neutrons with matter, 3) the interactions of electromagnetic radiations and charged-particles with matter, 4) neutron slowing-down, 5) resonant absorption, 6) Doppler effect, 7) neutron thermalization, 8) Boltzmann equation, 9) calculation methods in neutron transport theory, 10) neutron scattering, 11) reactor reactivity, 12) theory of the critical homogenous pile, 13) the neutron reflector, 14) the heterogeneous reactor, 15) the equations of the fuel cycle, 16) neutron counter-reactions, 17) reactor kinetics, and 18) calculation methods in neutron scattering

  5. The influence of the (n, 2n) and (n, {alpha}) reactions of beryllium on the neutron balance in a BeO or Be moderated reactor and its consequences on the long term reactivity changes; Influence des reactions (n, 2n) et (n, {alpha}) du beryllium sur le bilan neutronique d'un reacteur modere a l'oxyde de beryllium ou au beryllium. Consequences sur l'evolution a long terme de la reactivite

    Energy Technology Data Exchange (ETDEWEB)

    Sahai, K.; Benoist, P.; Horowitz, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The reaction probabilities in an infinite and homogeneous medium of BeO or Be have been calculated from neutron cross-section curves, for a neutron produced with an energy distribution similar to a fission spectrum; the calculation shows that, after several elastic collisions, the neutron has yet an appreciable probability to undergo a reaction, in spite of the energy degradation in the spectrum due to each collision. This degradation has been calculated, taking into account of anisotropy of the collisions. The gain of the reactivity in a reactor has been obtained after correcting these probabilities for the attenuation of the flux of fission neutrons due to the inelastic scattering in the uranium. Finally, the calculation shows that in a power reactor, this gain of reactivity is in practice destroyed in a few years by the accumulation of poisonous nuclei such as Li{sup 6} and He{sup 3} following (n, {alpha}) reaction. (author) [French] Les probabilites de reaction en milieu infini et homogene de glucine (BeO) ou de beryllium ont ete calculees a partir des courbes de section efficace pour un neutron naissant suivant un spectre de fission; le calcul montre qu'apres plusieurs diffusions elastiques le neutron a encore une probabilite appreciable de subir une reaction, malgre la degradation du spectre a chaque diffusion; cette degradation a ete calculee en tenant compte de l'anisotropie du choc. Le gain de reactivite dans un reacteur a ensuite ete obtenu en corrigeant les probabilites en milieu homogene de l'effet l'attenuation du flux des neutrons de fission par les chocs inelastiques dans les barres d'uranium. Enfin, le calcul montre que, dans un reacteur de puissance, ce gain de reactivite est pratiquement detruit en peu d'annees par l'accumulation de noyaux poisons Li{sup 6} et He{sup 3} consecutive a la reaction (n, {alpha}). (auteur)

  6. Marine dispersion of radioactive elements susceptible to be released by the reactors of the Kursk damaged nuclear submarine; Dispersion marine des elements radioactifs susceptibles d'etre liberes par les reacteurs du sous-marin nucleaire accidente Koursk

    Energy Technology Data Exchange (ETDEWEB)

    Calmet, D. [CEA/Fontenay-aux-Roses, Inst. de Protection et de Surete Nucleaire, IPSN, 92 (France); Lepicard, S. [Centre d' Etude sur l' Evaluation de la Protection dans le Domaine Nucleaire, 92 - Fontenay-aux-Roses (France)

    2000-07-01

    The Kursk nuclear submarine has been damaged on the 12. august 2000. It is on the bottom of the Barents sea. The loss of watertightness of the two nuclear reactors, that contain some hundred of kilograms of fuel (enriched uranium) would lead to the release of radioactive elements. This report specifies the general conditions of circulation of water mass susceptible to be concerned by an eventual radioactive contamination. evaluates the times of water transit that could be contaminated and then evaluates the activities contributions susceptible to be added with time to the sea waters and sea products from the French coasts of Atlantic and Channel. (N.C.)

  7. The molten salt reactors (MSR) pyro chemistry and fuel cycle for innovative nuclear systems; Congres sur les reacteurs a sels fondus (RSF) pyrochimie et cycles des combustibles nucleaires du futur

    Energy Technology Data Exchange (ETDEWEB)

    Brossard, Ph. [GEDEON, Groupement de Recherche CEA CNRS EDF FRAMATOME (France); Garzenne, C.; Mouney, H. [and others

    2002-07-01

    In the frame of the studies on next generation nuclear systems, and especially for the molten salt reactors and for the integrated fuel cycle (as IFR), the fuel cycle constraints must be taken into account in the preliminary studies of the system to improve the cycle and reactor optimisation. Among the purposes for next generation nuclear systems, sustainability and waste (radio-toxicity and mass) management are important goals. These goals imply reprocessing and recycling strategies. The objectives of this workshop are to present and to share the different strategies and scenarios, the needs based on these scenarios, the experimental facilities available today or in the future and their capabilities, the needs for demonstration. It aims at: identifying the needs for fuel cycle based on solid fuel or liquid fuel, and especially, the on-line reprocessing or clean up for the molten salt reactors; assessing the state-of-the-art on the pyro-chemistry applied to solid fuel and to present the research activities; assessing the state-of-the-art on liquid fuels (or others), and to present the research activities; expressing the R and D programs for pyro-chemistry, molten salt, and also to propose innovative processes; and proposing some joint activities in the frame of GEDEON and PRACTIS programs. This document brings together the transparencies of 18 contributions dealing with: scenario studies with AMSTER concept (Scenarios, MSR, breeders (Th) and burners); fuel cycle for innovative systems; current reprocessing of spent nuclear fuel (SNF) in molten salts (review of pyro-chemistry processes (non nuclear and nuclear)); high temperature NMR spectroscopies in molten salts; reductive extraction of An from molten fluorides (salt - liquid metal extraction); electrochemistry characterisation; characterisation with physical methods - extraction coefficient and kinetics; electrolytic extraction; dissolution-precipitation of plutonium in the eutectic LiCl-KCl (dissolution and precipitation processes); cold salt: potentiality and preliminary results; TOPIC: redox control of MSR fuel (MSR: nominal operating conditions for the reprocessing process and redox control); technical aspects of R and D of some advanced non-aqueous reprocessing technologies for MSR systems (promising innovative separation and partitioning processes for the MSR fuel cycle); nominal operating conditions for MSR reprocessing process - data base needed and experiments for reprocessing validation; corrosion and materials for MSR and for pyro-chemistry processes; MSR reactor physics - dynamic behaviour; what safety principles for MSR? (MSR and integrated cycle (IFR) safety approach); experimental programmes in the frame of the SPHINX project of MS transmuter (programme of irradiated probes BLANKA, experimental facilities (MSR)); ISTC 1606 status - experimental study of molten salt technology for safe, low-waste and proliferation resistant treatment of radioactive waste and plutonium in accelerator-driven and critical systems. (J.S.)

  8. Exploitation continuation of Fessenheim nuclear plant nr 1 reactor after thirty years of operation; Poursuite d'exploitation du reacteur n.1 de la centrale nucleaire de fessenheim apres trente annees de fonctionnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    After having recalled the regulatory framework, this report indicates how the Fukushima accident has been taken into account by the French nuclear safety authority (ASN) for the decision of keeping on operating the Fessenheim nuclear plant. Then, after a general presentation of nuclear installations, the report describes some peculiarities of the Fessenheim power plant with respect to the other French nuclear plants. It comments and discusses various issues: reactor exploitation, fuel management, vessel exploitation, exploitation of the main secondary circuits, of the confinement enclosure, and of other equipment. It recalls significant events, exploitation rules, and modifications brought to the reactor. It gives a global assessment. The authors report the safety re-examination (approach, compliance examination, security re-assessment), controls performed during decennial inspection (main controls and tests, implementation of modifications foreseen by safety re-examination, significant events, monitoring by the ASN, reactor restarting after the third decennial inspection). Perspectives are then discussed for the ten following years in terms of maintenance policy, ageing management, reactor vessel serviceability, and additional actions within the frame of ageing management. The operation continuation is then discussed

  9. Thermal radiation modeling inside a degraded reactor core in presence of steam and water droplets; Modelisation du rayonnement thermique dans un coeur de reacteur nucleaire degrade en presence de vapeur et de gouttes d'eau

    Energy Technology Data Exchange (ETDEWEB)

    Chahlafi, Miloud

    2011-01-19

    This work aims at modelling thermal radiation in a nuclear reactor, in the course of a severe accident leading to its degradation. Because the reactor coolant is water, radiative heat transfer occurs in presence of steam and water droplets. The 3D geometry of a fuel bundle with 21 damaged rods has been characterized from {gamma}-tomography images. The degradation of the rods has been simulated in the experimental small-scale facility PHEBUS. The homogenized radiative properties of the considered configurations with a transparent fluid phase have been completely characterized by both the extinction cumulated distribution function G{sub ext} and the scattering phase functions p. G{sub ext} strongly differs from the exponential function associated with the Beer law and p strongly depends on both the incidence and the scattering directions. By using the radiative transfer equation generalized for non Beerian porous media by Taine et al. the radiative conductivity tensor has been first determined with a transparent fluid phase, by a numerical perturbation method. Only the diagonal radial and axial components of this tensor are not equal to zero. They have been fitted by a simple law only depending on the porosity, the specific area and the wall absorptivity. In a second step, a radiative transfer equation based on three temperatures is established. This model takes into account a semi transparent fluid phase by coupling the radiative properties of fluid and solid phases. The radiative properties of water steam and droplets are calculated respectively with the CK approach and Mie theory, in typical thermal hydraulics conditions of reactor accidents. The radiative fluxes verify the Fourier law and are characterized by radiative coupled conductivity tensors associated with the temperatures of each phase. The radiative powers exchanged between phases per unit volume are also calculated from this model. (author)

  10. Modeling of the thermal transfer inside a porous environment: application to nuclear reactors in accident situation; Modelisation du transfert thermique dans un milieu poreux: application aux reacteurs nucleaires en situation accidentelle

    Energy Technology Data Exchange (ETDEWEB)

    Rubiolo, P.R

    2000-03-01

    The purpose of this report is to simulate heat exchanges occurring by conduction, by convection and by radiating in a porous medium made up of opaque particles in a semi-transparent fluid. Usually the determination of the macroscopic equations is based on homogenization techniques, but in the case of a major accident, the complexity of the problem is so overwhelming that semi-empirical methods are used to determine macroscopic coefficients. The author develops a new method to determine these coefficients, this method is based on the calculation of different tensors: the equivalent conductivity tensor, the radiative conductivity tensor, the thermal conductivity tensor and the heat exchange coefficient (h{sub sf}) between the solid phase and the fluid one. The first chapter briefly describes energy, impulse and mass balances. In the case of the energy balance the solid phase is not supposed to be in thermal equilibrium with the liquid phase. The second chapter presents an application of the porous media method to a one-dimensional and stationary problem, this application to a simple problem gives an idea of the performance of the method. The model allowing the calculation of h{sub sf} is developed, it is a wide range model. The second chapter ends with the presentation of the model allowing the computing of the effective conductivity of fuel rods. A comparison between results given by this new method and other numeric calculations or experimental data coming from benchmarks is presented in the third chapter. This chapter ends with the simulation of a reactor core in accidental situation, 2 cases are presented: with and without the presence of water steam. (A.C.)

  11. Modeling of delayed strains of concrete under biaxial loadings. Application to the reactor containment of nuclear power plants; Modelisation des deformations differees du beton sous sollicitations biaxiales. application aux enceintes de confinement de batiments reacteurs des centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Benboudjema, F

    2002-12-15

    The prediction of delayed strains is of crucial importance for durability and long-term serviceability of concrete structures (bridges, containment vessels of nuclear power plants, etc.). Indeed, creep and shrinkage cause cracking, losses of pre-stress and redistribution of stresses, and also, rarely, the ruin of the structure. The objective of this work is to develop numerical tools, able to predict the long-term behavior of concrete structures. Thus, a new hydro mechanical model is developed, including the description of drying, shrinkage, creep and cracking phenomena for concrete as a non-saturated porous medium. The modeling of drying shrinkage is based on an unified approach of creep and shrinkage. Basic and drying creep models are based on relevant chemo-physical mechanisms, which occur at different scales of the cement paste. The basic creep is explicitly related to the micro-diffusion of the adsorbed water between inter-hydrates and intra-hydrates and the capillary pores, and the sliding of the C-S-H gel at the nano-porosity level. The drying creep is induced by the micro-diffusion of the adsorbed water at different scales of the porosity, under the simultaneous effects of drying and mechanical loadings. Drying shrinkage is, therefore, assumed to result from the elastic and delayed response of the solid skeleton, submitted to both capillary and disjoining pressures. Furthermore, the cracking behavior of concrete is described by an orthotropic elastoplastic damage model. The coupling between all these phenomena is performed by using effective stresses which account for both external applied stresses and pore pressures. This model has been incorporated into a finite element code. The analysis of the long-term behavior is also performed on concrete specimens and prestressed concrete structures submitted to simultaneous drying and mechanical loadings. (author)

  12. Neutronic modelling of the reflector for the calculation of pressurized water reactors: application to EPR; Modelisation neutronique du reflecteur pour le calcul des coeurs des reacteurs nucleaires a eau pressurisee: application a l'EPR

    Energy Technology Data Exchange (ETDEWEB)

    Sandrin, Ch.

    2010-04-15

    This PhD Thesis aims to achieve a method for the modelling of the reflector surrounding the core for neutronics core calculations. This method should consider the EPR reactor specificities (steel reflector) and the increased demand in precision. In neutronics core calculations, the reflector can be represented either by albedos boundary conditions (current ratios) or by one or several media, surrounding the core, characterised by homogenized parameters. Those parameters (cross sections and diffusion coefficients) should be obtained using equivalence so that they allow a good reproduction of the reference albedos in a representative situation. During this PhD, such an equivalence method has been developed in the APOLLO-2 code with the minimization of a functional of the differences between the reference albedos and those computed with the equivalent parameters. Because of the positiveness constraints, a local minimization, such as Newton-like methods, is not always possible and we have therefore also implemented a Particle Swarm Optimization Algorithm for more than two energy groups' problems. The parameters obtained have been used in two dimensions EPR core calculations with the CRONOS-2 code for various fuel loadings in two to eight groups diffusion. Those core calculation have been validated against reference Monte-Carlo calculations and against core calculations with albedos boundary conditions. In addition to the increased easiness of utilization, the implemented equivalence method has yielded an improvement of the results for the two groups calculation. With a higher energy groups number, the use of a unique equivalent reflector does not account correctly for the two dimensions effects; a modelling with different reflector meshes has improved the results. The modelling of the reflector by two dimensions albedos boundary conditions is the more suited for the representation of the boundary conditions and, therefore, should the two dimensions albedos calculation be developed in a deterministic code, it is the advocated method in the future. (author)

  13. Organic chemistry and radiochemistry: study of chemical interactions between iodine and paint of French nuclear reactor in a severe accident situation; Chimie organique et radiochimie. Etude des interactions chimiques iode-peinture dans un reacteur nucleaire (de type R.E.P.) en situation d'accident grave

    Energy Technology Data Exchange (ETDEWEB)

    Aujollet, Y. [Direction Generale de la Surete Nucleaire et de la Radioprotection, 75 - Paris (France)

    2005-01-01

    In Phebus (French in pile facility; PWR scale 1/5000) experiments, performed by the Institut de Radioprotection et de Surete Nucleaire, few quantities of organic iodides were registered after interaction between iodine and reactor containment paint. This study concerns all mechanisms of chemical reactions between iodine and the polymer of the paint in order to estimate the organic iodides released from the paint. At first, all the paint components had been identified. Several models of chemical sites of the polymer were synthesized and tested with iodine in different conditions of temperature and radiation. These experiments showed interactions between iodine and secondary or tertiary amines by charge transfer. In few cases, the complex of tertiary amines creates oxidation reactions. (author)

  14. Decontamination of nuclear liquid wastes using ion exchange. Case of the treatment of the water of the storage pond of the EDF Bugey 1 nuclear reactor; Decontamination d'effluents nucleaires par echange d'ions. Cas du traitement de l'eau de la piscine d'entreposage du reacteur nucleaire EDF Bugey-1

    Energy Technology Data Exchange (ETDEWEB)

    Doury-Berthod, M. [CEA Saclay, 91 - Gif-sur-Yvette (France). Institut National des Sciences et Techniques Nucleaires

    2006-12-15

    The paper explains in detail the works carried out in order to decontaminate before dismantling the water contained in a cooling pond where were stored spent nuclear fuels from the Bugey 1 reactor. The studies included laboratory tests, the design and the operation of pilot and industrial units. The process was based on the use of ion exchange resins on several steps in order to completely fix the contaminating elements, especially cesium, strontium and plutonium.The procedure applied and the detailed results are given. (authors)

  15. New modelling method for fast reactor neutronic behaviours analysis; Nouvelles methodes de modelisation neutronique des reacteurs rapides de quatrieme Generation

    Energy Technology Data Exchange (ETDEWEB)

    Jacquet, P.

    2011-05-23

    Due to safety rules running on fourth generation reactors' core development, neutronics simulation tools have to be as accurate as never before. First part of this report enumerates every step of fast reactor's neutronics simulation implemented in current reference code: ECCO. Considering the field of fast reactors that meet criteria of fourth generation, ability of models to describe self-shielding phenomenon, to simulate neutrons leakage in a lattice of fuel assemblies and to produce representative macroscopic sections is evaluated. The second part of this thesis is dedicated to the simulation of fast reactors' core with steel reflector. These require the development of advanced methods of condensation and homogenization. Several methods are proposed and compared on a typical case: the ZONA2B core of MASURCA reactor. (author) [French] Les criteres de surete qui regissent le developpement de coeurs de reacteurs de quatrieme generation implique l'usage d'outils de calcul neutronique performants. Une premiere partie de la these reprend toutes les etapes de modelisation neutronique des reacteurs rapides actuellement d'usage dans le code de reference ECCO. La capacite des modeles a decrire le phenomene d'autoprotection, a representer les fuites neutroniques au niveau d'un reseau d'assemblages combustibles et a generer des sections macroscopiques representatives est appreciee sur le domaine des reacteurs rapides innovants respectant les criteres de quatrieme generation. La deuxieme partie de ce memoire se consacre a la modelisation des coeurs rapides avec reflecteur acier. Ces derniers necessitent le developpement de methodes avancees de condensation et d'homogenisation. Plusieurs methodes sont proposees et confrontees sur un probleme de modelisation typique: le coeur ZONA2B du reacteur maquette MASURCA

  16. Specific schedule conditions for the formation of personnel of A or B category working in nuclear facilities. Option nuclear reactor; Cahier des charges specifiques pour la formation du personnel de categorie A ou B travaillant dans les installations nucleaires. Option reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document describes the specific dispositions relative to the nuclear reactor domain, for the formation to the conventional and radiation risks prevention of personnel of A or B category working in nuclear facilities. The application domain, the applicable documents, the liability, the specificity of the nuclear reactor and of the retraining, the Passerelle formation, are presented. (A.L.B.)

  17. Specific schedule conditions for the formation of personnel of A or B category working in nuclear facilities. Option nuclear reactor-borne; Cahier des charges specifiques pour la formation du personnel de categorie A ou B travaillant dans les installations nucleaires. Option reacteur nucleaire embarque

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document describes the specific dispositions relative to the nuclear reactor-borne domain, for the formation to the conventional and radiation risks prevention of personnel of A or B category working in nuclear facilities. The application domain, the applicable documents, the liability, the specificity of the nuclear reactor-borne and of the retraining, the Passerelle formation, are presented. (A.L.B.)

  18. {alpha} grain refining and metallurgical study of alloyed uranium, Sicral F1, used for fuel elements; Affinage du grain {alpha} et etude metallurgique de l'alliage d'uranium sicral F1 pour elements combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Magnier, P. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    This study was made to know more about grain refining in low alloyed uranium of composition not very different from SICRAL F 1. Alpha grain refining of fuel elements made of these alloys was studied after casting and quenching by the methods used for mass production. The author describes the effect: - of the metallurgical history before quenching: - casting - purity - rate of solidification - of quenching parameters: - annealing temperature before quenching - annealing time - quenching rate - of the composition of the alloy. For the graphite gas fuel elements of various dimensions, he suggests some modifications to give a better adaptation of fabrication to size. He describes the grain refining made during quenching and the {beta} -> {alpha} and {gamma} -> {alpha} transformation types. He proposes the use of a U-Fe-Si especially useful from the point of view of grain refining. (author) [French] Le but de l'etude est de determiner les facteurs metallurgiques favorables a l'affinage du grain {alpha} des alliages d'uranium a tres faibles teneurs en elements d'addition voisins du SICRAL F 1 au cours du cycle de fabrication et de trempe industrielle des elements combustibles nucleaires prepares avec ces alliages. L'auteur met en evidence l'influence: - de l'histoire metallurgique avant trempe: - coulee - teneur en impuretes - vitesse de solidification - des parametres de la trempe: - temperature de trempe - temps et maintien a cette temperature - vitesse de trempe - des variations de composition de l'alliage. Il envisage les modifications a apporter au cycle de fabrication du SICRAL F 1 de facon a l'adapter aux differentes geometries des elements combustibles des reacteurs de la filiere graphite-gaz. L'auteur presente a cette occasion les mecanismes de l'affinage du grain {alpha} par trempe dans les alliages d'uranium et les modes de transformation {beta} -> {alpha} et {gamma} -> {alpha} au cours de la trempe

  19. Nuclear energy; Le dossier du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Pierret, Ch. [Ministere de l' Industrie et de l' Amenagement du Territoire, 75 - Paris (France); Bacher, P.; Tanguy, P. [and others

    2001-11-01

    11 contributions written by experts are gathered in this document dedicated to nuclear energy (N.E): 1) could we live without N.E?, 2) do we have to fear N.E?, 3) a critical point of view on N.E, 4) the sanitary consequences of Chernobyl accident, 5) the impact of low radiation doses, 6) the management of a nuclear power plant, 7) the optimisation of wastes at The Hague facility, 8) the management of radioactive wastes in France, 9) the next generation of nuclear reactors, 10) N.E and public acceptance, and 11) is N.E the energy for the future? (A.C.)

  20. The nuclear refugees; Les refugies du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Linton, M.

    2011-06-15

    The authors propose a report on the various situations of people who had to be evacuated after the Fukushima accident. Along with examples of people who left their homes with taking with them a single object, the authors describe and comment how this evacuation occurred, the problems faced by the authorities for refugee reception and accommodation. This evacuation has been either organised or spontaneous. Hospitals had to be evacuated as well. Then, local authorities faced food shortage. Some animals have been saved, other starved to death. Dead animals are covered with lime. Dead bodies are decontaminated before being given back to families. Tests are regularly performed to assess people contamination. A second article discussed the bad news concerning the different Fukushima reactors with their melted cores. The geophysical aspects of the earthquake are evoked in a last article

  1. Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann-Boutron, F. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-06-15

    An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

  2. Development and validation of calculation schemes dedicated to the interpretation of small reactivity effects for nuclear data improvement; Developpement et validation de schemas de calcul dedies a l'interpretation des mesures par oscillation pour l'amelioration des donnees nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Gruel, A.

    2011-10-24

    afin d'obtenir des informations pertinentes sur les donnees nucleaires de base. L'enjeu de cette these est le developpement d'un schema de calcul de reference, dont les incertitudes sont clairement identifiees et quantifiees, permettant l'interpretation des mesures par oscillation. Dans ce document plusieurs methodes de calcul de ces faibles effets en reactivite sont presentees, basees sur des codes de calculs neutroniques deterministes et/ou stochastiques. Ces methodes sont comparees sur un benchmark numerique, permettant leur validation par rapport a un calcul de reference. Trois applications sont ici presentees dans le detail: une methode purement deterministe utilisant la theorie des perturbations exacte pour la qualification des sections efficaces des principaux produits de fission en REP, dans le cadre d'etudes sur l'estimation de la perte du reactivite du combustible au cours du cycle; une methode hybride, basee sur un calcul stochastique et la theorie des perturbations exacte, permet d'obtenir un retour precis sur les donnees nucleaires de bases d'isotopes, dans notre cas l'{sup 241}Am; et enfin, une troisieme methode, reposant sur un calcul perturbatif Monte Carlo, est utilisee pour une etude de conception

  3. 1: the atom. 2: radioactivity. 3: man and radiations. 4: the energy. 5: nuclear energy: fusion and fission. 6: the operation of a nuclear reactor. 7: the nuclear fuel cycle; 1: l'atome. 2: la radioactivite. 3: l'homme et les rayonnements. 4: l'energie. 5: l'energie nucleaire: fusion et fission. 6: le fonctionnement d'un reacteur nucleaire. 7: le cycle du combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This series of 7 digest booklets present the bases of the nuclear physics and of the nuclear energy: 1 - the atom (structure of matter, chemical elements and isotopes, the four fundamental interactions, nuclear physics); 2 - radioactivity (definition, origins of radioelements, applications of radioactivity); 3 - man and radiations (radiations diversity, biological effects, radioprotection, examples of radiation applications); 4 - energy (energy states, different forms of energy, characteristics); 5 - nuclear energy: fusion and fission (nuclear energy release, thermonuclear fusion, nuclear fission and chain reaction); 6 - operation of a nuclear reactor (nuclear fission, reactor components, reactor types); 7 - nuclear fuel cycle (nuclear fuel preparation, fuel consumption, reprocessing, wastes management). (J.S.)

  4. Storage of plugs and experimental devices from reactors; Stockage des bouchons et dispositifs experimentaux en provenance des reacteurs (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P.; Mestre, E. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    - Within the general programme of storage and treatment of radioactive waste produced by the various operations carried out in an atomic center, it is useful to consider separately the problem of certain waste from reactors, which, because of its size and physical nature, has to be stored with a view to being later treated and finally evacuated. The solution which we propose for this storage problem is presented in this paper. (authors) [French] - Dans le cadre du stockage et du conditionnement des dechets radioactifs provenant des diverses manipulations effectuees dans un centre atomique, il y a lieu de considerer a part certains dechets des reacteurs qui, par leur dimension et leur nature physique doivent etre stockes en vue de leur reprise ulterieure pour un conditionnement et une evacuation definitifs. La solution que nous avons apportee a ce stockage fait l'objet de l'expose qui suit. (auteurs)

  5. Study of diluting and absorber materials to control reactivity during a postulated core melt down accident in Generation IV reactors; Etude des materiaux sacrificiels absorbants et diluants pour le controle de la reactivite dans le cas d'un accidnet hypothetique de fusion du coeur de reacteurs de quatrieme generation

    Energy Technology Data Exchange (ETDEWEB)

    Plevacova, K.

    2010-12-16

    In order to limit the consequences of a hypothetical core meltdown accident in Generation IV Sodium Fast Reactors, absorber materials in or near the core, such as boron carbide B{sub 4}C, and diluting materials in the core catcher will be used to prevent recriticality within the mixture of molten oxide fuel and molten structures called corium. The aim of the PhD thesis was to select materials of both types and to understand their behaviour during their interaction with corium, from chemical and thermodynamic point of view. Concerning B{sub 4}C, thermodynamic calculations and experiments agree with the formation of two immiscible phases at high temperature in the B{sub 4}C - UO{sub 2} system: one oxide and one boride. This separation of phases can reduce the efficiency of the neutrons absorption inside the molten fuel contained in the oxide phase. Moreover, a volatilization of a part of the boron element can occur. According to these results, the necessary quantity of B{sub 4}C to be introduced should be reconsidered for postulated severe accident sequence. Other solution could be the use of Eu{sub 2}O{sub 3} or HfO{sub 2} as absorber material. These oxides form a solid solution with the oxide fuel. Concerning the diluting materials, mixed oxides Al{sub 2}O{sub 3} - HfO{sub 2} and Al{sub 2}O{sub 3} - Eu{sub 2}O{sub 3} were preselected. These systems being completely unknown to date at high temperature in association with UO{sub 2}, first points on the corresponding ternary phase diagrams were researched. Contrary to Al{sub 2}O{sub 3} - Eu{sub 2}O{sub 3} - UO{sub 2} system, the Al{sub 2}O{sub 3} - HfO{sub 2} - UO{sub 2} mixture presents only one eutectic and thus only one solidification path which makes easier forecasting the behaviour of corium in the core catcher. (author) [French] Resume: Afin de limiter les consequences d'un accident grave avec la fusion du coeur dans un reacteur a neutrons rapides de generation IV refroidi au sodium, la recriticite doit

  6. Security report on Siloe - the descriptive part. (1963); Rapport de surete de Siloe - partie descriptive (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Ageron, P.; Chatoux, J.; Denielou, G.; Jacquemain, M.; Mitault, G.; Robien, E. de; Rossillon, F. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1963-07-01

    This report is a full description of the site, the reactor, the building and the experimental facilities. It gives the nuclear, thermodynamic and hydrodynamic characteristics of the core. (authors) [French] Ce rapport decrit completement le site, le reacteur, les batiments et les installations experimentales. Il donne les caracteristiques nucleaires, thermodynamiques et hydrodynamiques du coeur. (auteurs)

  7. Modelisation de la synthese reactive de poudres ultrafines dans un reacteur a plasma thermique

    Science.gov (United States)

    Desilets, Martin

    La presente these s'inscrit dans le cadre de la modelisation mathematique des ecoulements a plasmas thermiques inertes et reactifs. Elle vise plus precisement a combler les lacunes des modeles existants en portant une attention particuliere aux phenomenes de transport multicomposant et a la prediction des transformations chimiques. Pour repondre a ces attentes et ainsi poursuivre le developpement dans ce domaine, un modele global a ete developpe. Il combine la resolution d'equations conservatives pour la masse, l'energie et le momentum. La generation d'un plasma inductif (h.f ) y est traitee au moyen d'equations representant les champs electromagnetiques. La nucleation et la croissance de poudres ultrafines sont incluses dans le modele via l'analyse des principaux moments de la distribution des tailles de particules. Enfin, tous les phenomenes physico-chimiques d'importance dans un milieu comme les plasmas thermiques, de meme que lem interactions, sont consideres. Le modele est applique ici a l'analyse de trois problematiques differentes et complementaires. La premiere concerne l'etude du melange gazeux d'un jet froid (He, N 2 ou O2), injecte au coeur d'une decharge d'argon/hydrogene ou d'argon/oxygene. La comparaison des predictions du modele avec des mesures experimentales obtenues par une sonde enthalpique permet une validation partielle de ce dernier. La deuxieme problematique a trait a l'etude numerique de la pyrolyse du methane en reacteur a plasma h.f. Elle met en evidence les difficultes de convergence de la methode numerique lorsque appliquee a la resolution d'ecoulements reactifs a haute temperature. Finalement, le dernier sujet aborde dans cette these, soit l'analyse systematique des principales conditions d'operation d'un reacteur h.f utilise pour la synthese reactive de poudres ultrafines de silicium, engage tous les elements theoriques du modele. Il implique en effet la decomposition thermique d'un precurseur gazeux, le tetrachlorure de silicium, la

  8. Study of the uniform corrosion of an aluminium alloy used for the fuel cladding of the Jules Horowitz experimental reactor; Etude de la corrosion uniforme d'un alliage d'aluminium utilise comme gainage du combustible nucleaire du reacteur experimental Jules Horowitz

    Energy Technology Data Exchange (ETDEWEB)

    Wintergerst, M. [CEA Saclay, Dept. des Materiaux pour le Nucleaire (DEN/DANS/DMN/SEMI), 91 - Gif-sur-Yvette (France)

    2008-07-01

    For the Jules Horowitz new material testing reactor, an aluminium base alloy, AlFeNi, will be used for the cladding of the fuel plates. Taking into account the thermal properties of the alloy and of its oxide, the corrosion of the fuel cans presents many problems. The aim of this thesis is to provide a growing kinetic of the oxide layer at the surface of the AlFeNi fuel can in order to predict the life time of fuel element. Thus the mechanism of degradation of the cladding will be describe in order to integrate the different parameters of the operating reactor. (A.L.B.)

  9. Study of the ruthenium fission-product behavior in the containment, in the case of a nuclear reactor severe accident; Etude du comportement du produit de fission ruthenium dans l'enceinte de confinement d'un reacteur nucleaire, en cas d'accident grave

    Energy Technology Data Exchange (ETDEWEB)

    Mun, Ch

    2007-03-15

    Ruthenium tetroxide is an extremely volatile and highly radio-toxic species. During a severe accident with air ingress in the reactor vessel, ruthenium oxides may reach the reactor containment building in significant quantities. Therefore, a better understanding of the RuO{sub 4}(g) behaviour in the containment atmosphere is of primary importance for the assessment of radiological consequences, in the case of potential releases of this species into the environment. A RuO{sub 4}(g) decomposition kinetic law was determined. Steam seems to play a catalytic role, as well as the presence of ruthenium dioxide deposits. The temperature is also a key parameter. The nature of the substrate, stainless steel or paint, did not exhibit any chemical affinities with RuO{sub 4}(g). This absence of reactivity was confirmed by XPS analyses, which indicate the presence of the same species in the Ru deposits surface layer whatever the substrates considered. It has been concluded that RuO{sub 4}(g) decomposition corresponds to a bulk gas phase decomposition. The ruthenium re-volatilization phenomenon under irradiation from Ru deposits was also highlighted. An oxidation kinetic law was determined. The increase of the temperature and the steam concentration promote significantly the oxidation reaction. The establishment of Ru behavioural laws allowed making a modelling of the Ru source term. The results of the reactor calculations indicate that the values obtained for {sup 106}Ru source term are closed to the reference value considered currently by the IRSN, for 900 MWe PWR safety analysis. (author)

  10. Numerical simulation and analysis of axial instabilities occurrence and development in turbomachines. Application to a break transient in a helium nuclear reactor; Simulation numerique et analyse du declenchement et du developpement des instabilites axiales dans les turbomachines: application a un transitoire de breche dans un reacteur nucleaire a helium

    Energy Technology Data Exchange (ETDEWEB)

    Tauveron, N

    2006-02-15

    The subject of the present work was to develop models able to simulate axial instabilities occurrence and development in multistage turbomachines. The construction of a 1D unsteady axisymmetric model of internal flow in a turbomachine (at the scale of the row) has followed different steps: generation of steady correlations, adapted to different regimes (off-design conditions, low mass flowrate, negative mass flow rate); building of a model able to describe transient behaviour; use of implicit time schemes adapted to long transients; validation of the model in comparison of experimental investigations, measurements and numerical results from the bibliography. This model is integrated in a numerical tool, which has the capacity to describe the gas dynamics in a complete circuit containing different elements (ducts, valves, plenums). Thus, the complete model can represent the coupling between local and global phenomena, which is a very important mechanism in axial instability occurrence and development. An elementary theory has also been developed, based on a generalisation of Greitzer's model. These models, which were validated on various configurations, have provided complementary elements for the validation of the complete model. They have also allowed a more comprehensive description of physical phenomena at stake in instability occurrence and development by quantifying various effects (inertia, compressibility, performance levels) and underlying the main phenomena (in particular the collapse and recovery kinetics of the plenum), which were the only retained in the final elementary theory. The models were first applied to academic configurations (compression system), and then to an innovative industrial project: a helium cooled fast nuclear reactor with a Brayton cycle. The use of the models have brought comprehensive elements to surge occurrence due to a break event. It has been shown that surge occurrence is highly dependent of break location and that surge development is very limited (no more than few seconds). It is also shown that in the case of a break event, the turbomachine can have a significant contribution to decay heat removal from the nuclear core. At last, such a device is autonomous for a certain time only, and that this time is sensitive to some parameters such as break location and back pressure value. (author)

  11. Study of a method of detection for natural carbon-14 using a liquid scintillator, recent variations in the natural radio-activity due to artificial carbon-14 (1963); Etude d'une methode de detection du carrons 14 naturel, utilisant un scintillateur liquide - variations recentes de l'activite naturelle dues au carbone 14 artificiel (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Leger, C. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-06-15

    Among the various natural isotopes of carbon, a radioactive isotope, carbon-14, is formed by the action of secondary neutrons from cosmic rays on nitrogen in the air. Until 1950, the concentration of this isotope in ordinary carbon underwent weak fluctuations of about 2-3 per cent. The exact measurement of this concentration 6 X 10{sup 12} Ci/gm of carbon, and of its fluctuations, are difficult and in the first part of this report a highly sensitive method is given using a liquid scintillator. Since 1950 this natural activity has shown large fluctuations because of the carbon-14 formed during nuclear explosions, and in the second part, the evolution in France of this specific activity of carbon in the atmosphere and biosphere is examined. In the last part is studied the local increase in carbon activity in the atmosphere around the Saclay site, an increase caused by the carbon-14 given off as C{sup 14}O{sub 2}, by the reactors cooled partially with exterior air. (author) [French] Parmi les differents isotopes naturels du carbone, un isotope radioactif, le carbone 14, est forme par l'action de neutrons secondaires due aux rayons cosmiques sir l'azote de l'air. Jusqu'en 1950, la concentration de cet isotope dans le carbone ordinaire est soumise a des fluctuations de faible amplitude, de l'ordre de 2 a 3 pour cent. Les mesures precises de cette concentration, 6. 10{sup -12} Ci/g de carbone, et de ses fluctuations sont delicates, et dans la premiere partie de ce rapport, on decrit une methode de detection a grande sensibilite utilisant un scintillateur liquide. Depuis 1950, cette activite naturelle subit des fluctuations importantes dues au carbone 14 forme lors des explosions nucleaires, et dans la seconde partie, on examine l'evolution en France de l'activite specifique du carbone de l'atmosphere et ce la biosphere. Dans la derniere partie, on etudie l'accroissement local de l'activite du carbone de l'air aux

  12. Dynamic method for the measurement of Young'S modulus. Application to nuclear graphites; Methode de mesure dynamique du module d'Young. Application aux graphites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Pattou, F.; Trutt, J.C

    1963-07-01

    A dynamic method has been developed for measuring Young's modulus and the rigidity modulus using the 'Forster Elastomat'. The principle consists in the determination of the resonance frequencies of graphite samples submitted to transverse, longitudinal, and torsional vibrations. The first two modes of vibration make it possible to calculate the elasticity modulus or the Young's modulus E, the third mode makes possible the calculation of the rigidity modulus G. The relationships from which the moduli E and G are measured are given. A systematic study has been made of graphite samples produced by extrusion or compression and submitted afterwards to one or several impregnations with pitch. For graphites made from the same coke by the same method, a linear relationship has been found for Young's modulus as a function of the apparent density. For the same apparent density, graphites made from different starting materials have generally different Young's moduli that bear a relationship to the crystalline characteristics of the material. The measurements of the rigidity modulus C made on different graphites also show the influence of crystallite orientation. (authors) [French] Une methode de mesure dynamique du module d'Young et du module de rigidite du graphite utilisant 'l'Elastomat Forster' a ete mise au point. Le principe consiste a determiner les frequences de resonance d'echantillons de graphite soumis a des vibrations transversales, longitudinales et de torsion. Les deux premiers modes de vibration permettent de calculer le module d'elasticite ou module d'Young E, le troisieme mode de vibration permet de calculer le module de rigidite G. Apres avoir decrit la methode de mesure, on rappelle les relations qui permettent de calculer les modules E et G. L'etude systematique d'echantillons de graphite, fabriques par filage ou pressage et ayant subi eventuellement une ou plusieurs impregnations au

  13. Activities report of the Nuclear Physics Department (CEN Saclay). 1 Oct 1966 - 30 Sep 1967; Compte rendu d'activite du Departement de Physique Nucleaire (CEN Saclay). 1 Oct 1966 - 30 Sep 1967

    Energy Technology Data Exchange (ETDEWEB)

    Cotton, E. [and others

    1967-07-01

    Three parts of the report treat the questions related to the tandem, the cyclotrons and the electrons linear accelerators, then two annexes give the role of publications in this year, and the list of scientific and technical personnel. In the area of Van de Graaff and cyclotrons, progress has been made in the realisation of particles identification systems and in the methods of data processing. The starting up of the trochoidal injection has allowed an improvement of the protons polarisation rate and the intensity increase by a factor 1000. [French] Trois parties traitent des questions concernant le tandem, les cyclotrons et les accelerateurs lineaires a electrons, puis deux annexes donnent la liste des publications de l'annee et la liste du personnel scientifique et technique. Dans le domaine des Van de Graaf et cyclotrons, il faut signaler les progres dans la realisation de systemes d identification de particules et dans les methodes de traitement de donnees. La mise en service de l injection trochoidale a permis une amelioration du taux de polarisation des protons et l'accroissement de l'intensite d un facteur 1000. (auteurs)

  14. Decree n. 2007-534 of the 4. april 2007 allowing the creation of the base nuclear installation named Flamanville 3, including a EPR type reactor, on the site of Flamanville (Manche); Decret no 2007-534 du 10 avril 2007 autorisant la creation de l'installation nucleaire de base denommee Flamanville 3, comportant un reacteur nucleaire de type EPR, sur le site de Flamanville (Manche)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-04-15

    This decree gives the authorization to EDF to create on the site of Flamanville a nuclear installation including a PWR type reactor for a power of 4500 MW and devoted to the electric production. This reactor will can use uranium oxide or a mixture of uranium oxide and plutonium oxide. Considerations concerning the safety are given, as well as the control of the impact of this exploitation on the populations and the environment. (N.C.)

  15. Analytic index for nuclear physicians uses; Repertoire analytique a l'usage des physiciens nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R.; Barloutaud, R.; Bernas, R.; Bretonneau, P.; Chaminade, R.; Cohen, R.; Conjeaud, M.; Cotton, E.; Faraggi, H.; Grjebine, T.; Joffre, H.; Laboulaye, H. de; Lesueur, C.; Leveque, A.; Moreau, J.; Naggiar, V.; Papineau, L.; Prugne, P.; Schuhl, C.; Studinowski, FJ.; Netter, F.; Raievski, V.; Valladas, G. [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Marty, N.; Renard, G. [College de France, Lab. de Chimie Nucleaire (France)

    The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of new publications, always more numerous and more varied. To remedy to this facts that we tried, in the service of Nuclear Physics of the CEA, to give to the documentation a character of a collective and systematized work. The present report covers the literature appeared between first January 1950 and first July 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le premier Janvier 1950 et le premier Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

  16. The use of tracers in the study of the ionic permeability of the nerve; Utilisation des indicateurs nucleaires dans l'etude de la permeabilite ionique du nerf

    Energy Technology Data Exchange (ETDEWEB)

    Guinnebault, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    The use of the radioactive tracers {sup 24}Na and {sup 42}K, and the electrophysiological fine study carried out on the plant Cephalopods nervous cells have made it possible, during ten years, to study the relationships between the electrical phenomena observed during the propagation of the nervous impulse and the ionic movements which occur at the cell membrane between the intra- and extra-cellular media. In the state of rest, the nerve fibres present a certain permeability towards sodium and potassium, a permeability which allows the renewal, from the extra-cellular medium, of the cations contained in the cytoplasm. At the moment of the passage of the nervous impulse, it is possible to demonstrate a temporary increase in the permeability towards the sodium which causes the entry of Na{sup +} ions into the nerve fibre, whilst, a few milliseconds later, the increase in the potassium permeability causes the departure of an equivalent quantity of K{sup +} ions. A recovery phase follows the passage of the nervous impulse, during which the original ionic conditions are re-established. If the potassium movements can be considered as passive, the expulsion of Na{sup +} requires, on the part of the cell, the use of a part of the metabolic energy. (author) [French] L'utilisation des indicateurs radioactifs {sup 24}Na et {sup 42}K, et l'etude electrophysiologique fine realisee sur des cellules nerveuses geantes de Cephalopodes a permis, depuis une dizaine d'annees, d'etudier les rapports entre les phenomenes electriques observes lors de la propagation de l'influx nerveux et les mouvements ioniques qui s'effectuent au niveau de la membrane cellulaire entre milieux intracellulaire et extracellulaire. A l'etat de repos, les fibres nerveuses possedent pour le sodium et le potassium, une permeabilite qui permet le renouvellement, a partir du milieu extracellulaire des cations contenus dans le cytoplasme. Au moment du passage de l

  17. Analysis of space and energy homogenization techniques for the solving of the neutron transport equation in nuclear reactor; Analyse des techniques d'homogeneisation spatiale et energetique dans la resolution de l'equation du transport des neutrons dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Magat, Ph

    1997-04-01

    Today neutron transport in PWR's core is routinely computed through the transport-diffusion(2 groups) scheme. This method gives satisfactory results for reactors operating in normal conditions but the 2 group diffusion approximation is unable to take into account interface effects or anisotropy. The improvement of this scheme is logically possible through the use of a simplified P{sub N} method (SP{sub N}) for the modeling of the core. The comparison between S{sub N} calculations and SP{sub N} calculations shows an excellent agreement on eigenvalues as well as on power maps. We can notice that: -) it is no use extending the development beyond P{sub 3}, there is no effect; -) the P{sub 1} development is adequate; and -) the P{sub 0} development is totally inappropriate. Calculations performed on the N4 core of the Chooz power plant have enabled us to compare diffusion operators with transport operators (SP{sub 1}, SP{sub 3}, SP{sub 5} and SP{sub 7}). These calculations show that the implementation of the SP{sub N} method is feasible but the extra-costs in computation times and memory are important. We recommend: SP{sub 5}P{sub 1} calculations for heterogeneous 2-dimension geometry and SP{sub 3}P{sub 1} calculations for the homogeneous 3-dimension geometry. (A.C.)

  18. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 2:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 14 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 16, 2011, at 2:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of all 6 reactors of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  19. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 18, 2011, 2:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 18 mars 2011 a 14 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 18, 2011, at 2:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  20. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:30 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du mardi 15 mars 2011 a 10h30

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 10:30 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  1. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 3:30 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 15 mars 2011 a 15h30

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 3:30 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  2. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 17, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 17 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 17, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  3. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 12, 2011, 8:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur servenu le 11 mars 2011. Point de situation du 12 mars 2011 a 20 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 12, 2011, at 8:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2 and 3 of the Fukushima I site is briefly presented with the progress of the accident management actions. The operation principles of a BWR-type reactor and of a PWR-type reactor are presented in appendix as well as the confinement principle specific to Mark I-type BWR reactors designed by General Electric. The meteorological forecasts of the day are presented in a figure. (J.S.)

  4. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 9:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 9 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 16, 2011, at 9:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  5. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 20, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 20 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 20, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  6. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 7:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 19 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 16, 2011, at 7:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  7. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 13, 2011, 7:00 PM status - updated at 11:00 PM; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 13 mars 2011 a 19 heures - Mis a jour a 23 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 13, 2011, at 7:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2 and 3 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  8. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 19, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 19 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 19, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  9. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 17, 2011, 3:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 17 mars 2011 a 15 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 17, 2011, at 3:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  10. Contribution to the study of several chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses; Contribution a l'etude de quelques nuisances chimiques au centre d'etudes nucleaires de Fontenay-aux-Roses

    Energy Technology Data Exchange (ETDEWEB)

    Megemont, C.; Grau, C. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-10-01

    From the checking of 2750 index cards of hazards, the study relates the distribution of the chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses. Those concerning the greatest number of agents in the Centre are classified according to the categories corresponding to the different conditions of working. Thus, the most important are put forward. Then, the authors rapidly make a review of hazards which may have some special interest because they appear more specific of the nuclear energy or because they are the most frequently noted on the index cards of hazards. The case of the tributylphosphate is studied more precisely. (authors) [French] A partir de l'examen de 2750 fiches de nuisances, l'etude porte sur la repartition des nuisances chimiques au Centre d'Etudes Nucleaires de Fontenay-aux-Roses. Celles qui concernent le plus grand nombre d'agents du Centre sont classees selon les categories correspondant aux differentes conditions de travail. Les plus importantes d'entre elles sont ainsi mises en evidence. | Les auteurs passent ensuite en revue, rapidement, les nuisances qui peuvent presenter un interet particulier soit parce qu'elles semblent plus specifiques de l'Energie Nucleaire, soit parce qu'on les rencontre le plus frequemment sur les fiches de nuisances. Le cas du tributylphosphate est envisage de facon plus detaillee. (auteurs)

  11. The International Atomic Energy Agency: orientations for the 21. century. Nuclear facilities exploitation: three questions to Remy Carle. The civil nuclear and the electric power generation in Germany. Usa: the electric power marker deregulation and the perspective of the nuclear energy. The situation of nuclear energy in Japan. Finland.. debate about the 5. reactor. The electronuclear development in China. The last act of the swedish nuclear saga. The Korean nuclear programme. The civil nuclear energy in Eastern Europe... in brief; L'Agence Internationale de l'Energie Atomique: orientations pour le 21. siecle. Exploitation des centrales nucleaires: trois questions a Remy Carle. Le nucleaire civil et la production d'electricite en Allemagne. Etats-Unis: la deregulation du marche de l'electricite et les perspectives du nucleaire. La situation du nucleaire au Japon. Finlande... sur fond de debat a propos du 5. reacteur. Le developpement electronucleaire de la Chine.

    Energy Technology Data Exchange (ETDEWEB)

    Carle, R.; Thiebaud, Ph. [CEA, Direction des Relations Interantionales, 75 - Paris (France); Heuraux, Ch.; Tinturier, B.; Lavergne, B. de [EDF, 75 - Paris (France); Forum Atomique Allemand, Bonn (Germany); Lavigne, J.J. [Ambassade de France au Japon (Japan); Soyer, B. [Ambassade de Chine en France (France); Edin, K.A. [Institut Politique et Social de Stockholm (Sweden); Chaucheprat, P. [Ambassade de France en Coree (Korea, Republic of)

    2000-04-01

    This issue is dedicated to nuclear programmes throughout the world. A few articles give an overview of the major trends of nuclear industry, from the standpoints of economy, industry, environment and international regulations. A few articles give an overview of the major trends of nuclear industry, from the standpoints of economy, industry, environment and international regulations. A few specific countries or groups of countries are then highlighted, together with a typical economic and political backgrounds. The countries dealt with are Germany, China, Korea, the U.S., Finland, Japan and Sweden. Some specific data are given on nuclear industry in Eastern Europe. (author)

  12. Statistical pulses generator. Application to nuclear instrumentation (1962); Generateur d'impulsions aleatoires. Application a l'instrumentation nucleaire (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Beranger, R. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    This report describes a random pulses generator adapted to nuclear instrumentation. After a short survey on the statistical nature of electronic signals, the different ways for generating pulses with a Poisson's time-distribution are studied. The final generator built from a gaseous thyratron in a magnetic field is then described. Several tests are indicated : counting-rate stability, Pearson's criterion, distribution of time-intervals. Applications of the generator in 'whole testing' of nuclear instrumentation are then indicated for sealers, dead time measurements, time analyzers. In this application, pulse-height spectrums have been made by Poissonian sampling of a recurrent or random low-frequency signal. (author) [French] Cette etude decrit un generateur d'impulsions aleatoires et ses applications a l'instrumentation nucleaire. Apres un bref rappel sur la nature statistique des signaux en electronique nucleaire, sont passes en revue les principaux moyens d'obtenir des impulsions distribuees en temps suivant une loi de Poisson. Le generateur utilisant un thyratron a gaz dans un champ magnetique est ensuite decrit; diverses methodes de test sont appliquees (stabilite du taux de comptage, criterium de Pearson, spectre des intervalles ds temps). Les applications du generateur a l'electronique nucleaire dans le domaine des 'essais globaux' sont indiques: test des echelles de comptage et mesure des temps morts, test des analyseurs en temps apres division du taux de comptage par une puissance de deux, test des analyseurs multicanaux en amplitude. Pour cette derniere application, on a realise des spectres d'amplitudes suivant une loi connue, par echantillonnage poissonien d'un signal basse frequence recurrent ou aleatoire. (auteur)

  13. Protection of zirconium and its alloys by metallic coatings; Protection du zirconium et de ses alliages par des revetements metalliques

    Energy Technology Data Exchange (ETDEWEB)

    Loriers, H.; Lafon, A.; Darras, R.; Baque, P. [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    At 600 deg. C in an atmosphere of carbon dioxide, zirconium and its alloys undergo corrosion which presents two aspects simultaneously: - formation of a surface layer of zirconia, - dissolution of oxygen in the alloy sub-layer leading to brittleness. The two phenomena greatly restrict the possibilities of using zirconium alloys as a canning material for fuel elements in CO{sub 2} cooled nuclear reactors. An attempt has thus been made to limit, and perhaps to suppress, the corrosion effects in zirconium under these conditions by protecting it with metallic coatings. A first attempt to obtain a protection using copper-based coatings did not produce the result hoped for. Aluminium coatings produced by vacuum evaporation, followed by a consolidating thermal treatment make it possible to prevent the formation of the zirconia layer, but they do not eliminate the hardening effect produced by oxygen diffusion. On the other hand, electrolytically produced chromium deposits whose adherence is improved by a thermal vacuum treatment, counteract both these phenomena simultaneously. A similar result has been obtained with coatings of molybdenum produced by the technique of high-frequency inductive plasma sputtering. The particular effectiveness of the last two types of coatings is due to their structures characterized by the existence of an adherent film of chromium or molybdenum in the free state. (authors) [French] Le zirconium et ses alliages subissent, en atmosphere de gaz carbonique vers 600 deg. C, une corrosion qui prend deux aspects simultanes: - formation d'une couche de zircone superficielle, - dissolution fragilisante de l'oxygene dans l'alliage sous-jacent. Ces deux phenomenes restreignent fortement les possibilites d'utilisation des alliages de zirconium comme materiaux de gaine d'elements combustibles pour reacteurs nucleaires refroidis par le gaz carbonique. Il a donc ete cherche a limiter, voire supprimer, les effets de la corrosion du

  14. Decision no. 2011-DC-0216 of the French nuclear safety authority from May 5, 2011, ordering the Laue Langevin Institute to proceed to a complementary safety evaluation of its basic nuclear facility (high flux reactor - INB no. 67) in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0216 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a l'Institut Laue Langevin (ILL) de proceder a une evaluation complementaire de la surete de son installation nucleaire de base (Reacteur a Haut Flux - INB n.67) au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the Laue Langevin Institute, operator of the high flux research reactor (RHF) of Grenoble (France). (J.S.)

  15. Origin of elements of the Uranium-235 family observed in the Ellez river near the EL-4 experimental nuclear reactor in dismantling (Monts d'Arree- Finistere department); Origine des elements de la famille de l'uranium-235 observes dans la riviere Ellez a proximite du reacteur nucleaire experimental EL4 en cours de demantelement (Mont d'Arree - departement du Finistere). Resultats et premiers constats annee 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    In a previous study which concerned the catchment basin of the harbour of Brest, the A.C.R.O. put in evidence a marking by artificial radioelements around the power plant of Brennilis which can be imputed without ambiguities to the nuclear installation. It also put in evidence abnormalities concerning the natural radioactivity which justifies this new study. In the area of the Monts d'Arree, actinium 227 ({sup 227}Ac), non born by its ascendents which are {sup 235}U and {sup 231}Pa is observed. This phenomenon is characterized by mass activities superior to these ones of {sup 235}U and able to reach these ones of {sup 238}U. Its presence corresponds with the drainage of the Ellez river since the former channel of radioactive effluents releases from the nuclear power plant EL-4 up to the reservoir Saint-Herblot situated 6 km downstream. The strongest values of radioactivity are registered near the disused power plant, at this place a relationship exists between the level of actinium 227 and this one of the artificial radioactivity as it exists a relationship with the decay products of radon exhaled from the subsoil ({sup 210}Pb). But its presence is not limited to a part of the Ellez river, it is equally observed in terrestrial medium, in places in priori not influenced by the direct liquid effluents of the power plant. This place is situated at more than 4 km and without any connection with the Ellez waters. At this stage of the study, it is not possible to answer with certainty the question of the origin of this phenomenon. A new reorientation is considered indispensable to clarify definitively the origin of this unknown phenomenon in the scientific publications and the environmental monitoring. (N.C.)

  16. Nuclear situation in Japan; La situation du nucleaire au Japon

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This analysis takes stock on the nuclear situation in Japan. It discusses the ambitious equipment program in collaboration with the France, the destabilization of the japanese nuclear industry following the accidents and the energy policy evolutions. It presents the projects of the japanese nuclear industry: the Monju reactor restart, the Pluthermal project, the reprocessing power plant of Rokkasho Mura, the new reactors, the russian weapons dismantling, the ITER site selection and the buy out of Westinghouse by Toshiba. (A.L.B.)

  17. The control of nuclear sector; Le controle du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The Asn is loaded with the control of the nuclear safety and the radiation protection in France: it provides this control, in the name of the state, to protect the workers, the patients, the public and the environment of the risks in relation with nuclear activities. The control is the core business of Asn. Asn so checks the nuclear basic installations (I.N.B.), since their conception until their dismantling, the pressure equipment specially conceived for these installations, the management of the radioactive waste as well as the transport of radioactive substances. Asn also checks all the industrial and research installations as well as the hospitals where are used ionizing radiations. It is a more recent profession there, because dating the reform of the control of the nuclear power of 2002, which constitutes that of the radiation protection. The first responsibility of the activities at risks falls to the one who begins them. This principle applies to all the sectors checked by Asn: an industrialist is responsible for the safety of the nuclear installations which he exploits, a doctor is responsible for the use of the ionizing radiations which he uses. (N.C.)

  18. Exit this way; Par ici la sortie du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This paper aims to inform the public on the nuclear power phaseout necessity. The fist part presents the hazards bound the nuclear activities, from the uranium mines to the radioactive wastes disposal and the reasons of a necessary phaseout. The second part recalls the historical aspects of the nuclear power implementation in the french energy policy and the today government attitude to value its choice. The last part presents the advantages of other energies sources and scenario of nuclear power phaseout. (A.L.B.)

  19. The nuclear fuel cycle; Le cycle du combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    After a short introduction about nuclear power in the world, fission physics and the French nuclear power plants, this brochure describes in a digest way the different steps of the nuclear fuel cycle: uranium prospecting, mining activity, processing of uranium ores and production of uranium concentrates (yellow cake), uranium chemistry (conversion of the yellow cake into uranium hexafluoride), fabrication of nuclear fuels, use of fuels, reprocessing of spent fuels (uranium, plutonium and fission products), recycling of energetic materials, and storage of radioactive wastes. (J.S.)

  20. Analytic catalog for the use of the nuclear physicists; Repertoire analytique a l'usage des physiciens nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R.; Barloutaud, R.; Bernas, R.; Chaminade, R.; Cohen, R.; Conjeaud, M.; Cotton, E.; Faraggi, H.; Grjebine, T.; Laboulaye, H. de; Lehmann, P.; Leveque, A.; Levi, C.; Moreau, J.; Naggiar, V.; Olkowsky, J.; Papineau, L.; Papineau, L.; Prugne, P.; Schuhl, C.; Szteinsznaider, D.; Tzara, C.; Valladas, G. [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires; Marty, N.; Renard, G. [College de France, Lab. de Chimie Nucleaire (France)

    1952-07-01

    The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of publications, always more numerous and more varied. To remedy to this problem, we tried, at the Nuclear Physics Services of the CEA, to give to the documentation the character of a collective and systematized work. The present report covers the literature appeared between January 1, 1950 and July 1, 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le 1 Janvier 1950 et le 1 Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

  1. Flica: a code for the thermodynamic study of a reactor or a test loop; Programme FLICA etude thermodynamique d'un reacteur ou d'une boucle d'essai

    Energy Technology Data Exchange (ETDEWEB)

    Fajeau, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    This code handles the thermal problems of water loops or reactor cores under the following conditions: High or low pressure, steady state or transient behavior, one or two phases - Three-dimensional thermodynamic study of the flow in cylindrical geometry - Unidimensional study of heat transfer in heating elements - Neutronic studies can be coupled and a schematic representation of the safety rod behavior is given. The number of cells described in a flow cross-section is presently less than 20. This code is the logical following of FLID and CACTUS of which it constitutes a synthesis. (author) [French] Ce code permet de traiter les problemes thermiques d'une boucle ou d'un coeur de reacteur a eau dans les conditions suivantes: - Haute ou basse pression, regime permanent ou transitoire, simple ou double phase - Etude thermodynamique de l'ecoulement a 3 dimensions dans une geometrie cylindrique - Etude unidimensionnelle du transfert de chaleur dans les masses chauffantes - Possibilite de couplage avec la neutronique (reacteur point) et d'une representation schematique des actions de securite. Ce code dans lequel le nombre de cellules decrites dans une section droite de l'ecoulement est actuellement limite a 20 est la suite logique des codes FLID et CACTUS dont il constitue la synthese. (auteur)

  2. French research in the field of nuclear agronomy; Les recherches francaises en agronomie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Guerin De Montgareuil, P. [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    , industrial firms, university laboratories scientific institutes. The role of the Commissariat a l'Energie Atomique is defined: on the one hand it supplies information and support, and on the other hand it takes charge of specifically nuclear aspects of the work. Its part in the field has recently found expression in the creation, within the Biology Department, of a Radio-agronomy Section; its objective are described,, as well as the, means placed att its disposal at the Centre d'etudes Nucleaires, Cadarache. (author) [French] On propose un bilan des travaux les plus significatifs effectues en France depuis la deuxieme conference internationale en matiere d'agronomie nucleaire et qui vont d'une recherche apparemment desinteressee a l'application la plus directe. Une telle differenciation recouvre de moins en moins, au fur et a mesure de l'evolution des programmes, la distinction qui est faite dans l'expose entre l'action biologique des rayonnements et les autres emplois des techniques nucleaires. C'est ainsi que les recherches do radiogenetique agricole sont poursuivies dans deux directions: d'un point de vue theorique et methodologique avec l'etude comparative de l'action des divers types de rayonnements, l'influence du debit de dose et de la temperature, l'action des agents mutagenes chimiques, la production de chimeres sous irradiation gamma; et d'autre part, sous un aspect pratique aboutissant a la creation de varietes nouvelles plus resistantes ou plus precoces (riz, mil, arachide). Les problemes de destruction des insectes (eradication) et de conservation des denrees sous irradiation se trouvent egalement abordes par des voies et avec des objectifs tres divers. A la demarche globale representee par une irradiation pure et simple (grains humides, pommes de terre...) sont parfois associees des etudes souvent originales, d'ordre biochimique ou microbiologique (par exemple: alteration de l

  3. Automation of nonlinear calculations in the theory of fusion reactor; Automatisation des calculs non lineaires dans la theorie des reacteurs a fusion

    Energy Technology Data Exchange (ETDEWEB)

    Braffort, P.; Chaigne, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    1) Introduction: The difficulties of the formulation of the equations of phenomena occurring during the operation of a fusion reactor are underlined. 2) The possibilities presented by analog computation of the solution of nonlinear differential equations are enumerated. The accuracy and limitations of this method are discussed. 3) The analog solution in the stationary problem of the measurement of the discharge confinement is given and comparison with experimental results. 4) The analog solution of the dynamic problem of the evolution of the discharge current in a simple case is given and it is compared with experimental data. 5) The analog solution of the motion of an isolated ion in the electromagnetic field is given. A spatial field simulator used for this problem (bidimensional problem) is described. 6) The analog solution of the preceding problem for a tridimensional case for particular geometrical configurations using simultaneously 2 field simulators is given. 7) A method of computation derived from Monte Carlo method for the study of dynamic of plasma is described. 8) Conclusion: the essential differences between the analog computation of fission reactors and fusion reactors are analysed. In particular the theory of control of a fusion reactor as described by SCHULTZ is discussed and the results of linearized formulations are compared with those of nonlinear simulation. (author)Fren. [French] 1) Introduction. On souligne les difficultes que presente la mise en equation des phenomenes mis en jeu lors du fonctionnement d'un reacteur a fusion. On selectionne un certain nombre d'equations generalement utilisees et on montre les impossibilites analytiques auxquelles on se heurte alors. 2) On rappelle les possibilites du calcul analogique pour la resolution des systemes differentiels non lineaires et on indique la precision de la methode ainsi que ses limitations. 3) On decrit esolution analogique du probleme statique de la mesure du confinement de la

  4. Modelling of heterogenous neutron leakages in a nuclear reactor; Modelisation des fuites heterogenes de neutrons dans un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Wohleber, X

    1997-11-17

    The TIBERE Model is a neutron leakage method based on B{sub 1} heterogeneous transport equation resolution. In this work, we have studied the influence of the reflection mode at the boundary of the assembly. In particular the White boundary condition has been implemented in the APOLLO2 neutron transport code. We have compared the two TIBERE kinds of boundary conditions (specular and white) with the classical B{sub 1} homogeneous leakage method in the modelling of some reactors. We have remarked the better capability of the TIBERE Model to compute voided assemblies. The white boundary condition is also able to compute a completely voided assembly and, besides, wins a factor 10 in CPU time in comparison with the specular boundary condition. These two heterogenous leakage formalisms have been tested on a partially voided experiment and have shown that the TIBERE Model can compute this kind of situation with a greater precision than the classical B{sub 1} homogeneous leakage method, and with a shorter computational time. (author)

  5. Can a nuclear reactor operate for 100 years?; Un reacteur nucleaire peut-il fonctionner cent ans

    Energy Technology Data Exchange (ETDEWEB)

    Hertel, O.

    2010-06-15

    The TWR (Travelling Wave Reactor) concept was invented in the fifties, then forgotten and it reappeared in 2001 but it was considered too immature to be selected for the fourth generation of nuclear reactors, now an American company 'Terrapower' proposes one whose design is given in the article. This TWR operates with depleted uranium, only the lower part of the fuel rod involves uranium fuel with a civil enrichment ratio (less that 20%). The lower part of the fuel will ignite the fission reaction and enrich the part of fuel just above through neutron absorption. The burning part of the fuel will move up progressively. The main advantage of this reactor is that it can operate for decades without maintenance nor fuel loading. The principle is right on the paper but requires huge technological work to select materials and systems that will be able to withstand decades of operation time in harsh conditions. (A.C.)

  6. Nuclear fuel: from the mine to the reactor. Part. 1; Les combustibles nucleaire: de la mine au reacteur (1. partie)

    Energy Technology Data Exchange (ETDEWEB)

    Maillard, D. [Direction Generale de l' Energie et des Matieres Premieres, Direction du Gaz, de l' Electricite et du Charbon, (STEEGB), 75 - Paris (France); Dujardin, Th. [OCDE, 92 - Issy les Moulineaux (France); Capus, G.; Durante, P.; Devos, L.; Canat, J.N. [AREVA NC, 13 --Saint-Paul-lez-Durance (France); Durret, L.F. [AREVA, Unit Enrichissement (United States); Delevallee, C. [AREVA, FBFC, 26 - Romans (France); Aullo, M.; Alonsa, J. [ENUSA, Industrias Avanzadas (Spain); Chapin, D.; Bellanger, Ph.; Buechel, R. [Westinghouse Electric Company (United States); Blanc, M. [Westinghouse Electric Company (Sweden)

    2006-07-15

    This issue contains a selection of articles from the S.F.E.N. convention 2006, held in Paris, June 13 and 14, 2006, which was dedicated to nuclear fuel. the second part will be published in R.G.N. 5 2006. (author)

  7. Inception and evolution of Oklo natural nuclear reactors; Genese et evolution des reacteurs nucleaires fossiles d'Oklo

    Energy Technology Data Exchange (ETDEWEB)

    Bentridi, Salah-Eddine [UMR 7517, laboratoire d' hydrologie et de geochimie de Strasbourg, CNRS/universite de Strasbourg, 1, rue Blessig, 67084 Strasbourg (France); Laboratoire de l' energie et des systemes intelligents, CUKM, route de Theniet, El-Hed 44225 (Algeria); Gall, Benoit [UMR 7178, institut pluridisciplinaire Hubert-Curien, CNRS-IN2P3/universite de Strasbourg, 23, rue du Loess, 67037 Strasbourg (France); Gauthier-Lafaye, Francois [UMR 7517, laboratoire d' hydrologie et de geochimie de Strasbourg, CNRS/universite de Strasbourg, 1, rue Blessig, 67084 Strasbourg (France); Seghour, Abdeslam [Centre de recherches nucleaires d' Alger - CRNA, 2, boulevard Frantz-Fanon, 16000 Alger (Algeria); Medjadi, Djamel-Eddine [Ecole normale superieure, Vieux-Kouba, 16050 Alger (Algeria)

    2011-11-15

    The occurrence of more than 15 natural nuclear Reactor Zones (RZ) in a geological environment remains a mystery even 40 years after their discovery. The present work gives for the first time an explanation of the chemical and physical processes that caused the start-up of the fission reactions with two opposite processes, uranium enrichments and progressive impoverishment in {sup 235}U. Based on Monte-Carlo neutronics simulations, a solution space was defined taking into account realistic combinations of relevant parameters acting on geological conditions and neutron transport physics. This study explains criticality occurrence, operation, expansion and end of life conditions of Oklo natural nuclear reactors, from the smallest to the biggest ones. (authors)

  8. Modelling of heterogenous neutron leakages in a nuclear reactor; Modelisation des fuites heterogenes de neutrons dans un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Wohleber, X

    1997-11-17

    The TIBERE Model is a neutron leakage method based on B{sub 1} heterogeneous transport equation resolution. In this work, we have studied the influence of the reflection mode at the boundary of the assembly. In particular the White boundary condition has been implemented in the APOLLO2 neutron transport code. We have compared the two TIBERE kinds of boundary conditions (specular and white) with the classical B{sub 1} homogeneous leakage method in the modelling of some reactors. We have remarked the better capability of the TIBERE Model to compute voided assemblies. The white boundary condition is also able to compute a completely voided assembly and, besides, wins a factor 10 in CPU time in comparison with the specular boundary condition. These two heterogenous leakage formalisms have been tested on a partially voided experiment and have shown that the TIBERE Model can compute this kind of situation with a greater precision than the classical B{sub 1} homogeneous leakage method, and with a shorter computational time. (author)

  9. Improvements in gas supply systems for heavy-water moderated reactors; Etudes de perfectionnements aux systemes d'alimentation en gaz d'un reacteur modere a l'eau lourde

    Energy Technology Data Exchange (ETDEWEB)

    Aubert, G.; Hassig, J.M.; Laurent, N.; Thomas, B. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    In a heavy-water moderated reactor cooled by pressurized gas, an important problem from the point of view, of the reactor block and its economics is the choice of the gas supply system. In the pressure tube solution, the whole of the reactor block structure is at a relatively low temperature, whereas the gas supply equipment is at that of the gas, which is much higher. These parts, through which passes the heat carrying fluid have to present as low a resistance as possible to it so as to avoid costly extra blowing power. Finally, they may only be placed in the reactor block after it has been built; the time required for putting them in position should therefore not be too long. The work reported here concerns the various problems arising in the case of each channel being supplied individually by a tube at the entry and the exit which is connected to a main circuit made up of large size collectors. This individual tubing is sufficiently flexible to absorb the differential expansion and the movement of its ends without stresses or prohibitive reactions being produced; the tubing is also of relatively short length so as to reduce the pressure head of the pressurized gas outside the channels; the small amount of space taken up by the tubing makes it possible to assemble it in a manner which is satisfactory from the point of view both of the time required and of the technical quality. (authors) [French] Dans un reacteur modere a l'eau lourde et refroidi au gaz sous pression, un probleme important du point de vue du trace du bloc pile et de son economie est le choix du systeme d'alimentation en gaz. Pour une solution a tubes de force, l'ensemble des structures du bloc reacteur est a temperature relativement faible, alors que les organes d'alimentation en gaz sont a celle, notablement plus elevee, du gaz. Ces organes, traverses par le debit du caloporteur, doivent lui opposer le minimum de resistance afin de ne pas necessiter un supplement onereux de

  10. [Project for] a high-flux extracted neutron beam reactor [for physicists]; Un [projet de] reacteur a haut flux et faisceaux sortis [pour physiciens

    Energy Technology Data Exchange (ETDEWEB)

    Ageron, P. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    the beam extraction tubes and the experimental equipment which can support doses much higher than the ones which are biologically permissible. The final part of the communication describes the studies carried out on the realization of a liquid hydrogen cold sink, one of the most important experimental devices envisaged. (authors) [French] Les besoins francais en canaux pour sortie de neutrons de differentes energies sont brievement indiques. L'interet bien connu des neutrons froids (plus de 4 Angstroem) est souligne. Les grandes lignes d'un reacteur permettant de satisfaire les physiciens sont esquissees. Ce sont les suivantes: 1 - Flux dans l'eau lourde du reflecteur de l'ordre de 7. 10{sup 14} thermiques. 2 - Souplesse d'emploi maximum obtenue par: - separation physique du coeur et du reflecteur, - independance des experiences entre elles, - possibilite de modification, sans interruption notable du fonctionnement de la pile, des experiences physiques jusqu'a - et y compris - la nature du reflecteur utilise, - reduction au minimum des protections fixes; emploi largement generalise des protections liquides (eau) et fluidisees (sables). 3 - Continuite technologique aussi grande que possible avec les reacteurs de recherche francais existant ou en construction (SILOE, PEGASE, OSIRIS). 4 - Surete de fonctionnement recherche par la simplicite de conception. 5 - Minimisation des frais de construction. La reduction des frais d'exploitation est recherchee plutot indirectement par la simplicite des solutions et la reduction du personnel d'exploitation, que directement par la minimisation des consommations d'elements combustibles et d'energie. La solution preconisee peut etre decrite comme un reacteur de type piscine a coeur clos, non pressurise, tres sous modere par l'eau legere de refroidissement. Entourant le reacteur, se trouvent un certain nombre de 'canaux boucles' comprenant chacun: - une portion du

  11. Decision no. 2011-DC-0220 of the French nuclear safety authority from May 5, 2011, ordering the FBFC company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0220 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a FBFC de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the FBFC (Franco-Belge de Fabrication du Combustible), a daughter fuel fabrication company of Areva NC (France). (J.S.)

  12. Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

    Energy Technology Data Exchange (ETDEWEB)

    Le Coroller, Y. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-09-01

    A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux

  13. Siloette, Siloe mock-up; Siloette, modele nucleaire de siloe

    Energy Technology Data Exchange (ETDEWEB)

    Delcroix, V.; Jeanne, G.; Mitault, G.; Schulhof, P. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    Siloette is the Siloe mock-up. The main installations are described: various tanks, building, auxiliaries, control systems... Precis ions are given about precautions taken for using spent fuel elements. (authors) [French] Siloette est le modele nucleaire de SILOE. On decrit ses diverses installations: bassins, batiments, auxiliaires, controle... Des precisions sont donnees sur les precautions prises pour y utiliser des elements uses. (auteurs)

  14. Continuous dissolution of irradiated nuclear fuels; Dissolution continue des combustibles nucleaires irradies

    Energy Technology Data Exchange (ETDEWEB)

    Michel, P.; Talmont, X.; Tarnerq, M. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1967-07-01

    In the case of the continuous dissolution of nuclear fuels, the equations for the calculation of the fuel concentration of the solution flowing out of a pot dissolver have been written. Nitric acid feed flow rates have been calculated in order to obtain an adjusted solution when starting or stopping a dissolution, or when changing the number of rods introduced per hour. Then some transient states brought on by perturbations, have been studied: a) sudden change in nitric acid flow rate; b) continuous drift of the latter; c) sudden change in nitric acid feed concentration; d) transition from a fuel concentration to another by changing the flow rate of nitric acid feed. It has been shown that some transient states cannot be solved with general equations. Computer calculation programs would be probably more useful. (authors) [French] L'etude se rapporte a la dissolution dans l'acide nitrique des combustibles nucleaires irradies, en vue de la recuperation de la matiere fissile qu'ils contiennent. On a etabli, dans le cas de la dissolution continue, les differentes equations permettant le calcul de la concentration en combustible a la sortie d'un dissolveur du type 'marmite'. On a etudie les regimes du debit d'alimentation en acide nitrique a imposer lors du demarrage, de l'arret d'une dissolution, ou lors d'un changement de cadence d'introduction des barreaux, de facon a obtenir une solution ajustee. On a etudie ensuite differents regimes transitoires consecutifs a des perturbations: changement brusque du debit d'acide d'alimentation, derive continue de ce debit, changement brusque de la concentration de l'acide d'alimentation, passage d'une concentration en combustible a une autre par changement du debit d'acide d'alimentation. On a pu montrer que certains regimes transitoires ne peuvent se traiter par des equations generales, et necessiteraient plustot l'etablissement d

  15. Study of the origin of elements of the uranium-235 family observed in excess in the vicinity of the experimental nuclear EL4 reactor under dismantling. Lessons got at this day and conclusions; Etude de l'origine des elements de la famille de l'uranium-235 observes en exces dans les environs du reacteur nucleaire experimental EL4 en cours de demantelement. Enseignements retires a ce jour et conclusion

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This study resumes the discovery of an excess of actinium 227 found around by EL4 nuclear reactor actually in dismantling. The search for the origin of this excess revealed a real inquiry of investigation during three years. Because a nuclear reactor existed in this area a particular attention will have concerned this region. The doubt became the line of conduct to find the answer to the human or natural origin of this excess. Finally and against any evidence, it appears that the origin of this phenomenon was natural, consequence of the particular local geology. The detail of the different investigations is given: search of a possible correlation with the composition of elevations constituent of lanes, search (and underlining) of new sites in the surroundings of the Rusquec pond and the Plouenez station, study of the atmospheric deposits under winds of the nuclear power plant and in the east direction, search of a possible relationship with the gaseous effluents of the nuclear power plant in the past, historical study of radioactive effluents releases in the fifty last years by the analysis of the sedimentary deposits in the Saint-Herbiot reservoir, search of a possible correlation between the excess of actinium 227 and the nuclear power plant activity; search of a possible correlation with a human activity without any relationship with the nuclear activities, search of a correlation with the underground waters, search of a correlation with the geological context, collect of information on the possible transfers in direction of the food chain, determination of the radiological composition of the underground waters ( not perturbed by human activity), search of the cause of an excess of actinium 227 in the old channel of liquid effluents release of the nuclear power plant. The results are given and discussed. And contrary to all expectations the origin of the excess of actinium 227 is completely natural. (N.C.)

  16. General phenomenology of underground nuclear explosions; Phenomenologie generale des explosions nucleaires souterraines

    Energy Technology Data Exchange (ETDEWEB)

    Derlich, S.; Supiot, F. [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    An essentially qualitatively description is given of the phenomena related to underground nuclear explosions (explosion of a single unit, of several units in line, and simultaneous explosions). In the first chapter are described the phenomena which are common to contained explosions and to explosions forming craters (formation and propagation of a shock-wave causing the vaporization, the fusion and the fracturing of the medium). The second chapter describes the phenomena related to contained explosions (formation of a cavity with a chimney). The third chapter is devoted to the phenomenology of test explosions which form a crater; it describes in particular the mechanism of formation and the different types of craters as a function of the depth of the explosion and of the nature of the ground. The aerial phenomena connected with explosions which form a crater: shock wave in the air and focussing at a large distance, and dust clouds, are also dealt with. (authors) [French] On donne une description essentiellement qualitative des phenomenes lies aux explosions nucleaires souterraines (explosion d'un seul engin, d'engins en ligne et explosions simultanees). Dans un premier chapitre sont decrits les phenomenes communs aux explosions contenues et aux explosions formant un cratere (formation et propagation d'une onde de choc provoquant la vaporisation, la fusion et la fracturation du milieu). Le deuxieme chapitre decrit les phenomenes lies aux tirs contenus (formation d'une cavite et d'une cheminee). Le troisieme chapitre est consacre a la phenomenologie des tirs formant un cratere et decrit notamment le mecanisme de formation et les differents types de crateres en fonction de la profondeur d'explosion et de la nature du terrain. Les phenomenes aeriens lies aux explosions formant un cratere: onde de pression aerienne et focalisation a grande distance, nuages de poussieres, sont egalement abordes. (auteurs)

  17. French research in the field of nuclear agronomy; Les recherches francaises en agronomie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Guerin De Montgareuil, P. [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    , industrial firms, university laboratories scientific institutes. The role of the Commissariat a l'Energie Atomique is defined: on the one hand it supplies information and support, and on the other hand it takes charge of specifically nuclear aspects of the work. Its part in the field has recently found expression in the creation, within the Biology Department, of a Radio-agronomy Section; its objective are described,, as well as the, means placed att its disposal at the Centre d'etudes Nucleaires, Cadarache. (author) [French] On propose un bilan des travaux les plus significatifs effectues en France depuis la deuxieme conference internationale en matiere d'agronomie nucleaire et qui vont d'une recherche apparemment desinteressee a l'application la plus directe. Une telle differenciation recouvre de moins en moins, au fur et a mesure de l'evolution des programmes, la distinction qui est faite dans l'expose entre l'action biologique des rayonnements et les autres emplois des techniques nucleaires. C'est ainsi que les recherches do radiogenetique agricole sont poursuivies dans deux directions: d'un point de vue theorique et methodologique avec l'etude comparative de l'action des divers types de rayonnements, l'influence du debit de dose et de la temperature, l'action des agents mutagenes chimiques, la production de chimeres sous irradiation gamma; et d'autre part, sous un aspect pratique aboutissant a la creation de varietes nouvelles plus resistantes ou plus precoces (riz, mil, arachide). Les problemes de destruction des insectes (eradication) et de conservation des denrees sous irradiation se trouvent egalement abordes par des voies et avec des objectifs tres divers. A la demarche globale representee par une irradiation pure et simple (grains humides, pommes de terre...) sont parfois associees des etudes souvent originales, d'ordre biochimique ou microbiologique (par exemple: alteration de l

  18. Back end of the nuclear fuel cycle; Aval du cycle du combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Dognon, J.P.; Rabbe, C.; Beudaert, Ph.; Lamare, V.; Wipff, G.; Moisy, Ph.; Charrin, N.; Blanc, P.; Den Auwer, Ch.; Revel, R.; Charbonnel, M.C.; Presson, M.T.; Cau Dit Coumes, C.; Chopin-Dumas, J.; Devisme, F.; Rat, B.; Hill, C.; Guillaneux, D.; Madic, C.; Carrera, A.; Dozol, J.F.; Rouquette, H.; Allain, F.; Virelizier, H.; Moulin, Ch.; Lemort, F.; Orlhac, X.; Fillet, C.; Carpena, J.; Advocat, T.; Leturcq, G.; Lacombe, J.; Bonnetier, A.; Ribet, I.; Poitou, S.; Richaud, D.; Fiquet, O.; Gramondi, P.; Massit, H.; Meyer, D.; Conocar, O.; Pettier, J.L.; Raphael, T.; Bouniol, P.; Sercombe, J.; Badouix, P.; Adenot, F.; Le Bescop, P.; Mazoin, C.; Motellier, S.; Charles, Y.; Richet, C.; Ayache, R.; Pitsch, H.; Ly, J.; Beaucaire, C.; Devol-Brown, I.; Libert, M.F.; Besnainou, B

    1999-07-01

    In this chapter of the DCC 1999 scientific report, the following theoretical studies are detailed: electronic structure of lanthanides or actinides complexes, forecasting of the stoichiometry of europium nitrate complexes, actinides aqueous solutions analytical and thermodynamical chemistry, actinides complexes structural determination. It also provides experimental studies: actinides and lanthanides separation, radioactive wastes processing and conditioning, plasma torch vitrification process, simulation of the wastes packages characterization, wastes storage with concrete behaviour and biodegradation. (A.L.B.)

  19. Iranian nuclear power and international law; La question du nucleaire iranien au regard du droit international

    Energy Technology Data Exchange (ETDEWEB)

    Aivo, G. [Centre de droit international, 75 - Paris (France)

    2006-07-15

    Does the Iranian programme violate the Non-Proliferation Treaty (NPT)? Iran is a signatory to the NPT and whilst certainly within its rights in developing civil nuclear energy, this is not so for the development of nuclear weapons in order to become a regional power which Iran is already not far from becoming. In the face of diverging opinions among the major interested parties (including the UN, United States, EU, Russia and China), how might this crisis be resolved? (author)

  20. Decision nr 2011-DC-0231 of the 4 July 2001 by the ASN specifying to EDF - limited company (EDF-SA) - the additional specifications applicable to the Fessenheim (Haut-Rhin) electronuclear site according to the conclusions of the third safety re-examination of reactor nr 1 of the nr 75 INB; Decision de l'Autorite de surete nucleaire n. 2011-DC-0231 du 4 juillet 2011 fixant a Electricite de France - Societe Anonyme (EDF-SA) les prescriptions complementaires applicables au site electronucleaire de Fessenheim (Haut Rhin) au vu des conclusions du troisieme reexamen de surete du reacteur n.1 de l'INB n.75

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document defines the specifications EDF must comply with for the exploitation of the Fessenheim reactor nr 1. The specifications concern the safety policy and management for operations submitted to a declaration or to an agreement by the ASN, the management of accident risks (use of radioactive materials or susceptible to generate a nuclear reaction, other risks), the management and elimination of wastes and used fuels in a basic nuclear installation (waste and used fuel warehousing), the management of accidental chemical pollutions, the management of water sampling and effluent releases, the production of wastes within the installation

  1. 1. round table - Spent fuels composition. Back-end of the fuel cycle and reprocessing, plutonium and other nuclear materials management. 2. round table - Separation-transmutation. 3. round table - Scenarios for a long term inventory of nuclear materials and wastes; 1. table ronde - La composition des combustibles uses. L'aval du combustible et le retraitement, la gestion du plutonium et des autres matieres nucleaires. 2. table ronde - Separation-transmutation. 3. table ronde - Scenarii pour un inventaire des matieres et des dechets nucleaires a LT

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the round table debates which took place at Paris on the reprocessing of spent fuels. Three aspects are discussed: the risks linked with the recovery of valorizable materials, the economical viability of the separation/transmutation option, and the future of the nuclear option in the French energy policy. Six presentations (transparencies) are attached with these proceedings which treat of: the reprocessing/recycling to the test, perspectives of future wastes, present day wastes/valorizable materials and future scenarios, critical analysis scenarios, why reprocessing spent fuels?, processing of spent fuels and recycling, separation and transmutation of long-lived radioactive wastes, thorium-uranium cycle. (J.S.)

  2. Presentation of the Jules Horowitz reactor; Presentation du reacteur Jules Horowitz

    Energy Technology Data Exchange (ETDEWEB)

    Dupuy, J.P. [AREVA-Technicatome, 13 - Aix en Provence (France); Perotto, G. [AREVA Framatome ANP, 92 - Paris La Defense (France); Ithurrald, G. [Electricite de France (EDF), 13 - Aix en Provence (France)

    2005-07-01

    The concepts on which the RJH reactor has been designed are: -) flexibility: the reactor must be able to give experimental support to any type of reactor (light water- heavy water- gas- or molten metal-cooled power reactor); -) adaptability: RJH's operating life will be over 50 years so the reactor will have to adjust to the experimental needs that may change a lot over a so long period; -) reactor operation: RJH is optimized to produce an availability time of 275 full charge equivalent days a year; and -) costs: the minimization of experiment costs is obtained through the integration in the same facility (or located nearby on the site) of the technical means required to perform a complete experimental program from the design of the irradiation device to its recovery after irradiation and to the examination or the possible testing of the samples. Transport costs and time delays are spared. This article gives the main features of the RJH facility from the description of the building to the specificities of the reactor core. (A.C.)

  3. BWR: Development and Validation of KERENA reactor; Les REB: Developpement et validation du reacteur KERENA

    Energy Technology Data Exchange (ETDEWEB)

    Diercks, F.; Fuchs, M. [E.ON Kernkraft GmbH (Germany); Erve, M.; Pasler, D. [AREVA (Germany)

    2010-07-01

    KERENA is an advanced boiling water reactor, combining AREVA's and E.ON's expertise. A project was launched to customize the final basic design for this advanced nuclear power plant having a net power output of about 1, 250 MW, a net efficiency of about 37% and a design service life of 60 years. The development takes into account the technical and accumulated operating experience of the project partners. The plant safety concept is based on an optimized combination of a reduced number of proven active safety systems and passive safety systems, utilizing basic laws of physics, such as gravity, enabling them to function without electrical power supplies or activation by powered instrumentation and control systems. Control of a postulated core melt accident is assured with considerable safety margins thanks to passive flooding of the containment for in-vessel melt retention. All passive safety systems are validated in an experimental test program at AREVA, using 1:1 scale test facilities (INKA test facility Karlstein). The KERENA boiling water reactor is compliant with international nuclear codes and standards, and is also designed to withstand the effects of an aircraft crash involving a military aircraft or a large passenger airline. The safety level of the KERENA reactor has been able to be significantly increased compared to existing BWR plants. The advantages of the new safety concept are: -) Reduced susceptibility of safety systems to failures; -) Larger safety margins; -) Good plant behavior in the event of accidents due to the fact that conditions change at a slower rate; -) Grace periods of several days after an accident before operator intervention is required; -) Significantly reduced impact of operator error on reactor safety; -) No need for large-scale emergency response actions such as temporary evacuation or relocation of the neighboring population following a core melt accident. (A.C.)

  4. Optimisation de la gestion du combustible dans les reacteurs CANDU refroidis a l'eau legere

    Science.gov (United States)

    Chambon, Richard

    This research has two main goals. First, we wanted to introduce optimization tools in the diffusion code DONJON, mostly for fuel management. The second objective is more practical. The optimization capabilities are applied to the fuel management problem for different CANDU reactors at refueling equilibrium state. Two kinds of approaches are considered and implemented in this study to solve optimization problems in the code DONJON. The first methods are based on gradients and on the quasi-linear mathematical programming. The method initially developed in the code OPTEX is implemented as a reference approach for the gradient based methods. However, this approach has a major drawback. Indeed, the starting point has to be a feasible point. Then, several approaches have been developed to be more general and not limited by the initial point choice. Among the different methods we developed, two were found to be very efficient: the multi-step method and the mixte method. The second kind of approach are the meta-heuristic methods. We implemented the tabu search method. Initially, it was designed to optimize combinatory variable problems. However, we successfully used it for continuous variables. The major advantage of the tabu method over the gradient methods is the capability to exit from local minima. Optimisation of the average exit burnup has been performed for CANDU-6 and ACR-700 reactors. The fresh fuel enrichment has also been optimized for ACR-700. Results match very well what the reactor physics can predict. Moreover, a comparison of the two totally different types of optimization methods validated the results we obtained.

  5. Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The project of building of he EPR reactor at Flamanville (Manche, France) has been submitted to the public debate. This document includes a presentation of the project and of the rules of the public debate, a synthesis of the file made by the prime contractor (EDF), a synthesis of the collective book of national actors concerned by the project (a group of associations for environment protection, Areva company, the ministries of economy and ecology, Global Chance, association of pro-nuclear ecologists (AEPN), 'Sortir du Nucleaire' (out-of nuclear) network, group of scientists for the information about nuclear (GSIEN), association for the promotion of the Flamanville site (Proflam), French nuclear energy society (SFEN) in association with 'Sauvons le Climat' (let's save climate), regional collective association 'EPR non merci, ni ailleurs, ni ici' (EPR, no thanks, neither elsewhere, nor here), NegaWatt), and 5 detailed books of actors: ACRO (association for the control of radioactivity in Western France), CFDT and CGT syndicates, the economic and social council of Basse Normandie region, and Proflam. (J.S.)

  6. Nuclear developments at the international inter govern mental level (1961); Developpements nucleaires sur le plan international intergouvernemental (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Waynbaum, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    The United Nations organisation and nuclear energy rose simultaneously, in 1945, to occupy an important place in the public eye. The spiritual succession of the League of Nations which had foundered during the war was taken up by the new organisation which sought to implant its political ideal in a more tangible reality, so that it might thereby be inspired by concrete and substantial objectives. This is one of the reasons for the existence of the dozen specialized agencies created by the family of the United Nations and dealing with Health, Culture, Agriculture, Finance, etc. Nuclear energy is one of these techniques. Becoming suddenly an important power factor and exploiting for itself the prestige of Science, it became the favorite domain for the growth of this new spirit, as much in its universal form in 1945 as in its more regional form which it was later to adopt. The achievements are numerous and of varying importance; they deserve te be studied carefully. (author) [French] L'organisation des Nations Unies et le nucleaire ont ete places simultanement, en 1945, au premier plan de la scene mondiale. La Societe des Nations ayant sombre pendant la guerre, son heritage spirituel fut recueilli par la nouvelle organisation qui chercha a enraciner son ideal politique dans une realite plus materielle, de facon a y puiser une nourriture concrete et substantielle. C'est une des raisons d'existence de la douzaine d'institutions specialisees gravitant dans la famille des Nations Unies et s'occupant de Sante, de Culture, d'Agriculture, de Finances, etc. Le nucleaire est l'une de ces techniques. Devenu soudainement un facteur primordial de puissance, Cristallisant a son benefice le prestige de la Science, c'etait un terrain de predilection pour le developpement du nouvel esprit, aussi bien sous la forme universelle de 1945, que sous les formes regionales qui ont vu le jour ensuite. Les travaux realises que nombreux, d

  7. Contribution to the study of {beta} disintegration and of nuclear structure using experiments on certain {beta}-{gamma} cascades: 198{sub Au}, 86{sub Rb}, 170{sub Tm}; Contribution a l'etude de la desintegration beta et a l'etude de la structure nucleaire a l'aide d'experiences sur certaines cascades beta-gamma: 198{sub Au}, 86{sub Rb}, 170{sub Tm}

    Energy Technology Data Exchange (ETDEWEB)

    Lachkar, J. [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes; Paris-11 Univ., fabulte des Sciences 91 - Orsay (France)

    1969-07-01

    {beta}{gamma} directional angular correlations and shapes of inner beta spectra leading to the first excited level of the final nucleus enable one to determine the nuclear matrix elements typical of the {beta} transition. In the three observed first forbidden cases: {sup 170}Tm, {sup 86}Rb, {sup 198}Au, these matrix elements do not confirm the independent shell model theory. Other hypotheses are then suggested and discussed. (author) [French] Les experiences de correlation angulaire {beta}{gamma} et l'etude du spectre {beta} conduisant au premier niveau excite du noyau final permettent de determiner les elements de matrices nucleaires caracteristiques de cette transition. Dans les trois cas etudies (transitions une fois interdites): {sup 170}Tm, {sup 86}Rb, {sup 198}Au, ces elements de matrices ne peuvent etre retrouves a l'aide du modele en couches et a particules independantes. D'autres hypotheses sont alors emises et discutees. (auteur)

  8. Mise au point d'un reacteur epitaxial CBE

    Science.gov (United States)

    Pelletier, Hubert

    Ce projet de maîtrise consiste à l'asservissement et la mise en marche d'un réacteur d'épi-taxie par jets chimiques au Laboratoire d'Épitaxie Avancée de l'Université de Sherbrooke. Le réacteur sert à la croissance dans l'ultravide de matériaux semi-conducteurs tels que l'arséniure de gallium (GaAs) et le phosphure d'indium-gallium (GaInP). La programmation LabVIEW™ et du matériel informatique de National Instruments sont utilisés pour asservir le réacteur. Le contrôle de la température de l'échantillon et de la pression de contrôle des réactifs de croissance dans le réacteur est assuré par des boucles de rétroaction. Ainsi, la température de l'échantillon est stabilisée à ±0, 4 °C, alors que les pressions de contrôle de gaz peuvent être modulées sur un ordre de grandeur en 2 à 4 secondes, et stabilisées à ±0, 002 Torr. Le système de pompage du réacteur a été amélioré suite à des mesures de vitesse de pompage d'une pompe cryogénique. Ces mesures révèlent une dégradation sur plus d'un ordre de grandeur de son pompage d'hydrogène avec l'opération à long terme. Le remplacement de la pompe cryogénique par une pompe turbo-moléculaire comme pompe principale a permis d'améliorer la fiabilité du système de pompage du système sous vide. D'autre part, la conductance du système d'acheminement de gaz et d'injection a été augmentée afin de réduire un effet mémoire des sources le système et faciliter la croissance de matériaux ternaires. Ainsi, des croissances de GaAs (100) sur substrat de même nature ont été effectuées et ont révélé un matériau de bonne qualité. Sa rugosité moyenne de 0,17 nm, mesurée par microscopie à force atomique, est très faible selon la littérature. De plus, une mobilité élevée des porteurs est obtenue à fort dopage au silicium, au tellure et au carbone, notamment une mobilité de 42 ± 9 cm2V -1s-1 des porteurs majoritaires '(trous) lors du dopage au carbone à 1, 5 · 1019

  9. Contributions to safety studies for new concepts of nuclear reactors; Contributions aux etudes de surete pour des filieres innovantes de reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Perdu, F

    2003-12-01

    The complete study of molten salt reactors, designed for a massive and durable nuclear energy production, must include neutronics, hydraulics and thermal effects. This coupled study, using the MCNP and Trio{sub U} codes, is undertaken in the case of the MSRE (molten salt reactor experiment) prototype. The obtained results fit very well the experiment. Their extrapolation suggests ways of improving the safety coefficients of power molten salt reactors. A second part is devoted to accelerator driven subcritical reactors, developed to incinerate radioactive waste.We propose a method to measure the prompt reactivity from the decay following a neutron pulse. It relies only on the distribution of times between generations, which is a characteristic of the reactor. This method is implemented on the results of the MUSE 4 experiment, and the obtained reactivity is accurate within 5%. (author)

  10. Physicochemical state of the spent fuel leaving the reactors; Le combustible nucleaire et son etat physico-chimique a la sortie des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Dehaut, Ph

    2000-07-01

    This report focuses on the current knowledge, updated at the end of 1999, about the physicochemical state of the fuels leaving light water reactors, and particularly pressurized water reactors. Lessons are withdrawn from it making it possible to determine the points which require a necessary deepening of the data and coherence of interpretations. Lastly, evolution of the sailed fuel rod as well as the potential availability of gases and volatile fission products, during a secular storage or of a multi-millennium disposal, are the subject of an attempt at forecast. Accessible data in the scientific literature, or those acquired at the CEA, are particularly numerous. Their analysis and their synthesis are joined together to constitute a collection of references intended to the specialists in nuclear fuel and for all those which contribute to the reflexion on the storage or final disposal of the irradiated fuel. This memory is structured in ten chapters. The last chapter makes it possible to retain on some pages, the essential lessons of this study. Chapter I: Introduction; Chapter II: Characteristics of assemblies and fuels before irradiation; Chapter III: Transformations in reactor; Chapter IV: State of rods leaving the reactor; Chapter V: State of pellets; Chapter VI: Chemical and structural composition of the fuel; Chapter VII: Fuel fragmentation and density; Chapter VIII: Phenomena at the pellet periphery. Formation, characteristics and structure of the rim.Chemical interaction between pellet and cladding; Chapter IX: Location of fission gases and volatile fission products; Chapter X: Review, lessons and predictions. (authors)

  11. Experimental reactor regulation: the nuclear safety authority's approach; Le controle des reacteurs experimentaux: la demarche de l'Autorite de surete nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Rieu, J.; Conte, D.; Chevalier, A. [Autorite de Surete Nucleaire, 75 - Paris (France)

    2007-07-15

    French research reactors can be classified into 6 categories: 1) critical scale models (Eole, Minerve and Masurca) whose purpose is the study of the neutron production through the fission reaction; 2) reactors that produce neutron beams (Orphee, and the high flux reactor in Grenoble); 3) reactors devoted to safety studies (Cabri, Phebus) whose purpose is to reproduce accidental configurations of power reactors in reduced scale; 4) experimental reactors (Osiris, Phenix) whose purpose is the carrying-out of irradiation experiments concerning nuclear fuels or structure materials; 5) teaching reactors (Ulysse, Isis); and 6) reactors involved in defense programs (Caliban, Prospero, Apareillage-B). We have to note that 3 research reactors are currently being dismantled: Strasbourg University's reactor, Siloe and Siloette. Research reactors in France are of different types and present different hazards. Even if methods of control become more and more similar to those of power reactors, the French Nuclear Safety Authority (ASN) works to allow the necessary flexibility in the ever changing research reactor field while ensuring a high level of safety. Adopting the internal authorizations for operations of minor safety significance, under certain conditions, is one example of this approach. Another challenge in the coming years for ASN is to monitor the ageing of the French research reactors. This includes periodic safety reviews for each facility every ten years. But ASN has also to regulate the new research reactor projects such as Jules Horowitz Reactor, International Thermonuclear Experimental Reactor, which are about to be built.

  12. Life time of nuclear power plants and new types of reactors; La duree de vie des centrales nucleaires et les nouveaux types de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-01

    This report, realized by the Evaluation Parliamentary Office of scientific and technological choices, aims to answer simple but fundamental questions for the french electric power production. What are the phenomena which may limit the exploitation time of nuclear power plants? How can we fight against the aging, at which cost and with which safety? The first chapter presents the management of the nuclear power plants life time, an essential element of the park optimization but not a sufficient element. The second chapter details the EPR and the other reactors for 2015 as a bond between the today and tomorrow parks. The last chapter deals with the necessity of efforts in the research and development to succeed in 2035 and presents other reactors in project. (A.L.B.)

  13. Electric failure on the reactor n.3 of the nuclear power plant of Dampierre; Defaillance electrique sur le reacteur n. 3 de la centrale nucleaire de Dampierre

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-05-15

    This note of information resumes the progress of the electric failure on the reactor n.3 of the nuclear power plant of Dampierre, the organization during the incident, it establishes then a comparison with the incident arisen to Forsmark in 2006 and reminds that it lead in an inspection on behalf of the Asn which noticed that all the procedures had been respected by the operators and did not noticed any abnormality in the maintenance. This event was classified at the level 1 of the international nuclear event scale (INES). (N.C.)

  14. Assessment of subcriticality during PWR-type reactor refueling; Evaluation de la sous-criticite lors des operations de chargement d'un reacteur nucleaire REP

    Energy Technology Data Exchange (ETDEWEB)

    Verdier, A

    2005-04-15

    During the core loading period of a PWR, any fuel assembly misplacements may significantly reduce the existing criticality margin. The Dampierre 4-18 event showed the present monitoring based on the variations of the outside-core detector counting rate cannot detect such misplacements. In order to circumvent that, a more detailed analysis of the available signal was done. We particularly focused on the neutronic noise analysis methods such as MSM (modified source multiplication), MSA (amplified source multiplication), Rossi-{alpha} and Feynman-{alpha} methods. The experimental part of our work was dedicated to the application of those methods to a research reactor. Finally, our results showed that those methods cannot be used with the present PWR instrumentation. Various detector positions were then studied using Monte Carlo calculations capable of following the neutron origin. Our results showed that the present technology does not allow us to use any solution based on neutron detection for monitoring core loading. (author)

  15. Civacuve analysis software for mis machine examination of pressurized water reactor vessels; Civacuve logiciel d'analyse des controles mis des cuves de reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Dubois, Ph.; Gagnor, A. [Intercontrole, 94 - Rungis (France)

    2001-07-01

    The product software CIVACUVE is used by INTERCONTROLE for the analysis of UT examinations, for detection, performed by the In-Service Inspection Machine (MIS) of the vessels of nuclear power plants. This software is based on an adaptation of an algorithm of SEGMENTATION (CEA CEREM), which is applied prior to any analysis. It is equipped with tools adapted to industrial use. It allows to: - perform image analysis thanks to advanced graphic tools (Zooms, True Bscan, 'contour' selection...), - backup of all data in a database (complete and transparent backup of all informations used and obtained during the different analysis operations), - connect PC to the Database (export of Reports and even of segmented points), - issue Examination Reports, Operating Condition Sheets, Sizing curves... - and last, perform a graphic and numerical comparison between different inspections of the same vessel. Used in Belgium and France on different kind of reactor vessels, CIVACUVE has allowed to show that the principle of SEGMENTATION can be adapted to detection exams. The use of CIVACUVE generates a important time gain as well as the betterment of quality in analysis. Wide data opening toward PC's allows a real flexibility with regard to client's requirements and preoccupations.

  16. Contribution to the study of thermal-hydraulic problems in nuclear reactors; Contribution a l`etude de problemes de thermohydraulique dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Cognet, G

    1998-07-07

    In nuclear reactors, whatever the type considered, Pressurized Water Water Reactors (PWRs), Fast Breeder reactors (FBRs)..., thermal-hydraulics, the science of fluid mechanics and thermal behaviour, plays an essential role, both in nominal operating and accidental conditions. Fluid can either be the primary fluid (liquid or gas) or a very specific fluid called corium, which, in case of severe accident, could result from core and environning structure melting. The work reported here represents a 20-year contribution to thermal-hydraulic issues which could occur in FBRs and PWRs. Working on these two types of reactors, both in nominal and severe accident situations, has allowed me to compare the problems and to realize the importance of communication between research teams. The evolution in the complexity of studied problems, unavoidable in order to reduce costs and significantly improve safety, has led me from numerical modelling of single-phase flow turbulence to high temperature real melt experiments. The difficulties encountered in understanding the observed phenomena and in increasing experimental databases for computer code qualification have often entailed my participation in specific measurement device developments or adaptations, in particular non-intrusive devices generally based on optical techniques. Being concerned about the end-use of this research work, I actively participated in `in-situ` thermalhydraulic experiments in the FBRs: Phenix and Super-Phenix, of which I appreciated their undeniable scientific contribution. In my opinion, the thermal-hydraulic questions related to severe accidents are the most complex as they are at the cross-roads of several scientific specialities. Consequently, they require a multi-disciplinary approach and a continuous see-saw motion between experimentalists and modelling teams. After a brief description of the various problems encountered, the main ones are reported. Finally, the importance for research teams to participate in large international concerted actions is highlighted. (author) 64 refs.

  17. Strategy for nuclear wastes incineration in hybrid reactors; Strategies pour l'incineration de dechets nucleaires dans des reacteurs hybrides

    Energy Technology Data Exchange (ETDEWEB)

    Lelievre, F

    1998-12-11

    The transmutation of nuclear wastes in accelerator-driven nuclear reactorsoffers undeniable advantages. But before going into the detailed study of a particular project, we should (i) examine the possible applications of such systems and (ii) compare the different configurations, in order to guide technological decisions. We propose an approach, answering both concerns, based on the complete description of hybrid reactors. It is possible, with only the transmutation objective and a few technological constraints chosen a posteriori, to determine precisely the essential parameters of such reactors: number of reactors, beam current, size of the core, sub-criticality... The approach also clearly pinpoints the strategic decisions, for which the scientist or engineer is not competent. This global scheme is applied to three distinct nuclear cycles: incineration of solid fuel without recycling, incineration of liquid fuel without recycling and incineration of liquid fuel with on-line recycling; and for two spectra, either thermal or fast. We show that the radiotoxicity reduction with a solid fuel is significant only with a fast spectrum, but the incineration times range from 20 to 30 years. The liquid fuel is appropriate only with on-line recycling, at equilibrium. The gain on the radiotoxicity can be considerable and we describe a number of such systems. The potential of ADS for the transmutation of nuclear wastes is confirmed, but we should continue the description of specific systems obtained through this approach. (author)

  18. Research means to back the development of nuclear reactors; Les moyens de recherche en support a l'evolution des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    After 50 year long feedback experience on nuclear reactor operations it is legitimate to wonder whether experimental facilities used to support nuclear power programs are still necessary. The various participants of this conference said yes for mainly 4 reasons: -) to validate the extension of the service life of a reactor without putting at risk its high safety standard, -) to give the reactor more flexibility to cope with the power demand, -) to confront the results given by computerized simulations with experimental data, and -) to qualify the nuclear systems of tomorrow. (A.C.)

  19. Microstructure and embrittlement of VVER 440 reactor pressure vessel steels; Microstructure et fragilisation des aciers de cuve des reacteurs nucleaires VVER 440

    Energy Technology Data Exchange (ETDEWEB)

    Hennion, A

    1999-03-15

    27 VVER 440 pressurised water reactors operate in former Soviet Union and in Eastern Europe. The pressure vessel, is made of Cr-Mo-V steel. It contains a circumferential arc weld in front of the nuclear core. This weld undergoes a high neutron flux and contains large amounts of copper and phosphorus, elements well known for their embrittlement potency under irradiation. The embrittlement kinetic of the steel is accelerated, reducing the lifetime of the reactor. In order to get informations on the microstructure and mechanical properties of these steels, base metals, HAZ, and weld metals have been characterized. The high amount of phosphorus in weld metals promotes the reverse temper embrittlement that occurs during post-weld heat treatment. The radiation damage structure has been identified by small angle neutron scattering, atomic probe, and transmission electron microscopy. Nanometer-sized clusters of solute atoms, rich in copper with almost the same characteristics as in western pressure vessels steels, and an evolution of the size distribution of vanadium carbides, which are present on dislocation structure, are observed. These defects disappear during post-irradiation tempering. As in western steels, the embrittlement is due to both hardening and reduction of interphase cohesion. The radiation damage specificity of VVER steels arises from their high amount of phosphorus and from their significant density of fine vanadium carbides. (author)

  20. Functional approaches: a new view of nuclear reactors management; Les approches fonctionnelles: une nouvelle vision de la conduite des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Papin, B

    2000-07-01

    Since many years a research program on the future reactors command, has been decided by the CEA, in collaboration with EDF and Framatome. This program aims to enhance the reactor safety by a better control of the installation in any exploitation situations. The paper presents the state of the art and the first reflexions. (A.L.B.)

  1. The sea water desalination by the nuclear reactors; Le dessalement de l'eau de mer par les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Nisan, S. [CEA Cadarache, Dir. du Developpement et de l' Innovation Nucleares DDIN, 13 - Saint-Paul-lez-Durance (France)

    2002-07-01

    This document underlines the importance of water shortage in many areas in the world in the future. The water sea desalination can be a efficient solution to this problem. The desalination methods are presented. In this context the desalination reactors appear as a competitive solution, facing the fossil energies systems not only for the simultaneous electric power and drinking water production, but also for the minimization of greenhouse gases. (A.L.B.)

  2. Measurement of neutrinos released in nuclear reactors through the Borexino experiment; Mesure des neutrinos de reacteurs nucleaires dans l'experience Borexino

    Energy Technology Data Exchange (ETDEWEB)

    Dadoun, O

    2003-06-01

    The main goal of the Borexino experiment is to measure in real time the solar neutrino flux from the beryllium (Be{sup 7}) line at 862 keV. Beyond this pioneer low energy neutrino detection, Borexino will be able to measure solar neutrinos above the MeV, (B{sup 8} neutrinos and pep neutrinos), nuclear reactor neutrinos (with an average energy of 3 MeV) and the supernova neutrinos (their spectrum goes up to some ten MeV). In this work I mainly focus on the study of the nuclear reactors neutrinos. This field has recently been enriched by the results of the KamLAND experiment, which have greatly improved the determination of the neutrino oscillation parameters. In order to measure these events which are above the MeV, the Borexino collaboration entrusted the PCC group at College de France, with the tasks of developing a fast digit system running at 400 MHz: the FADC cards. The PCC group designed the FADC cards and completed them at the beginning of 2002. The first cards which were introduced in the main electronic acquisition unit allowed us to control their functioning and that of the acquisition software. FADC cards were also installed in the Borexino prototype, CTF. The data are analysed in order to determine a limit to the expected background noise of Borexino in measuring the nuclear reactor neutrinos. (author)

  3. Du fratinoj

    Institute of Scientific and Technical Information of China (English)

    1996-01-01

    Vivis iam du fratinoj-Aje kaj Fatme.Iliapatrino estis duon-patrino por Fatme kaj in neamis.Foje i diris al sia edzo:-Faru kion ajn,sed mi ne plu volas vidiFatme.La sekvan tagon la patro forkondukis la

  4. Contribution to the study of the evolution of radiation induced He in Be O; Etudes sur l'evolution de l'helium produit par reactions nucleaires dans l'oxyde de beryllium

    Energy Technology Data Exchange (ETDEWEB)

    Bareau, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1966-11-15

    The purpose of this work in-pile investigation of He formed by (n, 2n) and (n, {alpha}) nuclear reactions, released from irradiated BeO, in the temperature range 1000 - 1350 deg. C. The experimental results show that, for an instantaneous neutron fast flux of 10{sup 13} n cm{sup -2} sec{sup -1}, an equilibrium is attempted, after several days, for a part lower than 20 per cent of the quantity of He formed, theoretically calculated from the neutron cross sections of nuclear reactions, and from the analytical form of the neutron fast flux, releases from the solid. The validity of the values of calculated helium and the gas chromatographic analytical method are also verified by dissolution of the BeO pellets in cryolite. A new fast neutron flux measuring method may be so defined. The discussion of the experimental results enables to establish that the processus of He release is characterized by two phenomena: the first one which controls the release of He atoms out of the solid and the second which reveals a capture processus, connected to the irradiation and probably due to the vacancies induced in the lattice. (author) [French] On etudie en pile le degagement de l'helium forme par reactions nucleaires (n, 2 n) et (n, {alpha}) dans l'oxyde de beryllium irradie entre 1000 et 1350 deg. C. Les resultats experimentaux montrant que, pour un flux rapide instantane de 10{sup 13} n{sub r} cm{sup -2} s{sup -1}, on aboutit, au bout de quelques jours, a un etat d'equilibre pour lequel une partie, inferieure a 20 pour cent de la quantite d'helium forme, calculee theoriquement a partir des sections efficaces des reactions nucleaires et de la forme analytique du flux rapide, s'echappe du solide. On verifie egalement par dissolution des echantillons de BeO dans la cryolithe la validite du calcul de l'helium et de la methode de dosage par chromatographie en phase gazeuse. On peut ainsi definir une methode nouvelle de mesure des flux rapides. La

  5. Study, with the help of nuclear indicators (HTO, Urea {sup 14}C and {sup 24}Na), of the renewal of water, urea and sodium in different parts of the rat kidney in aqueous diuresis and of the gerbil kidney in osmotic diuresis or in oliguria; Etude, a l'aide d'indicateurs nucleaires (HTO, UREE {sup 14}C et {sup 24}Na), du renouvellement de l'eau, de l'uree et du sodium dans les differentes regions du rein de rat en diurese aqueuse et de merion en diurese osmotique ou en oligurie

    Energy Technology Data Exchange (ETDEWEB)

    Lechene, C.P. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-06-01

    In the kidney of the gerbil in oliguria there exists a cortico-papillary gradient in the concentration of the sodium and of the urea; this gradient disappears in the gerbil kidney in osmotic diuresis or in the rat kidney in aqueous diuresis; in these three states of diuresis there is no significant difference in the potassium concentration between the surface and interior regions of the kidneys. Kinetic studies using tritiated water, urea {sup 14}C and {sup 24}Na show that water and urea in the interior regions of the kidney are only renewed very slowly (1 h) whereas the sodium is rapidly changed (1 mn). These results can be explained using WIRZ's theory concerning the mechanism of the counter-current concentration of urine. Furthermore, the evolution of the specific radioactivity of urea {sup 14}C is favorable for a cortical synthesis of urea. (author) [French] II existe dans le rein de Merions en oligurie un gradient cortico papillaire de la concentration du sodium et de l'uree; ce gradient est aboli dans le rein de Merions en diurese osmotique ou de rats en diurese aqueuse; dans ces 3 etats de diurese il n'y a pas de difference significative de la concentration du potassium entre les regions superficielles et profondes des reins. Des etudes cinetiques a l'aide d'eau tritiee, d'uree {sup 14}C et de {sup 24}Na montrent que l'eau et l'uree des regions profondes des reins ne sont renouveles que tres lentement (1 h), alors que le sodium est tres vite renouvele (1 mn). Ces resultats s'expliquent par la theorie de WIRZ sur le mecanisme de la concentration de l'urine par contre-courant. En outre, l'evolution renale de la radioactivite specifique de l'uree {sup 14}C est en faveur d'une synthese corticale de l'uree. (auteur)

  6. Second inter-association evaluation of the PNLCC implementation. PNLCC 2000-2003: The Government economizes its energy; Deuxieme evaluation interassociative de la mise en oeuvre du PNLCC. PNLCC 2000-2003: Le gouvernement economise son energie

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-11-01

    A group of associations (RAC-F, FNE, WWF, ''les amis de la terre'', CLER, Greenpeace, Helio international, Hespul, ''energies et territoires'', Detente, ''sortir du nucleaire'') realized its own 2002 evaluation of the PNLCC implementation. For each chapters of the Plan (industry, transports, buildings, agriculture and forests, wastes, energy production and conservation and cooling gases, the document takes stock on the actions decided and realized and shows the deficiencies of the government management. (A.L.B.)

  7. modelisation du comportement hydrologique du bassin versant du ...

    African Journals Online (AJOL)

    LGE

    caractéristiques physiographiques du bassin dans le modèle permet la mise en évidence de son ... espèces les plus hygrophiles du secteur ombrophile. ...... [13] - F. HENDRICKX, Impact hydrologique d‟un changement climatique sur le bassin du ... LOPES, On the effect of uncertainty in spatial distribution of rainfall on ...

  8. Damage caused to houses and equipment by underground nuclear explosions; Degats dus aux explosions nucleaires souterraines sur les habitations et les equipements

    Energy Technology Data Exchange (ETDEWEB)

    Delort, F.; Guerrini, C. [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    A description is given of the damaged caused to various structures, buildings, houses, mechanical equipment and electrical equipment by underground nuclear explosions in granite. For each type of equipment or building are given the limiting distances for a given degree of damage. These distances have been related to a parameter characterizing the movement of the medium; it is thus possible to generalize the results obtained in granite, for different media. The problem of estimating the damage caused at a greater distance from the explosion is considered. (authors) [French] Les degats sur diverses structures, constructions, habitations, equipements mecaniques et materiels electriques provoques par des explosions nucleaires souterraines dans le granite sont decrits. On a indique pour chaque type de materiel ou de construction, les distances limites correspondant a un degre de gravite de dommage observe. Ces distances ont ete reliees a un parametre caracterisant le mouvement du milieu, permettant ainsi de generaliser les resultats obtenus dans le granite, a differents milieux. Le probleme de la prevision des degats en zone lointaine a ete aborde. (auteurs)

  9. Health survey on cancers about the Tricastin nuclear site; Etude sanitaire sur les cancers autour du site nucleaire du Tricastin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This survey aims at describing the health status of the population around the Tricastin site, and more particularly at determining whether there is a difference between death or cancer occurrence frequencies observed around this site with respect to reference frequencies. It does not aim at assessing the health impact of the site industrial installations. Cancer mortality data, cancer diagnosis data, demographic data, child cancer data, data related to hospital stays in relationship with cancer, long duration hospital stay data, and mortality data are used. Several indicators are defined and used: standardised mortality ratio, standardised hospitalisation ratio. Data are also analysed in terms of location, and socio-demographic categories. It appears that there is no specific health situation for the considered area, except for pancreas cancer for women

  10. Situation of nuclear industry in Japan; La situation du nucleaire au Japon

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-01

    This document presents the situation of nuclear industry in Japan: cooperation with France in the domain of the fuel cycle (in particular the back-end) and of for the industrial R and D about fast reactors and nuclear safety; present day situation characterized by a series of incidents in the domain of nuclear safety and by an administrative reorganization of the research and safety organizations; power of local representatives, results of April 2003 elections, liberalization of the electric power sector, impact of the TEPCO affair (falsification of safety reports) on the nuclear credibility, re-start up of the Monju reactor delayed by judicial procedures, stopping of the program of MOX fuel loading in Tepco's reactors, discovery of weld defects in the newly built Rokkasho-mura reprocessing plant, an ambitious program of reactors construction, the opportunity of Russian weapons dismantling for the re-launching of sodium-cooled fast reactors; the competition between France and Japan for the setting up of ITER reactor and its impact of the French/Japanese partnership. (J.S.)

  11. The nuclear future in France; Le futur du nucleaire en France

    Energy Technology Data Exchange (ETDEWEB)

    Lemperiere, F.

    2011-12-15

    After having outlined some important facts in the world concerning energy production (phasing out nuclear by many countries, share of nuclear energy, development of wind and solar energy, possibility of meeting electricity demand with 80% of renewable energies) and in France (nuclear plants, debate about nuclear, slow development of renewable energies), the author briefly assesses the cost of two scenarios: a reduction of nuclear energy from 450 to 300 TWh/year by 2025, and a reduction of nuclear energy from 300 to 0 TWh/year between 2025 and 2040

  12. The diverse applications of the nuclear power; Les diverses applications du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The three great categories of application in industry and environment of ionizing radiations are the use of ionizing radiation to transport energy in matter it is industrial irradiation, the use of radioactive sources of low activity to analyze and measure, it is the nucleonic instrumentation, the use of radioactive tracers to follow and study the matter transfer. Are explained the treatments to improve the plastic materials and the ionisation of food. (N.C.)

  13. Phasing out nuclear, a credible scenario; Sortir du nucleaire, un scenario credible

    Energy Technology Data Exchange (ETDEWEB)

    Chatelain, C.; Mulot, R.; Chauveau, L.; Hait, J.F.

    2011-08-15

    Based on data from different companies, institutions and associations involved in nuclear energy (either in its production or in its critic), this article comments the possible energy savings (50 to 64%) that may be reached in the different sectors, and more particularly in the building sector and in electrical equipment. It discusses the potential production from solar, wind and biogas energy. It notices that phasing out nuclear is possible by 2030-2050, but would entail an increase of electricity prices. The German approach is presented. An article comments the anger of Fukushima Japanese farmers and evokes the slow building up of a solidarity network between France and Japan. A last article comments the authorization given to a further exploitation of the Fessenheim nuclear power plant (ten more years)

  14. Critical aspects of the nuclear multifragmentation; Etude du caractere critique de la multifragmentation nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Marie, J

    2004-06-01

    From statistical mechanics, this thesis looks for a phase transition signal in nuclei. We try to describe critical aspects of the nuclear multifragmentation. Thermodynamical observables as fragment mass/charge distributions are used in those finite systems. The percolation theory is first applied to strictly statistical events from the lattice gas model framework at the thermodynamical critical point. The scaling functions obtained are quantitatively comparable for every sample. Critical exponents are almost the same as the liquid/gas universality class ones. The second part is devoted to Fisher's model framework taking into account for the chemical potential and the surface energy coefficient. The extracted critical temperature is compatible with the percolation one. Experimental samples are then studied from peripheral (Au+Au) and central (Xe+Sn) heavy ion collisions. Entrance channel memory effects are evidenced in peripheral events. The presence of collective flow make the central ones far away from the conditions required by Fisher's model. Nevertheless, the critical energy found is independent of the data characteristics. This curious stability has to be studied. (authors)

  15. Nuclear Power's Big Comeback?; Le grand retour du nucleaire?

    Energy Technology Data Exchange (ETDEWEB)

    Bonnaure, P.

    2011-01-15

    The autumn of 2010 has, in its turn, brought a trial of strength between anti-nuclear protestors and the authorities - in this case, over the train transporting 123 tons of nuclear waste between La Hague in France and Dannenberg in Germany. However, this episode, despite its spectacular nature and media impact, does not provide a true reflection of public opinion - and European opinion, in particular - with regard to nuclear power. As Pierre Bonnaure shows here, in the context of a progressive exhaustion of fossil fuels and the battle against climate change - which involves a reduction in greenhouse gas emissions - nuclear power may well recover its credibility. Public opinion seems less averse to it; states are developing new projects and ambitious nuclear programmes; and prospects in terms of resources (particularly, uranium) and technological developments seem set fair. After surveying the field and examining these various aspects, Pierre Bonnaure also reminds us of the remaining stumbling blocks: the question of radioactive waste, the lack of qualified labour in this sector and the funding difficulties. However, in these areas, it only needs states to make a substantial investment to consolidate an energy sector that has a bright future, provided it is assured of a technological research potential and safety conditions commensurate with the risks inherent in nuclear power. (author)

  16. Abandoning nuclear energy, a total industrial absurdity; Sortir du nucleaire, un non-sens industriel

    Energy Technology Data Exchange (ETDEWEB)

    Sorin, F.

    2011-09-15

    The abandoning of nuclear energy can not be considered without economic and social damages, it would amplify the des-industrialization process of France and would spoil its energy independence and would mean a step backwards in terms of world strategy. In France the nuclear sector gives work to a total of 410.000 people and generates a total added value of 33 billions euros each year. It would make no sense to stop an activity whose perspective is promising: a lot of reactors in the world will need soon maintenance, upgrading or replacement. (A.C.)

  17. The power of the will and the French nuclear programme; Volontarisme du programme nucleaire francais

    Energy Technology Data Exchange (ETDEWEB)

    Boureille, P. [Ministre de la Defense, Dept. Marine, Service Historique de la Defense, 75 - Paris (France)

    2010-03-15

    Using certain key episodes in the development of the French nuclear deterrent as examples, the author illustrates the extent to which boldness of decision-making, combined with far-thinking and resolute vision, is the foundation of any international defence policy built for the long term. (author)

  18. Situation of nuclear industry in Japan; La situation du nucleaire au Japon

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-08-01

    This document is a reprint of a note published by the nuclear service of the French embassy in Japan. It evokes the present day situation of nuclear facilities in Japan, the public acceptance and its attitude in front of accidents, the national energy program, the deregulation and competitiveness of nuclear power, the carrying out of the nuclear program, the future reactors, the fast neutron reactors, the dismantling activities, the fuel enrichment and reprocessing of spent fuels, the use of MOX fuel, the off-site storage, the vitrified and radiological wastes, the geological disposal of wastes, the prospects of the nuclear program, the companies involved in the Japan nuclear industry, the French-Japanese bilateral cooperation, and the ITER project in the domain of nuclear fusion. (J.S.)

  19. Cooling and spreading of corium during its fall into water in a pressurised water nuclear plant severe accident: description of mechanical and thermal interactions in a three phase flow during spreading of cold or heated spheres in a liquid pool; Refroidissement et dispersion du corium lors de sa chute dans l'eau pendant un accident severe de reacteur nucleaire a eau pressurisee: description des interactions mecaniques et thermiques en ecoulement triphasique lors de la dispersion de spheres solides froides ou chaudes dans un bain liquide

    Energy Technology Data Exchange (ETDEWEB)

    Duplat, F

    1998-10-26

    In the frame of nuclear safety studies about corium and water interactions, we address spreading and cooling stage of corium fragments in a liquid pool. Considering the complexity of encountered flow regimes and mechanical and thermal interactions coupling, modelling validation is based on a thermal-hydraulic computer code (MC3D). A bibliographical study shows that classical modelling of three phase flow is based on constitutive laws already established in the case of two phase flow. The present study states a complete analysis of BILLEAU experiments and defines a characterisation method for a sphere cloud. Some complementary QUEOS experiments are also described. Mechanical interaction terms such as added mass, lift and turbulent dispersion have been presented in the frame of a three phase flow and their influence has been tested in numerical simulations of BILLEAU tests. The effect of film vapour overheat, as well as particle diameter evolution have been studied. Moreover a radiative heat transfer modelling developed in Karlsruhe research centre (FZK) has been analysed and completed. Numerical simulations achieved for this study show that mechanical and thermal behaviour of the system are actually coupled. Taking into account lift and turbulent dispersion terms as well as heat transfer modifications all wed better results. This study also presents some considerations about flow regimes identification as a preliminary for studies about numerical diffusion that was already estimated in the present state of the computer code MC3D. (author)

  20. Some problems on the aqueous corrosion of structural materials in nuclear engineering; Problemes de corrosion aqueuse de materiaux de structure dans les constructions nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Coriou, H.; Grall, L. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The purpose of this report is to give a comprehensive view of some aqueous corrosion studies which have been carried out with various materials for utilization either in nuclear reactors or in irradiated fuel treatment plants. The various subjects are listed below. Austenitic Fe-Ni-Cr alloys: the behaviour of austenitic Fe-Ni-Cr alloys in nitric medium and in the presence of hexavalent chromium; the stress corrosion of austenitic alloys in alkaline media at high temperatures; the stress corrosion of austenitic Fe-Ni-Cr alloys in 650 C steam. Ferritic steels: corrosion of low alloy steels in water at 25 and 360 C; zirconium alloys; the behaviour of ultrapure zirconium in water and steam at high temperature. (authors) [French] On presente un ensemble d'etudes de corrosion en milieu aqueux effectuees sur des materiaux utilises, soit dans la construction des reacteurs soit pour la realisation des usines de traitement des combustibles irradies. Les differents sujets etudies sont les suivants. Les alliages austenitiques Fer-Nickel-Chrome: comportement d'alliages austenitiques fer-nickel-chrome en milieu nitrique en presence de chrome hexavalent; Corrosion sous contrainte d'alliages austenitiques dans les milieux alcalins a haute temperature; Corrosion sous contrainte dans la vapeur a 650 C d'alliages austenitiques fer-nickel-chrome. Les aciers ferritiques; Corrosion d'aciers faiblement allies dans l'eau a 25 et 360 C; le zirconium et ses alliages; Comportement du zirconium tres pur dans l'eau et la vapeur a haute temperature. (auteurs)

  1. La maquette digitale du tunnel du LEP

    CERN Document Server

    Brouns, G

    2000-01-01

    Pour l'installation du LHC et son équipement périphérique (ligne cryogénique, câbles, tuyauterie, etc.) dans le tunnel du LEP, une maquette digitale CAO doit être faite. Après un rappel de la définition théorique du tunnel du LEP, cette LHC project Note décrit comment sont utilisées et intégrées d'anciennes et de nouvelles mesures du tunnel pour arriver à un ensemble de données qui permettent de construire la maquette digitale (CAO) du tunnel du LHC. Ensuite, les résultats sont comparés à leur valeur théorique d'une part, et aux anciennes valeurs disponibles d'autre part.

  2. Future nuclear reactors. Evolution of the safety approach; Reacteurs du futur. Evolution de l`approche de surete

    Energy Technology Data Exchange (ETDEWEB)

    Vidard, M. [Electricite de France, 75 - Paris (France). Service Etudes et Projets Thermiques et Nucleaires

    1998-10-01

    The cumulated experience on operating nuclear power plants and the progress of safety knowledge allow to conceive reactors with high standard of safety and with optimized building and operating costs. In this article we present the proceedings followed by electricity producers, the main western nuclear plant builders and safety authorities to warrant the required level of safety. The main safety characteristics of new PWR projects are reviewed. A comparison is made between EPR, SYSTEM 80+, APWR and AP600 projects. Safety is also based on the quality of building and the excellence of operating staff. (A.C.) 16 refs.

  3. The launching of the construction of the Jules Horowitz Reactor; Lancement de la construction du reacteur de recherche Jules Horowitz

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    2007-03-15

    In March 2007 the French deputy minister of industry has officially launched the construction of the new research reactor called Jules Horowitz (RJH) on the Cea site of Cadarache. RJH, that is due to operate in 2014, will be used to study the aging process of irradiated materials in any type of reactors, the behaviour of new nuclear fuels irradiated in different configurations and scenarios, and to produce radionuclides for nuclear medicine and high-quality doped silicon for the electronics industry. The investment that reaches 500 million euros is dispatched between Cea (50%), EDF (20%), Areva (10%) and foreign contributors (20%). (A.C.)

  4. Mitigation of the hydrogen risk in fusion reactors; Mitigation du risque hydrogene dans les reacteurs de fusion

    Energy Technology Data Exchange (ETDEWEB)

    Maruejouls, C.; Robin, J.C. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Reacteurs; Arnould, F.; Bachellerie, E. [Technicatome DI SEPS, 13 - Aix en Provence (France); Latge, C. [CEA Cadarache, Dept. d' Etudes des Dechets DED, 13 - Saint Paul lez Durance (France); Laurent, A. [Institut National Polytechnique de Lorraine, Lab. des Sciences du Genie Chimique, 54 - Nancy (France)

    2001-07-01

    The rupture of the first wall and the intrusion of water vapor inside the torus, is one of the major accident that can occur in a thermonuclear fusion reactor. In this situation, water oxidizes the beryllium of the wall and the reaction produces hydrogen with a strong risk of explosion inside the reactor. In order to mitigate this risk, a process based on the reduction of metal oxides (MnO{sub 2}, Ag{sub 2}O) has been developed. The aim of this study is the determination of the kinetics of this reduction reaction. A mixture of both oxides has been deposited on the surface of porous balls for an experiment on fixed beds. The modeling of the phenomenon is based on the equations used in heterogenous catalysis and the experimental determination of the kinetics of the reaction is performed with the CIGNE test-facility. The velocity of the reduction reaction is deduced from the remaining amount of hydrogen in the test-gas (N{sub 2} with 1 to 2% of H{sub 2}) after it has been flowed on the oxides coated balls of the fixed bed. (J.S.)

  5. Nuclear program of Iran. Towards de-escalation of a nuclear crisis. Advisory letter; Nucleair programma van Iran. Naar de-escalatie van een nucleaire crisis. Briefadvies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-15

    The Dutch government, partly at the request of the House of Representatives (Second Chamber), the AIV asked to give an opinion about the position of Iran in the region and the role of the nuclear program of Iran in the geopolitical relations, in view of the most recent developments [Dutch] De Nederlandse regering heeft, mede op verzoek van de Tweede Kamer der Staten-Generaal, de AIV gevraagd advies uit te brengen over de positie van Iran in de regio en de rol van het nucleaire programma van Iran in de geopolitieke verhoudingen hierin, mede gelet op de meest recente ontwikkelingen.

  6. Narrow gap mechanised arc welding in nuclear components manufactured by AREVA NP; Le soudage mecanise a l'arc en chanfrein etroit dans les constructions nucleaires realisees par AREVA NP

    Energy Technology Data Exchange (ETDEWEB)

    Peigney, A. [Departement Soudage AREVA Centre Technique - 71380 Saint-Marcel (France)

    2007-07-01

    soude avec un ou deux fils en deux passes par couche. En TIG, on rencontre de multiples applications car ce procede presente l'avantage de permettre le soudage en toutes positions. On soude selon les cas en une ou deux passes par couche. Le procede est utilise en usine et sur les sites nucleaires pour des operations de montage neuf mais aussi pour des remplacements de composants et en reparation. Actuellement, on cherche a augmenter la productivite de ce procede en utilisant un fil chaud et/ou deux fils. Concernant le MIG/MAG, on developpe son utilisation dans les constructions nucleaires, y compris en chanfrein etroit. Ce procede, limite dans ses applications dans le passe a cause des defauts qu'il generait, beneficie actuellement des progres des generateurs de soudage. On peut alors utiliser ce procede performant pour des constructions de haute securite telles que celles du nucleaire. A noter que le procede est applicable dans diverses positions de soudage comme c'est le cas pour le TIG, tout en etant plus performant que ce dernier. La communication presente l'etat de l'art de l'utilisation des procedes de soudage mecanises a l'arc en chanfrein etroit par les unites d'AREVA NP. (auteur)

  7. Health physics problems in the context of the development of industrial uses of nuclear energy; Les problemes de radioprotection devant le developpement de l'utilisation industrielle de l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel, F.; Menoux, A. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    fate of radioactive ions in the hydrosphere may be determined. - experiments and studies linked with the possibilities for disposal a underground storage of wastes. All these studies cover a complementary field, that of radioprotection, which forms the necessary link between nuclear safety proper, which concerns the actual operation of nuclear installations and medical supervision which directly concerns the health of the individual and the population. At the same time each one of the Health Physics disciplines possesses an independence which increases their efficiency on the safety level. (authors) [French] Le developpement de l'utilisation industrielle de l'energie nucleaire a mis l'accent sur la necessite de promouvoir une doctrine rationnelle et coherente en matiere de securite des installations atomiques et plus particulierement en matiere de securite des sites nucleaires. Le but principal de la securite est de diminuer, voire d'annuler les risques d'irradiation ou de contamination des travailleurs et de la population, consecutifs au fonctionnement normal ou accidentel des installations. La securite est obtenue par la mise en oeuvre d'un ensemble complexe de moyens. Parmi ces moyens les auteurs considerent essentiellement ceux qui presentent une certaine independance a l'egard du type d'installation: moyens d'alerte et de mesure et leur mise en oeuvre - preparation psychologique et technique des individus - evaluation de la capacite d'un site a absorber les rejets radioactifs sans dommage pour la population. Il est clair en effet que les consequences d'un accident sont diminuees par l'augmentation de la valeur des moyens de surveillance, de mesure et d'alerte, l'elevation du niveau technique et l'entrainement du personnel, l'education de la population. Ceci est particulierement vrai aupres d'une installation nucleaire ou l'etude des dangers presente un caractere abstrait et

  8. Contribution to the study of molecular movements in cyclohexane by electron spin resonance and electron-nuclear double resonance using a radical probe; Contribution a l'etude des mouvements moleculaires dans le cyclohexane par resonance paramagnetique electronique et double resonance electronique-nucleaire a l'aide d'une sonde radicalaire

    Energy Technology Data Exchange (ETDEWEB)

    Volino, F. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1969-07-01

    Solutions of stable free radicals of the nitroxide type have been studied as a function of temperature. In the plastic or globular state, the cyclohexane molecules have rapid rotational and diffusional movements. They transmit this movement to dissolved free radicals. Conversely, measurements by electron spin resonance of the absolute movement of the radicals, and by electron nuclear double resonance of their movement relative to the cyclohexane molecules give very precise methods for local analyses of the movement present in the cyclohexane matrix. The principle of these techniques makes up the 'radical probe method'. (author) [French] Des solutions de radicaux libres stables, du type nitroxyde dans le cyclohexane ont ete etudiees, en fonction de la temperature. Les molecules de cyclohexane, dans l'etat plastique ou globulaire, sont animees de mouvements rapides de rotation sur elles-memes et de diffusion. Elles transmettent leur mobilite aux radicaux libres dissous. Reciproquement, la mesure du mouvement absolu des radicaux, a l'aide de la resonance paramagnetique electronique, et celle du mouvement relatif des radicaux et des molecules de cyclohexane par double resonance electronique-nucleaire, constituent des methodes tres precises pour analyser localement les mouvements presents dans la matrice de cyclohexane. Ce principe et ces techniques constituent la 'methode de la sonde radicalaire'. (auteur)

  9. Associative memories in nuclear physics; Les memoires associatives en physique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Blanca, E.; Carriere, A. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    Experiments in nuclear physics involve the use of large size 'memories'. After showing the difficulties arising from the use of such memories, the authors give the principles of the various programming methods which make it possible to operate the memories associatively thus benefiting from a reduction in size and better operational conditions. They attempt to estimate the shape and dimensions of an associative memory with cable connections which could be designed specially for nuclear research, contrary to those actually in service. (authors) [French] Les experiences de physique nucleaire necessitent l'emploi de 'memoires' de grandes dimensions. Apres avoir montre les inconvenients que presente l'utilisation de telles memoires, les auteurs exposent les principes des diverses methodes de programmation qui permettent d'assurer un fonctionnement des memoires sur le mode associatif donc une reduction de leurs dimensions et un meilleur usage. Ils tentent d'evaluer le format d'une memoire associative cablee qui, contrairement a celles qui existent actuellement, serait prevue specialement pour l'experimentation nucleaire. (auteurs)

  10. Nuclear biological studies in France; Les etudes de biologie nucleaires en France

    Energy Technology Data Exchange (ETDEWEB)

    Coursaget, J. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1961-07-01

    On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

  11. Learning about Cri du Chat Syndrome

    Science.gov (United States)

    ... Learning About Prostate Cancer Learning About Cri du Chat Syndrome What is cri du chat syndrome? What ... cri du chat syndrome What is cri du chat syndrome? Cri du chat syndrome - also known as ...

  12. "Cirque du Freak."

    Science.gov (United States)

    Rivett, Miriam

    2002-01-01

    Considers the marketing strategies that underpin the success of the "Cirque du Freak" series. Describes how "Cirque du Freak" is an account of events in the life of schoolboy Darren Shan. Notes that it is another reworking of the vampire narrative, a sub-genre of horror writing that has proved highly popular with both adult and…

  13. "Cirque du Freak."

    Science.gov (United States)

    Rivett, Miriam

    2002-01-01

    Considers the marketing strategies that underpin the success of the "Cirque du Freak" series. Describes how "Cirque du Freak" is an account of events in the life of schoolboy Darren Shan. Notes that it is another reworking of the vampire narrative, a sub-genre of horror writing that has proved highly popular with both adult and…

  14. Restaurant du Rivage, Vevey

    OpenAIRE

    Basini, Sari Bianca; Glocki, Ryszard Nikodem

    2015-01-01

    Après cinquante ans de mutilations, d'abandon et de spéculations économiques, le complexe du château de l'Aile et de la salle du Castillo à Vevey doit redéfinir son rôle public par rapport à la place du Marché et au Jardin du Rivage. S'appuyant sur la mémoire historique en ajoutant une unité à l'ensemble, nous créons un îlot regroupant des fonctions publiques. Il dessert ainsi l'espace ouvert environnant en articulant la relation entre le jardin et la place. L'élargissement de la promenade du...

  15. Atlas du Liban

    Directory of Open Access Journals (Sweden)

    Ramez Philippe Maalouf

    2008-11-01

    Full Text Available Compte-rendu de l’ouvrage Atlas du Liban: territoires et société, sous la direction d’Éric Verdeil, Ghaleb Faour et Sébastien Velut, édition franco-libanaise de l’IFPO (Institut Français du Proche-Orient et du CNRS Liban (Conseil National de la Recherche Scientifique – Liban, Beyrouth 2007.Resenha do livro Atlas du Liban: territoires et société, sob a direção de Éric Verdeil, Ghaleb Faour e Sébastien Velut, editado por iniciativa franco-libanesa do IFPO (Institut Français du Proche-Orient e pelo CNRS Liban (Conseil National de la Recherche Scientifique – Liban, Beirute, 2007.Review of Atlas du Liban: territoires et société, edited by Éric Verdeil, Ghaleb Faour and Sébastien Velut, french-lebanese edition by IFPO (Institut Français du Proche-Orient and CNRS Liban (Conseil National de la Recherche Scientifique – Liban Beirut, 2007.

  16. Ecologie du phytoplancton du lac Kivu

    Directory of Open Access Journals (Sweden)

    Sarmento, H.

    2008-01-01

    Full Text Available Speciation within the African Coffee Pathogen. Cet article analyse s'il est avantageux d'utiliser le compost au lieu de l'engrais minéral pour produire la laitue dans la zone urbaine et péri-urbaine de Yaoundé. Les résultats de terrain montrent l'obtention de rendements et profits plus élevés lorsqu'on utilise le compost. Les résultats de la fonction de production Cobb-Douglas prouvent que l'utilisation du compost est statistiquement significative pour expliquer la variation de rendement de la laitue et que le compost est l'intrant le plus productif. D'autres résultats montrent que le compost fournit la matière organique utile au sol et que les besoins d'irrigation en eau de la culture sont réduits grâce à l'utilisation du compost. Par conséquent, malgré le fait que l'application du compost demande une main-d'oeuvre beaucoup plus élevée, son utilisation est généralement bénéfique pour les agriculteurs vivant aux alentours de Yaoundé. Les programmes de vulgarisation de cet intrant pour encourager son adoption devraient donc figurer parmi les points prioritaires dans la politique agricole du gouvernement camerounais.

  17. MODELES EPIDEMIOLOGIQUES DU SIDA

    OpenAIRE

    M MERAIHI; F. L RAHMANI

    2009-01-01

    L’objectif de cet article est de présenter la modélisation mathématique de la propagation de l’infection dans le contexte de la transmission du virus de l’immunodéficience humaine (VIH) et du syndrome d’immunodéficience acquise (SIDA). Ces modèles sont basés en partie sur les modèles proposés dans le domaine de la modélisation mathématique du SIDA.

  18. The French civilian nuclear: connections and stakes; Le nucleaire civil francais: filieres et enjeux

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This document (18 power point slides) gives an overview of the French civilian nuclear industry and research and development: importance of the nuclear power generation in France, excellence of the education in nuclear sciences, organization of the nuclear connection (CEA, Areva, EDF, IRSN), the role of the French International Nuclear Agency (AFNI), the requirements for a renewal of human resources (French and foreign engineers) in the field of nuclear energy, the degree course for a diploma, examples of engineer and university diplomas, the educational networks in various regions of France, presentation of the Institut National des Sciences et Techniques Nucleaires (Nuclear Sciences and Techniques National Institute) and its master degrees, organization of the French education system in nuclear sciences with strong relations with the research and development programs

  19. The nuclear law: safety. 2006-2010; Le droit nucleaire: la surete 2006-2010

    Energy Technology Data Exchange (ETDEWEB)

    Bringuier, P. [Montpellier-1 Univ., UMR 5815, 34 (France)

    2010-11-15

    The author discusses the legal evolutions related to nuclear safety between 2006 and 2010. He identifies three main topics of unequal importance. Firstly, he comments the implementation of an international reference framework which has been completed at the European level and which aims at the harmonization of safety and security rules. Secondly, he comments the creation of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire). Thirdly, he comments the recast of the standard framework in order to update the French law with respect to the international reference framework. This leaded to a new distribution of power and authority, to more complete and constraining procedures, and to the definition of procedures for each step of an installation life cycle

  20. Nuclear systems of the future - generation 4. Proposals of strategic orientations for the nuclear systems of the future; Les systemes nucleaires du futur - generation 4. Propositions d'orientations strategiques pour les systemes nucleaires du futur

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    Several points, specific to France, must be taken into consideration for the long term strategic choice of future nuclear systems, in particular: taking the best profit of the progress potentialities of water reactors, optimizing the opportunities offered by the renewal of power plants in operation, integrating the consequences and the implementation of a strategy of optimized management of radioactive wastes, and looking for improvements that would make nuclear energy an active contributor to sustainable development. The prospective researches carried out by the CEA and its industrial partners have led to propose a R and D strategy with 3 complementary goals: search for innovations for water reactors, development of fast neutron reactors with closed fuel cycle (sodium fast reactor (SFR), gas fast reactor (GFR)), and development of key-technologies for nuclear hydrogen production (very high temperature reactor (VHTR)). The R and D effort concerns also the subcritical systems devoted to transmutation, the new cycle processes for a global management of actinides, and some other nuclear systems like the molten salt reactors (MSR) and the supercritical water reactors (SCWR). This paper presents the R and D strategy for each technology with its priorities, steps, financial means and collaborations. (J.S.)

  1. Types du Caucase

    OpenAIRE

    Makhacheva, Taus

    2015-01-01

    Tiré du site Internet de Onestar Press: "Types du Caucase - antique postcard collection/ 2013 to the present time. Coming from the personal archive of the artist, these postcards date back to the 19th century and can be considered representative for the "popularized ethnography" of the Russian Empire. Their primitive typology follows the classical rules of exotization : they depict "pittoresque" groups from various tribes, families or nationalities, or representatives of diverse professions. ...

  2. Les outils du CERN

    CERN Multimedia

    1999-01-01

    C'est le plus grand centre mondial de recherche en physique des particules. Les outils du Laboratoire, accélérateurs et détecteurs de particules, figurent parmi les instruments scientifiques les plus complexes au monde. Des prix Nobels ont d'ailleurs été attribués aux physiciens du CERN pour leurs développements.

  3. Contribution of prototypic material tests on the Plinius platform to the study of nuclear reactor severe accident; Contribution des essais en materiaux prototypiques sur la plate-forme Plinius a l'etude des accidents graves de reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Journeau, Ch

    2008-01-15

    The PLINIUS experimental platform at CEA Cadarache is dedicated to the experimental study of nuclear reactor severe accidents thanks to experiments between 2000 and 3500 K with prototypic corium. Corium is the mixture that would be formed by an hypothetical core melting and its mixing with structural materials. Prototypical corium has the same chemical composition as the corium corresponding to a given accident scenario but has a different isotopic composition (use of depleted uranium,...). Research programs and test series have been performed to study corium thermophysical properties, fission product behaviour, corium spreading, solidification and interaction with concrete as well as its coolability. It was the frame of research training of many students and was realized within national, European and international collaborations. (author)

  4. Stress corrosion cracking in the vessel closure head penetrations of French PWR`s; Fissuration par corrosion sous contrainte de penetrations de couvercle de cuve de reacteur nucleaire francais a eau pressurisee

    Energy Technology Data Exchange (ETDEWEB)

    Buisine, D.; Cattant, F.; Champredonde, J.; Pichon, C.; Benhamou, C.; Gelpi, A.; Vaindirlis, M.

    1994-01-01

    During a hydrotest in September 1991, part of the statutory decennial in-service inspection, a leak was detected on the vessel head of Bugey 3, which is one of the first 900 MW 3-loop PWR`s in France. This leak was due to a cracked penetration used for a control rod drive mechanism. The investigations performed identified Primary Stress Corrosion Cracking of Alloy 600 as being the origin of this degradation. So a lot of the same design PWR`s are a concern due to this generic problem. In this case, PWSCC was linked to: - hot temperature of the vessel head; - high residual stresses due to the welding process between peripherical penetrations and the vessel head; - sensitivity of forged Alloy 600 used for penetration manufacturing. This following paper will present the cracked analysis based, in particular, on the main results obtained in France on each of these items. These results come from the operating experience, the destructive examinations and the programs which are running on stress analysis and metallurgical characterizations. (authors). 9 figs., 2 tabs.

  5. Material effects on multiphase phenomena in late phases of severe accidents of nuclear reactors; Effets des materiaux sur les phenomenes multiphasiques se produisant lors des phases avancees d'accident grave de reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Seiler, J.M.; Froment, K

    2003-07-01

    This paper reviews and presents work carried out in the French Atomic Energy Commission (CEA) on the subject of nuclear severe accidents, i.e. those which are accompanied by melting of the nuclear core material. The emphasis is on the (crucial) thermodynamic and material behaviour of corium melts in the solidus-liquidus temperature interval, which is linked to the thermal hydraulic description. A global model approach is proposed. The work is presented in the context of the overall international effort in the area. (authors)

  6. Jules Horowitz reactor - Complementary safety assessment in the light of the Fukushima accident; Reacteur Jules Horowitz - Evaluation complementaire de la surete au regard de l'accident survenu a la centrale nucleaire de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-13

    This CSA (Complementary Safety Assessment) analyses the robustness of the Jules Horowitz reactor (RJH) to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. RJH is being built on the Cadarache CEA's site. Robustness is the ability for the facility to withstand events beyond the level for which the facility was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence (cliff edge effect). Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like RJH's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. This report is divided into 9 main chapters: 1) main features of the RJH facility, 2) identification of cliff edge risks and of equipment essential for safety, 3) earthquake risk, 4) flood risk, 5) risks due to other extreme natural disasters, 6) the loss of electrical power supplies and of cooling systems, 7) management of severe accidents, 8) subcontracting policy, 9) synthesis and list of improvements. This study shows a globally good robustness of the RJH for the considered risks. Nevertheless it can considered relevant to increase the robustness of the plant on a few points: -) to increase the seismic safety margins of some pieces of equipment, -) to increase the robustness of the internal electrical power supplies, -) to increase the fuel cooling capacity, and -) to improve the management of the post-accidental period. (A.C.)

  7. The EPR in a few words: all you need to know about the EPR nuclear reactor; L'EPR en bref: ce qu'il faut savoir sur le reacteur nucleaire EPR

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    After a brief presentation of the EPR (European - or Evolutionary - Pressurized Reactor) type nuclear reactor, this paper, proposed by the collective group 'Stop EPR', develops the following points: EPR is as dangerous as other reactors; EPR flouts democracy; France's energy demand do not need the construction of EPRs; the construction of EPRs is not a factor of economical and social development; EPR should not be constructed neither in France nor elsewhere and the present building sites should be cancelled; the EPR will not help France to increase its energy independence and protect itself from oil price increases; choosing the EPR is incompatible with the large investments to be made in energy conservation and renewable energies; the EPR is not a solution to climate change; the VHV line corridor that will starts at Flamanville is not justified and poses risks to the environment and public health

  8. Contribution to development of SPNDs for instantaneous and selective measurement of different radiation fields in nuclear reactors; Contribution au developpement de collectrons pour la mesure instantanee et selective des differents champs de rayonnements en reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Blandin, Christophe [Institut National Polytechnique, 38 - Grenoble (France)

    1998-02-20

    The objective of this work was conceiving and experimentally optimizing the SPNDs (Self-Powdered Neutron Detector) able to control fast power transients in test reactors and also to cope with requirements of surveillanceand protection of EDF reactors. Thus, different SPND emitters of platinum, gadolinium, hafnium and cobalt were provided according to their nature with sheathing and stainless steel plugs as well as with zirconium over-sheathing in order to render them faster, more selective and adapted for wear checking. Special experimental devices were designed for measuring inside the Siloe reactor the promptness of the signals from SPND, on one hand, and their sensitivity to thermal and epithermal neutrons as well as to gamma rays, on the other hand. The follow-up of power transients in test reactors is ensured by the instantaneous measurement of thermal and epithermal neutron flux as well as of gamma field by means of three special SPND with gadolinium, hafnium and platinum. Also, we have defined the characteristics of a new SPND with cobalt, that delivers a current of unique neutronic origin, able to ensure the surveillance and protection of a power reactor over a period of at least six years.

  9. Earthquake resistance of the PTR and ASG reservoirs of reactors 1 and 2 of the Fessenheim nuclear power plant; Resistance au seisme des reservoirs PTR et ASG des reacteurs 1 et 2 de la centrale nucleaire de Fessenheim

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-04-03

    This decision from the French authority of nuclear safety (ASN) concerns the improvement of the earthquake resistance of the PTR and ASG water tanks of the Fessenheim power plant. The PTR tank (refueling water storage tank) is used to fill up the reactor pool during the loading and unloading of the fuel and it ensures the cooling of the core during some accidental conditions by supplying the safety injection and spray systems. The ASG tank supplies the steam generators in case of failure of the normal water supply systems. A two-times restoration of the tanks has been considered as acceptable: a resistance to a maximum historically probable earthquake must be warranted by July 31, 2001, while a resistance to dimensioning earthquakes must be warranted by November 30, 2001. (J.S.)

  10. Modelling turbulent fluid flows in nuclear and fossil-fired power plants; La modelisation des ecoulements turbulents rencontres dans les reacteurs nucleaires et dans les centrales thermiques a flamme

    Energy Technology Data Exchange (ETDEWEB)

    Viollet, P.L.

    1995-06-01

    The turbulent flows encountered in nuclear reactor thermal hydraulic studies or fossil-fired plant thermo-aerodynamic analyses feature widely varying characteristics, frequently entailing heat transfers and two-phase flows so that modelling these phenomena tends more and more to involve coupling between several branches of engineering. Multi-scale geometries are often encountered, with complex wall shapes, such as a PWR vessel, a reactor coolant pump impeller or a circulating fluidized bed combustion chamber. When it comes to validating physical models of these flows, the analytical process highlights the main descriptive parameters of local flow conditions: tensor characterizing the turbulence anisotropy, characteristic time scales for turbulent flow particle dynamics. Cooperative procedures implemented between national or international working parties can accelerate validation by sharing and exchanging results obtained by the various organizations involved. With this principle accepted, we still have to validate the products themselves, i.e. the software used for the studies. In this context, the ESTET, ASTRID and N3S codes have been subjected to a battery of test cases covering their respective fields of application. These test cases are re-run for each new version, so that the sets of test cases systematically benefit from the gradually upgraded functionalities of the codes. (author). refs., 3 figs., 6 tabs.

  11. Study of water radiolysis in relation with the primary cooling circuit of pressurized water reactors; Etude sur la radiolyse de l`eau en relation avec le circuit primaire de refroidissement des reacteurs nucleaires a eau sous pression

    Energy Technology Data Exchange (ETDEWEB)

    Pastina, B

    1997-07-01

    This memorandum shows a fundamental study on the water radiolysis in relation with the cooling primary circuit of PWR type reactors. The water of the primary circuit contains boric acid a soluble neutronic poison and also hydrogen that has for role to inhibit the water decomposition under radiation effect. In the aim to better understand the mechanism of dissolved hydrogen action and to evaluate the impact of several parameters on this mechanism, aqueous solutions with boric acid and hydrogen have been irradiated in a experimental nuclear reactor, at 30, 100 and 200 Celsius degrees. It has been found that, with hydrogen, the water decomposition under irradiation is a threshold phenomenon in function of the ratio between the radiation flux `1` B(n, )`7 Li and the gamma flux. When this ratio become too high, the number of radicals is not sufficient to participate at the chain reaction, and then water is decomposed in O{sub 2} and H{sub 2}O{sub 2} in a irreversible way. The temperature has a beneficial part on this mechanism. The iron ion and the copper ion favour the water decomposition. (N.C.). 83 refs.

  12. Can-rupture detection in gas-cooled nuclear reactors; La detection des ruptures de gaine dans les piles nucleaires refroidies par gaz

    Energy Technology Data Exchange (ETDEWEB)

    Roguin, A. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    Can-rupture detection (DRG) is one important aspect of pile safety, more particularly so in the case of gas-cooled reactors. A rapid and sure detection constitutes also an improvement as far as the efficiency of electricity-producing nuclear power stations are concerned. Among the numerous can-rupture detection methods, that based on the measurement of the concentration of short-lived fission gases in the heat-carrying fluid has proved to be the most sensitive and the most rapid. A systematic study of detectors based on the electrostatic collection of the daughter products of fission gases has been undertaken with a view to equip the reactors EL 2, G 3, EDF 1, EDF 2 and EDF 3, the gas loops of PEGASE and EL 4. The different parameters are studied in detail in order to obtain a maximum sensitivity and to make it possible to construct detection devices having the maximum operational reliability and requiring the minimum maintenance. The primary applications of these devices are examined in the case of the above-mentioned reactors. (author) [French] La Detection des Ruptures de Gaines (D. R. G.) est un aspect important de la securite des piles et plus particulierement des piles refroidies par un gaz. Une detection rapide et sure constitue aussi un element d'amelioration du rendement des centrales nucleaires productrices d'energie electrique. Parmi les nombreuses methodes de detection des ruptures de gaines, la mesure de la concentration dans le fluide caloporteur des gaz de fission a vie courte s'est revelee comme la plus sensible et la plus rapide. Une etude systematique des detecteurs a collection electrostatique des descendants des gaz de fission a ete entreprise en vue d'equiper les piles EL 2, G 3, EDF 1, EDF 2 et EDF 3, les boucles a gaz de la pile Pegase et la pile EL 4. Les divers parametres sont etudies en detail pour obtenir une sensibilite maximum et permettre la realisation de dispositifs de detection ayant le maximum de securite de

  13. Civil liability and nuclear coverage: synthesis report; Responsabilite civile et coverture nucleaires. Rapport du Groupe de Travail

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The report has been written considering the advanced work which has been done by the Expert Committee, sponsored by the International Atomic Energy Agency (IAEA), Vienna, having the purpose to examine the modifications issued in course of Vienna Convention as well as the Paris convention and the complementary Brussels Convention, in view to adapt the legislation to the actual context and to answer the populations expectations. The work has been organized in three majors chapters: the first one in concerned to the damage definition, proposition to the to reach the environment, the prevention and charges. the research and military installations are also considered. The second chapter has been dedicated to the civil responsibility, its limits, financing modes, the national and international legal competence besides the litigation charges due to the nuclear accidents born on the occasion. In the third chapter the insurance considering the damage nature, the capacity to assure liability coverage and the damage management are harmonized.

  14. Nuclear power plant of Fessenheim: evaluation of the seismic risk; Centrale Nucleaire de Fessenheim: appreciation du risque sismique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The seismic risk taken into account during the sizing of the nuclear power plant of Fessenheim seems to have been under evaluated at this time. The revaluation of the seismic risk, as proposed, until this day by EDF in order to the third ten-year visit of the power plant, planned for 2009, leads to a significant under evaluation of the risk and then is not acceptable. The present expertise details point by point the weaknesses of these revaluation. The power plant has been sized in an elastic manner that is generally strongly for the safety side. It is imperative to proceed the most quickly as possible to a deep control of the seismic resistance of the power plant of Fessenheim and then after having proceeded to a revision of the seismic risk in taking into account the actual knowledge in this field. (N.C.)

  15. Fessenheim: 30 years of nuclear fuel operation; Fessenheim: 30 ans d'exploitation du combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Abgrall, G. [Centrale de Fessenheim, EDF, 68 - Dessenheim (France)

    2008-03-15

    Fessenheim units 1 and 2 are the first two 900 MW PWR put into operation in France (1977). This article reviews 30 years of change, optimization and feedback experience from Fessenheim, concerning: -) fuel assemblies (particularly the design of some components like grids, ends and guide tubes), -) the reload fuel management (to get a higher unloading burn-up), -) the refueling machine and tools (heavy modifications to reduce the human factor), and -) work organization (work shifts and staff training). (A.C.)

  16. Propagation of neutrinos in nuclear matter; Effets du milieu sur la propagation des neutrinos dans la matiere nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Margueron, J

    2001-07-01

    We study the elementary interactions between neutrinos and dense matter in a proto-neutron star. Equations of state obtained with different nuclear effective interactions (Skyrme, Gogny, Relativistic Lagrangians) are first discussed. Then, we characterize their stability in spin and isospin. We derive magnetic susceptibilities for all isospin asymmetry values as a function of Landau parameters G{sup {pi}}{sup {pi}}{sup '}{sub 0} (where {pi}, {pi}' = proton or neutron). From this work, we select a parametrization for each of the 3 effective forces: Sly230b,D1P,NL3. We calculate the pure neutron matter and asymmetric nuclear matter response functions with and without charge exchange, describing nuclear correlations in both approaches: non-relativistic (Hartree-Fock with Skyrme forces, then complete RPA) and relativistic (in the Hartree approximation). At the end, we calculate neutrino mean free paths neutral current and charged current reactions. Comparisons between relativistic and non-relativistic approaches allow us to identify relativistic effects in nuclear matter at densities as low as twice the saturation density. RPA correlations make the medium more transparent to neutrinos compared to free Fermi gas. The importance of the effective mass in mean free path calculations is also shown. (author)

  17. IAEA and the international nuclear law development; L`A.I.E.A. et le developpement du droit nucleaire international

    Energy Technology Data Exchange (ETDEWEB)

    Jankowitsh, O. [International Atomic Energy Agency, Vienna (Austria)

    1996-10-01

    This paper summarizes the different objectives of the IAEA (International Atomic Energy Agency) as far as nuclear energy use is concerned. It presents the status of the organization, its action int the non-proliferation treaty, and its work on the safeguard regulations. These measures have been taken during the Convention on nuclear safety in 1994. This convention concerns nuclear power plants as well as storage of radioactive wastes. (TEC).

  18. The radioactive wastes management of the little nuclear industry; La gestion des dechets radioactifs du nucleaire diffus

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Among the ANDRA customers, more than one million are little producers: hospital, research centers and industries. They are called little producers because of the low volume of produced wastes. Meanwhile these wastes management need an appropriate technology which is presented in this document. (A.L.B.)

  19. The nuclear industry: a new weapon for the Kremlin?; L'industrie nucleaire: nouvelle arme du Kremlin?

    Energy Technology Data Exchange (ETDEWEB)

    Du Castel, V.

    2010-07-01

    After having noticed the recent evolution of the Russian policy which tends to concentrate the economical and political power with a limited democratic pluralism, the author describes the re-structuring policy adopted for the energy sector, and notably the nuclear sector, in order to become a major international actor. First, she analyses the evolution of the hydrocarbon sector with a better management of tax incomes, and a stronger control of the industries of this sector based on a State capitalism development. She outlines that Russia now uses energy as a diplomatic arm, particularly in its relationship with the European Union. She states that Russia may want to follow the same kind of policy for nuclear energy as for the hydrocarbon sector by developing partnership with other countries, by regrouping the concerned activities within a single holding company (Atomenergoprom) and a federal agency (Rosatom). Russia increased its uranium production and became a powerful actor who challenges other international companies (Areva, Westinghouse, Toshiba). The author discusses the strategy defined by the Kremlin to reach supremacy in the nuclear sector

  20. Facing the climatic threat, the nuclear illusion; Face a la menace climatique, l'illusion du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    In the framework of the energy problem, the network Action Climate brings many propositions to explain that the nuclear is not a solution to the global warming. A boost to the nuclear will be done to the detriment of cheaper, safer and more adapted policies, as the energy conservation and efficiency, the energy production decentralization and the renewable energies development. The three parts shows how the nuclear cannot answer to the climatic problem, the nuclear refutes the Rio declaration on the environment and the sustainable development, the nuclear is a french specificity which damages the national policy against the climatic change. (A.L.B.)

  1. Japan abandons its all-nuclear policy; Le Japon s'eloigne du tout-nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Triendl, R. [Asian Technology Information Program, Tokyo (Japan)

    2000-06-01

    Japanese courts appear to be very lenient concerning accidents in nuclear facilities, and as a consequence they do not play an active role in reinforcing safety measures or questioning security procedures that have failed. Because of a series of accidents in nuclear facilities, the Japanese society becomes more aware of the weaknesses of the nuclear industry concerning safety. The MITI might relinquish its only-nuclear-energy policy and promote natural gas. (A.C.)

  2. Qualification of the Darwin code for the studies of the fuel cycle relative to the boiling water reactors; Qualification du formulaire Darwin pour les etudes du cycle du combustible pour les reacteurs a eau bouillante

    Energy Technology Data Exchange (ETDEWEB)

    Allais, V

    1998-03-01

    This thesis was carried out in the framework of fuel cycles studies in partnership with COGEMA; the aim is to determine physics parameters characterising Boiling Reactor Assemblies. Those reactors Firstly distinguish themselves from Pressurised Water Reactor by the boiling of the moderator in the core and secondary by the strong neutronics heterogeneity due to complex design. The diphasic mixture formed is characterised by the void fraction parameter. The loss of information, and neutronic studies characteristics of Boiling Water Reactors led us to make preliminary studies having in view to quantify the void fraction impact on the isotopics evolution. Studies on neutronics influence of assemblies and control rods from the immediate environment allows to define the cluster size to describe. The radial description optimisation with APOLLO-2 is necessary to improve the calculation performance and to reduce the errors coming from the modelization. The following points were studied: pellet radial discretization, clustering of cells characterized by a similar behaviour, options in flux spatial calculation (interface current formalism), self-shielding optimisation (specific to each isotopes). The three dimensional modelization with CRONOS-2 and the simplified accounting of the thermohydraulics / neutronics coupling done by a procedure developed and written during this thesis, allow an evaluation of axial distribution of void fraction, power and burn-up during the irradiation. The comparison with experimental analytic results of complete assembly and pin samples dissolutions allows the qualification of this procedure and confirms the necessity to take into account the void fraction axial variation during the evolution. The application of an automatic coupling with the DARWIN cycle code will allow a precise burnup calculation to be utilized in an industrial procedure. (author)

  3. Study of gas-solid contact in an ultra-rapid reactor for cumene catalytic cracking; Etude du contact gaz-solide dans un reacteur a co-courant descendant par la mise en oeuvre du craquage catalytique du cumene

    Energy Technology Data Exchange (ETDEWEB)

    Bayle, J.

    1996-11-05

    Few studies have been carried out on the notion of gas-solid contact in ultra-rapid reactors. Both gas and solid move in the reactor and the contact can be directly estimated when using a chemical reaction such as cumene cracking. It`s a pure and light feedstock whose kinetics can be determined in a fixed bed. The study was carried out on a downflow ultra-rapid reactor (ID = 20 mm, length = 1 m) at the University of Western Ontario. It proved that the quench and the ultra-rapid separation of gas and solid must be carefully designed in the pilot plant. Cumene conversion dropped when reducing gas-solid contact, which led to push the temperature over 550 deg. C and increase the cat/oil ratio at 25 working at solid mass fluxes below 85 kg/m{sup 2}.s. Change of selectivity at very short residence time were also observed due to deactivation effects. Experiments made by Roques (1994) with phosphorescent pigments on the Residence Time Distribution of solids gave Hydrodynamic data on a cold flow copy of the pilot plant. Experiments made on packed bed gave kinetic data on the cracking of cumene. These data were combined to optimize a mono dimensional plug flow model for cumene cracking. (author)

  4. The evaluation of the nuclear facilities safety at the CEA from 1999 to 2001; Le bilan de la surete des installations nucleaires du CEA du 1999 a 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-11-01

    The aim of this document is the presentation of an evaluation of the problems and the safety methods in the concerned period. The first chapter presents the nuclear safety in the CEA. The second chapter is devoted to the organization and the quality for the safety: liabilities, audits, relations with the safety authorities and with the public. The chapters three and four deal respectively with the methodological and technical abilities supporting the exploitation teams and with the nuclear safety projects. The last chapter presents the experiments and events from 1999 to 2001. (A.L.B.)

  5. Phasing out nuclear: shock statements by the EDF's CEO; Sortie du nucleaire: les declarations chocs du PDG d'EDF

    Energy Technology Data Exchange (ETDEWEB)

    Benezet, E.; Mouchon, F.; Lomazzi, M.; Jeanne, M.

    2011-11-09

    While costs associated with phasing out nuclear or cancelling of nuclear programs are briefly evoked for different European countries (Belgium, Germany, Italy), the EDF Chairman, Mr Proglio, comments the decisions of these countries, outlines the various risks associated with such a decision in France (job losses, greenhouse gas emissions), also outlines EDF involvement in nuclear safety and evokes the issues of Fessenheim and of the EPR. Some French political aspects on that matter are also evoked

  6. Atomic scale modelling of materials of the nuclear fuel cycle; Modelisation a l'echelle atomique de materiaux nucleaires du cycle du combustible

    Energy Technology Data Exchange (ETDEWEB)

    Bertolus, M.

    2011-10-15

    This document written to obtain the French accreditation to supervise research presents the research I conducted at CEA Cadarache since 1999 on the atomic scale modelling of non-metallic materials involved in the nuclear fuel cycle: host materials for radionuclides from nuclear waste (apatites), fuel (in particular uranium dioxide) and ceramic cladding materials (silicon carbide). These are complex materials at the frontier of modelling capabilities since they contain heavy elements (rare earths or actinides), exhibit complex structures or chemical compositions and/or are subjected to irradiation effects: creation of point defects and fission products, amorphization. The objective of my studies is to bring further insight into the physics and chemistry of the elementary processes involved using atomic scale modelling and its coupling with higher scale models and experimental studies. This work is organised in two parts: on the one hand the development, adaptation and implementation of atomic scale modelling methods and validation of the approximations used; on the other hand the application of these methods to the investigation of nuclear materials under irradiation. This document contains a synthesis of the studies performed, orientations for future research, a detailed resume and a list of publications and communications. (author)

  7. Le rythme du silence

    OpenAIRE

    Meschonnic, Henri

    2017-01-01

    1. Pour rompre le silence Dire « rythme du silence », c’est non seulement penser le silence comme langage, et parfois la réalisation maximale du langage, mais aussi parcourir les acceptions de la notion de silence. De ce qui n’est pas dit, ou qu’on est incapable de dire à ce que les mots ne peuvent pas dire, le fameux indicible, mais aussi l’innommable, et la censure, faire silence sur, jusqu’au problème poétique. Il y a aussi une langue de bois du silence. Et aussi le silence de ce qu’on ent...

  8. La profanation du montage

    OpenAIRE

    Hildebrandt, Toni

    2017-01-01

    Cet article examine les liens entre, pour l’aspect technique, le plan séquence et le montage, et, pour l’aspect philosophico-historique, la vie quotidienne et la politique mondiale, du point de vue d’une profanation capable de désamorcer la puissance et avec une attention particulière portée à l’unique film expérimental de Pasolini : La sequenza del fiore di (1968). Ce court métrage n’a pas seulement un statut spécial dans la filmographie de Pasolini, il marque aussi un tournant du tragique v...

  9. Utilisation de l'essai comete et du biomarqueur gamma-H2AX pour detecter les dommages induits a l'ADN cellulaire par le 5-bromodeoxyuridine post-irradiation

    Science.gov (United States)

    La Madeleine, Carole

    Ce memoire est presente a la Faculte de medecine et des sciences de la sante de l'Universite de Sherbrooke en vue de l'obtention du grade de maitre es sciences (M.Sc.) en radiobiologie (2009). Un jury a revise les informations contenues dans ce memoire. Il etait compose de professeurs de la Faculte de medecine et des sciences de la sante soit : Darel Hunting PhD, directeur de recherche (departement de medecine nucleaire et radiobiologie), Leon Sanche PhD, directeur de recherche (departement de medecine nucleaire et radiobiologie), Richard Wagner PhD, membre du programme (departement de medecine nucleaire et radiobiologie) et Guylain Boissonneault PhD, membre exterieur au programme (departement de biochimie). Le 5-bromodeoxyuridine (BrdU), un analogue halogene de la thymidine reconnu depuis les annees 60 comme etant un excellent radiosensibilisateur. L'hypothese la plus repandue au sujet de l'effet radio sensibilisant du BrdU est qu'il augmente le nombre de cassures simple et double brin lorsqu'il est incorpore dans l'ADN de la cellule et expose aux radiations ionisantes. Toutefois, de nouvelles recherches semblent remettre en question les observations precedentes. Ces dernieres etudes ont confirme que le BrdU est un bon radiosensibilisateur, car il augmente les dommages radio-induits dans l'ADN. Mais, c'est en etant incorpore dans une region simple brin que le BrdU radiosensibilise l'ADN. Ces recherches ont egalement revele pour la premiere fois un nouveau type de dommages produits lors de l'irradiation de l'ADN contenant du BrdU : les dimeres interbrins. Le but de ces travaux de recherche est de determiner si la presence de bromodeoxyuridine dans l'ADN augmente l'induction de bris simple et / ou double brin chez les cellules irradiees en utilisant de nouvelles techniques plus sensibles et specifiques que celles utilisees auparavant. Pour ce faire, les essais cometes et la detection des foci H2AX phosphorylee pourraient permettre d'etablir les effets engendres par

  10. Study of the long-term values and prices of plutonium; a simplified parametrized model; Etude des valeurs et des prix du plutonium a long terme; un modele parametre simplifie

    Energy Technology Data Exchange (ETDEWEB)

    Gaussens, J.; Paillot, H. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    The authors define the notions of use values and price of plutonium. They give a 'simplified parametrized model' simulating the equilibrium of the offer and the demand in time, concerning the plutonium and the price deriving from the relative scarcity of this metal, taking into account the technical and economic operating parameters of the various reactors confronted. This model is simple enough to allow direct computations and establish clear relations between the various parameters. The use of the linear programmes method allows on the other hand a wide extension of the model. This report includes three main parts: I - General description of the study (without detailed calculations) II - Mathematical development of the simplified parametrized model and application (the basic data and the results of the calculations are given) III - Appendices (giving the detailed computations of part II). (authors) [French] Les auteurs definissent les notions de valeurs d'usage et de prix du plutonium. Ils donnent un 'modele parametre simplifie' simulant l'equilibre de l'office et de la demande dans le temps concernant le plutonium et le prix qui decoule de la rarete relative de ce metal, compte tenu des parametres techniques et economiques de fonctionnement des divers reacteurs en presence. Ce modele est suffisamment simple pour permettre des calculs manuels et etablir des liaisons claires entre les divers parametres. L'utilisation de la technique des programmes lineaires permet par ailleurs une extension considerable du modele. Cette note comprend trois parties: I - Expose general de l'etude (sans expose du detail des calculs) II - Developpement mathematique du modele parametre simplifie et application (on precise les donnees de base et le resultat des calculs) III - Annexes (donnant le detail des calculs de la partie II). (auteurs)

  11. Historique du Web

    CERN Multimedia

    TV8 Mont-Blanc

    1995-01-01

    Documentaire court qui retrace l'implication de différentes personalités à la création du Web. Entrevues avec Robert Cailliau, Chris Llewellyn-Smith, David Williams, Tim Berners-Lee, Mike Sendall, Brian Carpenter.

  12. La foret du Banco

    NARCIS (Netherlands)

    Koning, de J.

    1983-01-01

    Deze publicatie over het Nationaal Park 'La Forêt du Banco' nabij Abidjan, Ivoorkust, verschijnt als resultaat van vier jaar veldwerk (1972-1976) in dat land.Het Centre Néerlandais, onderzoeks- en stageverblijf van de Landbouwhogeschool, was basis en de faciliteiten verleend door het Franse ORSTOM-i

  13. Origine du vieux slave

    Directory of Open Access Journals (Sweden)

    Witold Mańczak

    2005-12-01

    Full Text Available Comme, pour prouver l'identité du vieux slave et du vieux bulgare, on invoque uniquement des critères phonétiques, rappelons que l'orientaliste allemand du XVIIe siècle Ludolf affirmait déjà que "die Sprachverwandtschaft offenbart sich nicht im Wörterbuch, sondern in der Grammatik"3. Pendant les 300 dernières années, tellement d'autorites ant approuvé !l’opinion de Ludolf qu'elle est devenue un dogme de la linguistique. Pourtant il nous est venu à l'esprit de le confronter avec des faits et ainsi nous sommes arrivé à la conclusion qu'en réalité, c'est le vocabulaire (et non la phonétique et la flexion qui décide du degre de la parenté des langues4. Voici des arguments à l'appui de cette thèse.

  14. Integral validation of the effective beta parameter for the MOX reactors and incinerators; Validation integrale des estimations du parametre beta effectif pour les reacteurs Mox et incinerateurs

    Energy Technology Data Exchange (ETDEWEB)

    Zammit-Averlant, V

    1998-11-19

    {beta}{sub eff}, which represents the effective delayed neutron fraction, is an important parameter for the reactor nominal working as well as for studies of its behaviour in accidental situation. In order to improve the safety of nuclear reactors, we propose here to validate its calculation by using the ERANOS code with ERALIB1 library and by taking into account all the fission process physics through the {nu} energy dependence. To validate the quality of this calculation formalism, we calculated uncertainties as precisely as possible. The experimental values of {beta}{sub eff}, as well their uncertainties, have also been re-evaluated for consistency, because these `experimental` values actually contain a calculated component. We therefore obtained an entirely coherent set of calculated and measured {beta}{sub eff}. The comparative study of the calculated and measured values pointed out that the JEF2.2 {nu}{sub d} are already sufficient because the (E-C)/C are inferior to 3 % in average and in their uncertainly bars. The experimental uncertainties, even if lightly superior to those previously edited, remain inferior to the uncertainties of the calculated values. This allowed us to fit {nu}{sub d} with {beta}{sub eff}. This adjustment has brought an additional improvement on the recommendations of the {nu}{sub d} average values, for the classical scheme (thermal energy, fast energy) and for the new scheme which explains the {nu}{sub d} energy dependence. {beta}{sub eff}, for MOX or UOX fuel assemblies in thermal or fast configurations, can therefore be obtained with an uncertainty due to the nuclear data of about 2.0 %. (author) 110 refs.

  15. Analyse du transfert de chaleur et de la perte de pression pour des ecoulements supercritiques dans le reacteur CANDU-SCWR

    Science.gov (United States)

    Zoghlami, Sarra

    The supercritical water reactor is one of the six concepts of generation IV nuclear reactors that has been selected by the International Generation IV Forum (GIF). Canada has chosen to conduct advanced research on this type of reactor. For the design and safety analysis of the reactor concept, the development of numerical simulation codes is needed. The ARTHUR code is a thermal-hydraulic computer code developed by Fassi-Fehri (2008), at the Ecole Polytechnique de Montreal, to analyse the CANDU-6 reactor. The purpose of this project is to modify this numerical code so that it can be used to treat the CANDU-SCWR. To calculate the coolant thermal-hydraulics properties in the fuel channel of a CANDU-SCWR, it was assumed that the water flows under supercritical conditions is a one-phase flow. Thus within this code, we developed the conservation equations for one-phase flow. Hydraulic resistance and heat transfer at supercritical pressure are two important aspects to be considered in the modeling of a fuel channel in a nuclear reactor. To choose the accurate correlation to predict the pressure friction factor, we compared numerical calculations, using different correlations found in literature, to experimental data. We concluded that the Garimella (2008) correlation is the most consistent, to be incorporated in the ARTHUR &barbelow;SCWR code. We proved that the choice of the friction factor correlation affects slightly the distribution of thermal-hydraulic properties in the fuel channel. Under supercritical conditions, water thermal-physical properties are characterized by significant variations in the pseudo-critical region. This behavior influences the forced convection heat transfer phenomena. To choose the adequate correlation to calculate the forced convection heat transfer coefficient, we compared numerical results to experimental data, and we found that the standard deviation given by Mokry et al. (2010) correlation is the lowest. In order to model the fuel channel, some geometrical simplifications are made. In fact, we assumed that the coolant flow in the fuel channel is represented by the flow around the fuel rod, bounded by the first crown. This simplified model was used for neutronic/thermal-hydraulic coupled calculation performed with neutronic codes DRAGON/DONJON (Varin et al., 2005), to analyse the thermal-hydraulic behavior of the fuel channel in CANDU-SCWR. We observed that the coolant density at the fuel rod external surface, at the sixth fuel bundle is 3.5 times lower than the average coolant density in the fuel channel. This puts into question the assumption of considering the supercritical water flow as an homogeneous flow and the ability to build a supercritical water nuclear reactor in CANDU type, i.e., with horizontal fuel channels. In order to validate ARTHUR &barbelow;SCWR code, we compared our results to SUBCHAN code (Jiang et al., 2009), which is a thermal-hydraulic code developed to analyze CANDU-SCWR. Both codes give the same shapes and orders of magnitude for the coolant average temperature and the cladding-surface temperature. The axial distribution of the centerline temperature in the fuel rod is different. This is due to the fact that the calculations performed by the SUBCHAN code are not coupled to a neutronic code. For this reason, the thermal power distributions differs in the two codes. The variation of the mass flow influences the forced convective heat transfer, so, the distribution of thermal-physical properties in the channel. In fact, if the mass flow is reduced by 50% compared to the nominal mass flow rate, following a pump failure, the external fuel rod surface temperature exceeds the melting point, which is between 1400°C and 1455°C. This phenomenon may results in the radioactive contamination of the environment.

  16. A.S.N. regulation of Flamanville 3 EPR construction; L'inspection du reacteur Flamanville 3 de type EPR

    Energy Technology Data Exchange (ETDEWEB)

    Limousin, S. [Autorite de Surete Nucleaire, 75 - Paris (France)

    2009-02-15

    The EPR authorization decree for Flamanville 3 was issued by the French government (decree no. 2007-534) on the 10 April 2007. The construction activities are going on in the manufacturer workshops and at Flamanville site. The decree published in November 2007, and related to the so called TSN law (the nuclear transparency and safety nuclear law published in 2006), specifies that the commissioning licence (the agreement for first fuel load) has to be granted by an ASN decision on the basis of the assessment of the demonstration of the plant safety. In this aim, one part of ASN's work is to review, with its technical sup-port organisation (IRSN), the reactor construction in order to appreciate the safety level of the construction activities. This paper describes ASN's strategy for the regulation of Flamanville 3 EPR construction activities, endorsed by ASN commission at the end of November 2007, and the main events which have occurred on Flamanville site since the beginning of the construction. The article presents the main ASN conclusions of this regulation at this time. (author)

  17. ASN reviews the safety options of the new reactor ATMEA-1; L'ASN engage la revue des options de surete du nouveau reacteur ATMEA-1

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2010-07-15

    The French authorities of nuclear safety (ASN) have announced that they were asked by the ATMEA company to review the safety options of a new power reactor called ATMEA-1. ATMEA is a common sub-company between Areva and Mitsubishi Heavy Industries. ATMEA-1 belongs to the intermediate power range with a power output of 1100 MWe, this reactor is designed to be exported. ASN will make public the conclusions of this review in autumn 2011. ASN backs the WENRA initiative that states that the safety levels of new reactors must be higher than those of today's operating reactors. (A.C.)

  18. The ISRN has stated on the CABRI reactor restarting; L'IRSN a donne son avis sur le redemarrage du reacteur CABRI

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This paper presents the different issues examined by the ISRN (the French Institute of Radioprotection and Nuclear Safety) for the restarting of the pool type research CABRI reactor which is briefly described in appendix. These issues are: the design, realisation and monitoring of the new pressurised water test loop, the reassessment of the protection system limiting the reactivity injection during tests, inspection of fuel pencil condition, reassessment of safety studies, inspection of the condition of existing equipment which are essential for safety, reassessment of the seismic risk and of the fire risk, reassessment of operation conditions (personal radioprotection, human and organisational factors). An appendix contains the report by the Permanent Group of Experts for Nuclear Reactors with its recommendations.

  19. Mechanical, chemical and radiological characterization of the graphite of the UNGG reactors type; Caracterisation mecanique, chimique et radiologique du graphite des reacteurs de la filiere UNGG

    Energy Technology Data Exchange (ETDEWEB)

    Bresard, I.; Bonal, J.P

    2000-07-01

    In the framework of UNGG reactors type dismantling procedures, the characterization of the graphite, used as moderator, has to be realized. This paper presents the mechanical, chemical and radiological characterizations, the properties measured and gives some results in the case of the Bugey 1 reactor. (A.L.B.)

  20. Study of the seismic behaviour of the fast reactor cores; Etude du comportement sismique des coeurs de reacteurs a neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Cerqueira, E

    1998-12-31

    This work studies the seismic behaviour of fast neutrons reactor cores. It consists in analyzing the tests made on the models Rapsodie and Symphony by using the calculation code Castem 2000. Te difficulty is in the description of connections of the system and the effects of the fluid (calculation in water). The results for the programme Rapsodie are near the experimental results. For the programme Symphony, the calculations in air have allowed to represent the behaviour of fuel assemblies in a satisfying way. It is still to analyze the tests Symphony in water. (N.C.)

  1. Engine jet entrainment in the near field of an aircraft; Entrainement du jet d`un reacteur dans le champ aerodynamique proche d`un avion

    Energy Technology Data Exchange (ETDEWEB)

    Garnier, F.; Jacquin, L.; Laverdant, A.

    1997-12-31

    A simplified approach has been applied to analyse the mixing and entrainment processes of the engine exhaust through their interaction with the vortex wake of an aircraft. Our investigation is focused on the near field, extending from exit nozzle to the beginning of the vortex phase (i.e. to about twenty seconds after the wake is generated). This study is performed using an integral model and a numerical simulation for a two engine large civil aircraft. The properties of the wing-tip vortices on the calculation of the dilution ratio (defined as a tracer concentration) have been shown. The mixing process is also affected by the buoyancy effect, but only after the jet regime, when the trapping in the vortex core has occurred. Qualitative comparison with contrail photography shows similar features. Finally the distortion and stretching of the plume streamlines inside the vortices can be observed, and the role of the descent of the vortices on the maximum tracer concentration has been discussed. (author) 19 refs.

  2. Analysis and evaluation of the hydrogen risk in a thermonuclear fusion reactor; Analyse et evaluation du risque hydrogene dans un reacteur de fusion thermonucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Chaudron, V. [Societe Helion, 13 - Aix en Provence (France); Arnould, F. [Technicatome DI SEPS, 13 - Aix en Provence (France); Latge, C. [CEA Cadarache, Dept. d' Etudes des Dechets DED, 13 - Saint Paul lez Durance (France); Laurent, A. [Ecole Nationale Superieure des Industries Chimiques, ENSIC, Lab. des Sciences du Genie Chimique, CNRS INPL, 54 - Villers les Nancy (France)

    2001-07-01

    After a recall of the principle of controlled thermonuclear fusion, the ITER reactor project is briefly described. The integrity of the reactor must be preserved in the case of a potential explosion of the hydrogen generated inside the reactor, in order to avoid any dispersion radioactive, chemical or toxic materials in the environment. The fundamental principles of safety developed to fulfill these objectives, in particular the defense-in-depth concept, are presented. The main potential source of hydrogen production is the oxidation of beryllium, which is used as protection material in the first wall of the torus, and the accidental presence of water, as reported in several scenarios. The confinement strategy is then described with the qualification of the role of the different barriers. Finally, the hydrogen explosion risk is analyzed and evaluated with respect to the sources, to the reference envelope scenarios and to the location of hydrogen inside the ITER reactor. It appears, at the engineering stage, that the vacuum toric vessel, the discharge reservoir and the exchanger compartments are the most worrying parts. (J.S.)

  3. Systemic model for the aid for operating of the reactor Siloe; Modelisation systeme pour l`aide a l`exploitation du reacteur de recherche Siloe

    Energy Technology Data Exchange (ETDEWEB)

    Royer, J.C.; Moulin, V.; Monge, F. [CEA Centre d`Etudes de Grenoble, 38 (France). Direction des Reacteurs Nucleaires; Baradel, C. [ITMI APTOR, 38 - Meylan (France)

    1995-12-31

    The Service of the Reactor Siloe (CEA/DRN/DRE/SRS), fully aware of the abilities and knowledge of his teams in the field of research reactor operating, has undertaken a project of knowledge engineering in this domain. The following aims have been defined: knowledge capitalization for the installation in order to insure its perenniality and valorization, elaboration of a project for the aid of the reactor operators. This article deals with the different actions by the SRS to reach the aims: realization of a technical model for the operation of the Siloe reactor, development of a knowledge-based system for the aid for operating. These actions based on a knowledge engineering methodology, SAGACE, and using industrial tools will lead to an amelioration of the security and the operating of the Siloe reactor. (authors). 13 refs., 7 figs.

  4. Localized fast neutron flux enhancement for damage experiments in a research reactor; Accroissement local du flux rapide pour des experiences de dommages dans un reacteur de recherche

    Energy Technology Data Exchange (ETDEWEB)

    Malouch, F

    2003-06-01

    In irradiation experiments on materials in the core of the Osiris reactor (CEA-Saclay) we seek to increase damage in irradiated samples and to reduce the duration of their stay in the core. Damage is essentially caused by fast neutrons (E {>=} 1 MeV); we have therefore pursued the possibility of a localized increase of their level in an irradiation experiment by using a flux converter device made up of fissile material arranged according to a suitable geometry that allows the converter to receive experiments. We have studied several parameters that are influential in the increase of fast neutron flux within the converter. We have also considered the problem of the converter's cooling in the core and its effect on the operation of the reactor. We have carried out a specific neutron calculation scheme based on the modular 2D-transport code APOLLO2 using a two-level transport method. Experimental validation of the flux calculation scheme was carried out in the ISIS reactor, the mock-up of OSIRIS, by optimizing the loading of fuel elements in the core. The experimental results show that the neutron calculation scheme computes the fluxes in close agreement with the measurements especially the fast flux. This study allows us to master the essential physical parameters needed for the design of a flux converter in an MTR reactor. (author)

  5. Aux origines du monde

    CERN Multimedia

    2004-01-01

    "C'est l'histoire d'une aventure humaine, scientifique, international qui a vu le jour il y a cinquante ans, aux confins de la Suisse et du département de l'Ain. Le plus grand laboratoire de physique des particules du monde, le Cern, a été fondé en 1954. Les festivités organisées à l occasion de cet anniversaire connaîtront leur point d'orgue le 16 octobre prochain, avec portes-ouvertes, accueil de personallités et inauguration d'un monumnet spécifique, le Globe de l'innovation" (2 pages)

  6. Images du Valais

    Directory of Open Access Journals (Sweden)

    Micheline COSINSCHI

    1995-06-01

    Full Text Available Une étude des revenus fiscaux ventilés par branches économiques permet de clore un ouvrage portant sur ce canton alpin suisse par excellence qu’est le Valais. Pris comme traceurs de l’activité régionale, l’analyse de leurs configurations spatiales permet une évaluation pouvant être considérée comme une mesure de l’efficacité différentielle du système socio-spatial valaisan. L’article décrit certains processus qui ont permis la réalisation du dernier chapitre d’un atlas portant sur le Valais.

  7. CHOEUR DU CERN

    CERN Multimedia

    CHOEUR DU CERN

    2010-01-01

    Les répétitions du chœur du CERN reprendront le mercredi 15 septembre à 20.00 heures à l’amphithéâtre principal – bâtiment 500. Au programme la préparation de notre concert de Noël avec la Missa Brevis, KV115, de Léopold Mozart et de la musique de Noël d’Europe. Les personnes qui aiment chanter, notamment des sopranes et des ténors, sont les bienvenues. Pour tout contact s’adresser à : Baudouin Bleus - (tél.CERN 767 82 44) -(baudouin.bleus@cern.ch) ou Martin Gatehouse ( martin.gatehouse@wanadoo.fr) ou Jean-Paul Diss (jean-pauldiss@wanadoo.fr).  

  8. Oklo: The fossil nuclear reactors. Physics study - Translation of chapters 6, 13 and conclusions

    Energy Technology Data Exchange (ETDEWEB)

    Naudet, R. [CEA, Paris (France)

    1996-09-01

    Three parts of the 1991 book `Oklo: reacteurs nucleaires fossiles. Etude physique` have been translated in this report. The chapters bear the titles `Study of criticality`(45 p.), `Some problems with the overall functioning of the reactor zones`(45 p.) and `Conclusions` (15 p.), respectively.

  9. Les Cahiers du CREAD

    African Journals Online (AJOL)

    Admin

    les littératures économique et gestionnaire, mais souvent dans ces travaux, l'effet de ... chiffre d'affaires du nouvel ensemble résultant de la vente des produits mieux .... syndicalisme, droit de grève), fiscales (différents taux d'imposition, etc.) .... nouvel ensemble et aussi, les différentes relations avec les alliances verticales ...

  10. La mesure du danger

    CERN Document Server

    Manceron, Vanessa; Revet, Sandrine

    2014-01-01

    La mesure du danger permet d’explorer des dangers de nature aussi diverse que la délinquance, la pollution, l’écueil maritime, la maladie ou l’attaque sorcellaire, l’extinction d’espèces animales ou végétales, voire de la Planète tout entière. Au croisement de la sociologie, de l’anthropologie et de l’histoire, les différents articles analysent les pratiques concrètes de mesure pour tenter de comprendre ce qui se produit au cours de l’opération d’évaluation du danger sans préjuger de la nature de celui-ci. L’anthropologie a contribué à la réflexion sur l’infortune en s’intéressant aux temporalités de l’après : maladies, catastrophes, pandémies, etc. et en cherchant à rendre compte de l’expérience des victimes, de leur vie ordinaire bouleversée, de la recomposition du quotidien. Elle s’intéresse aussi aux autres types de mesures, les savoirs incorporés, qui reposent sur l’odorat, la vue ou le toucher et ceux qui ressortent d’une épistémologie « non ...

  11. Har du sikret din alderdom?

    DEFF Research Database (Denmark)

    Kiens, Bente; Aagaard, Peter Gjerndrup

    2006-01-01

    Daglig fysisk aktivitet kan betragtes som indbetaling op din personlige helbredspension. Jo mere du sætter ind på kontoen, og jo oftere du gør det, jo større er sandsynligheden for, at du lever længere og får et sundere helbred. Og det er aldrig for sent at starte med indbetalingerne....

  12. Les pirogues du Maroni

    Directory of Open Access Journals (Sweden)

    Sophie François

    2012-04-01

    Full Text Available Sur le Maroni, fleuve frontière entre la Guyane française et le Surinam, les pirogues amarrées le long des berges se comptent par centaines. Elles représentent le seul moyen de transport pour les milliers de personnes vivant sur les rives du Maroni. Les différentes formes de pirogues sont révélatrices de la diversité géographique du Maroni et de la diversité culturelle des populations. Les Amérindiens du littoral naviguent uniquement dans l’estuaire du fleuve. Ils construisent des pirogues larges, hautes et terminées à la poupe par une haute étrave qui fend les vagues. Ces pirogues sont construites à partir d’une coque monoxyle expansée et rehaussée d’un ou de deux bordages. En chauffant la grume évidée, le bois acquiert une certaine plasticité qui permet d’écarter les flancs et d’obtenir une coque très large à partir d’un arbre de faible diamètre. Les Bushinenge, populations d’origine africaine qui ont déserté les grandes plantations de la Guyane hollandaise dès le début du XVIIe siècle et se sont installées sur les deux rives du Maroni, ont développé des formes de pirogues adaptées au passage des sauts. Leurs pirogues, construites également en expansant la coque au feu, sont étroites et longues et possèdent des extrémités curvilignes qui dépassent largement au–dessus du bordage. Les longues pirogues à moteur comme les canots–pagaies sont ornés de motifs d’entrelacs appelés tembé ; et de décors d’inspiration contemporaine. L’inventaire des pirogues du Maroni a mis en évidence la richesse et la vitalité du patrimoine nautique de cette région au début du XXIe siècle, tant au niveau des formes des embarcations que des décors et des pratiques de navigation.On the Maroni river, natural border between French Guyana and the Surinam, canoes tied to the river banks can be counted by the hundreds. They are the only mean of transportation for thousands of people living along the

  13. Analysis and separation of boron isotopes; Analyse et separation des isotopes du bore

    Energy Technology Data Exchange (ETDEWEB)

    Perie, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1966-11-01

    The nuclear applications of boron-10 justify the study of a method of measurement of its isotopic abundance as well as of very small traces of boron in different materials. A systematic study of thermionic emission of BO{sub 2}Na{sub 2}{sup +} has been carried out. In the presence of a slight excess of alkalis, the thermionic emission is considerably reduced. On the other hand, the addition of a mixture of sodium hydroxide-glycerol (or mannitol) to borax permits to obtain an intense and stable beam. These results have permitted to establish an operative method for the analysis of traces of boron by isotopic dilution. In other respects, the needs of boron-10 in nuclear industry Justify the study of procedures of separation of isotopes of boron. A considerable isotopic effect has been exhibited in the chemical exchange reaction between methyl borate and borate salt in solution. In the case of exchange between methyl borate and sodium borate, the elementary separation factor {alpha} is: {alpha}=(({sup 11}B/{sup 10}B)vap.)/(({sup 11}B/{sup 10}B)liq.)=1.03{sub 3}. The high value of this elementary effect has been multiplied in a distillation column in which the problem of regeneration of the reactive has been resolved. An alternative procedure replacing the alkali borate by a borate of volatile base, for example diethylamine, has also been studied ({alpha}=1,02{sub 5} in medium hydro-methanolic with 2,2 per cent water). (author) [French] Les applications nucleaires du bore 10 justifient l'etude d'une methode de mesure de son abondance isotopique dans divers materiaux ainsi que le dosage de tres faibles traces de bore. Une etude systematique de l'emission thermoionique de BO{sub 2} Na{sub 2}{sup +} a ete effectuee. En presence d'un leger exces d'alcalins, l'emission thermoionique est considerablement reduite. Par contre l'addition au borax d'un melange soude-glycerol (ou mannitol) permet d'obtenir un faisceau stable et intense

  14. L'Origine du Monde

    CERN Multimedia

    CNET & Ecole Polytechnique Paris; Vincent Ferreira

    1996-01-01

    Création, théologie, science, découverte, recherche, religion, condition humaine.Avec Maurice Jacob physicien, Hubert Curien Président du Conseil du CERN, Michael Doser physicien, Frère Emile Communauté de Taizé.

  15. discours du Directeur General

    CERN Document Server

    CERN. Geneva

    2007-01-01

    L'année 2007 est une année très spéciale pour le CERN. Je vous propose de nous retrouver pour faire le point sur les activités en cours. Rendez-vous le mercredi 27 juin à 15h00 dans l'amphithéâtre principal. La transmission simultanée sera assurée dans les amphithéâtres IT, AT, AB Prevessin et dans la Salle du Conseil. Robert Aymar

  16. Les risques du travail

    CERN Document Server

    Thébaud-Mony, Annie

    2015-01-01

    Depuis les années 1990, les conditions de travail se sont peu à peu imposées dans le débat social. Néanmoins, la situation reste critique. Les risques traditionnels n'ont pas disparu : les manutentions lourdes, l'exposition professionnelle aux cancérogènes, au bruit ou aux vibrations demeurent répandues... De plus, certaines " améliorations " n'ont fait que déplacer et dissimuler les problèmes, telle l'externalisation des risques grâce à la sous-traitance. Dans le même temps, les transformations du travail et des modalités de gestion de la main-d'œuvre ont fragilisé les collectifs et accru l'isolement des salariés, conduisant à une montée visible de la souffrance psychique. Face à ces évolutions, il est plus que jamais nécessaire que tous les acteurs concernés, en particulier les salariés eux-mêmes et leurs représentants, s'approprient les connaissances indispensables pour améliorer la protection de la santé sur les lieux du travail. Tel est le but de ce livre, qui renouvelle int�...

  17. Les formes du fond

    Directory of Open Access Journals (Sweden)

    Michel Maffesoli

    2004-12-01

    Full Text Available Il n'est pas vrai que la nature a horreur du vide. Peut-être même s'y complait-elle. Le creux est aussi une modalité de l'être. Il est possible de s'y nicher, de s'y lover paresseusement et, ainsi, de se protéger contre l'angoisse du temps qui passe. Le creux des apparences est, à certains moments, une des formes d'expression de la vie sociale. Encore faut-il savoir le reconnaître. Certes, nous avons tous une existence personnelle, mais nous sommes, également, les représentants, parfois même les victimes, d'un "esprit commun", peut-être même d'un "inconscient collectif" qui s'est constitué de siècle en siècle. Et, très souvent, là où nous croyons exprimer nos propres idées, nous ne sommes que les porte-voix, les figurants d'un vaste "theatrum mundi" aux dimensions infinies.

  18. Choeur du CERN : Concert

    CERN Document Server

    CERN Choir

    2017-01-01

    Une œuvre à découvrir! La grande Missa pro defunctis de François-Joseph Gossec (1734-1829) est le chef-d’œuvre tôt venu (à vingt-cinq ans) d’un compositeur qui vivra encore 70 ans après sa création. Elle a connu la gloire, puis s’est fait un peu oublier. Pas du tout le monde cependant : des musicologues ont montré ce que le Requiem de Mozart lui devait ; et il suffit de l’avoir entendue pour comprendre pourquoi Berlioz (qui avait vingt-six ans à la mort de Gossec) en a été impressionné : les nombreux cuivres et bois répartis dans des endroits plus ou moins cachés de la salle de concert pour exprimer les frayeurs du Jugement dernier annoncent son Requiem – et celui de Verdi. Mais « plus encore que par...

  19. Jouer du piano

    Directory of Open Access Journals (Sweden)

    Fériel Kaddour

    2011-04-01

    Full Text Available La réflexion s’appuie dans un premier temps sur une opposition entre deux attitudes de pianistes  à l’égard du travail à l’instrument : Gould, qui revendique une séparation d’avec le clavier pour ne privilégier que la lecture; Arrau, dont la technique au contraire vise à « faire corps » avec son piano. L’étude de ces deux démarches d’interprètes conduit à une conclusion croisée : l’abstraction gouldienne n’est rien d’autre qu’un déplacement du jeu vers d’autres instruments (ceux qui servent à la prise de son et au montage de ses enregistrements ; le « faire-corps » hérité de la culture pianistique romantique est plus dialectique que fusionnel, et en cela implique une capacité de mise à distance. A partir de cette double conclusion, on tâche enfin de repenser la place du jeu à l’instrument dans la mise en œuvre d’une interprétation, en interrogeant le dialogue qui s’instaure entre la partition telle qu’elle s’écrit et le geste tel qu’il se joue.Our study leans on an opposition between two pianists' attitudes about their work with the instrument. Gould claims a necessary separation from the keyboard in order to prioritize reading. Arrau, on the contrary, relies on a technique which consists in “being one” with his piano. The analysis of these two interprets’ behaviours leads to a crossed conclusion: the gouldian abstraction is nothing else than a displacement of the playing towards another kind of instruments, the ones he uses in sound recording and cut up; Arrau’s “being one” is more dialectic than at first sight, and it therefore implies a real distancing from the piano. This constatation leads to rethink the place of the piano playing in the setting of an interpretation, and to highlight the real dialogue which develops itself between the score as it has been written and the gesture as it is played.

  20. Le sacre du printemps

    Directory of Open Access Journals (Sweden)

    Denise Pumain

    2002-03-01

    Full Text Available Cybergeo aura six ans en avril : dans la réalité du virtuel, dans l'univers récent et fluctuant de la publication en ligne, cela fait de nous, tout à la fois, des pionniers et des vétérans. De façon plus surprenante, il se trouve que nous sommes aussi uniques : parmi toutes les revues électroniques de sciences sociales, aucune ne combine comme Cybergeo ancienneté, publication exclusivement électronique, liberté d'accès au texte intégral, édition et gestion par des chercheurs, et comité de lec...

  1. Le Brahmane du Komintern

    Directory of Open Access Journals (Sweden)

    Elizabeth Burgos

    2008-01-01

    Full Text Available Le Brahmane du Komintern, largometraje documental del realizador francés Vladimir León, constituye un ejercicio ejemplar de investigación histórica y  de lograda factura de realización. Y, pese a no haber contado con la ayuda de ninguno organismo público, se trata de un ambicioso proyecto que cubre una amplia extensión geográfica que abarca: Estados Unidos, México, Moscú, Berlín, y la India. Gira en torno a una figura que tuvo en su tiempo su hora de gloria. Un bengalí, hijo de braman, la c...

  2. Cultures du travail

    OpenAIRE

    de Bonnault-Cornu, Phanette; Charrasse, David; Herberich-Marx, Geneviève; Lamy, Yvon; Lazier, Isabelle; Mairot, Philippe; Morel, Alain; Périssère, Michèle; Raphaël, Freddy; Ribeill, Georges; Salmeron, Pierre; Vant, André

    2015-01-01

    Qu’est-ce qu’une culture du travail ? Comment la définir autrement qu’en opposition à la culture savante ? Quelles relations une société entretient-elle avec son ou ses industries ? Comment définir et appréhender ce qu’on appelle la culture d’entreprise ? A ces questions ethnologues, sociologues, géographes et historiens apportent ici des réponses.Ce livre est aussi consacré à l’intérêt que ces sociétés, villes, petites régions, entreprises, portent à ce qui constitue leur patrimoine industri...

  3. OPERATION DU FOISONNEMENT

    Directory of Open Access Journals (Sweden)

    Gholamreza Djelveh

    2010-04-01

    Full Text Available Mousses alimentaires sont un sous-ensemble des aliments connus sous le nom de produits fouettés ou des produits aérés. Ils sont des produits formulés avec des qualités telles que la légèreté et la souplesse et sont principalement consommés à l'apéritif ou au dessert. Les produits en mousse obtenue par dispersion d'un gaz dans une matrice alimentaire (la phase continue ont connu un développement croissant au cours des années 80 et 90. Le processus d'aération liés à leurs activités de production est appelée l'expansion ou à fouetter. Le document présente les principaux-paramètres du procédé du point permanent de la formulation, la mise en œuvre processus dans les installations pilotes et à l'échelle industrielle, la caractérisation des produits finis, la base énergétique de l'échelle de processus en place, et le lien entre la formulation, émulsion préparation de l'expansion. Cette vue d'ensemble de l'opération d'expansion continue, nous a permis de mettre en évidence le fait qu'il ya des opérations de l'unité encore mal décrite par le génie des procédés et pour lesquels les méthodes et outils pour l'extrapolation et la prédiction sont encore à leurs balbutiements.

  4. Sur quelques Ichthyurus du Tonkin

    NARCIS (Netherlands)

    Gestro, R.

    1906-01-01

    Les espèces d Ichthyurus du Tonkin connues jusqu’ici étaient seulement trois: denticornis Gestro, décrite d’abord du Tenasserim (récoltes de feu Mr. L. Fea) et retrouvée ensuite dans le Haut Tonkin par S. A. R. le Prince Henri d’Orléans; Henrici Gestro, découverte par ce même explorateur, et dont le

  5. Ageing of palladium tritide: mechanical characterization, helium state and modelling; Vieillissement du tritiure de palladium: caracterisation mecanique, etat de l'helium et modelisation

    Energy Technology Data Exchange (ETDEWEB)

    Segard, M.

    2010-11-29

    deux modeles traitant, d'une part, de la germination des bulles d'helium-3 (utilisation d'un automate cellulaire) et, d'autre part, de la croissance des bulles (mecanique des milieux continus). Ces modeles etaient fonctionnels, mais leur utilisation etait limitee par le manque de donnees experimentales d'entree et de recalage. Ce travail de these a donc consiste a acquerir les donnees experimentales les plus pertinentes pour ameliorer la modelisation du vieillissement du tritiure de palladium. La premiere partie de ce travail a consiste a estimer les proprietes mecaniques du tritiure de palladium (limite d'elasticite, contrainte maximale, loi de comportementale), deduites de celles de l'hydrure et du deuterure de palladium, mesurees a l'aide d'essais de traction in situ. En seconde partie, la caracterisation du vieillissement a ete entreprise, focalisee sur des observations de bulles dans le tritiure de palladium par microscopie electronique en transmission, des mesures de pression a l'intErieur des bulles par resonance magnetique nucleaire et des mesures de gonflement macroscopique du materiau par pycnometrie. Ces travaux ont conduit a des avancees significatives quant a la comprehension du vieillissement et ont permis d'ameliorer considerablement sa modelisation

  6. Developpement de mesures non destructives, par ondes ultrasonores, d'epaisseurs de fronts de solidification dans les reacteurs metallurgiques

    Science.gov (United States)

    Floquet, Jimmy

    Dans les cuves d'electrolyse d'aluminium, le milieu de reaction tres corrosif attaque les parois de la cuve, ce qui diminue leur duree de vie et augmente les couts de production. Le talus, qui se forme sous l'effet des pertes de chaleur qui maintiennent un equilibre thermique dans la cuve, sert de protection naturelle a la cuve. Son epaisseur doit etre controlee pour maximiser cet effet. Advenant la resorption non voulue de ce talus, les degats generes peuvent s'evaluer a plusieurs centaines de milliers de dollars par cuve. Aussi, l'objectif est de developper une mesure ultrasonore de l'epaisseur du talus, car elle serait non intrusive et non destructive. La precision attendue est de l'ordre du centimetre pour des mesures d'epaisseurs comprenant 2 materiaux, allant de 5 a 20 cm. Cette precision est le facteur cle permettant aux industriels de controler l'epaisseur du talus de maniere efficace (maximiser la protection des parois tout en maximisant l'efficacite energetique du procede), par l'ajout d'un flux thermique. Cependant, l'efficacite d'une mesure ultrasonore dans cet environnement hostile reste a demontrer. Les travaux preliminaires ont permis de selectionner un transducteur ultrasonore a contact ayant la capacite a resister aux conditions de mesure (hautes temperatures, materiaux non caracterises...). Differentes mesures a froid (traite par analyse temps-frequence) ont permis d'evaluer la vitesse de propagation des ondes dans le materiau de la cuve en graphite et de la cryolite, demontrant la possibilite d'extraire l'information pertinente d'epaisseur du talus in fine. Fort de cette phase de caracterisation des materiaux sur la reponse acoustique des materiaux, les travaux a venir ont ete realises sur un modele reduit de la cuve. Le montage experimental, un four evoluant a 1050 °C, instrumente d'une multitude de capteurs thermique, permettra une comparaison de la mesure intrusive LVDT a celle du transducteur, dans des conditions proches de la mesure

  7. Synthesis of the IRSN report on the second safety re-inspection of the Orphee research reactor; Synthese du rapport de l'IRSN sur le deuxieme reexamen de surete du reacteur de recherche ORPHEE

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-09-09

    The second safety inspection of the Orphee base nuclear installation notably relies on international and French return on experience. This inspection addressed the robustness of the installation against extreme aggressions, organisational processes, radiation protection, waste and effluent management, the security of the reactor operation, handling operation security, nuclear waste warehousing safety, internal aggressions, the third confinement barrier, and the radiological consequences of incidental and accidental situations

  8. Evaluation of the neutrons spectrum near the Venus reactor: use of MCNPX-2.5C; Evaluation du spectre des neutrons pres du reacteur venus - utilisation de MCNPX-2.5C

    Energy Technology Data Exchange (ETDEWEB)

    Verboomen, B.; Coeck, M.; Baeten, P. [SCK.CEN, Centre d' Etude de l' Energie Nucleaire, Mol (Belgium)

    2003-07-01

    The present study has been justified by the choice of the Venus reactor (SCK-CEN) as a true work environment for the project of the fifth programme - frame E.V.I.D.O.S.. The objective of this programme is the evaluation, in neutron-photon combined field, and in true environment (nuclear industry), of the different methods of measurement used in neutron dosimetry. The project aims to the determination of abilities and limits of dosemeters and to establish methods to get doses equivalents from data gotten by spectrometry, personal and ambient dosimetry. For each environment, reference values have to be determined by spectrometry (energy and angle). The knowledge of the distribution in energy and in angle of neutrons allows then the calculation of the different doses equivalents. The determination of these references values by direct neutron calculation allows the validation of the Monte Carlo model. (N.C.)

  9. Position adopted by the government about the safety options of the EPR reactor project; Prise de position du gouvernement concernant les options de surete du projet de reacteur EPR

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-10-01

    On September 28, 2004, on behalf of the French ministers in charge of nuclear safety, the general director of nuclear safety and radiation protection addressed to the president of Electricite de France (EdF) a letter presenting the government's position about the safety options of the EPR (European Pressurized Reactor) project. On the basis of the examination carried out by the nuclear safety authority (ASN) and by the permanent group of reactor experts, the government has considered these options as satisfactory with respect to the safety improvement objectives. Therefore, the government requested EdF to comply with these technical rules for any future reactor development. This dossier includes: the letter of the government, the technical directives for the design and construction of the next generation of PWR-type reactors, the technical rules relative to the design of the main primary and secondary coolant circuits of PWR-type reactors, and the technical file about the safety of the EPR project reprinted from the 2003 report of nuclear safety and radiation protection authority. (J.S.)

  10. Study of colloidal particles behaviour in the PWR primary circuit conditions; Etude du comportement des particules colloidales dans les conditions physicochimiques du circuit primaire des reacteurs a eau sous pression

    Energy Technology Data Exchange (ETDEWEB)

    Barale, M

    2006-12-15

    EDF wants to understand, model and limit primary circuit contamination of Pressurized Water Reactors by colloidal particles resulting from corrosion. The electrostatic behaviour of representative oxide particles (cobalt ferrite, nickel ferrite and magnetite) has been studied in primary circuit conditions with the influence of boric acid and lithium hydroxide. The isoelectric point (IEP) and the point of zero charge (PZC) of particles, measured between 5 C and 320 C, exhibit a minimum towards 200 C. The thermodynamic constants of the protonation equilibrium of surface sites were calculated. When boric acid is added, zeta potential and IEP decrease because of borate ions sorption. On the contrary, there is not effect of lithium ions. The modelling of these results under conditions representative of primary circuit shows that these oxides exhibit a negative surface charge, explaining their sorption and adhesion behaviour. (author)

  11. The nuclear and the energy supply of tomorrow. Stop the useless quarrels about the nuclear; Le nucleaire et l'approvisionnement energetique de demain. Cesser les querelles inutiles a propos du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Following the paper of Hubert Reeves which developed the reasons of the the nuclear stopping, the author presents arguments to ease this opinion ( economic growth of the developing countries, greenhouse gases reduction, fossil fuels conservation, transportation sector) and proposes a cooperation between the nuclear and the renewable energies to satisfy a sustainable development. (A.L.B.)

  12. Analytic determination of plutonium in the environment; Determination analytique du plutonium dans l'environnement

    Energy Technology Data Exchange (ETDEWEB)

    Ballada, J. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1967-07-01

    The work described in this report was undertaken with a view to determining the plutonium content in the fall-out from nuclear explosions. In the first part are described in turn the importance of the problems due to the plutonium, the physico-chemical properties of the radioelement and the biological dangers which it presents. A detailed and critical analysis is made of the radio-toxicological determination of the plutonium as reported in the literature prior to this report. The second part consists in the presentation of a judicious choice of techniques making it possible to determine plutonium in air, rain-water, soils and ash. After a detailed description of the measurement equipment and the operational techniques which have been developed, a justification of these techniques is given with particular reference to their sensitivity and specificity. After a brief conclusion concerning the preceding chapters, the results are presented. These are then discussed in the ease of each element in which the plutonium has been determined. This discussion is concluded by a consideration of the importance of the occurrence of fall-out plutonium on problems relating to public health. From a consideration of 200 analyses carried out, it is concluded that the contribution of plutonium to the exposure of populations is still very small compared to that of natural radiation and that due to such fission products as strontium 90. The report includes 63 literature references, 26 figures and 11 tables. (author) [French] Les travaux decrits dans ce memoire ont ete entrepris et eflectues dans le but de mettre en evidence le plutonium des retombees radioactives consecutives aux explosions nucleaires. Dans la premiere partie nous etudions successivement l'importance des problemes poses par le plutonium puis les proprietes physicochimiques du radioelement et les dangers qu'il presente du point de vue biologique. Nous effectuons une analyse detaillee et critique des techniques

  13. AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle; AREVA Technical Days (ATD) session 2: les activites du pole Aval du cycle du combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

  14. Le bal du loup

    CERN Multimedia

    Happy Children's Home

    2013-01-01

    The Bord'eau amateur theatre group will graciously perform a play of their creation Le bal du loup Saturday 19 October 2013 at 20:00 Sunday 20 October at 17:00 in the Théâtre des Grottes Rue Louis Favre 43, 1201 Genève Children from age 12 upwards. Summary: The new-elected mayoress of a small village would like to clean up the town by prohibiting alcohol and getting rid of its prostitutes. Then along comes « Massimo Lupo » the pimp... The performances will be given to support the Happy Children's Home charity, which runs a foster-home in Pokhara for Nepali children:  http://www.happychildrenshome.org/ Admission : minimum charge of 10 CHF per person requested, to cover the cost of technical assistance and theatre rental. Any profit will be used solely for the foster-home. At the end of each performance members of the HCH charity will be happy to answer any questions you may have. The theatre has 86 seats, thank you for reserv...

  15. Le collisionneur du futur?

    CERN Multimedia

    CERN Audiovisual Service

    2009-01-01

    Pourquoi deux études parallèles pour un même collisionneur linéaire ? Loin d’être un double effort et un gaspillage de ressources, ces deux études s’inscrivent dans une stratégie de complémentarité afin de fournir la meilleure technologie requise par la physique du futur. Vendredi 12 juin a eu lieu au CERN la première réunion conjointe CLIC et ILC. Elle n’a pas été avare de bons résultats et d’importantes décisions. Le Collisionneur Linéaire International (ILC) et le Collisionneur Linéaire Compact (CLIC) sont deux études qui font, tous deux, appel à des technologies de pointe. A première vue en compétition, les deux études sont en réalité complémentaires et elles ont un objectif commun : proposer dans les plus brefs délais et au moindre coût, l‘accélérateur linéaire le mieux adapté pour prendre le relais de la physique des très hautes énergies après le LHC.

  16. Effets du fluor et du phosphogypse chez les organismes marins

    OpenAIRE

    Martin, J.L.; Le Guellec, Anne-marie; Cosson, R.

    1982-01-01

    Dans le cadre général des recherches visant à déterminer l'action des effluents industriels et plus précisément du fluor dans le cas de cette étude, le programme dont les résultats sont présentés avait pour but de déterminer les effets de cet élément sur les organismes marins. Trois aspects essentiels ont été envisagés : - Effets létaux du fluor ; - effets du fluor sur certaines fonctions éthologiques ; - bio-accumulation de l'élément par les organismes marins.

  17. Main: 1DU5 [RPSD[Archive

    Lifescience Database Archive (English)

    Full Text Available 1DU5 トウモロコシ Corn Zea mays L. Zeamatin Precursor. Name=Zlp; Zea Mays Molecule: Zeama...NNACPVFKKDEYCCVGSAANDCHPTNYSRYFKGQCPDAYSYPKDDATSTFTCPAGTNYKVVFCP corn_1DU5.jpg ...

  18. Gestion durable du paysage

    Directory of Open Access Journals (Sweden)

    Jean-David Gerber

    2009-03-01

    Full Text Available Le paysage est de plus en plus perçu comme une ressource. À ce titre, il est nécessaire de trouver des instruments juridiques, politiques ou économiques susceptibles de gérer cette « ressource-paysage » sur le long terme. Le gouvernement suisse a introduit récemment l’instrument des parcs naturels régionaux, organisés selon le modèle français, dans sa législation de protection de la nature et du paysage. Une mise en regard des nouveaux parcs avec des structures de gestion beaucoup plus anciennes, les bourgeoisies et les corporations, permet de mettre en évidence les forces et les faiblesses de chacun de ces instruments dans leur contribution à résoudre les rivalités d’usage entre acteurs utilisant ou influençant la ressource paysage. Cette comparaison permet de formuler des recommandations pratiques concernant la gestion de cette ressource.The landscape is increasingly perceived as a resource. For this reason, it is necessary to find legal, political and economic instruments that will succeed in managing this “resource landscape” in the long term. The Swiss government recently introduced the instrument of regional nature parks into the legislation governing nature and landscape preservation; the proposed parks are organized on the basis of the French model. The examination of the new parks from the perspective of much older management structures, i.e. the civic municipalities (bourgeoisies and corporations, makes it possible to demonstrate the strengths and weaknesses of each of these instruments in their contribution to the resolution of use rivalries between actors who use or influence the resource landscape. This comparison also enables the formulation of practical recommendations regarding the management of this resource.

  19. Cri du Chat syndrome

    Directory of Open Access Journals (Sweden)

    Cerruti Mainardi Paola

    2006-09-01

    Full Text Available Abstract The Cri du Chat syndrome (CdCS is a genetic disease resulting from a deletion of variable size occurring on the short arm of chromosome 5 (5p-. The incidence ranges from 1:15,000 to 1:50,000 live-born infants. The main clinical features are a high-pitched monochromatic cry, microcephaly, broad nasal bridge, epicanthal folds, micrognathia, abnormal dermatoglyphics, and severe psychomotor and mental retardation. Malformations, although not very frequent, may be present: cardiac, neurological and renal abnormalities, preauricular tags, syndactyly, hypospadias, and cryptorchidism. Molecular cytogenetic analysis has allowed a cytogenetic and phenotypic map of 5p to be defined, even if results from the studies reported up to now are not completely in agreement. Genotype-phenotype correlation studies showed a clinical and cytogenetic variability. The identification of phenotypic subsets associated with a specific size and type of deletion is of diagnostic and prognostic relevance. Specific growth and psychomotor development charts have been established. Two genes, Semaphorin F (SEMAF and δ-catenin (CTNND2, which have been mapped to the "critical regions", are potentially involved in cerebral development and their deletion may be associated with mental retardation in CdCS patients. Deletion of the telomerase reverse transcriptase (hTERT gene, localised to 5p15.33, could contribute to the phenotypic changes in CdCS. The critical regions were recently refined by using array comparative genomic hybridisation. The cat-like cry critical region was further narrowed using quantitative polymerase chain reaction (PCR and three candidate genes were characterised in this region. The diagnosis is based on typical clinical manifestations. Karyotype analysis and, in doubtful cases, FISH analysis will confirm the diagnosis. There is no specific therapy for CdCS but early rehabilitative and educational interventions improve the prognosis and considerable

  20. High energy resolution and high count rate gamma spectrometry measurement of primary coolant of generation 4 sodium-cooled fast reactor; Spectrometrie gamma haute resolution et hauts taux de comptage sur primaire de reacteur de type generation 4 au sodium liquide

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R.

    2010-11-10

    Sodium-cooled Fast Reactors are under development for the fourth generation of nuclear reactor. Breeders reactors could gives solutions for the need of energy and the preservation of uranium resources. An other purpose is the radioactive wastes production reduction by transmutation and the control of non-proliferation using a closed-cycle. These thesis shows safety and profit advantages that could be obtained by a new generation of gamma spectrometry system for SFR. Now, the high count rate abilities, allow us to study new methods of accurate power measurement and fast clad failure detection. Simulations have been done and an experimental test has been performed at the French Phenix SFR of the CEA Marcoule showing promising results for these new measurements. (author) [French] Les reacteurs a neutrons rapides refroidis au sodium sont en developpement en vue d'assurer une quatrieme generation de reacteurs repondant a la demande energetique, tout en assurant la preservation des ressources d'uranium par un fonctionnement en surgenerateur. L'objectif de la filiere est egalement d'ameliorer la gestion de la radiotoxicite des dechets produits par transmutation des actinides mineurs et de controler la non-proliferation par un fonctionnement en cycle ferme. Une instrumentation de surveillance et de controle de ce type de reacteur a ete etudiee dans cette these. La spectrometrie gamma de nouvelle generation permet, par les hauts taux de traitement aujourd'hui accessibles, d'envisager de nouvelles approches pour suivre avec une precision accrue la puissance neutronique et de detecter plus precocement des ruptures de gaine combustible. Des simulations numeriques ont ete realisees et une campagne d'essai a ete menee a bien sur le reacteur Phenix de Marcoule. Des perspectives prometteuses ont ete mises en exergue pour ces deux problematiques

  1. Les paradoxes du littoral Swahili

    Directory of Open Access Journals (Sweden)

    François Bart

    2008-10-01

    Full Text Available Le contact entre l'océan Indien occidental et le continent africain a forgé l'identité et l'originalité du littoral swahili. Cette interface, longue d'environ 2 000 kilomètres, du sud de la Somalie au nord du Mozambique, constitue un monde original où, au gré de traditions anciennes de circulation maritime et continentale se sont diffusées et mêlées des influences culturelles venues du continent africain, de la péninsule arabique et de la péninsule indienne. Le développement du continent, du littoral et des archipels s'inscrit dans une double logique de fragmentation et d'ouverture au monde. Dans cette vaste aire géographique, le rôle de relais des îles et des axes de pénétration continentale à partir des ports est essentiel.The identity and the original features of the Swahili seashore mainly proceed from the contact of African mainland and western indian Ocean. This coastal interface, stretching over 2 000 kilometres from southern Somalia to northern Mozambique, is characterized by ancient traditions of trade movements through maritime areas and mainland as well, which spread and mixed different cultural influences originating from Africa and both Arabic and Indian peninsulas. The development of this area is linked to both fragmentation and opening dynamics. In such a wide area, the relaying function of islands and continental corridors from main harbours is very important.

  2. Theory of a metrology for the earths magnetic field based on the resonance of polarised atomic nuclei (1962); Theorie d'une metrologie du champ magnetique terrestre basee sur la resonance de noyaux atomiques polarises (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Bonnet, G. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1961-06-15

    The problems presented by the metrology of the earths field are studied from two points of view. a. The first, purely physical, concerns the study of NMR transducers in their role for the transformation of the magnetic field into a frequency. The possibilities and limitations are outlined. The use of an equivalent model is introduced systematically in the considerations of NMR phenomena, this makes it possible to treat all problems of interaction between a spin system and an electric detection system in a unified form. b. The other point of view concerns the restitution of the nuclear signal frequency in the form of a directly perceptible observable. The treatment of information is considered from a statistical angle, which leads to the study of an optimisation process concerning the linearization of the measurement as well as the minimisation of noise effects. (author) [French] Les problemes que pose la metrologie du champ terrestre sont etudies sous un double aspect: a. L'un, purement physique, concerne l'etude des traducteurs a RMN dans leur role de transformation du champ magnetique en une frequence. On en degage les possibilites et les limitations. L'emploi d'un modele equivalent est introduit de maniere systematique pour rendre compte des phenomenes de RMN, ce qui permet de traiter sous forme unifiee tous les problemes d'interaction entre un systeme de spins et un systeme electrique de detection. b. L'autre aspect concerne la restitution de la frequence du signal nucleaire sous la forme d'une observable directement perceptible. On considere le traitement de l'information sous l'aspect statistique, ce qui amene a etudier un processus d'optimisation concernant la linearisation de la mesure aussi bien que la minimisation des effets des bruits. (auteur)

  3. Study of the behaviour of artificial radioactive aerosols. Applications to some problems of atmospheric circulation (1963); Etude du comportement dcs aerosols radioactifs artificiels. Applications a quelques problemes de circulation atmospherique (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, G. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-11-15

    The aim of this work, consists in the examination of the behaviour of radioactive aerosols produced in the atmosphere by nuclear explosions, in order to deduce the most general laws governing atmospheric circulation and diffusion. After having given a general table of the radioactive aerosols present the authors consider the validity and the precision of the measurement methods and the concentration of the aerosols at ground level and in the upper atmosphere, as well as their deposition on the ground. The existence is thus demonstrated of a tropospheric equatorial barrier and of discontinuous and seasonal aspects of stratosphere-troposphere transfers. The role is shown of precipitations and dry auto-filtration in the lower atmosphere cleaning processes. This work makes it possible to describe the general behaviour of dust from the stratosphere, and to improve the total radioactive contamination of the globe. (author) [French] L'objectif de ce travail consiste a examiner le comportement des aerosols radioactifs introduits dans l'atmosphere par les explosions nucleaires, pour en deduire les lois les plus generals de la circulation et diffusion atmospheriques. Apres avoir dresse un tableau d'ensemble des aerosols radioactifs presents, on examine la validite et la precision des methodes de mesure de leur concentration, au niveau du sol et en haute atmosphere, ainsi que de leur depot a la surface du sol. On met ainsi en evidence l'existence d'une barriere equatoriale tropospherique; l'aspect discontinu et saisonnier des transferts stratosphere-troposphere; le role des precipitations et de l'auto-filtration seche, dans les processus de nettoyage de la basse atmosphere. Ces etudes permettent de decrire le comportement general des poussieres d'origine stratospherique et d'ameliorer le bilan de la contamination radioactive du globe. (auteur)

  4. ETUDE GEOCHIMIQUE ET ISOTOPIQUE DES EAUX SUPERFICIELLES DU BASSIN VERSANT DU FURAN ET DES EAUX MINERALES DU GRABEN DU FOREZ, EST DU MASSIF CENTRAL FRANÇAIS

    OpenAIRE

    Gal, Frédérick

    2005-01-01

    Ce travail est basé sur l'étude d'un continuum eau de pluie – eau de surface – eau minérale, en utilisant différents outils chimiques et géochimiques. La zone d'étude se situe en bordure Est du Massif Central Français. Elle comprend des entités géographiques et géologiques variées (complexe granito-gneissique et cristallophyllien – Monts du Forez et du Lyonnais d'âge hercynien, graben Oligocène du Forez à venues volcaniques miocènes).La première partie repose sur l'étude en isotopes stables (...

  5. From the coupling between ion beam analysis techniques and physico-chemical characterization methods to the study of irradiation effects on materials behaviour; Du couplage des techniques d'analyse par faisceaux d'ions et des methodes de caracterisation physico-chimique a l'etude des effets d'irradiation sur le comportement des materiaux

    Energy Technology Data Exchange (ETDEWEB)

    Millard-Pinard, N

    2003-07-01

    The general purpose of my research work is to follow and to interpret the surface evolution of materials, which have received several treatments. During my PhD and my post-doc work, my field of research was tribology. Since I arrived in the 'Aval du Cycle Electronucleaire' group of the Institut de Physique Nucleaire de Lyon, my research activities are in line with the CNRS program 'PACE ' (Programme sur l'Aval du Cycle Electronucleaire) within the ACTINET network. They are coordinated by the PARIS (Physico-chimie des actinides et autres radioelements en solution et aux interfaces) and NOMADE (NOuveaux MAteriaux pour les DEchets) GDR with ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), EDF and IRSN (Institut de Radioprotection et de Surete Nucleaire) as partner organisations. My work focused on the study of fission products and actinides migration in barrier materials, which may be capable of assuring the long term safety of deep geological repositories. Until now, it was necessary to use the coupling of ion beam analysis techniques and physico-chemical characterization techniques. During the last few months, I have became interested in understanding radiolytic effects. This new orientation has led us to use ion beams as an irradiating tool. These irradiation experiments are pursued in three major projects. The study of cobalt sulfide inhibition effects of radiolysis gas production during the irradiation of model organic molecules. This is a collaboration with the IRSN, the Institut de Recherche sur la Catalyse and the Ecole Nationale Superieure des Mines de Saint-Etienne. A PhD, co-directed by M. Pijolat from ENSMSE and myself, concerning this study will start in October 2003. Water radiolysis effects on iron corrosion are also studied in the particular case of vitrified nuclear waste containers, which will be stored in deep geological repositories. One ANDRA financed PhD, co-directed by Nathalie Moncoffre and myself, is

  6. Réflexion sur l’origine du processus de segmentation du marche du travail

    Directory of Open Access Journals (Sweden)

    Attia Nicole

    2006-01-01

    Full Text Available (francuski Ce travail propose une réflexion sur l'origine du processus de segmentation du marché du travail par rapport à l'entreprise. Se situe-t-elle au sein même de l'entreprise ou en amont, c'est à dire entre les entreprises? Cela revient à se demander si on peut avoir une approche microéconomique ou macroéconomique de la segmentation et, à s'interroger sur le rôle réel tenu par les firmes dans le processus. Déterminant pour la théorie, ce rôle est à repenser selon la réponse apportée à notre question.

  7. Cri-du-chat syndrome

    NARCIS (Netherlands)

    Didden, H.C.M.; Curfs, L.M.G

    2013-01-01

    Cri-du-chat syndrome is a genetic disease resulting from a deletion occurring on the short arm of chromosome 5 (5p-). The incidence ranges from 1:15 000 to 1:50 000 live-born infants. Its main clinical features are a high-pitched monochromatic cry, microcephaly, broad nasal bridge, epicanthal folds,

  8. Caractérisation des sables et morphologie du fond du lac du ...

    African Journals Online (AJOL)

    Administrateur

    Map of this lake 26 years after its setting in water. Key words : Dam .... La méthode d'interpolation retenue est l'IDW (Inverse Distance Weighting) avec un pas .... Figure 2 : Répartition des faciès de surface des sédiments du lac de Taabo. 3.3.

  9. LES GITES PLOMBO-ZINCIFERES DU DISTRICT MINIER DU KOUDIAT SIDU AUSUD DU KEF EN TUNISIE

    Directory of Open Access Journals (Sweden)

    Ivan Jurković

    1992-12-01

    Full Text Available Les auteurs ont dćcrit l:i stratigiaphie. I.i tectonique, le corps de minerals, la paragenese et la genese dcs gttes Koudiat Sidri situ&s environ 20 km au sud de la ville du Kef en Tunisie.

  10. Le parcours migratoire de jeunes ruraux du bled du kif

    Directory of Open Access Journals (Sweden)

    Khalid Mouna

    2015-06-01

    Full Text Available Cet article analyse le parcours migratoire des jeunes ruraux originaires des zones de production du cannabis, jeunes qui cherchent à briser les chaînes de soumission et d’humiliation vécues au quotidien. Pour les jeunes concernés par notre étude, la migration constitue un moyen de s’intégrer dans des réseaux transnationaux et ainsi d’entamer une carrière de beznass (commerçant du cannabis. Ce parcours « initiatique » permet à ces jeunes de revenir au bled avec de nouvelles idées, des moyens accrus, et de jouer un rôle actif dans l’économie locale – qui reste pour eux focalisée sur la production de cannabis, cette dernière restant néanmoins officiellement interdite.

  11. Paul Celan in Translation: "Du sei wie du"

    Directory of Open Access Journals (Sweden)

    John Felstiner

    1983-09-01

    Full Text Available Translating the lyric poetry of Paul Celan, especially his later poems, carries not only the endemic challenge and difficulty of any verse translation, but the added incentive of doing justice to a writer whose whole recourse after the Holocaust—whose sanctuary, if he was to have any at all—he sought in language itself, specifically in the Muttersprache , the mother tongue that was as well the tongue of those who murdered his mother and father. This essay exposes a process of translating "Du sei wie du" (1970, which perhaps more than any other poem by Celan, at once solicits and defies translation, moving as it does from modern to medieval German, and closing with Hebrew words from Isaiah— a messianic imperative that shows Celan verging as ever on his Jewish identity.

  12. Dynamique narrative du texte, du film et de la musique

    OpenAIRE

    Wildgen, Wolfgang

    2015-01-01

    La narrativité est foncièrement liée à la dynamique des événements et des actions représentés, et elle dépend du champ pragmatique narrateur/récepteur, c’est-à-dire du discours narratif. Cette dynamique demande une théorisation adéquate, par exemple au sein de la théorie des systèmes dynamiques ou de l’analyse vectorielle, et elle se manifeste dans des modalités différentes. Nous présentons des exemples d’analyse dans la modalité linguistique (récit oral spontané, conte populaire), dans la mo...

  13. Plutonium isotopes and their decay products in civil nuclear engineering; Les isotopes du plutonium et leurs descendants dans le nucleaire civil

    Energy Technology Data Exchange (ETDEWEB)

    Dautray, R

    2005-07-01

    This book is the continuation and conclusion of a previous book from the same author, entitled 'civil nuclear energy in the temporal framework of climatic changes' (Tec and Doc editions). It focusses on plutonium and on its daughter products. A synthesis of the scientific and technical data gathered so far is presented, together with the different choices offered to political authorities in the light of present-day knowledge. The authors starts from existing and firmly implemented scientific and technical data and presents some ways to solve the pending questions about the management of radioactive wastes. He shows that in our democratic system, the choice belongs to people. Beside the storage and deep disposal facilities, still necessary, some processes and problems are reviewed and explored. Of course new scientific data will be obtained, which would change the ways to discover and evaluate the ways to follow up. (J.S.)

  14. The today situation and the nuclear sector perspectives in Usa; La situation actuelle et les perspectives du secteur nucleaire aux Etats-Unis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    In this analysis the author details and discusses the nuclear energy situation in the Usa: the park and the electric power production, the nuclear safety and the radiation protection, the licenses prolongation, the power increase, the regulation relative to the construction of new reactors, the combined construction permit and operating license, the uncertainties on the Yucca Mountain storage site and the Global Nuclear Energy Partnership initiative, the 2006 perspectives and the IV generation reactors. (A.L.B.)

  15. The technology of the bearings used in the nuclear power generation system turbine generator units; Technologie des paliers equipant les groupes turbo-alternateurs du parc nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Vialettes, J.M.; Rossato, M. [Service Ensembles de Production, Departement Machines, Direction des Etudes et Recherches, Electricite de France (EDF), 92 - Clamart (France)

    1997-01-01

    A bearing consists of all the stationary part which allow the relative motion in rotation or in translation, of a shaft line. Inside the bearing there is a journal bearing with a metallic anti-friction coating (the babbitt metal). The high power turbine generator unit rotors are supported by smooth transversal journal bearings fed with oil which fills the empty space and runs along the shaft. The technologies used for the bearings and the thrust bearings of the turbine generator units and the various shaft lines of the French CP0/CP1- and CP2/1300 MW-type nuclear power plants are described. The experience feedback is then discussed in terms of the dynamics of the shaft line, i.e. vibrational problems, the influence of the alignment and the babbitt metal incidents. (author) 4 refs., 11 figs.

  16. Nuclear trade and non-proliferation: report by working group; Commerce nucleaire et non-proliferation: rapport du groupe de travail

    Energy Technology Data Exchange (ETDEWEB)

    Kerever, M.

    1995-12-31

    The paper is organized in three parts. The first one analyses the Treaty on the Non-proliferation of Nuclear Weapons (NPT) mentioning the arrangements and registered agreements between the IAEA and Member States. Also, the most important international legal instruments concerned the peaceful uses of nuclear energy are considered. In the second part, other international, regional or national legal instruments are discussed, particularly the London Club Guidelines, Treaty of Tlatelolco, the EURATOM and the Commission of the European Communities (CEC) Treaties, besides the American law of 18 Mars, 1978 - Nuclear Non-proliferation Act (NNPA) about the exportation of materials and services or nuclear technology; An appreciation about the laws and treaties are presented in the third part. Special attention is given to reinforce the non-proliferation dispositives face the actions after Iraq`s event (1990): new installations and nuclear activities moratorium extension export controls extension established by the London Club Guidelines and full scope safeguards adoption to accomplish controls and protect of dual-use nuclear-related technologies. 3 refs.

  17. Investigating the irradiation behavior of nuclear materials: the contribution of the JANNUS platform; Etude du comportement sous irradiation des materiaux nucleaires: apport de la plateforme JANNUS

    Energy Technology Data Exchange (ETDEWEB)

    Trocellier, P.; Miro, S.; Serruys, Y. [Departement des materiaux pour le nucleaire, Direction de l' energie nucleaire, CEA Centre de Saclay, 91191 Gif-sur-Yvette (France)

    2010-07-01

    The JANNUS platform (Joint Accelerators for Nano-sciences and Nuclear Simulation) comprises two experimental facilities, one located at Saclay, the other nearby at Orsay. The Saclay facility brings together 3 electrostatic particle accelerators: a single-ended, 3-MV Pelletron-accelerator (EPIMETHEE), a tandem 2-MV Pelletron (JAPET), and a single-ended 2.5-MV Van de Graaff accelerator (YVETTE), set up around a common experiment chamber. The Orsay facility features a mixed-mode 2-MV accelerator (ARAMIS), and a 190-kV ion implanter (IRMA), both being coupled to a 200-kV transmission electron microscope. This setup allows the evolution of the sample's microstructure to be observed in situ, while it is undergoing irradiation, in single- or dual-beam configuration. A typical irradiation experiment, in triple-beam configuration, matches the conditions required, e.g., by applications in the area of fusion. The multicharged heavy-ion beam delivered by EPIMETHEE serves to simulate the atomic displacements caused, within the material, by neutrons. YVETTE provides helium ({sup 4}He), and JAPET hydrogen ({sup 1}H), as yielded by nuclear reactions (n, {alpha}) and (n, p). This characterization - whether structural, chemical, or mechanical - may be carried out during irradiation (in situ), or immediately subsequent to it (ex situ). Materials science can now avail itself of an altogether comprehensive panoply of physicochemical analysis techniques, e.g. electron microscopy, atom-probe tomography, X-ray diffraction and absorption... 2 examples illustrate the contribution made by the JANNUS platform to our understanding of the irradiation behavior of nuclear materials. The first example concerns hexagonal silicon carbide (6H-SiC), the second one an ODS (Oxide Dispersion Strengthened) ferritic-martensitic alloy. (A.C.)

  18. Nuclear systems of the future. Stakes, R and D strategy, and international cooperation; Les systemes nucleaires du futur. Enjeux, strategie de recherche et developpement, et cooperation internationale

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    As demonstrated by prospective studies, nuclear energy will represent a decisive contribution in the future energy mix. The long-term strategy of development of nuclear energy requires to foresee a new generation of nuclear systems, named generation 4. The goal of these new systems is to optimize the use of nuclear fuels, to minimize the generation of wastes and to enlarge the field of applications of nuclear energy to other applications like: hydrogen and synthetic fuels generation, heat generation for the industry etc. This document presents the French R and D strategy on nuclear systems of 4. generation that has been approved by the public authorities. This strategy follows three axes: a priority research on fast neutron systems with fuel recycle (sodium fast reactors (SFR) and gas fast reactors (GFR)), a research on key-technologies for the supply of very high temperature heat (very high temperature reactor (VHTR), fast and thermal neutron reactors, and water decomposition processes), and a continuation of researches on PWR reactors improvement. An integral recycling of all actinides in fast neutron reactors requires the development of new fuel reprocessing and fuel re-fabrication processes. A reference scenario for the progressive renewal of French nuclear facilities foresees the simultaneous development of fast neutron systems and the start-up of a new spent fuel reprocessing plant. France in involved in the development of the SFR, GFR and VHTR systems thanks to its participation to the Generation 4 international forum and to bilateral cooperation with other big nuclear partners like Russia and China. One of the main stakes of the French nuclear industry is to be able to invest in the R and D of future nuclear systems in order to valorize the experience gained so far in sodium FBR systems and in fuel cycle processes. (J.S.)

  19. Symmetry and geometry of the N-body problem. Application to the nuclear physics; Symetrie et geometrie du probleme a N-corps. Application a la physique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Chau, H.T.P

    2002-10-01

    One of the main goals of classical and quantum physics is to solve the many-body problem. In nuclear theory, several methods have been developed and provide accurate results. In this thesis, we remind how symmetry can be used to obtain analytical solutions of the quantum many-body problem. We emphasize that unitary Lie algebras play a crucial role in quantum mechanics and propose and implement a method to build irreducible representations of this algebra from its highest-weight state. Calculations of bosonic and fermionic spectra are performed with realistic and with random interactions. Studies with rotational invariant two-body random interactions have unveiled high degree of order (a marked statistical preference is found for ground states with angular momentum equal to zero). In the second chapter of this thesis, it is argued that the spectral properties of this kind of interaction depend on the choice of the valence space. In particular, we propose a geometrical method to predict the properties of the ground state in certain cases. We also present numerical results when the geometrical approach can not be applied. In the third chapter, we study the link between quantum chaos and nuclear spectra calculated with realistic interactions. (author)

  20. Thermal stability of the French nuclear waste glass - long term behavior modeling; Etude de la stabilite thermique du verre nucleaire. Modelisation de son evolution a long terme

    Energy Technology Data Exchange (ETDEWEB)

    Orlhac, X

    2000-07-01

    The thermal stability of the French nuclear waste glass was investigated experimentally and by modeling to predict its long-term evolution at low temperature. The crystallization mechanisms were analyzed by studying devitrification in the supercooled liquid. Three main crystalline phases were characterized (CaMoO{sub 4}, CeCO{sub 2}, ZnCr{sub 2}O{sub 4}). Their crystallisation was TO 4.24 wt%, due to the low concentration of the constituent elements. The nucleation and growth curves showed that platinoid elements catalysed nucleation but did not affect growth, which was governed by volume diffusion. The criteria of classic nucleation theory were applied to determine the thermodynamic and diffusional activation energies. Viscosity measurements illustrate the analogy between the activation energy of viscous flow and diffusion, indicating control of crystallization by viscous flow phenomena. The combined action of nucleation and growth was assessed by TTT plots, revealing a crystallization equilibrium line that enables the crystallized fractions to be predicted over the long term. The authors show that hetero-genetics catalyze the transformation without modifying the maximum crystallized fraction. A kinetic model was developed to describe devitrification in the glass based on the nucleation and growth curves alone. The authors show that the low-temperature growth exhibits scale behavior (between time and temperature) similar to thermo-rheological simplicity. The analogy between the resulting activation energy and that of the viscosity was used to model growth on the basis of viscosity. After validation with a simplified (BaO{sub 2}SiO{sub 2}) glass, the model was applied to the containment glass. The result indicated that the glass remained completely vitreous after a cooling scenario with the one measured at the glass core. Under isothermal conditions, several million years would be required to reach the maximum theoretical crystallization fraction. (author)

  1. The role of the nuclear industry in the Brazil's electricity system; Le role du nucleaire dans le systeme electrique Bresilien

    Energy Technology Data Exchange (ETDEWEB)

    Pinheiro Da Silva, O.L.; Dos Santos Guimaraes, L. [Electronuclear - Electrobras Termonuclear (Brazil)

    2009-11-15

    No form of energy - renewable, clean or whatever other name it is given - can constitute the sole solution to the challenge of ensuring electric power supplies that are compatible with a country's economic and social growth. Brazilian consumption and installed electrical generation capacity per capita are stiller low, below the world average - that is the main factor that needs to be stressed. The catch-up requires that the country benefit it as much as possible and as soon as possible from all available sources to increase electricity generation capacity allowing increased consumption compatible with the way of life that Brazilians aspire to. A country's electrical system planning requires the efficient management of a diversified array of energy sources. Regarding Brazil, hydro power will be or several decades the main component in its electricity generation portfolio. Nonetheless, it already needs to be complemented by thermal sources - uranium, coal, bio-mass, natural gas and petroleum-based oil - in that order of importance, taking account of such actors as availability on the home territory, costs, environmental impacts and uses in other applications. (authors)

  2. The cycle of the nuclear fuel used in EDF power plants; Le cycle du combustible nucleaire utilise dans les centrales EDF

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    This document briefly indicates the different stages of the nuclear fuel cycle, from the purchase of natural uranium to waste storage. It also indicates the main responsibilities of EDF regarding this fuel cycle (to secure supplies, to organise material transportation, to process and store used fuels and associated wastes). It presents the different associated processes: uranium extraction, purification and concentration, conversion or fluoridation, enrichment. It briefly describes the fuel assembly fabrication, and indicates the main uranium producers in the world. Other addressed steps are: the transportation of fuel assembly, fuel loading, and spent fuel management, the processing of spent fuel and radioactive wastes

  3. The threat of nuclear terrorism: from analysis to caution measures; La menace du terrorisme nucleaire: de l'analyse aux mesures de precaution

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, M

    2001-12-15

    In this work are analysed the different cases of terrorism attacks, the potential sources of risks, such reprocessing plants, nuclear power plants, every facility where is stored radioactive material. The vulnerability of these facilities is also evoked. Some solutions are recommended but more specially, further thought needs to be given to that kind of problems. (N.C.)

  4. How many to bring the nuclear part to 50% in 2020?; Quel cout pour ramener la part du nucleaire a 50% en 2020?

    Energy Technology Data Exchange (ETDEWEB)

    Nifenecker, H

    2007-02-15

    The author aims to evaluate the cost of a reduction of 50% of the nuclear part in the energy production in France. This evaluation, realized for 2020 gives a total of 42 giga euros. The consequences on the CO{sub 2} emissions are also calculated. (A.L.B.)

  5. Present day situation and perspectives of the nuclear sector in the USA; La situation actuelle et les perspectives du secteur nucleaire aux Etats-Unis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    With the restart-up of Browns Ferry NPP on May 22, 2007, the US nuclear park comprises now 104 reactors in operation: 35 BWR-type and 69 PWR-type. NPPs are present in only 31 states and mainly in the eastern half of the country. Nuclear energy represents 20% of the US energy mix (coal: 50%, gas: 19%, hydro-power: 6%, petroleum: 3% and other renewable energies: 2%). The highest average availability rate in power generation is reached by nuclear energy (89.9%). The nuclear power generation reached 787.2 TWh in 2006, i.e. the second best result after the 2004 record (788.5 TWh). This document presents also some nuclear safety and radioprotection indicators (number of unplanned outages, failures, injury frequency rate), the programme of licenses extension, the permissions for power increase, the demands for design certification, for early site permit, and for combined construction permit and operating license. The regulation may be different from one state to the other and sometimes not favorable to a re-launch of nuclear energy. The situation of each state in this domain is presented in appendix. (J.S.)

  6. The nuclear energy of the future: the researches and the objectives; L'energie nucleaire du futur: quelles recherches pour quels objectifs?

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    Today energy problems are global problems. That is why the new generation of energy production by nuclear power must be realized basely on serious forecasts at a world scale. The nuclear energy presents many trumps for an energetic answer, at long-dated, concerning the environment and the resources. This will be for two main conditions: the ability to answer the public opinion anxiety and the development of new systems more high- performance in terms of safety and economy in the framework of the sustainable development and the non proliferation policy. These subjects are at the earth of the CEA missions. This document proposes a detailed presentation of the nuclear origins, the fuel and its cycle, the radioactive wastes and their management,the dismantling and the decommissioning of the nuclear installations, the challenges of the nuclear safety, the energy in the world, the nuclear economy, the nuclear in the world, the researches of the future, the third generation reactors, the research on radioactive wastes, the fuel cycle of the nuclear systems of the future, the uranium resources, the generation four forum, the gas coolant reactors, the thorium, hybrid systems and the thermonuclear fusion. (A.L.B.)

  7. Pollution with an underlying of corruption. How Russia is becoming the world nuclear sewer; Pollution sur fond de corruption. Comment la Russie devient la poubelle nucleaire du monde

    Energy Technology Data Exchange (ETDEWEB)

    Melis, N

    2002-02-01

    Following the new laws decided by the Russian Government, concerning the radioactive wastes importation, many ecologist organizations fight against the future environmental and biological impacts of such a policy. This paper presents the legal situation, the Government attitude and the actions of russian and international organizations. (A.L.B.)

  8. Inventory of chemical releases of nuclear installations in the North-Cotentin; Inventaire des rejets chimiques des installations nucleaires du Nord-Cotentin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-15

    The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

  9. United Kingdom from past leadership to the renaissance of nuclear industry; Le Royaume-Uni: a l'avant-garde de la renaissance du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Capdevila, J.M. [CEA/Ambassade de France a Londres (United Kingdom)

    2010-07-15

    United-Kingdom has developed a long tradition of know-how in the domain of nuclear energy since 1956 when the first power reactor entered into service at Calder Hall site. From 1956 till now 45 reactors have been successively connected to the grid. All the sectors of nuclear industry were developed: uranium conversion, enrichment, fuel fabrication, MOX fabrication, spent fuels reprocessing and radioactive waste management. Now British nuclear industry is slowly getting out of a 20 year long period of lethargy due mainly to the lost competition with the oil and gas from the North sea fields. Since 2008 and because the North sea resources are waning, U.K. has become again an oil importer. The new energy policy of the government is to favor renewable energies and to support at least the renewal of the today's reactors. 19 reactors are operating but most are old: 14 reactors will have to be stopped by 2018 unless service life extensions are allowed. The French EDF company who purchased British-Energy in 2009 has announced the construction of 4 EPR by 2025. The renaissance of the nuclear industry in U.K. is all the easier as the past was glorious. (A.C.)

  10. Safe management of actinides in the nuclear fuel cycle: Role of mineralogy; La gestion des actinides dans le cycle du combustible nucleaire: le role de la mineralogie

    Energy Technology Data Exchange (ETDEWEB)

    Ewing, R.C. [Department of Nuclear Engineering and Radiological Sciences, Department of Geological Sciences, Department of Materials Science and Engineering, University of Michigan, Ann Arbor, Michigan 48109-1005 (United States)

    2011-02-15

    During the past 60 years, more than 1800 metric tonnes of Pu, and substantial quantities of the 'minor' actinides, such as Np, Am and Cm, have been generated in nuclear reactors. Some of these transuranium elements can be a source of energy in fission reactions (e.g., {sup 239}Pu), a source of fissile material for nuclear weapons (e.g., {sup 239}Pu and {sup 237}Np), and of environmental concern because of their long-half lives and radiotoxicity (e.g., {sup 239}Pu and {sup 237}Np). There are two basic strategies for the disposition of these heavy elements: (1) to 'burn' or transmute the actinides using nuclear reactors or accelerators; (2) to 'sequester' the actinides in chemically durable, radiation-resistant materials that are suitable for geologic disposal. There has been substantial interest in the use of actinide-bearing minerals, especially isometric pyrochlore, A{sub 2}B{sub 2}O{sub 7} (A rare earths; B = Ti, Zr, Sn, Hf), for the immobilization of actinides, particularly plutonium, both as inert matrix fuels and nuclear waste forms. Systematic studies of rare-earth pyrochlores have led to the discovery that certain compositions (B = Zr, Hf) are stable to very high doses of alpha-decay event damage. Recent developments in our understanding of the properties of heavy element solids have opened up new possibilities for the design of advanced nuclear fuels and waste forms. (author)

  11. Ascouf: an industrial software for the engineering of nuclear facilities in operation; Ascouf: un outil numerique industriel pour l`ingenierie nucleaire du parc en exploitation

    Energy Technology Data Exchange (ETDEWEB)

    Genette, P.; Martelet, B. [Electricite de France (EDF), 69 - Villeurbanne (France). Div. Mecanique des Structures du Septen; Debost-Eymart, I. [Electricite de France (EDF), 92 - Clamart (France). Dept. Mecanique et Modeles Numeriques

    1998-10-01

    The ASCOUF software has been developed par EDF to facilitate the quick analysis of defects contained in pipes or elbows of the primary loop. This preprocessing tool of Code Aster, the structural analysis finite element code of EDF, has been used to carry out, with an increase of productivity a series of numerical studies proving the mechanical strength of these components. Its validation, taking into account the feed-back from previous studies, leads us to rely on the results. ASCOUF has afterwards been extended to solve the problems of lack of thickness of pipes of the secondary loop. (authors)

  12. Crisis assistance to nuclear operators: the manufacturer missions and methods; L`assistance de crise a l`exploitant nucleaire: missions et methodes du constructeur

    Energy Technology Data Exchange (ETDEWEB)

    Touati, J. [Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Paris-La-Defense (France)

    1995-12-31

    Since 1985, the Framatome Company has provided to Electricite de France (EDF) a technical assistance in the case of major accident on a nuclear power plant. During the accident crisis, Framatome establishes a diagnosis and a forecast about the installation state and proposes the safest solutions to the operator for a limitation of accident consequences. Different tools have been developed by Framatome to identify the consequences of electric power outages or to control the state of coolant circuits using expert systems and a data base about reactor component characteristics. A thermo-hydraulic analysis of the accident is performed by the system, using data transmitted to the crisis center, and hypotheses about the origin of the accident are proposed by the expert. After validation, a classification of risks is established and the best strategy to follow is determined by the system, in particular when non-conventional means are required. (J.S.). 1 fig.

  13. Correlations between nuclear data and results of integral slab experiments. Case of hafnium; Correlations entre donnees nucleaires et experiences integrales a plaques: le cas du hafnium

    Energy Technology Data Exchange (ETDEWEB)

    Palau, J.M

    1997-10-22

    The aim of this thesis was to evaluate how much integral slab experiments can both reduce discrepancies between experimental results and calculations, and improve the knowledge of hafnium isotopes neutronic parameters by an adapted sensitivity and uncertainty method. A statistical approach, based on the generalized least squares method and perturbation theory, has been incorporated into our calculation system in order to deduce microscopic cross-section adjustments from observed integral measurements on this particular `mock-up` reactor. In this study it has been established that the correlations between integral parameters and hafnium capture cross-sections enable specific variations in the region of resolved resonances at the level of multigroup and punctual cross-sections recommended data (JEF-2.2 evaluation) to be highlighted. The use of determinist methods (APOLLO2 code) together with Monte Carlo- type simulations (TRIPOLI4 code) enabled a depth analysis of the modelling approximations to be carried out. Furthermore, the sensitivity coefficient validation technique employed leads to a reliable assessment of the quality of the new basic nuclear data. In this instance, the adjustments proposed for certain isotope {sup 177}Hf resonance parameters reduce, after error propagation, by 3 to 5 per cent the difference between experimental results and calculations related to this absorbent`s efficiency. Beyond this particular application, the qualification methodology integrated in our calculation system should enable other basic sizing parameters to be treated (chemical / geometric data or other unexplored nuclear data) to make technological requirements less stringent. (author) 128 refs.

  14. Correlations between nuclear data and integral slab experiments: the case of hafnium; Correlations entre donnees nucleaires et experiences integrales a plaques: le cas du hafnium

    Energy Technology Data Exchange (ETDEWEB)

    Palau, J.M

    1999-07-01

    The aim of this work was to evaluate how much integral slab experiments can both reduce discrepancies between experimental results and calculations, and improve the knowledge of hafnium isotopes neutronic parameters by an adapted sensitivity and uncertainty method. A statistical approach, based on the generalized least squares method and perturbation theory, has been incorporated into our calculation system in order to deduce microscopic cross-section adjustments from observed integral measurements on this particular 'mock-up' reactor.In this study it has been established that the correlations between integral parameters and hafnium capture cross-sections enable specific variations in the region of resolved resonances at the level of multigroup and punctual cross-sections recommended data (JEF-2.2 evaluation) to be highlighted. The use of determinist methods together with Monte Carlo- type simulations enabled a depth analysis of the modelling approximations to be carried out. Furthermore, the sensitivity coefficient validation technique employed leads to a reliable assessment of the quality of the new basic nuclear data. In this instance, the adjustments proposed for certain isotope {sup 177}Hf resonance parameters reduce, after error propagation, by 3 to 5 per cent the difference between experimental results and calculations related to this absorbent's efficiency. Beyond this particular application, the qualification methodology integrated in our calculation system should enable other basic sizing parameters to be treated (chemical / geometric data or other unexplored nuclear data) to make technological requirements less stringent. (author)

  15. Study of nuclear glasses alteration gel and synthesis of some model gels; Etude du gel d`alteration des verres nucleaires et synthese de gels modeles

    Energy Technology Data Exchange (ETDEWEB)

    Ricol, S.

    1995-10-05

    This work deals with the general problem of alteration of the reference nuclear glass R7T7. Attention is paid particularly to the altered layer formed at the glass surface during alteration process. In opposition to previous works, related essentially to glass dissolution kinetics based on chemical analyses of lixiviated elements, this thesis deals with alteration problems through structural studies of the reference glass and derived gel. This approach allows the determination of mechanisms for the gel formation and a better understanding of the behaviour of glasses towards lixiviation. Both approaches appeared complementary. Based on several spectroscopic techniques, this work showed the particular role of cations such as calcium, zirconium and iron. Studies of silica-based synthetic gels showed the synergic effect of formers cation and of one highly coordinated cation. The variation of the wavenumber related to Si-O-Si asymmetric stretching vibration can be correlated to O/Si ratio for ternary systems Si/Na/Zr. On the contrary, the Si losses of the materials depend on the number of non-bridging oxygen atoms. In the perspective of long-term behaviour, the alteration gel presents better characteristics than initial glass. It is therefore a highly stable material in static conditions. In the same way, synthetic gels are materials with very low solubilities (much lower than the alteration gel) and could be used as confining matrices. (authors). refs., 71 figs., 37 tabs.

  16. Correlations between nuclear data and results of integral slab experiments. Case of hafnium; Correlations entre donnees nucleaires et experiences integrales a plaques: le cas du hafnium

    Energy Technology Data Exchange (ETDEWEB)

    Palau, J.M

    1997-10-22

    The aim of this thesis was to evaluate how much integral slab experiments can both reduce discrepancies between experimental results and calculations, and improve the knowledge of hafnium isotopes neutronic parameters by an adapted sensitivity and uncertainty method. A statistical approach, based on the generalized least squares method and perturbation theory, has been incorporated into our calculation system in order to deduce microscopic cross-section adjustments from observed integral measurements on this particular `mock-up` reactor. In this study it has been established that the correlations between integral parameters and hafnium capture cross-sections enable specific variations in the region of resolved resonances at the level of multigroup and punctual cross-sections recommended data (JEF-2.2 evaluation) to be highlighted. The use of determinist methods (APOLLO2 code) together with Monte Carlo- type simulations (TRIPOLI4 code) enabled a depth analysis of the modelling approximations to be carried out. Furthermore, the sensitivity coefficient validation technique employed leads to a reliable assessment of the quality of the new basic nuclear data. In this instance, the adjustments proposed for certain isotope {sup 177}Hf resonance parameters reduce, after error propagation, by 3 to 5 per cent the difference between experimental results and calculations related to this absorbent`s efficiency. Beyond this particular application, the qualification methodology integrated in our calculation system should enable other basic sizing parameters to be treated (chemical / geometric data or other unexplored nuclear data) to make technological requirements less stringent. (author) 128 refs.

  17. Assessment of the feasibility of indefinite containment of canadian nuclear fuel wastes; Evaluation de la faisabilite du confinement illimite des dechets de combustible nucleaire canadiens

    Energy Technology Data Exchange (ETDEWEB)

    Shoesmith, D.W.; King, F.; Ikeda, B.M.

    1995-05-01

    This report presents an analysis of the expected corrosion behavior of nuclear fuel waste containers in a conceptual Canadian disposal vault. The container materials considered are dilute Ti alloys (Grades-2, -12 and -16) and oxygen-free copper.

  18. Non-proliferation and nuclear disarmament: speech of the president Obama at Prague; Non-proliferation et desarmement nucleaires: discours de Prague du president Obama

    Energy Technology Data Exchange (ETDEWEB)

    Hautecouverture, B. [Centre d' Etudes de Securits Internationale et de Maitrise des armements (CESIM), 75 - Paris (France)

    2009-10-15

    Introduced by the Prague speech of april 7 2009, the Obama President program towards the non proliferation and the nuclear disarmament was pointed out by its optimism ambition and determination. But a more detailed lecture shows concurrent positions. The author analyzes the political aspects of the President speech. (A.L.B.)

  19. Nuclear non-proliferation and disarmament: the President Obama's Prague speech; Non-proliferation et desarmement nucleaires: discours de Prague du president Obama

    Energy Technology Data Exchange (ETDEWEB)

    Hautecouverture, B. [Centre d' Etudes de Securite Internationale et de Maitrise des Armements (CESIM), 75 - Paris (France)

    2010-07-15

    The author comments the content and the consequences of President Obama's speech on the future of nuclear weapons in the 21. century. After a recall of the political context, the author shows how this declaration sounded with a real new tone, defined a new direction and introduced a new method, but may reach its objectives only on a long term. Then, he comments how these objectives are challenged by the present context and events, and outlines how the US Nuclear Posture Review will be important

  20. By-law from December 12, 2005 relative to nuclear pressure systems; Arrete du 12 decembre 2005 relatif aux equipements sous pression nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

    This by-law deals with the specifications relative to the design, fabrication and conformability evaluations of nuclear pressure system, i.e. systems that may lead to a radioactive contamination in the case of failure. The main safety requirements of these systems are recalled in appendixes (nondestructive testing and qualification). (J.S.)

  1. Obligation of information and nuclear medicine after the law of march 4. 2002; Obligation d'information en medecine nucleaire apres la loi du 4 mars 2002

    Energy Technology Data Exchange (ETDEWEB)

    Bloch, L. [Universite Montesquieu, ATER, 33 - Bordeaux (France)

    2002-06-01

    The default of the obligation of information, which should only be a deontological fault, had begun to intrude on the area of responsibility, whether it be criminal or indeed civil. 'Ethical' responsibility took over a 'technical' responsibility limited by the primacy of fault. The law of March 4, 2002 prepared the ground for a return of this sword of Damocles towards its natural area, that is to say deontological fault which comes within ordinal jurisdictions. Thus the main contribution of this law is to be found in the definition of medical responsibility which, by limiting responsibility to a technical fault, seems to rule out the default of the obligation of information. The law of March 4, 2002 has not stirred up the content of the obligation of information for all that. The question of the information on exceptional risks is the only one to have noticeably evolved, since information now concerns only predictable risks. Therefore, the law of March 4, 2002, in no way leads to the death of the obligation of information, quite the reverse: the quality requirements in the information of the patient are even reinforced in some of their aspects, but in compensation for these requirements, there is no exacerbated responsibility anymore. (author)

  2. L’Harmonie du monde

    Directory of Open Access Journals (Sweden)

    Martine Clouzot

    2003-11-01

    Full Text Available La Bourgogne est particulièrement bien présente et représentée dans l’exposition sur la musique et ses représentations au Moyen Âge organisée par Isabelle Marchesin (université de Poitiers, Christine Laloue (conservatrice du Patrimoine au Musée et Martine Clouzot (université de Bourgogne, au Musée de la Musique à Paris du 26 mars au 27 juin 2004. En Côte-d’Or, à Dijon, la Bibliothèque municipale a donné son accord officiel pour le prêt de la Bible d’Etienne Harding, les Moralia in Job et u...

  3. L'energie du moustique

    CERN Document Server

    Augereau, J F

    2002-01-01

    ENSEMBLE DE QUATRE ARTICLES - LARGE HADRON COLLIDER: Le dernier accelerateur de particules du CERN, le LEP, produisait des faisceaux d'electrons de 100 GeV chacun. Le LHC, qui accelere des faisceaux de protons, leur communiquera une energie de 7 TeV chacun. Une energie a la fois colossale et derisoire. Un TeV represente a peu pres l'energie cinetique d'un moustique (1/2 page).

  4. Revision du Genre Aseraggodes Kaup

    NARCIS (Netherlands)

    Chabanaud, P.

    1930-01-01

    Le présent travail comprend la définition du genre Aseraggodes Kaup et la revision, sous forme d'une clef dichotomique, de toutes les espèces qui le composent, revision établie d'après les types eux-mêmes de ces espèces. Ce genre Aseraggodes appartient à la famille des Soleidae et à la sousfamille

  5. Collecting uncollectables: Joachim Du Bellay

    Directory of Open Access Journals (Sweden)

    Gro Bjørnerud Mo

    2017-09-01

    Full Text Available Lists of wonders have circulated for millennia. Over and over, such inventories of spectacular man made constructions have been rewritten, re-edited and reimagi-ned. Both the wonders and the lists of wonders, preferably of the seven, have had a profound and long-lasting effect, and have been abundantly imitated, copied and reworked. Renaissance creative thinking was obsessed with the seven wonders of the ancient world, and early-modern Europe experienced a surge of visual and verbal depictions of wonders. This article is about a remarkable list of seven wonders, included in one of Joachim Du Bellay's canonical poems on Roman antiquities (Antiquités de Rome, published in Paris in 1558. Du Bellay shapes his list of wonders by exploring pat-terns of both repetition and mutability. Almost imperceptibly, he starts suggesting connections between 16th-century Rome and distant civilizations. Through the eyes of a fictive traveller and collector, the poet venerates the greatness and la-ments the loss of ancient buildings, sites and works of art, slowly developing a ver-bal, visual and open-ended gallery, creating a collection of crumbling or vanished, mainly Roman, architecture. This poetic display of ruins and dust in the Eternal City is nourished by the attraction of the inevitable destruction of past splendour and beauty. In the sonnets, Du Bellay imitates classical models and patterns. Whi-le compiling powerful images and stories of destruction, he combines techniques associated with both a modern concept of copy and more ancient theories of co-pia. In this context, this article also explores whether Pliny's Natural History might be a source for the imaginary collection of lost sites and wonders in Du Bellay's Antiquit's.

  6. Prairie du Chien: A Historical Study,

    Science.gov (United States)

    1976-10-01

    Naudouwessee with whom this governor made peace and introduced trade and commerce among the whole nation. His son the successor told me that some of the...Nicholas Perrot, French Commandant of the West, with a party of couriers du bois and voyageurs descended the Wisconsin River and erected Fort St...number of traders and voyageurs settled at Prairie du Chien. Thomas Anderson who settled at Prairie du Chien in 1800 described the conditions on his

  7. Genetics Home Reference: cri-du-chat syndrome

    Science.gov (United States)

    ... Health Conditions cri-du-chat syndrome cri-du-chat syndrome Enable Javascript to view the expand/collapse ... PDF Open All Close All Description Cri-du-chat (cat's cry) syndrome, also known as 5p- (5p ...

  8. Au fil du temps (1976 ou la loi du seuil

    Directory of Open Access Journals (Sweden)

    Isabelle Singer

    2010-04-01

    Full Text Available Ayant choisi de vivre dans un camion, les héros d’Au fil du temps (film de Wim Wenders de 1976 font du seuil une expérience particulière. Celle de la rupture avec toute idée de foyer et celle du refus d’appartenance à la terre natale, cette terre allemande traversée par une frontière le long de laquelle ils vont voyager, et qui les renvoie à chaque instant aux traumatismes de l’Histoire. Sur le pare-brise du camion, l’extérieur (campagnes indifférenciées, villes à l’abandon… et l’intérieur se superposent. Au fil du temps questionne le paysage : il s’agit d’en décoller un à un les mythes qui le recouvrent. L’image alors n’est plus surface mais volume à traverser, à lacérer et découvrir ce qui est tissé dans le paysage. La démarche de Wenders est alors proche de celle d’un de ses contemporains : Anselm Kiefer. Le paysage allemand provoque le rejet parce qu’il y a là toujours plus que le visible : des strates et des strates de culpabilité que le mythe - et c’est sa fonction - a recouvert. Et qu’il s’agira ici, de soulever. Le choix du nomadisme, c’est celui d’un état de l’humanité antérieur à l’idée de patrie. Et c’est aussi celui de la solitude, comme prix à payer à ce refus d’appartenance et à cette mise à jour des mythes. L’appartenance à la terre allemande et à son Histoire est profondément problématique parce que les pères sont fondamentalement coupables. On se reconnaîtra alors des pères de substitution : des pères de cinéma (Nicholas Ray ou Fritz Lang. Et l’on substituera l’Histoire du cinéma à l’Histoire. Bruno est réparateur ambulant de projecteurs et Au fil du temps dressera, au gré de ses pérégrinations, un état des lieux du cinéma allemand des années soixante-dix : déliquescent, colonisé par les images hollywoodiennes. Il faut que cela change : état du cinéma ; état des protagonistes solitaires en quête d’une identit

  9. The long-term future for civilian nuclear power generation in France: The case for breeder reactors. Breeder reactors: The physical and physical chemistry parameters, associate material thermodynamics and mechanical engineering: Novelties and issues; La production d'electricite d'origine nucleaire en France, dans le futur a long terme: Le cas des surgenerateurs: Les reacteurs nucleaires surgenerateurs: Les parametres physique et physico-chimiques, la thermodynamique associee des materiaux et de l'ingenierie mecanique: Nouveautes et options

    Energy Technology Data Exchange (ETDEWEB)

    Dautray, R. [Academie des sciences, 23, quai de Conti, 75270 Paris cedex 06 (France)

    2011-06-15

    The author gives a summary overview of the knowledge base acquired since the first breeder reactors became operational in the fifties. Neutron transport theory, thermal phenomena, reactor core cooling, various coolants used and envisioned for this function, fuel fabrication from separated materials, main equipment (pumps, valves, heat exchanges...) have now attained maturity, sufficient to implement sodium cooling circuits. However, the use of metallic sodium still raises certain severe questions in terms of safe handling and security considerations. The structural components, both inside the reactor core and outside (i.e. heat exchangers) are undergoing in-depth research so as to last longer. The fuel cycle, notably the re-fabrication of fuel elements and fertile elements, the case of transuranic elements, etc., call for studies into radiation induced phenomena, chemistry separation, separate or otherwise treatments for materials that have different radioactive, physical, thermodynamical, chemical and biological properties. The concerns that surround the definitive disposal of certain radioactive wastes could be qualitatively improved with respect to the pressurized water reactors (PWRs) in service today. Lastly, the author notes that breeder reactors eliminate the need for an isotope separation facility, and this constitutes a significant contribution to contain nuclear proliferation. France was in the forefront of nuclear breeder power generation science, technological research and also in the knowledge base related to breeder reactors. It is in the country's interest to pursue these efforts. (author)

  10. Métastases gastro-intestinales du cancer du sein: à propos de 2 cas

    Science.gov (United States)

    Loubna, Mezouar; Mohamed, El Hfid; Tijani, El Harroudi; Fouzia, Ghadouani; Hanane, Haj Kacem; Zouhour, Bourhaleb; Asmae, Ouabdelmoumen

    2013-01-01

    Le cancer du sein est le cancer le plus fréquent chez la femme, notamment au Maroc, avec un taux de mortalité élevé. Les métastases gastro-intestinales d'un carcinome canalaire du sein sont rares. Leur diagnostic est difficile du fait de la nature non spécifique des symptômes. Nous rapportons deux observations originales de métastases gastroduodénales d'un cancer canalaire infiltrant du sein. Les métastases gastro-intestinales du cancer du sein sont très rares; la présence de symptômes gastro-intestinaux chez une malade ayant un antécédent de cancer du sein doit faire suspecter une atteinte métastatique gastro-intestinale. PMID:24198876

  11. Session du Conseil du CERN : le ministre britannique, Robert Jackson, souligne l'intérêt de on pays pour l'avenir du CERN : décisions du Conseil pour la mise en oeuvre des recommandations du Comité d'évaluation du CERN: départ anticipé pour 200 membres au moins du personnel - mise à jour de la méthode de calcule pour les contributions des Etats Membres au budget

    CERN Multimedia

    CERN Press Office. Geneva

    1988-01-01

    Session du Conseil du CERN : le ministre britannique, Robert Jackson, souligne l'intérêt de on pays pour l'avenir du CERN : décisions du Conseil pour la mise en oeuvre des recommandations du Comité d'évaluation du CERN: départ anticipé pour 200 membres au moins du personnel - mise à jour de la méthode de calcule pour les contributions des Etats Membres au budget

  12. Des Taiwanais dans Ie sud du Fujian

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    Se trouvant dans le sud-est de la Chine au bord dela mer, la province du Fujian s’appelle aussi toutsimplement "Min". Les anc(?)tres d’une grande partie de lapopulation de Taiwan sont venus du Fujian (Min). Les deux

  13. Le vide univers du tout et du rien

    CERN Document Server

    Diner, Simon

    1997-01-01

    Pourquoi l'Univers plutôt que le vide ? Le temps et l'espace existent-ils en l'absence de l'Univers ? Que reste-t-il quand tout est enlevé ? Pourquoi quelque chose plutôt que rien ? Depuis des siècles, ces interrogations mobilisent philosophes et physiciens. Mais aujourd'hui, le vide n'est pas le rien. Il serait même l'acteur central de l'histoire de la matière et de l'Univers, le partenaire privilégié de la physique. Vide et matière ne sont plus deux manifestations séparées de la nature, mais deux aspects d'une même réalité. Le vide est l'état de base dont la matière émerge, sans couper son cordon ombilical Le vide comme Univers du rien cède la place au vide comme Univers du tout. Que le vide puisse être conçu par les physiciens comme réservoir potentiel d'univers, voici qui ne devrait laisser personne indifférent. Ce livre ouvre un débat et nous convie à une réflexion surprenante.

  14. Image du savoir, image du pouvoir dans le Lapidaire

    Directory of Open Access Journals (Sweden)

    Marta LACOMBA

    2007-01-01

    Full Text Available À travers le prologue et les enluminures de présentation, le Lapidaire d’Alphonse X oriente l’interprétation de l’œuvre. Ces paratextes mettent en avant le rôle capital du savoir, représenté par la métaphore du trésor caché, qui a ici une valeur topique. Ils mettent également en exergue le rôle que s’attribue le roi dans la transmission de ce savoir, et placent cette nouvelle attribution royale au cœur de son projet politique.A través del prólogo y las miniaturas de presentación, el Lapidario de Alfonso X orienta la interpretación de la obra. Estos paratextos subrayan el papel capital del saber, representado por la metáfora del tesoro escondido, que tiene aquí un valor tópico. Ponen asimismo de manifiesto el papel que se atribuye el monarca en la transmisión de ese saber y colocan esta nueva atribución real en el centro de su proyecto político.

  15. Calculation of reactivity by digital processing; Calcul de la reactivite par traitement numerique

    Energy Technology Data Exchange (ETDEWEB)

    Hedde, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-12-01

    With a view to exploring the new possibilities offered by digital techniques, a description is given of the optimum theoretical conditions of a computation of the realtime reactivity using counting samples (obtained from a nuclear reactor). The degree to which these optimum conditions can be attained depends on the complexity of the processing which can be accepted. A compromise thus has to be made between the accuracy required and the simplicity of the equipment carrying out the processing. An example is given, using a relatively simple structure, which gives an idea of the accuracy of the results obtained over a wide range of reactor power. (author) [French] Dans le but d'explorer les possibilites nouvelles des techniques numeriques, on decrit les conditions theoriques optimales d'un calcul de la reactivite en temps reel a partir d'echantillons de comptage (en provenance d'un reacteur nucleaire). Ces conditions optimales peuvent etre approchees d'autant mieux que l'on accepte un traitement plus complexe. Un compromis est donc a faire entre la precision desiree et la simplicite du materiel assurant le traitement. Un exemple adoptant une structure de complexite reduite permet de juger de la precision des resultats obtenus sur une importante plage d'evolution de la puissance. (auteur)

  16. Les esclaves du commandant Quiquandon

    OpenAIRE

    Tymowski, Michal

    2003-01-01

    Le 10 janvier 1895, Albert Grodet, gouverneur général du Soudan français, adressa au ministère des Colonies une dépêche accusant le commandant Quiquandon, dirigeant de la région Nord-Est (Ségou), d'exploiter illégalement un domaine sur lequel travaillent 140 esclaves. À partir de ce cas particulier, l'auteur analyse les conflits qui existaient à l'époque entre l'administration civile et un groupe d'officiers soudanais. Il se demande si la possession d'esclaves par des officiers, prenant...

  17. Du comptoir à la toge

    OpenAIRE

    Buti, Gilbert

    2007-01-01

    Descendant d’une famille de petits notables du Dauphiné, Antoine Anthoine (1749-1826) qui n’a pas pu accéder à la magistrature se destine à la marchandise. Après un apprentissage à Marseille au comptoir des Seimandy, il est nommé, par ces négociants, régisseur pour leur commandite de Constantinople. La mobilisation de sa proche parenté et les soutiens des pouvoirs politiques locaux, nationaux et internationaux lui permettent d’obtenir une mission destinée à ouvrir le commerce de la Russie mér...

  18. Aventures radiophoniques du Nouveau Roman

    Directory of Open Access Journals (Sweden)

    Beatrice Nickel

    2015-12-01

    Full Text Available  Aventures radiophoniques du Nouveau Roman Colloque international organisé par l’Université Paul-Valéry Montpellier, en partenariat avec l’Université de Stuttgart 19-20 novembre 2015   Organisateurs :  Pierre-Marie Héron, Annie Pibarot, Université Paul-Valéry Montpellier, centre de recherche Rirra21. Françoise Joly, Beatrice Nickel, Universität Stuttgart 

  19. Advanced modeling of the size poly-dispersion of boiling flows; Modelisation avancee de la polydispersion en taille des ecoulements bouillants

    Energy Technology Data Exchange (ETDEWEB)

    Ruyer, Pierre; Seiler, Nathalie [Cadarache Batiment 700, IRSN/DPAM/SEMCA/LEIDC, BP 3, 13 115 Saint Paul lez Durance cedex (France)

    2008-07-01

    Full text of publication follows: This work has been performed within the Institut de Radioprotection et de Surete Nucleaire that leads research programs concerning safety analysis of nuclear power plants. During a LOCA (Loss Of Coolant Accident), in-vessel pressure decreases and temperature increases, leading to the onset of nucleate boiling. The present study focuses on the numerical simulation of the local topology of the boiling flow. There is experimental evidence of a local and statistical large spectra of possible bubble sizes. The relative importance of the correct description of this poly-dispersion in size is due to the dependency of (i) main hydrodynamic forces, like lift, as well as of (ii) transfer area with respect to the individual bubble size. We study the corresponding CFD model in the framework of an ensemble averaged description of the dispersed two-phase flow. The transport equations of the main statistical moment densities of the population size distribution are derived and models for the mass, momentum and heat transfers at the bubble scale as well as for bubble coalescence are achieved. This model introduced within NEPTUNE-CFD code of the NEPTUNE thermal-hydraulic platform, a joint project of CEA, EDF, IRSN and AREVA, has been tested on boiling flows obtained on the DEBORA facility of the CEA at Grenoble. These numerical simulations provide a validation and attest the impact of the proposed model. (authors) [French] Un programme de Recherche et Developpement dans le domaine de l'Accident de Perte du Refrigerent Primaire, sur un Reacteur a Eau sous Pression, a ete lance par l'Institut de Radioprotection et de Surete Nucleaire, a la Direction de Prevention des Accidents Majeurs. Au cours d'un transitoire accidentel de type APRP, le denoyage du coeur du reacteur conduit a une ebullition locale du fluide sur la paroi des crayons accompagnee d'une montee en temperature des gaines des crayons, terminee par une phase de renoyage

  20. Sociologie et sociolinguistique du franbreu

    Directory of Open Access Journals (Sweden)

    Ben-Rafael Eliezer

    2014-07-01

    Full Text Available Des enquêtes ont montré que plus de 20 % des adultes israéliens ont quelque connaissance du français. Parmi cette population, 250 000 à 300 000 personnes pouvaient être considérées comme francophones. Le français a affirmé une présence importante – pas toujours reconnue – dès la phase cruciale du développement de cette société. Une immigration de masse suivit la création de l’État (1948 dont la population a quasiment triplé en moins de deux décennies, avec l’arrivée de plus de 200 000 immigrants d’Afrique du Nord et des dizaines de milliers des Balkans et du Moyen-Orient. Beaucoup parmi ces immigrants étaient francophones – le français étant pour eux soit la première langue soit une deuxième qu’ils contrôlaient. C’est depuis lors que la présence du français est devenue démographiquement significative dans la société israélienne, se prolongeant de nos jours dans l’immigration en provenance de France qui se poursuit jusqu’à aujourd’hui. Comme nous l’avons montré ailleurs (Ben-Rafael et Ben-Rafael 2013, Israël fait l’expérience simultanée de plusieurs francophonies originales qui diffèrent par leurs sources aussi bien que leurs expressions (Ben-Rafael et Ben-Rafael 2013. Un premier modèle est le « français vernaculaire » (voir Boudras-Chapon 2008 amené par les immigrants de classes défavorisées arrivant d’Afrique du nord qui se sont regroupés en Israël. Leur français n’a offert qu’une faible résistance à l’hébreu qui s’est imposée dans le processus d’intégration. Un bilinguisme fonctionnant sur un mode additif au début qui s’est mué progressivement en modèle soustractif. Un second modèle concerne les immigrants de même origine ainsi que des immigrants francophones d’autres pays (pays balkaniques, Turquie ou Egypte formant une strate instruite de classe moyenne, pour qui le français était d’utilisation quotidienne aussi bien que de langue de

  1. Rejets et environnement du CERN

    CERN Document Server

    Vojtyla, P

    2007-01-01

    La radioactivité de l’environnement autour de l’Organisation Européenne pour la Recherche Nucléaire (CERN) et les doses de rayonnements qui en résultent pour la population avoisinante sont contrôlées par la Commission de Sécurité du CERN et de manière indépendante par les autorités compétentes des deux États Hôtes, l’Institut de Radioprotection et de Sûreté Nucléaire (IRSN) côté France et l’Office Fédéral de la Santé Publique (OFSP) côté Suisse (voire Chapitre 8.6). Dans ce rapport, les résultats de mesures concernent en particulier le territoire suisse. L’ensemble des mesures effectuées en 2006 prouve que le fonctionnement des installations du CERN était sans conséquence radiologique sur l’environnement et la population. Le contrôle des émissions montre que les rejets effectifs se situent, également en 2006, nettement en dessous des limites réglementaires. Ce constat est confirmé par le contrôle des immissions dans l’environnement. Le CERN a bien respecté en 2...

  2. Bases en technique du vide

    CERN Document Server

    Rouviere, Nelly

    2017-01-01

    Cette seconde édition, 20 ans après la première, devrait continuer à aider les techniciens pour la réalisation de leur système de vide. La technologie du vide est utilisée, à présent, dans de nombreux domaines très différents les uns des autres et avec des matériels très fiables. Or, elle est souvent bien peu étudiée, de plus, c'est une discipline où le savoir-faire prend tout son sens. Malheureusement la transmission par des ingénieurs et techniciens expérimentés ne se fait plus ou trop rapidement. La technologie du vide fait appel à la physique, à la chimie, à la mécanique, à la métallurgie, au dessin industriel, à l'électronique, à la thermique, etc. Cette discipline demande donc de maîtriser des techniques de domaines très divers, et ce n'est pas chose facile. Chaque installation est en soi un cas particulier avec ses besoins, sa façon de traiter les matériaux et celle d'utiliser les matériels. Les systèmes de vide sont parfois copiés d'un laboratoire à un autre et le...

  3. Report 2000 of EDF nuclear park '' Humans, architects of the progress; Bilan 2000 du parc nucleaire d'EDF ''les hommes, artisans du progres''

    Energy Technology Data Exchange (ETDEWEB)

    Stricker, L.

    2001-03-01

    This report presents the results of the EDF nuclear park, during 2000, in matter of safety, environment and competitiveness. In 2000, the EDF nuclear installations safety still improved. Hopeful the nuclear energy part in its power production, EDF avoids the carbon dioxide diffusion in the atmosphere. EDF also commits itself to reduce the liquid effluents, the gaseous emissions and the solid wastes. At the same time EDF remained competitive with a decrease of the kWh price of 7%. (A.L.B.)

  4. Microbial issues pertaining to the canadian concept for the disposal of nuclear fuel waste. Questions a examiner quant aux microbes lors du developpement du concept canadien de stockage permanent des dechets de combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Stroes-Gascoyne, S.; West, J.M.

    1994-01-01

    This report formulates a number of views and positions on microbiological factors that could influence the performance of a disposal vault in plutonic rock. Microbiological factors discussed include the presence and survival of microbes, biofilms, corrosion, biodegradation (of emplaced materials), gas production, geochemical changes, radionuclide migration, colloid formation, mutation, pathogens and methylation. Not all issues can be fully resolved with the current state of knowledge. Studies being performed to underscore and strengthen current knowledge are briefly discussed.

  5. Research on the chemistry of actinides and fission products for the development of nuclear fuel cycle; Developpement du cycle du combustible nucleaire. Recherche sur la chimie des actinides et des produits de fission

    Energy Technology Data Exchange (ETDEWEB)

    Peretroukhine, V.F. [Institute of Physical Chemistry Russian Academy of Sciences (IPC-Moscow) (Russian Federation); Lecomte, M. [CEA Valrho, Dept. Radiochimie et Procedes, 30 - Marcoule (France); David, F. [Institut de Physique Nucleaire, (IN2P3/CNRS) 91 - Orsay (France)

    2004-07-01

    The present document is prepared for CEA, IPNO and Russian Academy of Sciences administrations in compliance with the decision, accepted by the Director Committee of the three-parties-Convention on its seventh meeting in Moscow 21 May 2002. Being the general frame, determining the strategy of three-party cooperation, the Convention 1993-2003 consists of the number of contracts between organisation-participants. The present document is compiled, using annual proceedings of Director Committee and Technical Committee meetings and using published French-Russian papers and technical reports, produced in the frame of all contracts of the convention. Lists of published papers and personal summary reports of Russian participants of the contracts are presented in Appendix 1. (authors)

  6. Nuclear systems of the future: international forum generation 4 and research and development projects at the Cea; Systemes nucleaires du futur: forum international generation 4 et projets de R et D du CEA

    Energy Technology Data Exchange (ETDEWEB)

    Carre, F

    2003-07-01

    To advance nuclear energy to meet future energy needs, ten countries have agreed to develop a future generation of nuclear energy systems, known as Generation 4. A technology road map to guide the Generation 4 effort was begun. This document presents the goals for these nuclear systems and the research programs of the Cea on the gas technology, GT-MHR, VHTR and GFR and the other systems as sodium Fast Neutron reactors, supercritical water and space nuclear. (A.L.B.)

  7. The nuclear core of sun: theoretical perspectives and characterization of the scientific performances of the GOLF / SOHO experiment detector; La region nucleaire du soleil: perspectives theoriques et caracterisation des performances scientifiques du detecteur de l`experience GOLF / SOHO

    Energy Technology Data Exchange (ETDEWEB)

    Dzitko, H.

    1995-06-23

    The subject of this thesis is the nuclear core of the sun. The first part is theoretical and concerns neutrino flux predictions. A precise description of the solar plasma is necessary to predict boron, beryllium and CNO cycle neutrinos. We treat here the nuclear reaction rates. They are mainly determined by the cross sections and the enhancement factors due to plasma particles, the co-called screening factors. We have discussed the various possible formalisms that could be used in stellar evolution and performed direct calculations of screened cross sections. We concluded that the screening prescriptions which have been used so far in stellar evolution should be replaced by the Mitler formalism. Next, we examine the cross section uncertainties and we show that it is possible to get a better agreement between theory and experiment. Discrepancies between the gallium experiments and the calculations suggest that we should go beyond the classical solar model. This has motivated our study on possible magnetic fields deeply buried in the solar core. We discuss here the influence of a magnetic pressure perturbation on solar evolution. In the experimental part of this work, we deal with the GOLF experiment, one of the three helio-seismological experiments on board the space probe SOHO. The purpose of this instrument is the study of the global oscillation modes in the frequency range 10{sup -7} to 6 10{sup -3} Hz with a sensitivity for frequencies higher than 2 10{sup -4} Hz of about 1 mm/s over 20 days of continuous integration at counting rates of 12 10{sup 6} cs/s. One part of this work was devoted to the precise characterization of the photomultipliers and their associated electronics in order to select them according to their intrinsic performances. This step was followed by long duration tests of three weeks simulating as well as possible the flight conditions. We show that the detection chain effectively meets the stability requirements of around 10{sup -7} by velocity measurement. (Abstract Truncated)

  8. Reinforced concrete corrosion: application of Bayesian networks to the risk management of cooling towers in nuclear plants; Corrosion du beton arme: application des reseaux bayesiens a la gestion du risque des aerorefrigerants des centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Capra, B.; Le Drogo, J.; Wolff, V. [OXAND S.A., 77 - Avon (France)

    2007-07-01

    Degradation modeling of concrete structures uses uncertain variables and leads, using reliability assessment, to time dependant evolution of failure probabilities. However, only few data are generally available to feed models leading to two types of uncertainties: an intrinsic one depending on the modeled phenomena and one related to the precision of the measurements. Each new data available is a piece of information which allows updating the initial prediction. In this article, an example of updating process, based on a Bayesian network, is presented and applied on the corrosion risk of a cooling tower in a nuclear plant. (authors)

  9. Is the nuclear phaseout compatible with the respect of the Kyoto protocol? The example of Belgium; La sortie du nucleaire est-elle compatible avec le respect du protocole de Kyoto? l'exemple de la Belgique

    Energy Technology Data Exchange (ETDEWEB)

    Berger, A

    2008-12-15

    This document provides data and operations needed to evaluate the impacts of the nuclear phaseout on the respect of the Kyoto protocol. The data are based on the belgium electricity production. The author concludes that the nuclear power plants shutdown will lead to a non respect of the kyoto protocol in unacceptable limits. To respect the protocol, he presents two possibilities: the today nuclear park and the use of 1600 wind turbines of 2 MW, or the improvement of the energy efficiency of the thermal power plants. (A.L.B.)

  10. De Sumer à Seattle, le voyage du bout du monde

    Directory of Open Access Journals (Sweden)

    Olivier Walther

    2008-12-01

    Full Text Available « Les affaires qui se nouent par-dessus les frontières qui séparent les peuples ne font pas que ces frontières n'existent pas » notait Émile Durkheim en 1895 (1895 : 113. Un peu plus d’un siècle plus tard, l’ouvrage de William J. Bernstein intitulé A Splendid Exchange et sous-titré de manière inspirée How Trade Shaped the World vient apporter une confirmation étayée au sociologue français. De Sumer où fut introduit le commerce du cuivre 3000 ans avant Jésus-Christ, à Seattle où se tint la tr...

  11. Le cas du Haut-Adige ou Tyrol du Sud

    Directory of Open Access Journals (Sweden)

    Licia Bagini Scantamburlo

    2007-06-01

    Full Text Available La situation de cette région italienne est vraiment emblématique des rapports entre « les territoires et l’identité » à cause de la présence de différentes communautés linguistiques autochtones, dont les plus importantes sont les minorités germanophone et latine. S’il est vrai que cette situation existe également dans d’autres régions italiennes, il est incontestable que dans le Haut-Adige/Tyrol du Sud elle présente des caractéristiques très spécifiques et uniques pour l’Italie, car les italo...

  12. COMMUNICATION DU CREDIT AGRICOLE - French version only

    CERN Multimedia

    2003-01-01

    La Direction du Crédit Agricole informe son aimable clientèle du CERN des jours et heures d'ouverture de l'agence du site de Prévessin à compter du mardi 14 janvier 2003 : 1. Horaires pour les opérations bancaires courantes 7 jours sur 7 et 24h/24 avec l'espace libre service bancaire. 2. Horaires conseil du mardi au vendredi - Mardi, de 9h. à 12h. et de 14h.15 à 16h.30. - Mercredi, jeudi et vendredi, de 9h. à 12h. et de 13h.30 à 16h.30. Deux collaboratrices au lieu d'une seront désormais présentes toute la journée du mardi au vendredi pour vous accueillir, vous informer et vous conseiller en crédits et placements (réception conseil sur rendez-vous). Autre nouveauté : les mêmes conseillers seront aussi à votre disposition le samedi, sur notre agence de Gex, de 8h.15 à 13h.05, notamment pour les études de financements habitat. La Direction et toute l'équipe de l'agence du Crédit Agricole vous souhaitent une excellent année 2003.

  13. Approche de prise en charge du trouble du spectre de l’autisme

    Science.gov (United States)

    Lee, Patrick F.; Thomas, Roger E.; Lee, Patricia A.

    2015-01-01

    Résumé Objectif Se pencher sur les critères diagnostiques du trouble du spectre de l’autisme (TSA) comme les définit le Manuel diagnostique et statistique des troubles mentaux, cinquième édition (DSM-V), et concevoir une approche de prise en charge du TSA à l’aide du cadre CanMEDS–Médecine familiale (CanMEDS-MF). Sources d’information Le DSM-V, publié par l’American Psychiatric Association en mai 2013, énonce de nouveaux critères diagnostiques du TSA. Le cadre CanMEDS-MF du Collège des médecins de famille du Canada fournit un plan d’orientation pour la prise en charge complexe du TSA. Nous avons utilisé des données recueillies par le Centers for Disease Control and Prevention afin de déterminer la prévalence du TSA, ainsi que la revue systématique et méta-analyse détaillée effectuée par le National Institute for Health and Care Excellence du R.-U. pour ses lignes directrices sur le TSA dans le but d’évaluer les données probantes issues de plus de 100 interventions. Message principal Selon les données du Centers for Disease Control and Prevention, la prévalence du TSA se chiffrait à 1 sur 88 en 2008 aux États-Unis. La classification du TSA dans la quatrième édition du DSM incluait l’autisme, le syndrome d’Asperger, le trouble envahissant du développement et le trouble désintégratif de l’enfance. La dernière révision du DSM-V réunit tous ces troubles sous la mention TSA, avec différents niveaux de sévérité. La prise en charge du TSA est complexe; elle exige les efforts d’une équipe multidisciplinaire ainsi que des soins continus. Les rôles CanMEDS-MF fournissent un cadre de prise en charge. Conclusion Les médecins de famille sont au cœur de l’équipe de soins multidisciplinaire pour le TSA, et le cadre CanMEDS-MF tient lieu de plan détaillé pour guider la prise en charge d’un enfant atteint de TSA et aider la famille de cet enfant.

  14. Nouvelles du Centre Aéré de l’Association du Personnel du CERN

    CERN Multimedia

    Jardin d'enfants

    2015-01-01

    Cet été 2015, durant quatre semaines d’été, le Centre Aéré a accueilli plus de 40 enfants âgés de 4 à 6 ans. Devant le succès rencontré, et à la demande des parents, il a été décidé d’en doubler la capacité maximale. A l'été 2016, du 4 au 29 juillet, la structure pourra accueillir les enfants de 4 ans révolus et de moins de 7 ans (nés après le 31/07/2009 mais avant  01/07/2012). Les inscriptions se feront à la semaine durant le mois d'Avril 2016. Les programmes sont en cours d'élaboration cependant nous pouvons déjà vous communiquer le thème conducteur du centre qui sera : à la découverte d'un continent différent chaque ...

  15. Sylvain Fagot, Le cirque. Entre culture du corps et culture du risque

    OpenAIRE

    Crochet-Giacometti, Nicolas

    2011-01-01

    Cet ouvrage écrit par Sylvain Fagot, chercheur en sociologie associé à l'université du Québec, et auteur d'une thèse soutenue en 2003 intitulée « Ethno-sociologie du cirque. Arts de la piste / Arts du corps / Arts du risque », s'intéresse à un monde peu connu : celui du cirque. L'objectif y est de montrer comment chaque forme du cirque, le cirque dit « classique » et le cirque dit « nouveau », ont des stratégies sociales et économiques différentes mais surtout un rapport au corps et au risque...

  16. Chapitre VI. Prudence du financement

    OpenAIRE

    Jambard, Pierre

    2015-01-01

    L’histoire financière de la société permet de comprendre bien des traits de son histoire. Comme toutes les entreprises du bâtiment et des travaux publics, la Société Auxiliaire s’est trouvée devant la nécessité de disposer d’importants capitaux circulants. Grâce à une gestion financière efficace, elle est, en général, parvenue à dégager de son activité les fonds nécessaires, bien que l’aisance de la trésorerie quotidienne n’ait été acquise qu’avec la reconversion. Les années 1927-1946 sont ce...

  17. DU COTÉ DE CHEZ SOI

    OpenAIRE

    Marc Smeets

    2013-01-01

    Le voyage en Hollande, au XIXe siècle, s'inscrit dans une longue tradition où résonnent les notions de liberté, tolérance et commerce, mais il acquiert aussi une spécificité étant donné l’importance que prend la figure du « chez soi » : les Pays-Bas, terre d'agrément où le voyageur français se sent à l'aise et où il aimerait, si possible, vivre. Proust, de ce point de vue-là, ne fait rien de neuf quand il rêve dans la Recherche d'une « vie domestique » en terre batave. Les Pays-Bas, pour le v...

  18. L’abolition du vieillissement

    Directory of Open Access Journals (Sweden)

    Josef Reindl

    2012-02-01

    Full Text Available I « L’humanité vieillit à un rythme inimaginable. (... »« L’humanité vieillit à un rythme inimaginable. Nous devons résoudre le problème de notre propre vieillissement pour résoudre celui du monde entier. » M. Schirrmacher, l’un des intellectuels médiatiques les plus connus de l’Allemagne, joue comme toujours de façon magistrale la partition de l’effroi. Il ne se contente nullement de s’arranger avec son propre vieillissement, mais il veut sauver le monde à travers « une révolution militante...

  19. Sulphite metabolism; Metabolisme du sulfite

    Energy Technology Data Exchange (ETDEWEB)

    Fromageot, P.; Chapeville, F. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Although the formation of sulphite by micro-organisms was observed as early as 1914 by Neuberg, it was only in 1932 that Nightingale showed it to be present inside cells, in the case of tomato leaf stalks, its formation being due to the reaction: SO{sub 3}H{sup -} + (S{sub 2}O{sub 3}){sub 2}{sup --} {yields} S{sub 2}O{sub 3}{sup --} + O{sub 3}S{sub 2}O{sub 3}{sup --}. The presence of the thiosulphate formed was shown by the high refractive index of its barium salt. Today we have a certain amount of data concerning the formation and use of sulphite in the living cell, even through the knowledge is still incomplete. In this article we will describe and discuss the facts which are known, with particular reference to the oxidation of sulphite. (author) [French] Si la formation de sulfite par des micro-organismes a ete observee des 1914 par Neuberg, sa presence a l'interieur des cellules a ete demontree pour la premiere fois par Nightingale en 1932, dans des tiges et des feuilles de tomates, par la reaction: SO{sub 3}H{sup -} + (S{sub 2}O{sub 3}){sub 2}{sup --} {yields} S{sub 2}O{sub 3}{sup --} + O{sub 3}S{sub 2}O{sub 3}{sup --}. Le thiosulfate forme etait mis en evidence par l'indice de refraction eleve de son sel de baryum. Aujourd'hui on possede un certain nombre de donnees, cependant encore tres incompletes, sur la formation du sulfite et son utilisation par la cellule vivante. Dans cet expose nous decrirons et discuterons quelques-unes de ces acquisitions, tout particulierement celles relatives a l'oxydation du sulfite. (auteur)

  20. Sulphite metabolism; Metabolisme du sulfite

    Energy Technology Data Exchange (ETDEWEB)

    Fromageot, P.; Chapeville, F. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Although the formation of sulphite by micro-organisms was observed as early as 1914 by Neuberg, it was only in 1932 that Nightingale showed it to be present inside cells, in the case of tomato leaf stalks, its formation being due to the reaction: SO{sub 3}H{sup -} + (S{sub 2}O{sub 3}){sub 2}{sup --} {yields} S{sub 2}O{sub 3}{sup --} + O{sub 3}S{sub 2}O{sub 3}{sup --}. The presence of the thiosulphate formed was shown by the high refractive index of its barium salt. Today we have a certain amount of data concerning the formation and use of sulphite in the living cell, even through the knowledge is still incomplete. In this article we will describe and discuss the facts which are known, with particular reference to the oxidation of sulphite. (author) [French] Si la formation de sulfite par des micro-organismes a ete observee des 1914 par Neuberg, sa presence a l'interieur des cellules a ete demontree pour la premiere fois par Nightingale en 1932, dans des tiges et des feuilles de tomates, par la reaction: SO{sub 3}H{sup -} + (S{sub 2}O{sub 3}){sub 2}{sup --} {yields} S{sub 2}O{sub 3}{sup --} + O{sub 3}S{sub 2}O{sub 3}{sup --}. Le thiosulfate forme etait mis en evidence par l'indice de refraction eleve de son sel de baryum. Aujourd'hui on possede un certain nombre de donnees, cependant encore tres incompletes, sur la formation du sulfite et son utilisation par la cellule vivante. Dans cet expose nous decrirons et discuterons quelques-unes de ces acquisitions, tout particulierement celles relatives a l'oxydation du sulfite. (auteur)

  1. Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport; Decret no 2007-1557 du 2 novembre 2007 relatif aux installations nucleaires de base et au controle, en matiere de surete nucleaire, du transport de substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-11-15

    This decree concerns the enforcement of articles 5, 17 and 36 of the law 2006-686 from June 13, 2006, relative to the transparency and safety in the nuclear domain. A consultative commission of basic nuclear facilities is established. The decree presents the general dispositions relative to basic nuclear facilities, the dispositions relative to their creation and operation, to their shutdown and dismantling. It precises the dispositions in the domain of public utility services, administrative procedures and sanctions. It stipulates also the particular dispositions relative to other facilities located in the vicinity of nuclear facilities, relative to the use of pressure systems, and relative to the transport of radioactive materials. (J.S.)

  2. Daphne du Maurier' unustatud jutud / Udo Uibo

    Index Scriptorium Estoniae

    Uibo, Udo, 1956-

    2011-01-01

    Ajalehe "The Independent" teatel kavatseb kirjastus "Virago" maikuus avaldada Daphne Du Maurier lühiproosa kogumiku "Nukk" (The Doll), mille on koostanud tema loomingu suur austaja Ann Willmore ja mis sisaldab 13 unustatud ja seni avaldamata novelli

  3. Flaubert et Du Camp : quelques remarques

    Directory of Open Access Journals (Sweden)

    Michel Brix

    2016-12-01

    Full Text Available Les spécialistes de Flaubert ont fait de nombreux reproches à Maxime Du Camp et ne prêtent plus guère d’attention à ce qu’il a écrit. C’est une situation très regrettable, qui prive les lecteurs d’informations nombreuses, susceptibles d’éclairer les enjeux mais aussi les impasses et les contradictions du projet esthétique de Flaubert. Quelques cas significatifs sont évoqués dans le présent article, qui se penche plus particulièrement sur la ressemblance entre un passage du livre de Du Camp Le Nil (1854 et les lignes de L’Éducation sentimentale (1869 qui rapportent l’“apparition” de Mme Arnoux.

  4. Inauguration du C/R Forum (Belgique

    Directory of Open Access Journals (Sweden)

    2009-04-01

    Full Text Available Le 16 février dernier, la Vlaamse beroepsvereniging Conservatie en Restauratie Forum (C/R Forum a été constituée à l'initiative de 18 personnes du milieu de la conservation/restauration et du secteur de la protection du patrimoine. Etant donné que la conservation et la gestion du patrimoine culturel mobilier et immobilier de même que la formation et la recherche relèvent des communautés et des régions, la nécessité est apparue depuis un certain temps de créer une organisation Flamande au sei...

  5. Daphne du Maurier' unustatud jutud / Udo Uibo

    Index Scriptorium Estoniae

    Uibo, Udo, 1956-

    2011-01-01

    Ajalehe "The Independent" teatel kavatseb kirjastus "Virago" maikuus avaldada Daphne Du Maurier lühiproosa kogumiku "Nukk" (The Doll), mille on koostanud tema loomingu suur austaja Ann Willmore ja mis sisaldab 13 unustatud ja seni avaldamata novelli

  6. DU-127090 Solvay/H Lundbeck.

    Science.gov (United States)

    Wolf, William

    2003-01-01

    DU-127090 is a mixed dopamine antagonist/serotonin agonist in development by Solvay and H Lundbeck as a potential treatment for psychosis and schizophrenia, for which it is in phase II clinical trials. In August 2002, phase II trials were ongoing and Lundbeck expected to commence phase III trials in 2003 and file an NDA after 2004. DU-127090 is also under development for Parkinson's disease, for which it is in phase I clinical trials.

  7. INB 40 OSIRIS and ISIS reactors: complementary safety evaluation in the light of the Fukushima Daiichi nuclear power station accident; INB 40 reacteurs OSIRIS et ISIS evaluation complementaire de la surete au regard de l'accident servenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This report proposes a complementary safety evaluation of the Osiris and Isis reactors (INB 40) in Saclay, one of the French basic nuclear installations (BNI, in French INB) in the light of the Fukushima accident. This evaluation takes the following risks into account: risks of flooding, earthquake, loss of power supply and loss of cooling, in addition to operational management of accident situations. It presents some characteristics of the installation (brief description, buildings, effluents, control-command, radioprotection), identifies the risks of cliff effect and the main structures and equipment, evaluates the seismic risk (installation sizing, installation conformity, margin evaluation), evaluates the flooding risk (installation sizing, installation conformity, margin evaluation), briefly examines other extreme natural phenomena (extreme events, combination of events, earthquake or flooding with a higher level than that for which the installation is designed, measures to prevent a cliff effect). It analyzes the risk of a loss of power supply and of cooling (loss of external and internal electric sources, loss of the ultimate cooling system). It analyzes the management of severe accidents: crisis management organization, training and exercises, available intervention means, robustness of available means, measures for the protection of the confinement integrity after fuel damage. It discusses the conditions of the use of subcontractors

  8. The Jules Horowitz reactor: complementary safety evaluation in the light of the Fukushima 1 nuclear power station accident; Reacteur Jules Horowitz evaluation complementaire de la surete au regard de l'accident servenu a la centrale nucleaire de Fukushima 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This report proposes a complementary safety evaluation of the Jules Horowitz reactor in Cadarache (INB 172), one of the French basic nuclear installations (BNI, in French INB) in the light of the Fukushima accident. This evaluation takes the following risks into account: risks of flooding, earthquake, loss of power supply and loss of cooling, in addition to operational management of accident situations. It presents the main characteristics of the installation, identifies the risks of a cliff effect and the main structures and equipment, evaluates the seismic risk (installation sizing, installation conformity, margin evaluation), evaluates the flooding risk (installation sizing, installation conformity, margin evaluation), briefly examines other extreme natural phenomena (extreme meteorological conditions related to flooding, earthquake or flooding with a higher level than that for which the installation is designed). It analyzes the risk of a loss of power supply and of cooling (loss of external and internal electric sources, loss of the ultimate cooling system). It analyzes the management of severe accidents: crisis management organization, available intervention means, robustness of available means. It discusses the conditions of the use of subcontractors

  9. Safety approach for a facility coupling a nuclear reactor to a chemical plant, generic principles and application to a hydrogen production process; Approche de surete d'une installation associant un reacteur nucleaire a une usine chimique, principes generiques et application a un procede de production d'hydrogene

    Energy Technology Data Exchange (ETDEWEB)

    Bertrand, F.; Barbier, D.; Bassi, A. [CEA Cadarache, Direction de l' Energie Nucleaire, 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Reacteurs

    2006-07-01

    The aim of this paper is to propose an overall safety approach devoted to the coupling on a same site of a nuclear reactor to a plant of hydrogen production. Such facilities depend on their own safety principles and practices and are submitted to their own regulation. Therefore, the approach presented here takes into account the aforementioned constraints and takes into consideration the various risks on the site in the design process of the coupling system. This approach relying on the defence in depth concept declined in five levels led to a generalization of the notion of physical barriers and safety functions applied in the French nuclear safety approach. Three main safety functions can be considered for the whole coupled facility : the control of the nuclear and chemical reactivity, the power extraction and the confinement of hazardous materials. Moreover, according to the concept of defence in depth, different plant conditions (normal, incidents and accidents) have been analyzed for the whole facility. Furthermore, the safety approach proposed for the chemical plant is aimed to select reference scenarios taking into account their probability and their consequences on the basis of the methodology presented in the ARAMIS European project. Finally, the purpose of the safety analysis of the chemical plant is the assessment of adequate safety distances to protect people outside of the site as well as the coupling system and, above everything, the nuclear reactor containment. In other respects, a progressive response aiming to avoid the reactor scram is proposed to manage with incidents. (authors)

  10. SARNET european excellence network on nuclear reactor major accidents. Display and realizations after a year of operating; Sarnet reseau d'excellence europeen sur les accidents graves de reacteur nucleaire. Son deploiement et ses realisations apres une annee de fonctionnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

    The Sarnet (Severe Accident Research NETwork of excellence) is devoted to the research on major accidents of water cooled reactors. The developed knowledge will be integrated in a simulation tool ASTEC co-developed with the IRSN and the GRS. This evaluation report presents the context, the objectives and the program of the Sarnet network. It discusses the network operating and the ASTEC simulation code. Some examples of experimental programs are provided. (A.L.B.)

  11. A numerical study on a lumped-parameter model and a CFD code coupling for the analysis of the loss of coolant accident in a reactor containment; Etude numerique 0D-multiD pour l'analyse de perte de refrigerant dans une enceinte de confinement d'un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Y.J.

    2005-12-15

    In the case of PWR severe accident (Loss of Coolant Accident, LOCA), the inner containment ambient properties such as temperature, pressure and gas species concentrations due to the released steam condensation are the main factors that determine the risk. For this reason, their distributions should be known accurately, but the complexity of the geometry and the computational costs are strong limitations to conduct full three-dimensional numerical simulations. An alternative approach is presented in this thesis, namely, the coupling between a lumped-parameter model and a CFD. The coupling is based on the introduction of a 'heat transfer function' between both models and it is expected that large decreases in the CPU-costs may be achieved. First of all, wall condensation models, such as the Uchida or the Chilton-Colburn models which are implemented in the code CAST3M/TONUS, are investigated. They are examined through steady-state calculations by using the code TONUS-0D, based on lumped parameter models. The temperature and the pressure within the inner containment are compared with those reported in the archival literature. In order to build the 'heat transfer function', natural convection heat transfer is then studied by using the code CAST3M for a partitioned cavity which represents a simplified geometry of the reactor containment. At a first step, two-dimensional natural convection heat transfer without condensation is investigated only. Either the incompressible-Boussinesq fluid flow model or the asymptotic low Mach model are considered for solving the time dependent conservation equations. The SUPG finite element method and the implicit scheme are applied for the numerical discretization. The computed results are qualified by the second-order Richardson extrapolation method which allows obtaining the so-called 'Exact values', i.e. grid size independent values. The computations are also validated through non-partitioned cavity case studies. The discussion is focused on heat transfer characteristics such as the variations of the average Nusselt number (Nu-bar) versus the dimensionless thickness of the partition (0.01 {<=} {gamma} {<=} 0.2) and conductivity ratio of the partition wall to the fluid (1 {<=} {sigma} {<=} 10{sup 5}). Finally, a 'heat transfer function' is suggested based upon the thermal resistance of the partition wall. The validity of the model is assessed thanks to comparisons with 'half-cavity' simulations. (author)

  12. Development of a shell finite element. Application to the thermo-viscoplastic behaviour of a PWR vessel during a severe accident; Developpement d`un element fini coque. Application au comportement thermo-viscoplastique d`une cuve de reacteur nucleaire (REP) en situation d`accident grave

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, V

    1998-10-07

    The aim of this study is to develop a model for the thermo-viscoplastic behaviour of he power water reactor lower head during a severe accident, so as to implement it in codes representing the whole accident progress (scenario codes). So it has to give a precise solution in a short cpu-time. The main loadings are the internal pressure and the strong longitudinal and transverse thermal gradients. To deal with this problem, the idea is to develop a new shell element with variable mechanical parameters with the temperature. This is possible in taking advantage of the properties of the bending center line, called neutral fiber. Besides, this new shell element has the particularity to be able to melt without modifying the initial dimensions of the structure. Then, we have developed a complete program to study the mechanical resistance of the vessel. The visco-plastic behaviour is considered as a loading (so it is placed in the second member of the system to be solved) and represented by a Norton law whose parameters depend on the temperature, the law is integrated explicitly which necessitates the introduction of criteria limiting the time step. The rupture criterion by creep is defined by a damage law whereas the rupture criterion by plasticity is based on the exceeding of the mean limit stress in the thickness. Then the model was validated by comparing the results with those of a Castem 2000 volume mesh (finite element code). Finally the model was coupled with the scenario codes ICARE2 and MAAP4 and tested on two typical severe accidents. The results are very satisfactory both on accuracy and cpu-time execution. (author) 113 refs.

  13. Nuclear data covariances and sensitivity analysis, validation of a methodology based on the perturbation theory; application to an innovative concept: the molten thorium salt fueled reactor; Analyses de sensibilite et d'incertitude de donnees nucleaires. Contribution a la validation d'une methodologie utilisant la theorie des perturbations; application a un concept innovant: reacteur a sels fondus thorium a spectre epithermique

    Energy Technology Data Exchange (ETDEWEB)

    Bidaud, A

    2005-10-15

    Neutron transport simulation of nuclear reactors is based on the knowledge of the neutron-nucleus interaction (cross-sections, fission neutron yields and spectra...) for the dozens of nuclei present in the core over a very large energy range (fractions of eV to several MeV). To obtain the goal of the sustainable development of nuclear power, future reactors must have new and more strict constraints to their design: optimization of ore materials will necessitate breeding (generation of fissile material from fertile material), and waste management will require transmutation. Innovative reactors that could achieve such objectives - generation IV or ADS (accelerator driven system) - are loaded with new fuels (thorium, heavy actinides) and function with neutron spectra for which nuclear data do not benefit from 50 years of industrial experience, and thus present particular challenges. After validation on an experimental reactor using an international benchmark, we take classical reactor physics tools along with available nuclear data uncertainties to calculate the sensitivities and uncertainties of the criticality and temperature coefficient of a thorium molten salt reactor. In addition, a study based on the important reaction rates for the calculation of cycle's equilibrium allows us to estimate the efficiency of different reprocessing strategies and the contribution of these reaction rates on the uncertainty of the breeding and then on the uncertainty of the size of the reprocessing plant. Finally, we use this work to propose an improvement of the high priority experimental request list. (author)

  14. A homogenization method for the modal analysis of a nuclear reactor with internal structures modelling and fluid-structure interaction coupling; Une methode d'homogeneisation pour l'analyse modale d'un reacteur nucleaire avec modelisation des structures internes et de l'interaction fluide / structure

    Energy Technology Data Exchange (ETDEWEB)

    Sigrist, J.F. [DCN Propulsion, Service Technique et Scientifique, 44 - La Montagne (France); Broc, D. [CEA Saclay, Lab. d' Etude Mecanique et Sismique, 91 - Gif-sur-Yvette (France)

    2007-03-15

    A homogenization method is presented and validated in order to perform the dynamic analysis of a nuclear pressure vessel with a 'reduced' numerical model accounting for inertial fluid-structure coupling and describing the geometrical details of the internal structures, periodically embedded within the nuclear reactor. Homogenization techniques have been widely used in nuclear engineering to model confinement effects in reactor cores or tubes bundles. Application of such techniques to reactor internals is investigated in the present paper. The theory bases of the method are first recalled. Adaptation of the homogenization approach to the case of reactor internals is then exposed: it is shown that in such case, confinement effects can be modelled by a suitable modification of classical fluid-structure symmetric formulation. The method is then validated by comparison of 3D and 2D calculations. In the latter, a 'reduced' model with homogenized fluid is used, whereas in the former, a full finite element model of the nuclear pressure vessel with internal structures is elaborated. The homogenization approach is proved to be efficient from the numerical of view point and accurate from the physical point of view. Confinement effects in the industrial case can then be highlighted. (authors)

  15. Measurement of the neutron capture cross section of U{sup 234} in n-TOF at CERN for Generation IV nuclear reactors; Mesure de la section efficace de capture neutronique de l'{sup 234}U a n-TOF au CERN pour les reacteurs nucleaires de generation 4

    Energy Technology Data Exchange (ETDEWEB)

    Dridi, W

    2006-11-15

    Accurate and reliable neutron capture cross sections are needed in many research areas, including stellar nucleosynthesis, advanced nuclear fuel cycles, waste transmutation, and other applied programs. In particular, the accurate knowledge of U{sup 234}(n,{gamma}) reaction cross section is required for the design and realization of nuclear power plants based on the thorium fuel cycle. We have measured the neutron capture cross section of U{sup 234}, with a 4{pi} BaF{sub 2} Total Absorption Calorimeter, at the recently constructed neutron time-of-flight facility n-TOF at CERN in the energy range from 0.03 eV to 1 MeV. Monte-Carlo simulations with GEANT4 and MCNPX of the detector response have been performed. After the background subtraction and correction with dead time and pile-up, the capture yield from 0.03 eV up to 1.5 keV was derived. The analysis of the capture yield in terms of R-matrix resonance parameters is discussed. We have identified 123 resonances and measured the resonance parameters in the energy range from 0.03 eV to 1.5 keV. The mean radiative width <{gamma}{sub {gamma}}> is found to be (38.2 {+-} 1.5) meV and the mean spacing parameter is (11.0 {+-} 0.2) eV, both values agree well with recommended values.

  16. Contribution to multi-agents modeling of the operation of industrial processes: application to the operation of a pressurized water reactor under accidental situation; Contribution a la modelisation multi-agents de la conduite de processus industriels: application a la conduite en situation accidentelle d`un reacteur nucleaire a eau sous pression

    Energy Technology Data Exchange (ETDEWEB)

    Elias, P.

    1996-11-13

    This work is related to the CEA `Escrime` project which concerns the reliability and functioning safety of nuclear reactors, and in particular the operation and supervision of nuclear installations. Its aim is the analysis and the formalizing of PWRs operation in order to define the collaboration and optimum sharing of tasks between human operators and automatized systems for an improved functioning safety. Chapter 1 describes the operation of nuclear reactors and the instrumentation and control activities. It focusses on the weaknesses of actual automatized systems and examines the interest of the multi-agents approach to build an improved automatized system. Chapter 2 presents the actual state of the art about multi-agent systems and about their application to reactor operation. Chapter 3 is devoted to the definition of the conceptual model of automatized systems developed in this work (distribution of operation activities, competition between agents, hierarchy, arbitration). Chapter 4 describes the computer model of the essential operating system elaborated according to the conceptual model defined above. Modeling is performed using Spirit and an application is described in chapter 5. (J.S.). 58 refs.

  17. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 13, 2011, 7:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011 (13 mars 2011 - Point a 7h)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 13, 2011, at 7:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2 and 3 of the Fukushima I site is briefly presented with the progress of the accident management actions. (J.S.)

  18. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011 (15 mars 2011 - point a 22h00 heures)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 10:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  19. La fin du risque zéro : du homegrown jihadism au terrorisme du loup solitaire

    Directory of Open Access Journals (Sweden)

    Rémi Baudouï

    2015-09-01

    Full Text Available Le risque zéro représente un moment historique particulier dans la conceptualisation de la socio-politique du risque. Son application repose au début des années 1980 sur l’hypothèse de la possibilité de progresser dans le domaine de l’anticipation et de la gestion sécuritaire des crises potentielles au point de pouvoir prémunir les populations contre toute forme de menace. Il fut employé dans les domaines de la protection civile et de la sécurité militaire. Comme élément de gouvernance politique, il réfutait l’idée selon laquelle le risque existe en préalable comme catégorie d’acceptabilité collective de la menace.

  20. Aux frontières du politique et du religieux

    Directory of Open Access Journals (Sweden)

    Frédéric Sylvanise

    2006-05-01

    Full Text Available The Autobiography of Miss Jane Pittman met en scène de manière spectaculaire deux figures de leadership noir-américain au XIXe siècle (Ned et au XXe siècle (Jimmy. Ned, fils adoptif de Jane Pittman, se rebaptise Professor Douglass en hommage au leader abolitionniste Frederick Douglass. S’il est fondamentalement laïc (il est instituteur, le texte lui confère néanmoins une dimension religieuse, notamment dans le chapitre intitulé « The Sermon at the River » , qui renvoie à la fois à Moïse (le fleuve et à Jésus (le sermon sur la montagne. Abattu par un tueur à gages, Ned est un martyr dont l’histoire était déjà écrite. Le personnage de Jimmy, attendu par toute une communauté comme le messie (alors que lui aussi est un laïc et un homme qui perd la foi, s’inscrit dans la même histoire. Lettré, éloquent et impliqué dans le mouvement pour les droits civils, il est assassiné comme son prédécesseur. Dans les deux cas, le texte lie donc le politique et le biblique comme s’il ne faisait qu’un : être un leader politique, c’est être un preacher et un messie qui guide le peuple. Il est possible de lire l’évocation de ces deux hommes à la lumière d’une certaine actualité. Ned et Jimmy connaissent en effet un sort proche de celui de Malcolm X et de Martin Luther King, récemment assassinés au moment de l’écriture de The Autobiography of Miss Jane Pittman. C’est l’histoire de la répression du leadership noir, au travers du portrait de deux de ses avatars, qui peut donc se lire en creux ici.

  1. Modeling by artificial neural networks. Application to the management of fuel in a nuclear power plant; Modelisation par reseaux de neurones. Application a la gestion du combustible dans un reacteur

    Energy Technology Data Exchange (ETDEWEB)

    Gaudier, F

    1999-07-01

    The determination of the family of optimum core loading patterns for Pressurized Water Reactors (PWRs) involves the assessment of the core attributes, such as the power peaking factor for thousands of candidate loading patterns. Despite the rapid advances in computer architecture, the direct calculation of these attributes by a neutronic code needs a lot of of time and memory. With the goal of reducing the calculation time and optimizing the loading pattern, we propose in this thesis a method based on ideas of neural and statistical learning to provide a feed forward neural network capable of calculating the power peaking corresponding to an eighth core PWR. We use statistical methods to deduct judicious inputs (reduction of the input space dimension) and neural methods to train the model (learning capabilities). Indeed, on one hand, a principal component analysis allows us to characterize more efficiently the fuel assemblies (neural model inputs) and the other hand, the introduction of the a priori knowledge allows us to reducing the number of freedom parameters in the neural network. The model was built using a multi layered perceptron trained with the standard back propagation algorithm. We introduced our neural network in the automatic optimization code FORMOSA, and on EDF real problems we showed an important saving in time. Finally, we propose an hybrid method which combining the best characteristics of the linear local approximator GPT (Generalized Perturbation Theory) and the artificial neural network. (author)

  2. Pilot-plant scale separation and reuse of TiO{sub 2}- photo-catalyst in degrading reactions; Photo reacteur solaire pilote pour separation et reutilisation du catalyseur TiO{sub 2} utilise pour des reactions de degradation

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez-Ibanez, P.; Blanco, J.; Malato, S. [CIEMAT, Centro de Investigacion Energica Medioambiental y Technologia, Plataforma Solar de Almeria (Spain); Las Nieves, F.J. de [University of Almeria, Dept. of Applied Physics, Almeria (Spain)

    2000-07-01

    TiO{sub 2}-catalyst suspensions work very efficiently in photo-catalysis for waste-water treatment. Nevertheless, once photo-catalysis is complete, separation of the catalyst from solution becomes the main problem. The catalyst has been recovered by introducing accelerated sedimentation of TiO{sub 2} particles. This paper reports on the reuse of two types of TiO{sub 2} catalysts for photo-catalysis of tetra-chloro-ethylene at pilot plant scale (50L). One is the well-known Degussa P25 and the other was obtained from ENEL Labs (Italy). Two procedures for reuse were tested: the reuse of slurry after degradation without separation of the catalyst and reuse of the catalyst after it has settled to the bottom. (authors)

  3. Comparative analysis of operation and safety of subcritical nuclear systems and innovative critical reactors; Analyse comparative du fonctionnement et de la surete de systemes sous-critiques et de reacteurs critiques innovants

    Energy Technology Data Exchange (ETDEWEB)

    Bokov, P.M

    2005-05-01

    The main goal of this thesis work is to investigate the role of core subcriticality for safety enhancement of advanced nuclear systems, in particular, molten salt reactors, devoted to both energy production and waste incineration/transmutation. The inherent safety is considered as ultimate goal of this safety improvement. An attempt to apply a systematic approach for the analysis of the subcriticality contribution to inherent properties of hybrid system was performed. The results of this research prove that in many cases the subcriticality may improve radically the safety characteristics of nuclear reactors, and in some configurations it helps to reach the 'absolute' intrinsic safety. In any case, a proper choice of subcriticality level makes all analyzed transients considerably slower and monotonic. It was shown that the weakest point of the independent-source systems with respect to the intrinsic safety is thermohydraulic unprotected transients, while in the case of the coupled-source systems the excess reactivity/current insertion events remain a matter of concern. To overcome these inherent drawbacks a new principle of realization of a coupled sub-critical system (DENNY concept) is proposed. In addition, the ways to remedy some particular safety-related problems with the help of the core sub-criticality are demonstrated. A preliminary safety analysis of the fast-spectrum molten salt reactor (REBUS concept) is also carried out in this thesis work. Finally, the potential of the alternative (to spallation) neutron sources for application in hybrid systems is examined. (author)

  4. EPR safety. Consideration of the internal and external hazards in the safety studies; Surete du reacteur EPR. Prise en compte des agressions internes et externes dans les etudes de surete EPR

    Energy Technology Data Exchange (ETDEWEB)

    Gueguin, H. [Electricite de France (EDF-DIN), Centre National d' Equipement Nucleaire, Service Controle Commande, 92 - Montrouge (France)

    2008-04-15

    The author presents the main points of the Preliminary Safety Report of EDF on the EPR reactor safety. It concerns the considerations of the internal (fire, flood, explosions, pipes failures) and external (earthquakes, airplane falls, explosions, exceptional natural disasters, extreme meteorological conditions) damages. It presents how the safety report takes into account the aggression. (A.L.B.)

  5. The ASN allows the Tricastin-1 reactor to operate 40 years; L'ASN autorise le reacteur n. 1 de la centrale du Tricastin a fonctionner 40 ans

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2010-11-15

    The ASN (French Authority for Nuclear Safety) has allowed the Tricastin reactor number 1 to operate 10 years more. In July 2009 the ASN agreed to a global 10 year lifetime extension for the fleet of 900 MWe PWR under the condition of a thoroughly overhaul on a case by case basis. Tricastin-1 reactor went through this overhaul. During this inspection a particular attention was drawn on material aging and on the state of the reactor vessel. Supplementary works will have to be made in order to assure an adequate protection of the plant in case of flooding. There are 34 900 MWe PWR that operate in France, they have an average service life of 27-28 years. (A.C.)

  6. Synthesis of the study performed by the IRSN regarding safety options of the ATMEA1 reactor; Synthese de l'examen mene par l'IRSN au sujet des options de surete du reacteur ATMEA1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    The ATMEA1 reactor is a new concept for next generation 1000 MWe pressurized water reactors. This report first recalls the context of the IRSN study of safety options regarding this reactor: a first phase for the examination of these options, and a second phase for the examination of the safety option report and complementary reports on topics identified in phase 1. The main conclusions of phase 1 are recalled, as well as the topics addressed during the several meetings. Then, it lists the significant issues addressed in the different reports associated with these meetings

  7. Towards the prediction of the rupture of a pressurized water reactor vessel in case of accident; Vers la prevision du dechirement d'une cuve de reacteur a eau pressurisee en cas d'accident

    Energy Technology Data Exchange (ETDEWEB)

    Tardif, N.; Coret, M.; Combescure, A. [Lyon Univ., CNRS, INSA-Lyon, LaMCoS UMR5259, 69 (France); Tardif, N.; Nicaise, G. [Institut de Radioprotection et de Surete Nucleaire, DSR/SAGR/BPhAG, 92 - Fontenay-aux-Roses (France)

    2009-07-01

    Through a scale model of a reactor vessel submitted to a thermal and mechanical load during a severe accident, it is possible to follow the initiation and propagation of cracks in real time by tests carried out on laboratory. (O.M.)

  8. Experience feedback examination in PWR type reactors operating for the 1997-1999 period; Examen du retour d'experience en exploitation des reacteurs a eau sous pression pour la periode 1997-1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The present report is relative to the examination that the permanent group has made on the experience feedback in operation for PWR type reactors for the period 1997-1999 that was on eleven themes chosen by the Nuclear Safety and Radiation Protection Authority. It used analysis reports made by I.R.S.N. in support of four meetings of the permanent group devoted to this examination from April 2001 to June 2002. The different themes were operating uncertainties, machining to vibrations, analysis of incidents and gaseous releases, circuits, human factors, behaviour of electric batteries, risk of cold source loss. (N.C.)

  9. Optimization by simulation of the coupling between a sub-critical reactor and its spallation source. Towards a pilot reactor; Optimisation par simulation du couplage entre un reacteur sous-critique et sa source de spallation. Application a un demonstrateur

    Energy Technology Data Exchange (ETDEWEB)

    Kerdraon, D

    2001-10-01

    Accelerator Driven Systems (ADS), based on a proton accelerator and a sub-critical core coupled with a spallation target, offer advantages in order to reduce the nuclear waste radiotoxicity before repository closure. Many studies carried out on the ADS should lead to the definition of an experimental plan which would federate the different works in progress. This thesis deals with the neutronic Monte Carlo simulations with the MCNPX code to optimize such a system in view of a pilot reactor building. First, we have recalled the main neutronic properties of an hybrid reactor. The concept of gas-cooled eXperimental Accelerator Driven System (XADS) chosen for our investigations comes from the preliminary studies done by the Framatome company. In order to transmute minor actinides, we have considered the time evolution of the main fuels which could be reasonably used for the demonstration phases. The neutronic parameters of the reactor, concerning minor actinide transmutation, are reported. Also, we have calculated the characteristic times and the transmutation rates in the case of {sup 99}Tc and {sup 129}I isotopes. We have identified some neutronic differences between an experimental and a power ADS according to the infinite multiplication coefficient, the shape factor and the level of flux to extend the demonstrator concept. We have proposed geometric solutions to keep the radial shape factor of a power ADS acceptable. In the last part, beyond the experimental XADS scope, we have examined the possible transition towards an uranium/thorium cycle based on Molten Salt Reactors using a power ADS in order to generate the required {sup 233}U proportion. (author)

  10. Microstructural characterization and model of hardening for the irradiated austenitic stainless steels of the internals of pressurized water reactors; Caracterisation microstructurale et modelisation du durcissement des aciers austenitiques irradies des structures internes des reacteurs a eau pressurisee

    Energy Technology Data Exchange (ETDEWEB)

    Pokor, C

    2003-07-01

    The core internals of Pressurized Water Reactors (PWR) are composed of SA 304 stainless steel plates and CW 316 stainless steel bolts. These internals undergo a neutron flux at a temperature between 280 deg C and 380 deg C which modifies their mechanical properties. These modifications are due to the changes in the microstructure of these materials under irradiation which depend on flux, dose and irradiation temperature. We have studied, by Transmission Electron Microscopy, the microstructure of stainless steels SA 304, CW 316 and CW 316Ti irradiated in a mixed flux reactor (OSIRIS at 330 deg C between 0,8 dpa et 3,4 dpa) and in a fast breeder reactor at 330 deg C (BOR-60) up to doses of 40 dpa. Moreover, samples have been irradiated at 375 deg C in a fast breeder reactor (EBR-II) up to doses of 10 dpa. The microstructure of the irradiated stainless steels consists in faulted Frank dislocation loops in the [111] planes of austenitic, with a Burgers vector of [111]. It is possible to find some voids in the solution annealed samples irradiated at 375 deg C. The evolution of the dislocations loops and voids has been simulated with a 'cluster dynamic' model. The fit of the model parameters has allowed us to have a quantitative description of our experimental results. This description of the microstructure after irradiation was coupled together with a hardening model by Frank loops that has permitted us to make a quantitative description of the hardening of SA 304, CW 316 and CW 316Ti stainless steels after irradiation at a certain dose, flux and temperature. The irradiation doses studied grow up to 90 dpa, dose of the end of life of PWR internals. (author)

  11. Etude du revenu de l'acier z 10 CDNbV0902 (type 9% Cr, 2% Mo + Nb,V) envisage pour la realisation de certains composants des reacteurs a neutrons rapides

    Science.gov (United States)

    Pelletier, M.; Vilar, R. M.; Cizeron, G.

    1982-02-01

    Après trempe depuis 1100°C, l'acier étudié est formé de ferrite stable à haute température et de martensite. Au cours de revenus anisothermes, la phase martensitique est le siège de la précipitation successive de carbures des types M 3C, M 7C 3 et M 2C, ces deux derniers étant responsables d'un durcissement secondaire significatif. Aux températures plus élevées, ces carbures se dissolvent tandis qu'apparaissent des carbures des types M 23C 6 et M 6C. La phase ferritique initialement sursaturée est, par ailleurs, le siège d'une précipitation de carbures des types M 2C et M 23C 6.

  12. ALIBABA, an assistance system for the detection of confinement leaks in a PWR reactor; ALIBABA, un systeme d`aide a la detection des voies de fuites du confinement sur un reacteur a eau sous pression

    Energy Technology Data Exchange (ETDEWEB)

    Bedier, P.O.; Libmann, M. [CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie

    1995-12-31

    The objective of the Crisis Technical Center (CTC) of the French Institute for Nuclear Protection and Safety (IPSN) is to estimates the consequences of a given nuclear accident on the populations and the environment. ALIBABA is a data processing tool available at the CTC and devoted to the detection of confinement leaks in 900 MWe PWR reactors using the activity values measured by the captors of the installation. The heart of this expert system is a structural and functional representation of the different components directly involved in the leak detection (isolating valves, ventilation systems, electric boards etc..). This tool can manage the availability of each component to make qualitative and quantitative balance-sheets. This paper presents the ALIBABA software, an industrial prototype realized with the SPIRAL knowledge base systems generator at the CEA Reactor Studies and Applied Mathematics Service (SERMA) and commercialized by CRIL-Ingenierie Society. It describes the techniques used for the modeling of PWR systems and for the visualization of the survey. The functionality of the man-machine interface is discussed and the means used for the validation of the software are summarized. (J.S.). 6 refs.

  13. AREVA Technical Days (ATD) session 3: operations of the reactors and services division, technical and economic aspects; AREVA Technical Days (ATD) session 3: les activites du pole reacteurs et services, aspects techniques et economiques

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This third session deals with the reactors technologies basics, the EPR and SWR 1000 issues and outlook, the nuclear systems of the future, the business opportunities and business models. (A.L.B.)

  14. Burnup extension and evolution in the fuel management of EDF's nuclear power plants; Accroissement des taux de combustion et impact des evolutions de gestion sur l'exploitation des reacteurs du parc EDF

    Energy Technology Data Exchange (ETDEWEB)

    Provost, J.L.; Thibault, X. [Electricite de France (EDF/DPN), 93 - Saint-Denis (France); Debes, M. [Electricite de France (EDF/DCN), 92 - Clamart (France); Kaplan, P. [Cogema, 78 - Velizy Villacoublay (France)

    2004-07-01

    Today the use of enhanced nuclear fuels that can sustain higher burnups has allowed a better optimization of the fuel management in nuclear power plants. The optimization for the near future is based on 3 aims: -) a better competitiveness of nuclear energy, longer campaigns mean a higher availability and less refueling so it has a direct impact on costs, -) a better flexibility to meet energy demand: a modulation of cycle lengths by more or less 2 months is possible by introducing or withdrawing 8 assemblies in the refueling load, this modulation will allow an optimization of the scheduling of the refueling shutdowns with respect to the seasonal energy demand peaks, -) a reduced volume of spent fuels (but with a higher level of radioactivity). (A.C.)

  15. Fuel cycle: the transition between the third and the fourth generation of reactors; Cycle du combustible: faire la transition vers les 3eme et 4eme generations de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Many challenges arrive today for the french research and development on the fuel cycle: promote the industrial technologies, improve the world increase of the nuclear and adapt the fuel cycle technologies to the future reactors. In this framework the report presents after a recall on the fuel cycle, the researches on the fuel, the optimization of the recycling, the wastes management, the simulation and Phenix an experimentation tool for the fuel. (A.L.B.)

  16. Original Paper Performances comparées du HDL-cholestérol et du ...

    African Journals Online (AJOL)

    CT/HDL-C) et du HDL-Cholestérol est le meilleur prédicteur du SMet chez les adultes béninois. L'étude de ..... d'hypertension artérielle avaient observé qu'une ... facteurs tels que l'alimentation et l'activité physique sur les lipides sanguins.

  17. Engagez-vous, devenez délégué(e) du personnel du CERN

    CERN Multimedia

    Staff Association

    2017-01-01

    Dans notre ECHO N° 275, nous avons annoncé les élections à venir au Conseil du personnel du CERN. Dans le présent ECHO, nous vous informons du lancement du processus des élections qui débute par le dépôt des candidatures. Tous les titulaires, boursiers et associés, qui sont aussi membres de l’Association du personnel, peuvent s’engager et déposer leur candidature entre le 11 septembre à 08 h 00 et le 13 octobre 2017 à 17 h 00. N’hésitez plus, remplissez le formulaire de candidature, présentez-vous aux élections au Conseil du personnel afin de pouvoir représenter et défendre vos collègues du personnel du CERN. ÊTRE DÉLÉGUÉ(E), C’EST QUOI ? Poser la question à plusieurs d...

  18. Biokinetics and dosimetry of depleted uranium (DU) in rats implanted with DU fragments.

    Energy Technology Data Exchange (ETDEWEB)

    Guilmette, Ray A.; Hahn, Fletcher F.; Durbin, P. W.

    2004-01-01

    A number of U. S. veterans of the Persian Gulf War were wounded with depleted uranium (DU) metal fragments as a result of 'friendly fire' incidents, in which Abrams tanks and Bradley fighting vehicles were struck by DU anti-armor munitions. Some of the crew members who survived were left with multiple small fragments of DU in their muscles and soft tissues. The number, size and location of the fragments made them inoperable in general, and therefore subject to long-term retention. Because there was inadequate data to predict the potential carcinogenicity of DU fragments in soft tissues, Hahn et al. (2003) conducted a lifespan cancer study in rats. As part of that study, a number of rats were maintained to study the biokinetics and dosimetry of DU implanted intramuscularly in male Wistar rats. Typically, four metal fragments, either as cylindrical pellets or square wafers were implanted into the biceps femoris muscles of the rats. Urine samples were collected periodically during their lifespans, and DU was analyzed in kidneys and eviscerated carcass (minus the implant sites) at death. The daily DU urinary excretion rate increased steeply during the first 30 d after implantation peaking at about 90 d at 3-10 x 10{sup -3}%/d. During the first 150 d, the average excretion rate was 2.4 x 10{sup -3}%/d, decreasing thereafter to about 1 x 10{sup -3}%/d. Serial radiographs were made of the wound sites to monitor gross morphologic changes in the DU implant and the surrounding tissue. As early as 1 w after implantation, radiographs showed the presence of surface corrosion and small, dense bodies near the original implant, presumably DU. This corrosion from the surface of the implant continued with time, but did not result in an increasing amount of DU reaching the blood and urine after the first 3 mo. During this 3-mo period, connective tissue capsules formed around the implants, and are hypothesized to have reduced the access of DU to tissue fluids by limiting the

  19. Comportement du carbone aux joints de grains du molybdène

    OpenAIRE

    1994-01-01

    Pas de résumé en anglais; La mise en évidence et l'interprétation du rôle bénéfique du carbone et du rôle néfaste de l'oxygène sur la cohésion intergranulaire du molybdène en l'absence de précipitation visible au MEB constituaient le but de cette étude. Une méthode efficace de purification du molybdène a été mise au point. Les mesures de la concentration intergranulaire de carbone en fonction de la température de carburation et de la teneur volumique ont été effectuées à l'aide d'un spectromè...

  20. DU COTÉ DE CHEZ SOI

    Directory of Open Access Journals (Sweden)

    Marc Smeets

    2013-12-01

    Full Text Available Le voyage en Hollande, au XIXe siècle, s'inscrit dans une longue tradition où résonnent les notions de liberté, tolérance et commerce, mais il acquiert aussi une spécificité étant donné l’importance que prend la figure du « chez soi » : les Pays-Bas, terre d'agrément où le voyageur français se sent à l'aise et où il aimerait, si possible, vivre. Proust, de ce point de vue-là, ne fait rien de neuf quand il rêve dans la Recherche d'une « vie domestique » en terre batave. Les Pays-Bas, pour le voyageur français au XIXe, c'est le home sweet home.

  1. Influence of the flux axial form on the conversion rate and duration of cycle between recharging for ThPu and U{sub nat} fuels in CANDU reactors; Influence de la forme axiale du flux sur le taux de conversion et la duree du cycle entre rechargements pour du combustible ThPu et U{sub nat} dans les reacteurs CANDU

    Energy Technology Data Exchange (ETDEWEB)

    Chambon, Richard [Laboratoire de Physique Subatomique et de Cosmologie, Universite Joseph Fourier / CNRS-IN2P3, 53 Avenue des Martyrs, F-38026 Grenoble (France)

    2007-01-15

    To face the increasing world power demand the world nuclear sector must be continuously updated and developed as well. Thus reactors of new types are introduced and advanced fuel cycles are proposed. The technological and economic feasibility and the transition of the present power park to a renewed park require thorough studies and scenarios, which are highly dependent on the reactor performances. The conversion rate and cycle span between recharging are important parameters in the scenarios studies. In this frame, we have studied the utilisation of thorium in the CANDU type reactors and particularly the influence of axial form of the flux, i.e. of the recharging mode, on the conversion rate and duration of the cycle between recharging. The results show that up to a first approximation the axial form of the flux resulting from the neutron transport calculations for assessing the conversion rate is not necessary to be taken into account. However the time span between recharging differs up to several percents if the axial form of the flux is taken into consideration in transport calculations. Thus if the burnup or the recharging frequency are parameters which influence significantly the deployment scenarios of a nuclear park an approach more refined than a simple transport evolution in a typical cell/assembly is recommended. Finally, the results of this study are not more general than for the assumed conditions but they give a thorough calculation method valid for any recharging/fuel combination in a CANDU type reactor.

  2. Synthesis of the IRSN report on the control-command architecture of the Flamanville 3 EPR reactor and the associated platforms; Synthese du rapport de l'IRSN portant sur l'architecture du controle commande du reacteur EPR de Flamanville 3 et les plateformes associees

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-06-15

    This document briefly reports the IRSN's comments on the robustness of the control-command architecture of the Flamanville 3 EPR (European pressurized reactor), that is of the equipment which, to various extent, contribute to the installation safety. This report identifies the equipment the robustness of which should be improved, outlines the problems created by the complexity of computerized systems. Notably, the authors comment the ability of the off-the-shelf computer platforms acquired by EDF to deal with the nuclear context.

  3. Cirque du Monde as a health intervention

    Science.gov (United States)

    Fournier, Cynthia; Drouin, Mélodie-Anne; Marcoux, Jérémie; Garel, Patricia; Bochud, Emmanuel; Théberge, Julie; Aubertin, Patrice; Favreau, Gil; Fleet, Richard

    2014-01-01

    Abstract Objective To present Cirque du Soleil’s social circus program, Cirque du Monde, to explore its potential as a primary health care tool for family physicians. Data sources A review of the literature in PubMed, the Cochrane Library, PsycINFO, LaPresse, Eureka, Google Scholar, and Érudit using the key words circus, social circus, Cirque du Monde, and Cirque du Soleil; a Montreal-based initiative, Espace Transition, modeled on Cirque du Monde; and personal communication with Cirque du Soleil’s Social Circus Training Advisor. Study selection The first 50 articles or websites identified for each key word in each of the databases were examined on the basis of their titles and abstracts in the case of articles, and on the basis of their titles and page content in the case of websites. Articles and websites that explored an aspect of social circuses or that described an intervention that involved circuses were then retained for analysis. Because all literature on social circuses was searched, no criterion for year of publication was used. Synthesis No articles on the social circus as a health intervention were found. One study on the use of the circus as an intervention in schools was identified. It demonstrated an increase in self-esteem in the children who took part. One study on the use of the circus in a First Nations community was found; it contained nonspecific, qualitative findings. The other articles identified were merely descriptions of social circuses. One website was identified on the use of the social circus to help youth who had been treated in a hospital setting for major psychiatric disorders to re-enter the community. The team in the pediatric psychiatry department at Centre Hospitalier Universitaire Sainte-Justine, the children’s hospital in Montreal, Que, was contacted; they were leading this project, called Espace Transition. The unpublished preliminary findings of its pilot project demonstrate substantial improvements in overall patient

  4. Établissements recevant du public

    CERN Document Server

    2014-01-01

    Synthèse pour les installations électriques, des règles de sécurité contre les risques d’incendie et de panique dans les établissements recevant du public (ERP), selon l’arrêté du 25 juin 1980 modifié. L'ouvrage traite à la fois des dispositions communes aux établissements du 1er groupe (1ère à 4ème catégorie), du 2ème groupe (5ème catégorie) et des règles particulières applicables aux différents types d'établissements (structures d'accueil pour personnes âgées ou handicapées, hôtels, magasins de vente, restaurants et débit de boisson, établissements de soins, administration, châpiteaux, etc...) Sont ainsi notamment traités, dans le cadre des dispositions communes aux établissements du 1er groupe, pour les installations électriques normales : les installations des appareils, tableaux et canalisations, les locaux électriques et installation de machines, l'éclairage normal des locaux accessibles au public, le chauffage et la ventilation, l'installation d'eau chaude sanita...

  5. L’internationalisation du roman arabe

    Directory of Open Access Journals (Sweden)

    Dr Dalia Khraibani

    2016-09-01

    Full Text Available La littérature arabe est presque invisible dans l’espace littéraire mondiale pour des raisons diverses. Pourtant, des écrivains réussissent à s’imposer sur la scène littéraire internationale et leurs œuvres deviennent des chefs d’œuvre de la littérature mondiale. Parmi ces écrivains, nous citons Tayeb Saleh qui connaît un succès international surtout avec la parution de son second roman "Saison de migration vers le Nord". Notre étude vise à montrer comment ce roman par son contenu et sa forme, occupe une place de choix dans la littérature mondiale. En effet, nous allons examiner le contexte historique de l’émergence du roman qui joue un rôle dans sa diffusion au niveau mondial. L’une des clés de réussite du roman est la technique narrative qui retient l’haleine du lecteur dès la première page. De plus, le roman répond à l’horizon d’attente du lectorat occidental en représentant des images particulières de la société arabo-africaine qui correspondent aux stéréotypes et clichés du public occidental vis-à-vis des Arabes.

  6. Influence du pH, d'acides aminés et de diverses substances organiques sur la fongitoxicité du pyriméthanil, du glufosinate, du captafol, du cymoxanil et du fenpiclonil vis-à-vis de certaines souches de Botrytis cinerea

    OpenAIRE

    1994-01-01

    L’effet du pyriméthanil, du fenpiclonil, du captafol, du glufosinate et du cymoxanil sur l’élongation des filaments germinatifs des spores de Botrytis cinerea est étudié dans diverses conditions culturales du champignon. Si le fenpiclonil présente un niveau d’activité stable entre pH 3,6 et 7,3, en revanche les autres pesticides voient leur toxicité chuter dans des milieux acides (ex pyriméthanil) ou neutres à faiblement basiques (ex captafol, cymoxanil, glufosinate). L’adjonction d’extrait d...

  7. De Gainsborough à Turner : l'âge d'or du paysage et du portrait anglais dans les collections du musée du Louvre

    OpenAIRE

    Adrien, Muriel

    2015-01-01

    L’exposition De Gainsborough à Turner : l'âge d'or du paysage et du portrait anglais dans les collections du musée du Louvre co-organisée par le Musée du Louvre, le Musée d’Art et d’Archéologie de Valence et le Musée des Beaux-arts de Quimper présentait une sélection de 35 peintures de la collection du Louvre, complétée par 38 dessins du département des Arts Graphiques. Les commissaires de l'exposition étaient : Guillaume Faroult, conservateur en charge des peintures françaises du 18ème siècl...

  8. Analyse énonciative du point du vue, narration et analyse de discours

    Directory of Open Access Journals (Sweden)

    Alain Rabatel

    2007-01-01

    Full Text Available Cet article montre que l’analyse énonciative du point de vue (PDV, en rupture avec la typologie des focalisations de Genette, peut renouveler partiellement la narratologie, à la condition de substituter à l’approche immanentiste du récit une analyse interactionnelle de la narration. L’article présente d’abord l’approche énonciative du PDV, en appui des théories de Ducrot, et, sur cette base, propose diverses modalités de PDV (représenté, raconté, asserté qui donnent corps au point de vue des personnages ou du narrateur en modifiant sensiblement les analyses de Genette. Dans une deuxième partie, l’article envisage le rôle des PDV dans la narration, notamment dans la réévaluation des dimensions cognitive et pragmatique de la mimésis, puis dans les mécanismes inférentiels-interprétatifs, proches du système de sympathie de Jouve, enfin, dans la revalorisation du rôle du narrateur •puisque ce dernier se construit dans le même temps qu’il construit ses personnages.

  9. Science et technologie du collage

    CERN Document Server

    Cognard, Jacques

    2003-01-01

    L'Homme a su coller avant de savoir écrire et compter. Le collage est en effet l'une des premières techniques d'assemblage d'une structure que l'homme ait utilisée, technique qui n'est devenue science qu'au début du 20e siècle avec la fabrication des premières colles synthétiques. Cette science de l'adhésion a considérablement progressé ces dix dernières années et ce livre présente l'état actuel des connaissances en décrivant les progrès considérables réalisés dans la compréhension des phénomènes fondamentaux qui font qu'un collage tient bien et durablement. Après l'exposé des bases scientifiques nécessaires et des modèles théoriques récents, l'auteur introduit la distinction entre collages faibles et collages forts puis expose les difficultés rencontrées dans les cas pratiques, difficultés souvent dues à la complexité de la chimie des surfaces et des réactions surface-polymère. L'ouvrage se termine par la présentation de quelques applications récentes, en particulier dans...

  10. Les métamorphoses du pouvoir

    OpenAIRE

    Adler, Alfred

    2004-01-01

    On sait que la sorcellerie en Afrique peut s'exercer du faible au fort ou l'inverse. Les situations qui sont ici analysées sont celles où les rois ou les chefs sont expressément désignés comme sorciers, soit qu'ils le deviennent du fait même de leur investiture, soit qu'il leur ait fallu le devenir pour accéder au pouvoir et le conserver face à des rivaux usant des mêmes moyens. Quoi qu'il en soit, un roi-sorcier offre une figure paradoxale du pouvoir, et cela doublement : garant de l'...

  11. Au fond de la logique du lieu.

    Directory of Open Access Journals (Sweden)

    Augustin Berque

    2009-03-01

    Full Text Available L’école de Kyôto ( Kyôto gakuha est cette mouvance philosophique, née dans l’entre-deux-guerres, dont le Nihonshi jiten ( Dictionnaire historique du Japon des éditions Iwanami donne la présentation suivante : 1 École centrée sur la Faculté de philosophie de l’Université de Kyôto dans les années Taishô et Shôwa. Elle débuta autour de Nishida Kitarô et de Tanabe Hajime, mais on la connaît plutôt du fait que peu après le début de la guerre du Pacifique, en 1942, ...

  12. Oncoplastie avec conservation mammaire dans le traitement du cancer du sein: à propos de 16 cas

    OpenAIRE

    2015-01-01

    Le cancer du sein est actuellement le cancer le plus fréquent chez la femme, et pose un véritable problème diagnostique et thérapeutique. Le dépistage des lésions à un stade de plus en plus précoce, a permis une extension des indications du traitement conservateur radiochirurgical, qui était initialement limitées aux tumeurs de moins de 3 cm, unifocales, non inflammatoires. Par ailleurs, l'utilisation de traitements préopératoires permet d’étendre les indications du traitement conservateur à ...

  13. Le Flaubert de Charles Du Bos

    Directory of Open Access Journals (Sweden)

    Jacques Neefs

    2009-01-01

    Full Text Available Charles Du Bos a porté une attention constante à l’œuvre de Flaubert (à l’exclusion de Bouvard et Pécuchet qui semble ne pas exister pour lui, à Madame Bovary et à L’Éducation sentimentale en particulier. La mise en relation de son étude : « Sur le milieu intérieur chez Flaubert », écrite en 1921, avec des textes du Journal de 1923 et de 1937, les rapprochements avec Gogol, Thomas Hardy, Tolstoï, Baudelaire, Henry James qui traversent les écrits de Du Bos, permettent de suivre ce que celui-ci décrit comme « l’expérience spirituelle » d’une matérialité comprise dans la conquête de la triple exigence du Beau, du Vivant et du Vrai. Du Bos décèle la force de l’œuvre de Flaubert dans la « disproportion » du style, et dans la puissance d’absorption qui fait la densité de cette prose, et qui désigne un extraordinaire travail de conversion. L’obscure expérience spirituelle ainsi poursuivie est celle d’un absolu de l’art, expérience paradoxale d’un « mystique qui ne croit à rien » (comme se désignait Flaubert lui-même, que le critique lie à une interrogation sur sa propre conversion.Charles Du Bos devoted an unflagging attention to Flaubert’s work (except for Bouvard et Pécuchet, which, apparently, according to him did not exist, to Madame Bovary and in particular L’Éducation sentimentale. The connection between his essay “Sur le milieu intérieur chez Flaubert”, written in 1921, and extracts from his Journal, from 1923 to 1937, the comparisons with Gogol, Thomas Hardy, Tolstoy, Baudelaire, and Henry James that run through the writings of Du Bos, allow us to follow what he terms “the spiritual experience” of a materiality encompassed in the conquest of the triple demand of the Beautiful, the Living, the Truth. Du Bos detects the power of Flaubert’s work in the “disproportion” of his style, and the power of absorption that forms the density of his prose, showing an

  14. L’ombre du Condor

    Directory of Open Access Journals (Sweden)

    Franck Gaudichaud

    2003-09-01

    Full Text Available Si l’on observe aujourd’hui, avec un regard d’historien, le Cône Sud à la fin des années soixante soixante-dix et que par, la suite, on tourne une page de quelques années, pour fixer la même partie du monde, le constat est sans appel : le sous-continent latino-américain est passé, en général, d’une phase de forte mobilisation et politisation sociale, montée en puissance de partis et organisations révolutionnaires, surgissements de gouvernements populistes de gauche ou progressistes – appelant à une rupture avec l’impérialisme –, à un reflux généralisé du mouvement ouvrier, une ère de violence politique étatisée, la destruction massive de tous les espaces d’expression et de participation démocratiques, l’écrasement physique et idéologique sans relâche des militants et mouvements révolutionnaires, la mise en place de modèles économiques capitalistes dirigistes puis/ou néolibéraux. Que s’est-il passé ? Quel fil conducteur a été rompu et par quels moyens l’Amérique Latine a été conduite à ce reflux des luttes sociales ? Pour répondre à cette question, nous nous contenterons dans cet article de focaliser notre objectif sur un aspect spécifique et essentiel de ce retournement de tendance que vit alors l���Amérique Latine : celui de la mise en place d’un terrorisme d’Etat contre-révolutionnaire transnational, appuyé par l’impérialisme américain, nommé « l’Opération Condor ». Dans cet article, il s’agit de montrer le fonctionnement d’un terrorisme hégémonique dont l’impact sur les sociétés latino-américaines est considérable en termes de destruction du mouvement social, des activités culturelles et de l’ensemble de la vie sociale et politique qui restent marquées, encore aujourd’hui à des degrés divers, par la violence, la peur et l’atomisation structurelle.Si miramos hoy en día, desde una perspectiva histórica, el Cono Sur hacia finales de

  15. Stravinsky : figures clownesques du spectacle dansé

    OpenAIRE

    Frey, Leonard H.

    2013-01-01

    L’origine du mot clown remonte au vieux Scandinave klunni (lourdaud / benêt). Comme nous avons pu en juger au cours de ces rencontres, la sémantique historique du terme a connu de nombreuses variations, a été, au fil du temps, soumise aux fluctuations plus ou moins heureuses imposées par le théâtre. Dans cette étude, je me propose d’étudier l’iconographie de la représentation du clown à travers l’une des variantes du spectacle, la danse, le ballet et les musiques d’Igor Stravinsky. Au cours d...

  16. Une force venant du futur chercherait à saboter l'expérience du LHC...

    CERN Multimedia

    Scappaticci, Bruno

    2009-01-01

    "A quelques jours de la reprise de l'expérience du LHC, on ne parle plus de la menace d'un trou noir, mais deux physicines souteinnent aujourd'hui une tout autres hypothèse: la nature, depuis le futur, va continuer de contrarier les travaux du Cern, afin d'éviter à l'Homme de mettre le doigt là où il ne faut pas..." (1.5 pages)

  17. OGM : vers une définition commune du contenu du problème ?

    Directory of Open Access Journals (Sweden)

    Icart Jean-Claude

    2001-07-01

    Full Text Available Les divergences croissantes depuis des années entre experts, responsables économiques, et acteurs sociaux et « citoyens » au sujet des OGM, ont pu être analysées à juste titre, comme exprimant la difficulté de dégager une « définition commune du contenu du problème »1.

  18. Utilisation du langage signal pour l'etude d'algorithmes de traitement du Signal electrocardiographique

    OpenAIRE

    Médigue, Claire; Clairambault, Jean; Kauffmann, François; Sorine, Michel; Cursi-Dascalova, Lilia

    1992-01-01

    Projet SOSSO; Pour etudier la maturation du Systeme Nerveux Autonome (SNA) chez les nouveaux nes, on analyse la Variabilite du Rythme Cardiaque (VRC), en relation avec d'autres informations biologiques telles que les changements de stades de sommeil. La VRC est calculee par la Transformee de Fourier a Court Terme dans trois bandes de frequence : la haute frequence, refletant le controle para sympathique seul et liee au cycle respiratoire ; les moyenne et basse frequences, refletant a la fois ...

  19. ESTIMATION DU MODELE LINEAIRE GENERALISE ET APPLICATION

    Directory of Open Access Journals (Sweden)

    Malika CHIKHI

    2012-06-01

    Full Text Available Cet article présente  le modèle linéaire généralisé englobant les  techniques de modélisation telles que la régression linéaire, la régression logistique, la régression  log linéaire et la régression  de Poisson . On Commence par la présentation des modèles  des lois exponentielles pour ensuite estimer les paramètres du modèle par la méthode du maximum de vraisemblance. Par la suite on teste les coefficients du modèle pour voir leurs significations et leurs intervalles de confiances, en utilisant le test de Wald qui porte sur la signification  de la vraie valeur du paramètre  basé sur l'estimation de l'échantillon.

  20. Clinical Application of the Du Channel

    Institute of Scientific and Technical Information of China (English)

    刘淑娅; 王世杰

    2003-01-01

    @@ The authors have, in recent years, obtained quite good therapeutic results in their acupuncture treatment of mental diseases, heat syndromes and cerebrovascular diseases through treating mainly the Du Channel with the methods of resuscitating and regulating the mind, and clearing and activating the channels and collaterals. The illustrative cases are reported below.

  1. Annonce du diagnostic et rupture biographique

    African Journals Online (AJOL)

    du cancer en Tunisie , maladie chronique identifiée parmi les plus répandues ... et quelques tentatives de redéploiement des activités des praticiens .... appréhendant ainsi la nature de la souffrance physique mais aussi morale, ces cliniciens.

  2. Prejudice: From Allport to DuBois.

    Science.gov (United States)

    Gaines, Stanley O., Jr.; Reed, Edward S.

    1995-01-01

    Examines the differences between Gordon Allport's and W. E. B. DuBois's theories on the origins of prejudice and the impact of discrimination on the personality and social development of blacks. The article argues that prejudice is a historically developed process, not a universal feature of human psychology. Implications for U.S. race relations…

  3. Le PT à la conquête du pouvoir

    OpenAIRE

    Mendes, Candido

    2014-01-01

    LES PREMIERS PAS DU PT AU POUVOIR La première victoire du PT pour l′accès à un exécutif fut celle de la candidate Maria Luiza, en 1989, dans la capitale du Ceará, Fortaleza. Son arrivée au pouvoir démontra à la fois un certain manque d′expérience personnel ainsi qu′un bégaiement des cadres du parti, trop empreints de la radicalité, de l′utopie de gauche, du culte des « razzias » de pureté politique, du changement complet de tous les acteurs du pouvoir, tant la victoire était marquée par le dé...

  4. The creation of a uranium oxide industry, from the laboratory stage to a pilot plant (1961); Creation d'une industrie de l'oxyde d'uranium du laboratoire a l'usine pilote (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Caillat, R.; Delange, M.; Sauteron, J. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Hauser, R. [Compagnie Industrielle des Combustibles atomiques frittes (France)

    1961-07-01

    The qualities of uranium oxide, in particular its good in-pile characteristics and its resistance to corrosion by the usual heat-exchange fluids, have led to this material being chose at the present time as a nuclear fuel in many power reactors, either planned or under construction. A great effort has been made these last few years in France in studying processes for transforming powdered uranium oxide into a dense material with satisfactory behaviour in a neutron flux. The laboratories at Saclay have studied the physico-chemical features of the phenomena accompanying the calcination of uranium peroxide or ammonium uranate to give uranium trioxide, and the subsequent reduction of the latter to dioxide as well as the sintering of the powders obtained. This work has made it possible on one hand to prepare powder of known specific surface area, and on the other to show the overriding influence of this factor, all other things being equal, on the behaviour of powders during sintering in a hydrogen atmosphere. The work has led to defining two methods for sintering stoichiometric uranium oxide of high density. The technological study of the preparation of the powder and its industrial production are carried out at the plant of Le Bouchet which produces at the moment powders of known characteristics suitable for sintering in hydrogen at 1650 deg. C without prior grinding. The industrial sintering is carried out by the Compagnie industrielle des Combustibles Atomiques Frittes who has set up a pilot plant having a capacity of 25 metric tons/year, for the Commissariat l'Energie Atomique and has been operating this plant since May 1958. This plant is presented by a film entitled 'uranium oxide'. (author) [French] Les qualites de l'oxyde d'uranium, en particulier son bon comportement en pile et sa resistance a la corrosion par les fluides caloporteurs habituels, font choisir aujourd'hui ce materiau comme combustible de nombreux reacteurs de

  5. Sébastien Broca, Utopie du logiciel libre. Du bricolage informatique à la réinvention sociale

    OpenAIRE

    Goëta, Samuel

    2014-01-01

    Traitant des pratiques et des conceptions du logiciel libre mais aussi, plus largement, du mouvement pour l’ouverture des savoirs, Utopie du logiciel libre ambitionne, premièrement, de nourrir une réflexion critique sur l’ethos du libre au sens d’un « ensemble de valeurs qui constituent un cadre pour l’action et s’actualisent dans des pratiques » (p. 24) et, deuxièmement, d’élaborer une sociologie critique du libre. Reprenant la notion d’utopie concrète chez Ernst Bloch (Le principe Espérance...

  6. Néotoponymie contestée à Potchefstroom / Tlokwe (Province du Nord-Ouest, Afrique du Sud

    Directory of Open Access Journals (Sweden)

    Myriam Houssay-Holzschuch

    2010-09-01

    Full Text Available Illustration 1 - Extrait du site de la municipalité de Potchefstroom / TlokweSource : http://www.potch.co.za/newsarchive/streetnames.htmlIllustration 2- Potchefstroom (Afrique du SudAuteur : Béatrice Obry-Guyot, début décembre 2007.Illustration 3 - Extrait du plan Google Map de PotchefstroomSource : Google Map.La question toponymique en Afrique du Sud sur la longue durée porte sur deux thèmes essentiels porteurs de controverses : le plurilinguisme et le marquage symbolique et mémoriel du te...

  7. Esquisse du parlementarisme et du monopartisme en Afrique: le cas du Togo

    Directory of Open Access Journals (Sweden)

    E. A. B. van Rouveroy van Nieuwaal

    1989-01-01

    Full Text Available Witnessed the last hundred years profound political and constitutional changes. In this respect there are many differences between African States depending on which kind of colonial overlord has been the ruling power. The African State was a juridical entity in international law, but was it also, at the time of independence, an empirical entity in national fact?In almost all cases the empirical reality as a functioning government was still primarily the presence of European bureaucrats who has embodied the colonial state. Independence therefore opened a gap between the international legitimacy and the internal marginality of many emergent African State. The gap often presented a real political dilemma to the new African rulers: they usually could retain European officials only by compromising their national independence and could dispense with them only at the risk of undermining governmental performance. After adoption of European constitutional law and with, initially, a high degree of similarity between most constitutions in French-speaking Africa, nowadays these constitutions differ widely, contrary to the Commonwealth Africa that has experienced fewer innovations and constitutional breakdowns.Parliamentary systems of government gave way to One Party Systems, introduced in many cases by the national army, as the best equiped, trained, paid and organised power in the country. This has been the political and constitutional development in Togo as well. Since 1969, it has a One Party System, the Rassemblement du Peuple Togolais, founded by the President of the Togolese Republic, Gen. Gnassingbé Eyadéma. But, as everywhere else, doubts are growing about the effectiveness of the One Party System. Are the Togolese perspectives such that Eyadéma is willing to have an open mind and to be all ears for the critics to his own creation? Another intriguing question is to know in which way the Africantraditional authorities (" chieftancy", as the core

  8. Report by the AERES on the unit: Reactor Study Department (DER) under the supervision of the establishments and bodies: Atomic Energy and Alternative Energies Commission (CEA); Rapport de l'AERES sur l'unite: Departement d'Etudes des Reacteurs (DER) sous tutelle des etablissements et organismes: CEA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-02-15

    This report is a kind of audit report on a research laboratory, the DER (Departement d'Etudes des Reacteurs, Reactor Study Department) whose activity if focused on four main themes: neutron transport simulation in reactor cores, thermal-hydraulic simulation of reactors, design and safety of innovative reactors, nuclear instrumentation for reactors. The authors discuss an assessment of the whole unit activities in terms of strengths and opportunities, aspects to be improved, risks and recommendations, productions and publications, scientific quality, influence and attractiveness (awards, recruitment capacity, capacity to obtain financing and to tender, participation to international programs), strategy and governance, and project. These same aspects are then discussed and commented for each theme

  9. Présentation du volume

    Directory of Open Access Journals (Sweden)

    Ana Zwitter Vitez

    2012-12-01

    Full Text Available Dans de nombreuses disciplines scientifiques, le discours parlé représente depuis quelques décennies un objet de recherche proéminent. Ce fait s’explique probablement par deux caractéristiques principales du discours parlé: la structure complexe de sa matérialité et les fonctions variées de différentes pratiques langagières. C’est pourquoi le présent numéro réunit les articles basés sur les approches actuelles du discours parlé et sur les pratiques langagières spécifiques. Le volume est introduit par deux articles interdisciplinaires: Peter Garrard et Ahmed Samrah présentent le domaine de la pathologie du langage en donnant une revue fouillée sur les approches actuelles de l’analyse linguistique lors de la détection de la maladie d’Alzheimer, tandis que Harry Hollien donne un aperçu structuré sur le domaine de la phonétique judiciaire destiné à dévoiler l’identité des locuteurs et de détecter la déception dans le discours parlé. Les analyses explorant l’acquisition du langage commencent par l’article de Katharina Zipser qui examine la progression de structures grammaticales en les mettant en comparaison avec la compétence des apprenants et continuent par l’étude de Meta Lah proposant une évaluation des documents audiovisuels proposés aux apprenants de langue étrangère. Vesna Požgaj Hadži, Damir Horga et Tatjana Balažic Bulc remettent en question la corrélation entre la compétence linguistique et la fluence linguistique auprès de locuteurs non-maternels et l'analyse de Gemma Santiago Alonso aborde l'acquisition de l'article défini dans le langage enfantin. Les articles suivants se réunissent autour du domaine de l'interprétation: Jana Zidar Forte présente une approche actuelle dans l'entrainement d'interprètes, Lea Burjan analyse les phénomènes issus de la pratique de l'interprétation juridique et Simona  Šumrada traite de la reformulation dans le discours de la traduction et de

  10. L’écologie du coupable.

    Directory of Open Access Journals (Sweden)

    André Ourednik

    2006-04-01

    Full Text Available « Denn dass der Mensch erlöst werde von der Rache  : das ist mir die Brücke zur höchsten Hoffnung und ein Regenbogen nach langen Unwettern. » 1 Nous l’aurions presque oublié, en fouillant parmi les fondations du rapport moral au monde de nos sociétés, nous trouverons encore bien en place deux piliers érigés au cours du processus de la chrétienté : celui de l’ empathie et celui de la culpabilité . Le premier semble offrir le seul appui plausible à notre vivre ...

  11. Les Nymphes dans les rites du mariage

    OpenAIRE

    2013-01-01

    Le champ du mariage (où l’on rencontre à la fois les Nymphes puissances surnaturelles et les numphai humaines) peut se révéler intéressant pour croiser des données littéraires, archéologiques et épigraphiques sur le culte des Nymphes. Lors des préliminaires, ces puissances peuvent être l’objet des protéléia (sacrifices prénuptiaux) ou être associées avec la loutrophorie et le bain prénuptial. Les Nymphes n’interviennent guère pendant la journée de célébration du mariage, sauf dans des textes ...

  12. Sustainable growth, the DuPont way.

    Science.gov (United States)

    Holliday, C

    2001-09-01

    Like many manufacturers, DuPont traditionally has grown by making more and more "stuff." And its business growth has been proportional to the amount of raw materials and energy used--as well as the resulting waste and emissions from operations. Over the years, though, DuPont became aware that cheap supplies of nonrenewable resources wouldn't be endlessly available and that the earth's ecosystems couldn't indefinitely absorb the waste and emissions of production and consumption. Chad Holliday, chairman and CEO of DuPont, believes strongly in the challenge of sustainable growth and makes the business case for it: By using creativity and scientific knowledge effectively, he says, companies can provide strong returns for shareholders and grow their businesses--while also meeting the human needs of societies around the world and reducing the environmental footprint of their operations and products. In fact, a focus on sustainability can help identify new products, markets, partnerships, and intellectual property and lead to substantial business growth. Holliday describes how DuPont developed a three-pronged strategy to translate the concept of sustainability into nuts-and-bolts business practices. Focusing on integrated science, knowledge intensity, and productivity improvement, the strategy was accompanied by a new way to measure progress quantitatively. Sustainable growth should be viewed not as a program for stepped-up environmental performance but as a comprehensive way of doing business, one that delivers tremendous economic value and opens up new opportunities. Ultimately, companies will find that they can generate substantial business value through sustainability while both enhancing the quality of life around the world and protecting the environment.

  13. Pourfour Du Petit syndrome after interscalene block

    Directory of Open Access Journals (Sweden)

    Mysore Chandramouli Basappji Santhosh

    2013-01-01

    Full Text Available Interscalene block is commonly associated with reversible ipsilateral phrenic nerve block, recurrent laryngeal nerve block, and cervical sympathetic plexus block, presenting as Horner′s syndrome. We report a very rare Pourfour Du Petit syndrome which has a clinical presentation opposite to that of Horner′s syndrome in a 24-year-old male who was given interscalene block for open reduction and internal fixation of fracture upper third shaft of left humerus.

  14. Sådan forebygger du faldulykker

    DEFF Research Database (Denmark)

    Evron, Lotte

    2015-01-01

    Bidrag til serien 'Eksperten skriver'. Her gennemgås en kort vejledning til, hvordan man arbejder systematisk med faldforebyggelse. Ved at arbejde systematisk med dine hverdagsobservationer kan du få øje på og reagere på ændringer hos svækkede ældre borgere og på den måde forebygge faldet, før de...

  15. Technostress et autres revers du travail nomade

    NARCIS (Netherlands)

    Popma, J.

    2013-01-01

    L'Internet et l'utilisation des ordinateurs portables, des téléphones mobiles et des tablettes ont accru l'importance du « travail nomade». Ce type de travail, sans contrainte de lieu ni de temps, peut entraîner, d’après ce working paper, une plus grande autonomie et une plus grande flexibilité pour

  16. Pourfour Du Petit syndrome after interscalene block.

    Science.gov (United States)

    Santhosh, Mysore Chandramouli Basappji; Pai, Rohini B; Rao, Raghavendra P

    2013-04-01

    Interscalene block is commonly associated with reversible ipsilateral phrenic nerve block, recurrent laryngeal nerve block, and cervical sympathetic plexus block, presenting as Horner's syndrome. We report a very rare Pourfour Du Petit syndrome which has a clinical presentation opposite to that of Horner's syndrome in a 24-year-old male who was given interscalene block for open reduction and internal fixation of fracture upper third shaft of left humerus.

  17. Autour du paradigme d’écotourisme

    Directory of Open Access Journals (Sweden)

    Anne-Laure Transler

    2008-02-01

    Full Text Available L’écotourisme ouvre un cadre conceptuel original qui permet d’envisager des démarches renouvelées de développement à partir des revenus issus de consommations touristiques mieux réfléchies et organisées, susceptibles de soutenir des initiatives de développement local s’inscrivant dans un projet global de développement durable. Variante douce du tourisme, loin du tourisme de masse, le champ de l’écotourisme s’étend aux confins du tourisme de nature, du tourisme culturel et des pratiques scientifiques et sportives de plein air. Une définition de l’écotourisme peut être proposée à partir des six points suivants : 1/ nature et culture, 2/ le bien-être des sociétés hôtes, 3/ des touristes responsables, 4/ la participation des sociétés hôtes, 5/ la durabilité, 6/ l’art de la rencontre.Ecotourism provides an original conceptual framework that enables approaches to development that are better able to provide a more equitable distribution of income, as well as better organized and thought through initiatives which are more likely to promote a holistic sustainable local development. With somewhat less negative impact than normal tourism, considerably less that mass tourism, ecotourism can encompass nature tourism, cultural tourism, scientific exploration, and even outdoor sports... A definition of ecotourism should take into account the following six points: 1/ nature and culture, 2/ the welfare of the host community, tourists acting responsibly, 3/ participation by the local community, 5 / sustainability , 6/ promotion of cultural exchanges

  18. Pertinence du dépistage du cancer du col de l'utérus au sein d'un établissement de santé

    OpenAIRE

    Chignier, Pauline

    2014-01-01

    Le dépistage du cancer du col de l'utérus est un enjeu de Santé Publique. Le plan cancer 2014-2019 souligne l'importance de réduire les inégalités face au dépistage et de couvrir 80% de la population cible. L'objectif principal de l'étude était d'évaluer la conformité des pratiques cliniques des professionnels de santé aux recommandations de la HAS. L'objectif secondaire était d'évaluer la qualité du dépistage du cancer du col selon le type de suivi : gynécologique versus obstétrical. Il s'ag...

  19. Enfants du soleil histoire de nos origines

    CERN Document Server

    Brahic, André

    1999-01-01

    D'où venons-nous ? Comment le Soleil et la Terre sont-ils apparus ? Nous avons enfin atteint le moment où la science peut apporter des réponses de plus en plus précises, de plus en plus étonnantes. La Nature a décidément plus d'imagination que les hommes ! Depuis l'exploration spatiale, nous en avons plus appris sur notre système solaire et son origine en une génération qu'en quarante siècles. Là où l'on attendait l'uniformité, on a trouvé la plus grande diversité. André Brahic, qui a découvert les anneaux de Neptune, nous présente les multiples facettes du système solaire et nous raconte quatre milliards et demi d'années de son histoire. Les planètes sont les soeurs du Soleil. Nous sommes les enfants du temps et des étoiles. Sommes-nous seuls dans l'Univers ? Les astronomes commencent à apercevoir d'autres planètes autour de quelques soleils proches, Ils espèrent bientôt trouver d'autres Terres...

  20. Tribunal administratif de l'Organisation internationale du Travail (TAOIT)

    CERN Document Server

    International Labour Organization. Geneva

    Le Tribunal administratif de l'Organisation internationale du Travail connaît des requêtes formées par les fonctionnaires ou les anciens fonctionnaires du Bureau international du Travail et des quelque trente organisations qui ont reconnu sa compétence. The ILO Administrative Tribunal (ILOAT) hears complaints from serving and former officials of the International Labour Office or one of the thirty-odd intergovernmental organizations that recognise its jurisdiction.

  1. Rapport d'Activite du Service Medical - 2001/2002

    CERN Document Server

    Fassnacht, V

    2003-01-01

    Le rapport annuel de l’année 2002 fait état de l’activité du service médical et de ses conclusions en matière de santé au travail ou de conditions de travail pour les membres du personnel du CERN, c’est à dire!: les titulaires, boursiers, étudiants, utilisateurs, attachés, etc…

  2. Quelques observations sur les Bryopsis du Golfe de Naples

    NARCIS (Netherlands)

    Koster, Joséphine Th.

    1941-01-01

    Evidemment la flore algologique du Golfe de Naples a été étudiée, d’assez près, tant du point de vue floristique que du point de vue écologique. Surtout FALKENBERG (1879), BERTHOLD (1882) et FUNK (1927) se sont occupés des investigations de cette nature. Il reste cependant un certain nombre de genre

  3. Le corps du saint dans l'hagiographie du Maghreb médiéval

    Directory of Open Access Journals (Sweden)

    Nelly Amri

    2006-11-01

    Full Text Available Ce travail tente de réfléchir sur la place accordée par l’hagiographie du Maghreb médiéval au corps dans l'expérience de sainteté et dans le processus de “sanctification” d’un homme ou d’une femme, ainsi que dans la reconnaissance ou la “consécration” de cette sainteté. Il vise à repérer les infléchissements perceptibles dans les critères de sainteté et la valeur accordée par l'hagiographie à telle ou telle voie de sanctification. Il se propose également d’examiner la représentation par les contemporains du corps du saint vivant et les bénéfices qu’ils en attendent.

  4. Christophe Brissonneau, Olivier Aubel, Fabien Ohl, L'épreuve du dopage. Sociologie du cyclisme professionnel

    OpenAIRE

    Martinache, Igor

    2011-01-01

    L'épreuve du dopage se lit comme un roman policier. A la manière d'une intrigue, la trame du livre invite à chaque fin de page à tourner la suivante pour découvrir si le cycliste va basculer dans la pratique du dopage. De fait, il ne bascule jamais. Et c'est bien là l'intérêt de l'ouvrage qui, à l'encontre de la plupart des discours sur le sujet, montre que le dopage est une pratique processuelle qui rend rigoureusement impossible toute distinction binaire entre deux états : dopé ou non. Une ...

  5. ETUDE DU COMPORTEMENT MECANIQUE DU BETON CELLULAIRE AUTOCLAVE PRODUIT EN ALGERIE

    OpenAIRE

    R BELOUETTAR; Klepaczko, J.R.; Abadlia, M.T.

    2002-01-01

    Ce travail présente une étude expérimentale du comportement mécanique du béton cellulaire autoclavé. L’étude est portée essentiellement sur une série d’essais mécaniques en compression quasistatique à différentes vitesses de déformation variables entre 10-4 s-1 et 10 s-1 et à deux états différents (état sec et état saturé d’eau). En général, l’augmentation de la vitesse de déformation donne une augmentation de la contrainte critique du béton cellulaire autoclavé. Le béton cellulaire autoclavé...

  6. Consequences economiques du transfert de marché de cotation : cas du NYSE-Euronext Paris

    OpenAIRE

    Cisse, A.K

    2010-01-01

    Cahier de recherche n° 2010-06 E2; Cette étude empirique a pour objet d'analyser les effets d'un changement de marché de cotation sur la rentabilité, la liquidité et le risque systématique. Elle porte sur des sociétés qui ont transféré le marché de cotation de leurs titres d'un compartiment non (ou peu) réglementé à un compartiment plus réglementé du marché français (Euronext Paris) entre 1995 et 2007. Globalement, les résultats montrent une réaction positive du marché à l'annonce du transfer...

  7. PENERAPAN ANALISIS DU PONT PADA INDUSTRI PROPERTY DAN REAL ESTATE

    National Research Council Canada - National Science Library

    Novita Ratna Satiti

    2016-01-01

    Penelitian ini bertujuan untuk mengetahui bagaimana analisis Du Pont System menilai kinerja keuangan industry property dan real estate, apakah analisis tersebut dapat mengetahui perusahaan mana yang...

  8. La diffusion du football de haut niveau en France

    Directory of Open Access Journals (Sweden)

    Loïc RAVENEL

    1996-06-01

    Full Text Available La pratique du football de haut niveau s'est diffusée sur le territoire français selon deux modèles complémentaires: une diffusion hiérarchique privilégiant les plus grandes villes du pays; une diffusion de proximité soucieuse d'imitation et indispensable à la création des compétitions. Les dirigeants du football ont valorisé le processus par l'intégration de nouvelles aires géographiques, évitant ainsi la saturation du système.

  9. Construire les défis du génie civil du LHC

    CERN Document Server

    CERN. Geneva

    2007-01-01

    Dans les années 80, le CERN a vécu la formidable aventure de la construction du tunnel de 27 kilomètres de circonférence. Ces dernières années, les équipes du génie civil se sont lancées dans l’excavation d’immenses cavernes souterraines et de kilomètres de galeries pour le LHC. Ces travaux ont exigé de véritables prouesses techniques.

  10. Influence du traitement thermique sur l'usinabilite du laiton monophase

    Science.gov (United States)

    Cholley, Airy

    La connaissance des proprietes et du comportement d'un materiau en usinage est primordiale pour optimiser son utilisation et obtenir une usinabilite maximale. Dans ce but, l'etude de la modification de la ductilite par traitement thermiques sur plusieurs criteres d'usinabilite tels que les efforts de coupe, la rugosite, les bavures et la formation du copeau a ete menee sur le laiton monophase. A cette fin, l'influence du traitement thermique sur la microstructure du laiton a d'abord ete etudiee. La taille des grains et la durete ont permis de determiner les proprietes mecaniques des etats metallurgiques. Des essais de percage ont ensuite ete effectues sur les etats metallurgiques H01 (99HV), OS100 (88HV) et OS250 (47HV) pour regarder l'influence du traitement thermique sur l'usinabilite. Cette etude experimentale a permis de comprendre l'influence du taux de laminage et de la temperature de recuit sur les proprietes mecaniques. Les essais d'usinabilite ont ensuite permis de prouver que les efforts de coupe sont dependants des conditions de coupe mais pas de la ductilite dans les etats metallurgiques testes. La taille des bavures augmente avec la ductilite et la vitesse de coupe, et diminue avec l'avance. La rugosite de la surface des trous apres l'usinage a egalement ete etudiee. Il a aussi ete prouve par une etude sur les copeaux que la temperature croit avec la vitesse de coupe. L'analyse de la segmentation des copeaux n'a en revanche pas permis de trouver une correlation significative avec les traitements thermiques testes. Enfin, le revetement de l'outil a montre une grande importance sur l'usinabilite du materiau. Il a ete conclu que l'usinabilite du laiton C26000 (CuZn30) est meilleure lorsqu'on travaille dans un etat metallurgique dur. Ces conclusions sont valables pour le laiton monophase etudie, il serait interessant d'examiner aussi le cas des laitons biphases.

  11. Optimisation du renforcement parasismique du viaduc de Caronte par une analyse dynamique temporelle

    OpenAIRE

    VIVIER, Aurélie; Charles, Pascal; DAVI, Denis

    2013-01-01

    Cet article présente un exemple d'application de l'analyse temporelle dynamique à un cas concret : l'optimisation du renforcement parasismique du viaduc de Caronte. Le diagnostic a permis de converger vers une solution de renforcement avec amortisseurs. Cette étude a été l'occasion de mettre en oeuvre des méthodes d'analyse temporelle, seules rigoureusement compatibles avec l'emploi d'amortisseurs et la complexité de l'ouvrage. Des outils de prédimensionnement des caractéristiques des disposi...

  12. Analyse du développement du tourisme pour tous dans le Val d’Anniviers

    OpenAIRE

    Rossier, Sandrine; Margot-Cattin, Pierre

    2015-01-01

    Cette étude vise à offrir une image actuelle du développement du tourisme pour tous dans le Val d’Anniviers. Cette activité touristique permet aux destinations de proposer leur offre à un public très large. S’adressant tout d’abord à une clientèle en situation de handicap, le tourisme pour tous peut également bénéficier à toute personne ayant des besoins particuliers en termes d’accessibilité. Son implantation dans une région touristique exige de franchir un certain nombre de barrières. Quell...

  13. Synthesis of the IRSN report of general directions to be retained for an evolution of the referential of investigation of core cooling after leakage on the primary circuit of a pressurized water reactor; Synthese du rapport de l'IRSN sur les orientations a retenir en vue d'une evolution du referentiel d'etude du refroidissement du coeur suite a une fuite sur le circuit primaire d'un reacteur a eau sous pression

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-05-15

    This document from the French Nuclear Safety and Radioprotection Institute (IRSN) describes the accident of loss of primary coolant in a pressurized water reactor, and its consequences with two possible damage modes (ductile and brittle). It describes the present requirement referential associated to this accident, and justifies the need to make this referential evolve. It discusses the main directions and topics to be examined again: scenarios, requirements and criteria, physical phenomena to be taken into account. For each of them, it comments the options proposed by EDF and gives the IRSN opinion on these options

  14. Speech by Prime Minister Francois Fillon. Visit of the Jules Horowitz experimental reactor works on the Commissariat a l'Energie et aux Energies Alternatives site. Cadarache, May 3, 2010; Discours du Premier ministre Francois FILLON Cadarache, lundi 3 mai 2010. Visite du chantier du Reacteur experimental Jules Horowitz sur le site du Commissariat a l'Energie Atomique et aux Energies Alternatives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    In this speech, the French Prime Minister evokes the present context, the importance of strategic technologies, and the challenge of investing in these technologies within a context of reduction of public expenses. He comments the decision of his government to finance research and education activities in different domains, and more specifically in the energy sector with this fourth generation Jules Horowitz experimental reactor. He recalls that the nuclear sector has always been very important to the eyes of the successive French governments, and outlines how this reactor will contribute to reactor operational optimization, lifetime extension and safety, nuclear fuel development, etc.

  15. Automatisation partielle du traitement de la littérature grise dans le service d'information scientifique du CERN

    CERN Document Server

    Deroche, C

    1998-01-01

    L'automatisation partielle du traitement de la litterature grise est un projet ineluctable dans un service d'information scientifique aussi important que celui du CERN. Ce rapport presente l'automatis ation du rapport annuel par la detection et l'importation automatique d'informations de publication pour les articles ecrits par les physiciens travaillant au CERN et par d'autres utilisant les outils du CERN. La recherche de ces articles est effectuee dans la base de donnees scientifiques INSPEC.

  16. Analyse quantitative du réseau hydrographique du bassin versant du Slănic (Roumanie

    Directory of Open Access Journals (Sweden)

    Florina Grecu

    2007-12-01

    Full Text Available L'étude porte sur le bassin versant du Slănic, un affluent du Buzău. Ce bassin de taille relativement réduite (433 km2 est situé dans la région des Carpates et des Subcarpates de la Courbure, région très active sur le plan sismique. Du point de vue lithologique, le bassin du Slănic correspond à des flyschs paléogènes et à des molasses mio-pliocènes. Ces roches peu résistantes ont facilité une forte érosion du relief. Actuellement, les précipitations présentent souvent une forte intensité, et elles se produisent fréquemment après des périodes de sécheresse. Elles sont ainsi très agressives et déclenchent une érosion intense. L'analyse de quelques paramètres morphométriques [grand nombre de segments de cours d'eau d'ordres 1 (5230 et 2 (944 ; densité élevée des segments par rapport à la superficie du bassin (environ 15 segments / km2 ; longueur moyenne réduite des segments d'ordre 1 (260 m par rapport à ceux d'ordre 2 (530 m] s'accorde avec des temps de concentration des eaux courts et une forte énergie des écoulements. La vitesse de réaction aux précipitations des segments d'ordres inférieurs est en outre favorisée par la répartition spatiale des pluies et par les conditions lithologiques.The study is focused on the Slănic basin which has a small size (433 km2. The hydrographical basin of Slănic, situated in the Carpathian and Subcarpathian Curvature, a very active from neotectonical viewpoint area, is a part of the Buzău basin. From a petrographic point of view, the Slănic hydrographic basin belongs to the paleogen flysch deposits (within the Carpathian sector and to the mio-pliocen molasse (within the Subcarpathian area latter formed by predominantely friable rocks which have encouraged deep fragmentation of the relief. Actual rainfalls are often very intensive, and they frequently occur after dry seasons. The analysis of morphometric parameters shows many elementary segments of first

  17. Nuclear energy; Le nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This digest document was written by members of the union of associations of ex-members and retired people of the Areva group (UARGA). It gives a comprehensive overview of the nuclear industry world, starting from radioactivity and its applications, and going on with the fuel cycle (front-end, back-end, fuel reprocessing, transports), the nuclear reactors (PWR, BWR, Candu, HTR, generation 4 systems), the effluents from nuclear facilities, the nuclear wastes (processing, disposal), and the management and safety of nuclear activities. (J.S.)

  18. Nuclear wastes; Dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Here is made a general survey of the situation relative to radioactive wastes. The different kinds of radioactive wastes and the different way to store them are detailed. A comparative evaluation of the situation in France and in the world is made. The case of transport of radioactive wastes is tackled. (N.C.)

  19. Progrès de la connaissance du Congo, du Rwanda et du Burundi de 1993 à 2008

    Directory of Open Access Journals (Sweden)

    Henri Nicolaï

    2013-03-01

    Full Text Available Cette chronique, la vingt et unième d’une série qui a commencé avec l’année 1949, couvre la période 1993-2008 et a pour objectif de faire le point sur les progrès réalisés sur la connaissance du Congo (République démocratique du Congo, du Rwanda et du Burundi, dans le domaine de la géographie mais aussi dans les domaines des sciences naturelles et des sciences humaines qui peuvent fournir des données utiles ou indispensables aux géographes. Chaque référence bibliographique, livre ou article, est accompagnée d’un bref commentaire qui en retient les éléments principaux et surtout les faits ou les idées qui intéressent particulièrement les géographes. L’article comporte onze chapitres dont les plus importants concernent le milieu naturel, la géographie de la santé, la démographie, l’histoire (y compris l’histoire récente, la vie sociale et économique des campagnes traditionnelles et modernes, le secteur informel, les aspects de la vie urbaine. Les événements dramatiques qui se sont produits dans ces territoires africains au cours des quinze dernières années ont rendu la recherche sur le terrain particulièrement difficile tant pour les chercheurs nationaux que pour les chercheurs étrangers, ce qui se traduit notamment par une part de plus en plus importante des recherches menées en milieu urbain.This paper, the 21st issue of an edition of books and paper reviews on the knowledge of three countries of former Belgian Africa (DR Congo, Rwanda, and Burundi, covers the period 1993-2008. A short text for each reference points out the facts or ideas that are useful for geographers. The paper is composed of eleven sections. The most important are coping with the natural environment, health geography, population geography, history (including recent events, social and economic life in traditional and modern rural areas, informal economy, and urban geography. During the last sixteen years, conditions for field

  20. Évaluation de l'effet du stress hydrique et du porte- greffe sur la ...

    African Journals Online (AJOL)

    SARAH

    30 nov. 2013 ... orchards are often in water shortage situations in the most of the ..... significative de la hauteur finale et du diamètre au point ..... quantifying resistance to drought, salt and freezing, abiotic stresses that affect plant water status.

  1. Perception locale de l'évolution du milieu à Oula au Nord du Burkina ...

    African Journals Online (AJOL)

    Laboratoire Dynamiques des Espaces et Sociétés (LDES)/Université Ouaga I ... variabilités climatiques ainsi que la perception des impacts sur la production agricole. ... The purpose of this study in the Northern Region of Burkina Faso is to ... (2008), l'impact du changement climatique ... Partant de la position géographique.

  2. LE MARCHE MONDIAL DU VIN ET LES NOUVELLES ORIENTATIONS DU MARKETING

    Directory of Open Access Journals (Sweden)

    Epuran Gheorghe

    2008-05-01

    Full Text Available Le marché mondial du vin est caractérisé par un développement sans précédent en ce qui concerne la production, mais aussi l’aire géographique qu’il comprend. La surproduction qui a tendance ŕ dégénérer en une crise est due premičrement ŕ l’apparition de nouveaux acteurs sur ce marché, c’est-ŕ-dire les pays du nouveau monde du vin: les Etats-Unis, le Chili, l’Afrique de Sud, l’Australie. Dans ce contexte, les grands producteurs traditionnels de l’Europe sont soumis ŕ une forte pression concurrentielle aussi bien sur leurs marchés qu’ŕ l’extérieur. Męme si en matičre d’image et de notoriété les vins de ces pays sont restés encore trčs connus, les pays du nouveau monde des vins ont réussi, par un marketing «ŕ l’américain», ŕ pénétrer en force sur plusieurs marchés, inclusivement sur les pays qui étaient pas traditionnellement consommateurs de vins (la Russie, la Chine, etc..

  3. Un Genevois coopte a la tete du Front islamique du salut

    CERN Document Server

    Merckling, N

    2002-01-01

    "Le Front islamique du salut (FIS), a nomme a la tete de ce parti fondamentaliste un resident genevois, Mourad Dhani, chois parmi trois candidats. Ce physicien algerien est arrive a Geneve il y a 14 ans pour travailler au CERN (1 page).

  4. La reconstruction du sourcil par greffon composite du cuir chevelu: une astuce pour faciliter la technique

    Science.gov (United States)

    El Omari, Mounia; El Mazouz, Samir; Gharib, Noureddine; EL Abbassi, Abdallah

    2015-01-01

    Les sourcils jouent un rôle important dans l’équilibre esthétique du visage. Leur reconstruction ou ophriopoïése, après séquelle de brûlure fait partie intégrante du programme de réhabilitation de la face brûlée. Plusieurs techniques ont été décrites. Nous insistons ici sur l'intérêt d'une technique simple, à la portée de tous les chirurgiens, et dont la méthode et les résultats peuvent être améliorés par un dessin bien planifié des zones donneuse et receveuse: la greffe composite prélevée au niveau du cuir chevelu dessinée à l'aide d'un calque du sourcil controlatéral. PMID:26401195

  5. ETUDE DU COMPORTEMENT MECANIQUE DU BETON CELLULAIRE AUTOCLAVE PRODUIT EN ALGERIE

    Directory of Open Access Journals (Sweden)

    R BELOUETTAR

    2002-12-01

    Full Text Available Ce travail présente une étude expérimentale du comportement mécanique du béton cellulaire autoclavé. L’étude est portée essentiellement sur une série d’essais mécaniques en compression quasistatique à différentes vitesses de déformation variables entre 10-4 s-1 et 10 s-1 et à deux états différents (état sec et état saturé d’eau. En général, l’augmentation de la vitesse de déformation donne une augmentation de la contrainte critique du béton cellulaire autoclavé. Le béton cellulaire autoclavé présente une sensibilité à la vitesse de déformation positive. La valeur du module d’élasticité est proche de la valeur standard (1.5 GPa pour un béton cellulaire autoclavé de masse volumique égale à 500-550 kg/m3.

  6. La préparation et le passage du recensement du Soudan 2008

    Directory of Open Access Journals (Sweden)

    Eric Denis

    2008-06-01

    Full Text Available Les opérations de comptage du 5e recensement de la population du Soudan viennent de s'achever. Elles se devaient d'aller à la rencontre des quelques 38 millions d'habitants du plus étendu des pays d'Afrique avec un questionnaire unique. Elles étaient conduites par deux institutions statistiques, l'une au Nord et l'autre au Sud. Le principe du recensement  a été scellé dans les accords de paix qui ont mis fin à la guerre civile entre le Sud et le Nord Soudan en 2005. Les résultats sont extrêmement attendus puisqu'ils doivent servir de base pour déterminer le partage des revenus pétroliers, préparer les élections législatives de 2009 et le référendum d'auto-détermination du Sud en 2011. Autant d'enjeux, les multiples conflits identitaires et pour l'accès, le contrôle et la redistribution des ressources à toutes les échelles et sur toutes les marges du Soudan font du recensement un catalyseur et finalement un révélateur des limites tragiques de la gouvernance ethnocratique.The Fith population census enumeration operations have just been achieved. They have to meet the 38 millions inhabitants of the largest countries of Africa with a unique questionnaire shared by two statistical institutions, one in the North and a second for the South. The census is a milestone of the peace agreement of 2005 that put an end to the civil war between the Nord and the South. The census results are extremely waited as they will determine the petrol dividend sharing, the parlement election of 2009 and the independence referendum of 2011. So much stakes, identity and ressources access, control and redistribution conflicts at all scales and in every sudanese margin are pushing the census to catalyse and finally reveal the tragical limits of an ethnocratic governance.

  7. Developpement du systeme de gestion des ressources humaines ...

    African Journals Online (AJOL)

    Dans l'optique du pilotage de la performance, une évaluation régulière du système ... Lacs Health District faced different issues in human resources management ... management, the policy and practice for the welfare of the human resources, ...

  8. Cyber Dhaba: un kiosque internet en Inde du Nord

    CERN Multimedia

    2002-01-01

    Il y a deux ans, l'association Orient Yourself installait un PC connecté sous un banyan sacré, dans un village agricole du Rajasthan (Inde du Nord). Claire Dixsaut dirige ELSE, elle est membre fondateur de l'association Orient Yourself.

  9. Role of Du Channel in Treating Senile Dementia

    Institute of Scientific and Technical Information of China (English)

    Lu Fan

    2006-01-01

    @@ The author believes that senile dementia is very closely related to not only deficiency of the liver and kidney, but also Eight Extra Channels, Du Channel in particular. Nourishing the liver and kidney and clearing Du Channel in the treatment can greatly enhance the therapeutic effect.

  10. Du Yuzhou Art Exhibition Will Open in the United Nations

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    From June 5th to 15th 2007,the headquarters of the United Nations will enjoy a show time of Du Yuzhou works,where works of photograph and painting will be exhibited. Mr.Yuzhou Du,President of the China National

  11. Le devenir actif du corps affectif

    Directory of Open Access Journals (Sweden)

    Pascal Séverac

    2005-09-01

    Full Text Available Le but de cet article est de saisir ce que signifie, pour le corps, être actif. À partir de la proposition 49 de la partie IV de l’Éthique, on propose de distinguer deux manières d’appréhender le corps – soit comme corps organique, soit comme corps affectif -, et l’on montre que la question éthique du devenir actif s’adresse à la dimension affective du corps. Il faut penser le devenir actif du corps affectif comme augmentation de son aptitude non seulement à affecter, mais aussi à être affecté. En effet, être affecté pour le corps n’est pas identique à pâtir : au contraire, plus est grande l’ouverture sensible d’un corps aux autres corps, plus est grande son activité éthique.The aim of this paper is to understand how the body can be active. With the proposition 49 of the fourth part of Ethics, two ways of conceiving of the body are distinguished : like an organic body or like an affective body. The ethics question of becoming active is about the affective body. This becoming active must be understood as increasing of the ability to affect, as well as to be affected. To be affected is different from to be passive. On the contrary, the more the body is able to be affected, the more he becomes active.

  12. Le pari du numérique

    Directory of Open Access Journals (Sweden)

    Marie-Françoise Durand

    2011-01-01

    Full Text Available En lançant ce premier numéro du Ceriscope, le Centre de recherches et d’études internationales (CERI et l’Atelier de cartographie de Sciences Po ont conscience de relever un défi. Engagés dans l’analyse scientifique des sociétés du monde, le CERI, en tant que centre de recherche, et l’Atelier de cartographie, en sa qualité de concepteurs de cartes, entendent faire accéder un grand nombre de lecteurs à leurs productions en utilisant la gratuité d’Internet. L’avantage d’une publication en ligne par rapport au livre papier ne se résume évidemment pas à la gratuité. Elle permet en effet un usage plus souple de la lecture en autorisant, grâce à l’indexation par mots clés, une recherche à l’intérieur des textes. Elle offre ensuite une rapidité de mise à jour des connaissances qui, compte tenu de l’évolution de l’économie et des sociétés, sont vite touchées par l’obsolescence. Les contributions mises en ligne seront ainsi actualisées et de nouvelles publications pourront les développer et les enrichir au fil du temps. La publication en ligne permet enfin les réactions des lecteurs qui deviennent ainsi des « acteurs » de la publication.

  13. Oncoplastie avec conservation mammaire dans le traitement du cancer du sein: à propos de 16 cas

    Science.gov (United States)

    Bouzoubaa, Wail; Laadioui, Meryam; Jayi, Sofia; Alaoui, Fatime Zahra Fdili; Bouguern, Hakima; Chaara, Hikmat; Melhouf, Moulay Abdelilah

    2015-01-01

    Le cancer du sein est actuellement le cancer le plus fréquent chez la femme, et pose un véritable problème diagnostique et thérapeutique. Le dépistage des lésions à un stade de plus en plus précoce, a permis une extension des indications du traitement conservateur radiochirurgical, qui était initialement limitées aux tumeurs de moins de 3 cm, unifocales, non inflammatoires. Par ailleurs, l'utilisation de traitements préopératoires permet d’étendre les indications du traitement conservateur à des tumeurs plus volumineuses. Parallèlement à cette extension des indications de conservation mammaire, on a observé le développement de nouvelles approches thérapeutiques notamment la chirurgie oncoplastique, technique du ganglion sentinelle et chirurgie stéréotaxique, dont les résultats initiaux sont très encouragent. A travers cette étude réalisée dans le service de gynécologie et obstétrique II du CHU HASSAN II de FES au MAROC, après l'analyse rétrospective de 16 patientes traitées par traitement conservateur et oncoplastie, nous avons voulus montrer notre aptitude a réalisé ses techniques chirurgicales et a bien prendre en charge ces patientes, mais aussi évaluer ces techniques en termes de résultat carcinologique et de résultat esthétique, aussi en terme de survie globale, survie sans métastase et en termes de récidive locale entre les plasties mammaires et les traitements usuels: mastectomie et traitement conservateur classique. PMID:26430477

  14. Perception de la gestion du paysage

    Directory of Open Access Journals (Sweden)

    Martin Coy

    2009-03-01

    Full Text Available Complex landscape management instruments based on a dynamic, innovative land-conservation paradigm and spatial zoning to provide for graded intensity of protection and human use are being implemented in the newer generation of biosphere reserves and biosphere parks. The multifunctionality of these exemplary landscapes with sustainable development is a great challenge; it also offers considerable potential for conflict. This paper intends to demonstrate the extent to which multifunctionality has been realised in the alpine Großes Walsertal Biosphere Park, and how the local population perceive the quality of their park five years after it was created. Landscape management efforts in the Großes Walsertal were monitored by accompanying regional-economic and perceptional studies, resulting in a discussion of required future actions.Des instruments complexes de gestion du paysage, fondés sur un paradigme dynamique et innovant de conservation ainsi que sur un zonage de l’espace visant à réguler la protection du territoire et son utilisation par l’homme, ont été mis en œuvre dans la dernière génération de réserves de biosphère et de parcs. La multifonctionnalité de ces paysages exemplaires du développement durable constitue un défi majeur, mais représente également une importante source de conflits. L’objectif de cet article est de démontrer dans quelle mesure la notion de multifonctionnalité a été appliquée à la réserve de biosphère alpine de Grosse Walsertal et d’évaluer comment la population locale perçoit la qualité de son parc, cinq ans après sa création. Les efforts de gestion du paysage dans la réserve de Grosse Walsertal ont été évalués par des études économiques régionales et par des enquêtes de perception, à l’origine d’un débat sur les actions futures à mettre en place.

  15. Modos de ver. Du Bois y Fanon

    Directory of Open Access Journals (Sweden)

    Sandro Mezzadra

    2014-07-01

    Full Text Available The sovereignty of glance and the primacy of sight represent the Western modern culture far beyond its artistic expression, organizing its philosophical and political conceptuality. They deeply influence the way in which subjects are conceived and constructed in Western modernity. This is the point of departure of the long-distance dialogue between W. E. B. Du Bois and Frantz Fanon staged in the article. Their political thought and militancy developed against the background of experiences – such as slavery and colonialism – characterized by process of construction of subjectivities which appear as “anomalous” with regard to the “standards” set by Modernity.

  16. QUELQUES RESULTATS SUR LA COMMANDE DU CHEMOSTAT

    OpenAIRE

    ROBLEDO VELOSO, GONZALO

    2006-01-01

    L'Introduction est essentiellement consacrée á dresser un aperçu de la modélisation de quelques processus biologiques dans le chemostat, á introduire les notions de base de la théorie de la comniande (commandabilité, stabilisation asymptotique, ensemble atteignable) et á montrer á quoi elles correspondent dans le cas spécifique du chemostat. Pour cela nous avons partagé l'introduction en deux parties: la premiére partie décrit le modéle de compétition dans le chemostat (section 1.1) ...

  17. Generic 'du' in time and context

    DEFF Research Database (Denmark)

    Jensen, Torben Juel

    2017-01-01

    speakers, and that variation also prevails within a micro-diachronic perspective (between conversations recorded within a few months, and even within the same conversation). The results emphasise that great caution should be exercised when taking the difference between two pieces of attested language use......This article considers the way individual speakers respond to a macro-level process of language change: an increased use of the second-person pronoun du for generic reference. Real time panel studies show that life span change is much more common than is often assumed, particularly among adult...

  18. Environmental behaviour and bioavailability of Depleted Uranium (DU) material

    Energy Technology Data Exchange (ETDEWEB)

    Oeh, U.; Gerstmann, U.; Schimmack, W.; Szymczak, W.; Li, W.B.; Hoellriegl, V.; Roth, P.; Paretzke, H.G. [GSF - National Research Center for Environment and Health, Inst. of Radiation Protection, Neuherberg (Germany)

    2005-07-01

    This work was performed to assess a possible health risk of depleted uranium (DU) for residents and KFOR personnel serving on the Balkans. Therefore, the environmental behaviour and bioavailability of DU material have been explored. In order to investigate the environmental impact of DU ammunition, leaching experiments were carried out. DU penetrators were buried in soil filled in columns. The soil was irrigated (16 mm/week) and the uranium isotopes {sup 238}U and {sup 235}U which were washed out and transported into the eluate were determined by inductively coupled plasma mass spectrometry (ICP-MS). After one year, an average of 1.7% of the original DU material corroded. About 40% of the corrosion products were located on the surface of the penetrator, 60% were recovered in the soil. On the other hand, only very small amounts of the DU material could be found in the eluate (about 1 ppm per year) suggesting a low solubility of DU and the corrosion products and/or a strong sorption to the soil. In another part of the study, the solubility of DU material in human body fluids was investigated to assess the bioavailability after oral intake and inhalation of DU particles. Therefore, DU corrosion products were powdered and incubated in artificial gastric juice and simulated lung fluid. About three-fourths of the DU material was dissolved in artificial gastric juice after 30 minutes. This fraction could not be increased, even when the incubation time was extended to 120 minutes. The dissolution of DU material in artificial lung fluid showed a distinct bi-phasic course with a readily soluble fraction and a fraction of very low solubility. These findings suggest that the DU corrosion products consist mainly of two types of uranium oxides, hexavalent and fast soluble compounds and tetravalent compounds with low solubility. Additional measurements with time-of-flight secondary ion mass spectrometry (TOF-SIMS) of DU corrosion material support this conclusion. The resulting

  19. Le kyste hydatique du cordon spermatique : une localisation exceptionnelle

    Directory of Open Access Journals (Sweden)

    Mohamed Moncef Hamdane

    2011-12-01

    Full Text Available L� hydatidose est une anthropozoonose due au developpement chez l�homme de la forme larvaire du taenia Echinococcus granulosis. La plupart des kystes hydatiques se localisent dans le foie et les poumons. Le kyste hydatique du cordon spermatique est extremement rare avec seulement 4 cas rapportes dans la litterature. Les auteurs rapportent dans cet article un nouveau cas d�hydatidose du cordon spermatique. Il s�agissait d�un homme de 40 ans qui consultait pour des douleurs scrotales evoluant depuis huit mois. L�examen clinique a mis en evidence une tumefaction mobile, inguino-scrotale, droite. L�echographie testiculaire a objective une hernie inguinale droite associee a deux kystes epididymaires bilateraux. Le patient a ete opere pour cure de son hernie avec decouverte en per-operatoire d�un kyste du cordon spermatique qui a ete reseque. L�examen anatomopathologique a conclu a une hydatidose du cordon spermatique.

  20. Luminescence de transfert de charge dans les composés oxyfluorés du molybdène, du tungstène, du niobum et du tantale

    OpenAIRE

    Zhang, Hong Jie

    1993-01-01

    Non disponible; Les caractéristique de la luminescence de transfert de charge de composés oxifluorés du niobium, du tantale, du molybdène et du tungstène ont été déterminées. L'influence de la coordinence de l'élément de transition et du mode d'assemblage des polyèdres de coordination a été examinée. Contrairement aux oxydes homologués, les phases comportant des ions alcalins peuvent présenter un rendement de luminescence élevé à 300 K lorsque les groupements oxifluorés sont isolés (ex. K3NbO...

  1. Festival du rire de Genève

    CERN Multimedia

    Staff Association

    2015-01-01

    Connaissez-vous le Festival du rire de Genève ? La deuxième édition aura lieu du 25 au 28 mars 2015 au Casino-Théâtre à Carouge. Côté programmation, Marc Donnet-Monay ouvre les festivités avant trois autres soirées de folie et d’humour que nous vous laissons le soin de découvrir dans le programme : http://www.rire-geneve.ch/#programme. Réduction de 30% sur l’achat de places pour les membres du personnel du CERN. Pour cela, il suffit de se rendre sur la billetterie en ligne de notre site : www.rire-geneve.ch et d’utiliser le code promotionnel. Contacter le secrétariat de l’Association du personnel (Staff.Association@cern.ch) pour connaitre ce code promotionnel.

  2. Harmonization of welding qualification provisions in RCC-M and European standards; Rapprochement des regles relatives aux qualifications de soudage dans les normes europeennes et le RCC-M

    Energy Technology Data Exchange (ETDEWEB)

    Lemoine, M. [Areva-NP, Tour AREVA, 92084 - Paris La Defense cedex (France); Lainez, B. [Areva-NP, usine de Chalon sur Saone 71380 Saint Marcel (France); Anastassiades, P. [EDF/Ceidre - 2 rue Ampere - 93206 SAINT-DENIS Cedex (France)

    2007-07-01

    Since a long time, numerous precautions for welding have been integrated in the nuclear codes, in particular in the RCC-M applicable to pressurized water reactors, in order to guarantee a high quality level of permanent assemblies. In parallel, European and ISO standardization works have led to a harmonisation of practices on qualification of welding processes, welders and operators. In the context of the regulatory evolutions presented during this conference, it was judged appropriate to bring closer the RCC-M practices and those of EN and ISO standards, while taking the precaution of specifying, if necessary, the complementary provisions allowing maintaining guarantees of quality consistent with the prior experience feedback. This paper presents the amendments brought to the RCC-M Code by the 2005 and 2007 addenda, in order to respond to this objective, and develops their motivations. (authors) [French] De nombreuses precautions ont ete integrees de longue date dans les codes nucleaires, et en particulier dans le RCC-M applicable aux reacteurs a eau sous pression, en matiere de soudage afin de garantir un haut niveau de qualite de ces assemblages permanents. Par ailleurs, des travaux europeens, puis ISO, ont conduit a une harmonisation des pratiques en matiere de qualification des modes operatoires de soudage et des soudeurs et operateurs. Dans le contexte des evolutions reglementaires presentees par ailleurs au cours de cette conference, il a ete juge opportun de rapprocher les pratiques du RCC-M et celles des normes EN et ISO, en prenant la precaution de specifier au besoin les dispositions complementaires permettant de maintenir des garanties de qualite coherentes avec le retour d'experience anterieur. La communication presente les amenagements apportees au code RCC-M par les modificatifs 2005 et 2007, afin de repondre a cet objectif, et en developpe les motivations. (auteurs)

  3. Activity report 1999; Rapport d'activites 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    The aim of this report is to outline the main developments of the ''Departement des Reacteurs Experimentaux'', (DRE) during the year 1999. DRE is one of the Department of the ''Direction des Reacteurs Nucleaires'', itself depending of the CEA Institution. After a presentation of the year highlights, this report gathers the main research and development programs. The second part concerns the production of radioisotopes, the silicon doping, the neutron radiography, the Orphee experiments and the activation analysis. The installations management, the closed reactors improvement program and the effluents and wastes processing of Grenoble, are presented in the other parts. Data on staff, budget and safety are also provided. (A.L.B.)

  4. Activity report 1998; Rapport d'activites 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The aim of this report is to outline the main developments of the ''Departement des Reacteurs Experimentaux'', (DRE) during the year 1998. DRE is one of the Department of the ''Direction des Reacteurs Nucleaires'', itself depending of the CEA Institution. After a presentation of the year highlights, this report gathers the main research and development programs. The second part concerns the production of radioisotopes, the silicon doping, the neutron radiography, the Orphee experiments and the activation analysis. The installations management, the closed reactors improvement program and the effluents and wastes processing of Grenoble, are presented in the other parts. Data on staff, budget and safety are also provided. (A.L.B.)

  5. Evaluation épidémiologique du programme genevois de dépistage du cancer du sein : 2007-2011

    OpenAIRE

    2014-01-01

    A l'instar de nombreux pays industrialisés, le cancer du sein est à Genève le cancer le plus fréquent (environ 460 cas par an) et la première cause de décès chez les femmes entre 45 et 55 ans. Depuis mars 1999, le Programme genevois de dépistage du cancer du sein a pour missions de promouvoir, d'organiser et de mener une action de prévention auprès de la population féminine du canton âgée de 50 à 69 ans. Ce rapport décrit l'évolution de 15 ans d'activité de dépistage (chapitre 2) et analys...

  6. Irradiation and lithium presence influence on the crystallographic nature of zirconia in the framework of PWR zircaloy 4 fuel cladding corrosion study; Influence de l'irradiation et de la presence du lithium sur la nature cristallographique de la zircone dans le cadre de l'etude de la corrosion du zircaloy 4 en milieu reacteur a eau pressurisee

    Energy Technology Data Exchange (ETDEWEB)

    Gibert, C

    1999-07-01

    The-increasing deterioration of the initially protective zirconia layer is one of the hypotheses which can explain the impairment with time of PWR fuel cladding corrosion. This deterioration could be worsened by irradiation or lithium presence in the oxidizing medium. The aim of this thesis was to underline the influence of those two parameters on zirconia crystallographic nature. We first studied the impact of ionic irradiation on pure, powdery, monoclinic zirconia and oxidation formed zirconia, mainly with X-ray diffraction and Raman microscopy. The high or low energy particles used (Kr{sup n+-}, Ar{sup n+}) respectively favored electronic or atomic defaults production. The crystallographic analyses showed that these irradiation have a significant effect on zirconia by inducing nucleation or growth of tetragonal phase. The extent depends on sample nature and particles energy. In all cases, phase transformation is correlated with crystalline parameters, grain size and especially micro-stress changes. The results are consistent with those obtained with 1 to 5 cycles PWR claddings. Therefore, the corrosion acceleration observed in reactor can partly be explained by the stress fields appearance under irradiation, which is particularly detrimental to zirconia layer cohesion. Last, we have underlined that the presence of considerable amounts of lithium in the oxidizing medium ((> 700 ppm) induces the disappearance of the tetragonal zirconia located at the metal/oxide interface and the appearance of a porosity of the dense under layer, which looses its protectiveness. (author)

  7. Synthesis of the IRSN analysis of the control-command architecture and platforms of the Flamanville 3 EPR reactor; Synthese de l'analyse par l'IRSN de l'architecture et des plateformes du controle-commande du reacteur EPR de Flamanville 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-16

    This document first briefly describes the context: control-command systems and functions, examples of control-command systems of the EPR, control-command platforms, and control-command architecture. It describes the method implemented by the IRSN to analyze the reactor control-command: assessment of the capacity of each system to perform its functions, assessment of the control-command architecture, hardware qualification. Then, it briefly recalls the assessments performed for the Teleperm XS platform and for the SPPA-T2000 platform, for the architecture (separation of systems belonging to different classes, in-depth defence, management of the architecture complexity)

  8. Opinion on the examination of the control-command general architecture of the Flamanville 3 EPR reactor and of its associated platforms; Avis relatif a l'examen de l'architecture generale du controle-commande du reacteur EPR Flamanville 3 et des plateformes associees

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-06-15

    This report first recalls the different technical and hardware elements and components discussed by the ISRN (Nuclear Radioprotection and Safety Institute) in front of the Expert Permanent Group for nuclear reactors. These elements and components are concerning the control-command architecture as a whole, and the technical ability of networks, computers, and robots. It outlines the main principles which the control-and-command must comply with: compliance of each component of the retained technological solution with the design requirements corresponding to the safety classification, robustness of the whole control-command architecture. Then, it comments and sometimes criticizes the status of the various components of the control-command platforms with respect to this compliance. Eight recommendations are given for the SPPA T2000 control-command platform and for the robustness of the control-command architecture.

  9. The rejection of the comprehensive nuclear test ban treaty by the US Senate: a reverse for the nuclear arms control?; Le rejet du traite d'interdiction complete des essais nucleaires par le Senat Americain: un revers pour l'arms control nucleaire?

    Energy Technology Data Exchange (ETDEWEB)

    Sitt, B. [Universite de Marne la Vallee, 77 (France)

    2000-07-01

    On October 13, 1999, after a hasty debate, the US Senate rejected the comprehensive nuclear test ban treaty (CTBT) signed 3 years ago. This article analyses this event with respect to the US domestic context (discussions at the Senate, reaction of the Presidency) and with respect to the international context (international reactions, future of the treaty, consequences on arms control policy). (J.S.)

  10. La mathématique du physicien

    CERN Document Server

    Diu, Bernard

    2012-01-01

    " Le livre de la nature est écrit dans la langue mathématique, et ses caractères sont des triangles, des cercles et autres figures géométriques, sans lesquels il est humainement impossible d'en comprendre le moindre mot ". Ce célèbre aphorisme de Galilée a scellé l'alliance des mathématiques et de la physique. Et pourtant, trois siècles plus tard, Einstein se montrait plus sceptique. Dans ce livre, Bernard Diu montre que, en effet, si les mathématiques sont un instrument indispensable de la physique, elles n'en constituent pas le fondement. En multipliant les exemples, il marque la différence entre la mathématique du mathématicien et celle du physicien. Un livre de nature à remettre en question l'enseignement de la physique dans nos écoles et des sciences en général, soumis à l'hégémonie des mathématiques.

  11. Du Bois的对话句法

    Institute of Scientific and Technical Information of China (English)

    高彦梅

    2015-01-01

    日常口语交流过程中,人们会自觉不自觉地复用即时语境中前面说话人或历史上前人的词语、短语、句法结构等成分。这样便在自己和前面说话人的话语之间唤起了共鸣。Du Bois在Bakhtin的对话理论、Jakobson的平行理论和Harris的话语分析程序的启发之下,依据自然口语语料、从社会认知角度发展了对话句法理论,目的在于揭示人类交流过程中符号与符号之间并通过符号表达的介入结构。本文综合Du Bois以及相关学者过去三十年间对对话句法的研究,呈现对话句法理论的主体脉络。

  12. Rejets et environnement du CERN - 2005

    CERN Document Server

    Vojtyla, P

    2006-01-01

    La radioactivité de l’environnement autour de l’Organisation Européenne pour la Recherche Nucléaire (CERN) et les doses de rayonnements qui en résultent pour la population avoisinante sont contrôlées par la Commission de Sécurité du CERN et de manière indépendante par les autorités compétentes des deux États Hôtes, l’Institut de Radioprotection et de Sûreté Nucléaire (IRSN) côté France et l’Office Fédéral de la Santé Publique (OFSP) côté Suisse. Dans ce rapport, les résultats de mesures concernent en particulier le territoire suisse. L’ensemble des mesures effectuées en 2005 prouve que le fonctionnement des installations du CERN était sans conséquence radiologique sur l’environnement et la population. Le contrôle des émissions montre que les rejets effectifs se situent également en 2005 nettement en dessous des limites réglementaires. Ce constat est confirmé par le contrôle des immissions dans l’environnement. Le CERN a bien respecté en 2005 comme dans les ann�...

  13. The CNRS and the nuclear wastes management. Contribution to the program on the electronuclear cycle downstream PACE at the law of the 30 December 1991; Le CNRS et la gestion des dechets nucleaires. Contribution du programme sur l'aval du cycle electronucleaire PACE a la loi du 30 decembre 1991

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document is a presentation of the activities of the PACE program. It presents the researches historical aspects, the researches concerning the axis 1 (transmutation, nuclear data acquisition, scenarios, separation and physico-chemistry in homogenous solution, the specific conditioning) and the axis 2 researches (the containment safety studies of the underground disposal, the physico-chemical phenomenons at the interfaces, the radionuclides migration). (A.L.B.)

  14. Project of decree relative to the licensing and statement system of nuclear activities and to their control and bearing various modifications of the public health code and working code; Projet de decret relatif au regime d'autorisation et de declaration des activites nucleaires et a leur controle et portant diverses modifications du code de la sante publique et du code du travail

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This decree concerns the control of high level sealed radioactive sources and orphan sources. It has for objective to introduce administrative simplification, especially the radiation sources licensing and statement system, to reinforce the control measures planed by the public health code and by the employment code, to bring precision and complements in the editing of several already existing arrangements. (N.C.)

  15. Study of the SPECT T.D.M. indications pertinence in nuclear medicine daily practice; Etude de la pertinence des indications du SPECT TDM en pratique quotidienne de medecine nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Bourahla, K.; Schneegans, O.; Nguyen, L.; Deharvengt, C.; Grauss, R.; Hoffmann, C. [CLCC Paul-Strauss, Strasbourg, (France)

    2009-05-15

    The objective of this work is to try to ripen the real contribution and the pertinence degree of some indications on basing on the information impact really got by the SPECT/T.D.M.. This examination is going to be more largely used in the study of soft tissues media and in the frame of skeleton evaluations (K{sub c} prostate), K{sub c} of breast except lumbar rachis, lytic context). (N.C.)

  16. The management of nuclear wastes from diffuse nuclear activities. A processing adapted to each situation; La gestion des dechets radioactifs du nucleaire diffus. Un traitement adapte a chaque situation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The French national agency of radioactive wastes (ANDRA) works with more than a thousand of clients belonging to hospitals, research centers and industries. These are called 'small producers' because they generate a small quantity of wastes. However, because of the large variety of these wastes, they require suitable and specific processes for their management which are presented in this brochure. (J.S.)

  17. Doping influence by some transition elements on the irradiation effects in nuclear waste glasses; Influence du dopage par certains elements de transition sur les effets d'irradiation dans des verres d'interet nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Florent, Olivier

    2006-06-15

    High-level waste glasses are submitted to auto-irradiation. Modelling it using external irradiations on simple glasses revealed defects production and non negligible structural changes. This thesis aims at determining the impact of a more complex composition on these effects, especially the influence of adding polyvalent transition metals. Silicate, soda-lime and alumino-borosilicate glasses are doped with different iron, chromium and manganese concentrations then {beta} irradiated at different doses up to 10{sup 9} Gy. Non doped glasses show an increase of their density and polymerisation coupled with a molecular oxygen and point defects production. Adding 0.16 mol% Fe decreases the amount of defects by 85 % and all irradiation effects. A Fe{sup 3+} reduction is also observed by EPR, optical absorption and indirectly by Raman spectroscopy. A higher than 0.32 mol% Fe concentration causes complete blockage of the evolution of polymerisation, density and defect production. The same results are obtained on chromium or manganese doped glasses. An original in situ optical absorption device shows the quick decrease of Fe{sup 3+} amount to a 25 % lower level during irradiation. Stopping irradiation causes a lower decrease of 65 %, suggesting a dynamic (h{sup 0}/e-) consuming equilibrium. He{sup +} and Kr{sup 3+} ions and {gamma} irradiated glasses tend to confirm these phenomena for all kind of irradiation with electronic excitations. (author)

  18. The introductory role of the nuclear energy in the environmental impact development studies; Le role precurseur du nucleaire dans le developpement des etudes de l`impact sur l`environnement

    Energy Technology Data Exchange (ETDEWEB)

    Ha-Vinh Phuong

    1995-12-31

    The nuclear installation regulatory process of authorization normally requires, in good safety practice that the safety analysis of a particular nuclear installation should go along with the environmental impact assessment (EIA). The organization and actions of a programme and inspections for environmental radioactivity are then requirements as conditions that should anticipate the licence authorization. The nuclear energy, in that case, plays an important role for the environment integration in the planning and decisions related to develop projects in ecologically sensible domains. In fact, environmental impact assessment concept was progressively introduced by an increasing number of national regulations to be applied in a large gamma of activities. The impact studies provides a contribution for the global environment management perception an the sustainable economical development interest. 2 tabs.

  19. Evaluation of the nuclear cross section variance-covariance matrices issued from the nuclear optical model; Evaluation des matrices de variance-covariance des sections efficaces nucleaires issues du modele optique

    Energy Technology Data Exchange (ETDEWEB)

    Brassart, M. [Ecole Nationale Superieure Ingenieurs de Bourges, 18 - Bourges (France); Mounier, C. [CEA Saclay, Dir. de l' Energie Nucleaire DEN, Service d' Etudes des Reacteurs et de Modelisation Avancee, 91 - Gif sur Yvette (France); Dossantos-Uzarralde, P. [CEA Bruyeres le Chatel, 91 (France). Dept. de Physique Theorique et Appliquee

    2004-07-01

    Nuclear reaction models play an important role in today's nuclear data evaluations. There are, however, difficulties associated with evaluating data uncertainties, both while performing the experimental measurements as well as constructing them by nuclear models. In this general context, our interest is particularly targeted towards the study of the propagation uncertainties within nuclear models. In this report we discuss two distinct ways of calculating the nuclear cross section variance-covariance matrices and then show these can be applied to the nuclear spherical optical model. (authors)

  20. Contributions of vitreous natural analogs to the investigation of long-term nuclear glass behavior; Apports des analogues naturels vitreux a la validation des codes de prediction du comportement a long terme des verres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Techer, I

    1999-07-01

    This study assesses the extend of the analogy between the alteration behavior in water and in a moist clay environment of aluminosilicate volcanic glass and alumino-borosilicate nuclear containment glass. Basaltic glass alteration in water initially occurs by hydrolysis processes with an activation energy on the order of 73 kJ.mol{sup -1}. As the reaction progresses, the alteration rate drops by over four orders of magnitude from the initial rate r{sub 0}, The alteration kinetics are not governed by the alteration solution chemistry alone, the glass alteration film appears to have a major role as a diffusion barrier limiting the transfer of reaction species and products. All these aspects highlight the behavioral analogy between basaltic glass and nuclear borosilicate glass in aqueous media. Conversely, the alteration reaction of obsidian-type volcanic glass involves other mechanisms than those governing the dissolution of borosilicate glass. Basaltic glass alteration is also examined in the presence of a clay environmental material, in a study of the natural basaltic glass and argillaceous pelites system of the Salagou basin in southern France, in an approach combining mineralogical, chemical and isotopic data to assess the interactions between a basaltic glass and the argillaceous pelites. Laboratory leach test results with basaltic glass and measured data for the Salagou glass in its natural environment are modeled using a code implementing a kinetic law coupling diffusive transfer of dissolved silica with a reaction affinity law. (author)

  1. Classification of spectra and search for bio-makers in prostate tumours form proton nuclear magnetic resonance spectroscopy; Classification de spectres et recherche de biomarqueurs en spectroscopie par resonnance magnetique nucleaire du proton dans les tumeurs prostatiques

    Energy Technology Data Exchange (ETDEWEB)

    Parfait, S.

    2010-12-06

    Prostate cancer is the most common cancer in men over 50 years. Current detection methods either lack sensitivity or specificity or are unpleasant for the patient. Magnetic resonance spectroscopy allows the study of metabolism in vivo. The use of a high field machine (>3 T) has allowed us to dispense with the use of an endorectal coil, which is particularly uncomfortable for the patient. The objective of this work is to create an automatic method to detect cancer by processing data obtained through magnetic resonance spectroscopy. MRS is a complex phenomenon, very sensitive to acquisition conditions. First, we have studied how to improve and optimise signal acquisition. However, even with a very good quality signal, it must still undergo further post-processing to be analysed automatically by a classification method. Further work was therefore needed to investigate which post-processing steps were required in order to optimize the spectra for classification. We then investigated the optimal classification method for this problem. A particular set of steps (signal acquisition, processing and spectral classification data) allows us to highlight the presence of prostate tumors with an overall error rate of less than 12%. In a second step, we searched for new bio-markers within the spectra. These bio-markers could be a metabolite or a specific frequency range corresponding to several metabolites. We did not find any additional significant attributes other than choline and citrate, however, some frequency bands seem to participate in improving the error rate. Finally, we expanded our investigation by attempting to apply these techniques to the rat. Technical constraints related to acquisition did not allow us to obtain a sufficient number of spectra in the pre-clinical cases. Nonetheless, we have validated the feasibility of MRS in rodents and its relevance in the brain. The technique, however, must be improved in order to be validated in the case of prostate cancer in rats. (author)

  2. RANS / LES coupling applied to high Reynolds number turbulent flows of the nuclear industry; Application du couplage RANS / LES aux ecoulements turbulents a haut nombre de Reynolds de l'industrie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Benarafa, Y

    2005-12-15

    The main issue to perform a computational study of high Reynolds numbered turbulent flows consists on predicting their unsteadiness without implying a tremendous computational cost. First, the main drawbacks of large-eddy simulation with standard wall model on a coarse mesh for a plane channel flow are highlighted. To correct these drawbacks two coupling RANS/LES methods have been proposed. The first one relies on a sophisticated wall model (TBLE) which consists on solving Thin Boundary Layer Equations with a RANS type turbulent closure in the near wall region. The second one consists on a RANS/LES methods have been proposed. The second one consists on a RANS/LES coupling method using a forcing term approach. These various approaches have been implemented in the TRIO-U code developed at CEA (French Atomic Center) at Grenoble, France. The studied flow configurations are the fully developed plane channel flow and a flow around a surface-mounted cubical obstacle. Both approaches provide encouraging results and allow a surface-mounted cubical obstacle. Both approaches provide encouraging results and allow unsteady simulations for a low computational cost. (author)

  3. Mortality in nuclear workers of the French electricity company: period 1968-2003; Cohorte des travailleurs du nucleaire a Electricite de France: mortalite des agents statutaires sur la periode 1968-2003

    Energy Technology Data Exchange (ETDEWEB)

    Rogel, A.; Joly, K.; Metz-Flamant, C.; Laurent, O.; Tirmarche, M.; Laurier, D. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Lab. d' Epidemiologie, DRPH/SRBE/LEPID, 92 - Fontenay-aux-roses (France); Hubert, D.; Garcier, Y. [Electricite de France (EDF), 93 - Saint-Denis (France)

    2009-08-15

    Background We conducted a mortality study on a cohort of French nuclear workers employed at Electricite de France (EDF). A first cancer mortality analysis had covered the period 1968-1994. This paper presents results from a mortality analysis including nine additional years of follow-up to cover workers employed from 1968 to 2003. Methods The cohort includes 22 393 workers, 97% of whom are males. Employment data were updated using the EDF personnel file. Vital status was ascertained using the French National Registry of Population, and further completed using EDF personnel and pension files. Causes of death were obtained from the National registry of causes of death. Standardised Mortality Ratios (S.M.R.) were computed using national rates as references. Variations of all causes and all cancers S.M.R.s were studied according to demographic and occupational characteristics. Results At the study end point (31/12/2003), 74% of workers are still in active employment. Only 0.3% of workers are lost to follow-up. The median duration of follow-up is 20 years. Causes are ascertained for 96% of deaths. The total number of deaths is 874, 307 of which are cancer deaths. S.M.R.s for all causes and cancers show a significant deficit compared to the French national mortality. No significant excess was observed for any of the cancer sites studied. Non-significant excesses are observed for pancreatic, pleural, kidney and brain cancer. Significant variations of all causes S.M.R.s according to age at study entry and attained age are observed. Significant variations of all causes and all cancers S.M.R.s according to diploma at employment are observed, with a reduced S.M.R. for a higher level of diploma. Conclusion There is a significant deficit of mortality compared to the general population, reflecting a strong Healthy Worker Effect. Although nine years of follow-up were added, this cohort is made up of young workers, most of whom are still in active service. Regular updating of the follow up of this cohort is planned, aiming for an occupational health surveillance of workers occupationally exposed to ionizing radiation in France. (authors)

  4. Whole study of nuclear matter collective motion in central collisions of heavy ions of the FOPI detector; Etude complete du mouvement collectif de la matiere nucleaire dans les collisions centrales d'ions lourds avec le detecteur FOPI

    Energy Technology Data Exchange (ETDEWEB)

    Bendarag, A

    1999-07-09

    In this work we study the collective phenomena in the central collisions of heavy ions for the Au + Au, Xe + CsI and Ni + Ni systems at incident energies from 150 to 400 MeV/nucleon with the data of the FOPI detector. In order to describe completely the flow of the nuclear matter, we fit the double differential momentum distributions with two-dimensional Gaussian. We study the characteristic parameters of the collective flow (flow range, aspect ratios, flow parameter) versus the charge and the mass of the fragments as well as the incident energy and the centrality of the collisions. The transverse energy is used for selecting the central collisions. The method of the Gaussian fits requires also to reconstruct the reaction plane of the event. Then we correct the parameters for the finite number of particles effects and account for the influence of the acceptance of the detector. We confirm the importance of the thermal motion for the light charge or mass fragments and, conversely, the predominance of the collective motion for the heavy fragments. A common flow angle for all the types of particles is highlighted for the first time, demonstrating the power of the method of the Gaussian fits; The evolution of the other parameters confirms the observations done with other methods of flow analysis. These results should contribute to put constraints on the collision models and to enlarge our knowledge of the properties of the nuclear matter. (author)

  5. Noninvasive quantification of myocardial perfusion heterogeneity by Markovian analysis in SPECT nuclear imaging; Quantification non invasive de l'heterogeneite de la perfusion du myocarde par analyse markovienne en imageries nucleaire SPECT

    Energy Technology Data Exchange (ETDEWEB)

    Pons, G.

    2011-04-28

    Cardiovascular diseases are the leading cause of mortality worldwide, and third of these deaths are caused by coronary artery disease and rupture of vulnerable atherosclerotic plaques. The heterogeneous alteration of the coronary microcirculation is an early phenomenon associated with many cardiovascular risk factors that can strongly predict the subsequent development of coronary artery disease, and lead to the appearance of myocardial perfusion heterogeneity. Nuclear medicine allows the study of myocardial perfusion in clinical routine through scintigraphic scans performed after injection of a radioactive tracer of coronary blood flow. Analysis of scintigraphic perfusion images currently allows the detection of myocardial ischemia, but the ability of the technique to measure the perfusion heterogeneity in apparently normally perfused areas is unknown. The first part of this thesis focuses on a retrospective clinical study to determine the feasibility of myocardial perfusion heterogeneity quantification measured by Thallium-201 single photon emission computed tomography (SPECT) in diabetic patients compared with healthy subjects. The clinical study has demonstrated the ability of routine thallium-201 SPECT imaging to quantify greater myocardial perfusion heterogeneity in diabetic patients compared with normal subjects. The second part of this thesis tests the hypothesis that the myocardial perfusion heterogeneity could be quantified in small animal SPECT imaging by Thallium-201 and/or Technetium-99m-MIBI in an experimental study using two animal models of diabetes, and is correlated with histological changes. The lack of difference in myocardial perfusion heterogeneity between control and diabetic animals suggests that animal models are poorly suited, or that the technology currently available does not seem satisfactory to obtain similar results as the clinical study. (author)

  6. Decision-making guide for management of agriculture in the case of a nuclear accident; Guide d'aide a la decision pour la gestion du milieu agricole en cas d'accident nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Reales, N. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Fourrie, L. [Association De Coordination Technique Agricole, 75 - Paris (France); Quinio, C.; Grastilleur, Ch. [Ministere de l' Agriculture et de la Peche, 75 - Paris (France). Direction Generale de l' Alimentation

    2008-07-15

    For several years, agricultural and nuclear professionals in France have been working on how to manage the agricultural situation in the event of a nuclear accident. This work resulted in measures at both the national (Aube nuclear safety exercises in 2003, INEX3 in 2005) and international levels (EURATOM Programmes). Following on from the European FARMING (FP5) and EURANOS (FP6) works, ACTA', IRSN and six agricultural technical institutes which are specialized in agricultural production and processing network (arable crop [especially cereals, maize, pulses, potatoes and forage crops], fruits and vegetables, vine and wine, livestock farming [cattle, sheep, goats, pigs, poultry]), created a resource adapted to the French context: the Decision-aiding Tool for the Management of Agriculture in case of a Nuclear Accident. Devised for the Ministry of Agriculture services supporting state officials in a radiation emergency, this manual focuses on the early phase following the accident when the state of emergency would make discussion on countermeasures with a large stakeholder panel impossible. Supported by the Ministry of Agriculture and Fisheries and the French Nuclear Safety Authority, this project increased knowledge of post-accident management strategies and made an important contribution to the national think tank set up within the framework of the French Steering Committee for managing the post-event phase of a nuclear accident (CODIRPA). This article describes how the manual evolved throughout the project and the development of new resources. (authors)

  7. Analysis of sensitivity and uncertainty on the leukemia risk attributable to the nuclear installations of North Cotentin; Analyse de sensibilite et d'incertitude sur le risque de leucemie attribuable aux installations nucleaires du Nord-Cotentin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-15

    The study realised includes several phases: the delimitation of the field of the study, the identification of the paramount parameters, the determination of the variations intervals of the paramount parameters, the analysis of the sensitivity and finally the analysis of uncertainty. (N.C.)

  8. About the treaty of complete nuclear test ban: the USA between unilateralism and multilateralism; A propos du traite sur l'interdiction complete des essais nucleaires: les Etats-Unis entre l'unilateralisme et le multilateralisme

    Energy Technology Data Exchange (ETDEWEB)

    Sur, S. [Universite Pantheon-Assas, 75 - Paris (France); Centre Thucydide, Analyse et Recherche en Relations Internationales, 75 - Paris (France)

    2000-07-01

    This article analyses the possible reasons that have led the US Senate to reject the treaty of comprehensive nuclear test ban. Even if this decision did not retained the attention of the international public opinion, it appears as surprising because the USA have worked a lot for the elaboration of this treaty and were considered as the main beneficiaries of it. Three interpretations are proposed by the author: some purely internal disputes inside Clinton's administration, a real will of the USA to abandon the arms control policy, or an intermediate attitude which allows the USA to act on different levels and to get rid of common rules. (J.S.)

  9. Experimental investigation of the effects of aqueous species on the dissolution kinetics of R7T7 glass; Etude experimentale de l`influence d`especes aqueuses sur la cinetique de dissolution du verre nucleaire R7T7

    Energy Technology Data Exchange (ETDEWEB)

    Gin, S.

    1994-10-01

    This contribution to the study of aqueous corrosion of the French ``R7T7`` reference nuclear containment glass includes a bibliographic survey of prior investigations, highlighting the problems encountered in interpreting the interactions in systems containing clay materials in contact with the glass. An experimental methodology is proposed to investigate the effects of inorganic aqueous species separately from those of a few organic acids on the dissolution mechanisms and kinetics of R7T7 glass at 90 deg. C. The experimental results discussed support the idea that several glass network forming elements may have a kinetically limiting role. The most likely hypothesis to account for the absence of saturation conditions with respect to the glass in certain clay media involves the formation of complexes with kinetically limiting metallic elements such as aluminum released by glass corrosion. This work contributes to a better understanding of the basic mechanisms of nuclear glass dissolution in a geological repository environment. It facilitates the interpretation of glass alteration studies in realistic or actual solutions and may contribute to specifying near field chemical barriers in the form of additives (amorphous silica, aluminum hydroxides or phosphates) around the glass disposal package to enhance the stability of the glass matrix. (author). 148 refs., 40 figs., 32 tabs., 1 append.

  10. Open letter to Mr Christian Bataille, Deputy of Nord region, France. Open letter on nuclear energy; Lettre ouverte a Monsieur Christian Bataille, depute du Nord. Lettre ouverte sur le nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Delacroix P

    2007-02-15

    The author, by means of a letter to the deputy Christian Bataille, presents arguments to the shutdown of old nuclear power plants. He points out the environmental and economical arguments in favor of a decrease of the nuclear power use in France. (A.L.B.)

  11. Oxidation of nuclear fuel below 400 deg. Consequence on long-term dry storage; L'oxydation du combustible nucleaire au-dessous de 400 deg. Consequences sur l'entreposage a sec de longue duree

    Energy Technology Data Exchange (ETDEWEB)

    Dehaudt, Ph

    2000-07-01

    This document reviews the status of the knowledge on the oxidation of fuels below 400 deg C, in all its forms, including fuel rods, by examining the consequences of this reaction on the strength or ruin of the fuel rods during dry storage in air for a hundred years. The data available in the scientific literature, and the data acquired by CEA, are abundant on irradiated powders and pellets, but sparser for irradiated fuel fragments and for rods or sections of fuel rods. A bibliographic review is made to identify the morphological and structural changes, as well as the kinetic laws. An analysis and a summary is made with a concern to evaluate the risks of rod ruin by oxidation. The final section, in a few pages, addresses the essential lessons from this study. It presents: first, a summary of the main results of this review and its analysis, recommendations and remedies for storage; proposed research guidelines as well as precise topics, in order to fill out our knowledge and, even better, to identify the acceptable limits for storage. (author)

  12. Recent outputs of the Oklo (Gabon) natural analogue study to nuclear waste disposal; Apports recents de l'etude de l'analogue naturel Oklo (Gabon) dans le domaine du stockage des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Michaud, V.; Trotignon, L. [CEA Cadarache, Dept. d' Entreposage et de Stockage des Dechets (DCC/DESD/SESD), 13 - Saint-Paul-lez-Durance (France); Louvat, D. [CEA Cadarache, (IPSN/DPRE/SERNAT/LERCM), 13 - Saint-Paul-lez-Durance (France)

    2000-07-01

    In the past twenty five years, the natural nuclear reactors of Oklo have been the subject of numerous detailed studies. First investigated for the physical and neutron aspects of the nuclear reaction, they were then reconsidered because they provide a unique opportunity in the world to study the containment of actinides and fission products in a geological formation over a broad timescale (two billion years). Although the sites investigated do not represent a complete analogue of a repository system, many of the processes studied (mass transfer to the surface, transport, migration / retention), the spatial extent of these processes, and the timescales involved, are compatible with processes liable to occur during the lifespan of a repository for the deep geological disposal of spent nuclear fuel. A fresh program was therefore initiated as a European Commission project in 1990, entitled''Oklo as a natural analog for transfer processes in a radioactive waste repository'- phase 7, and then extended by a phase 2 entitled Oklo, Natural Analogue - Behavior of Nuclear Reaction Products in a Natural Environment''. Researches conducted in phase I served to determine the physical conditions of the operation of the natural reactor, reconstruct the geological history of the reactor environment, and decode the behavior of actinides as well as fission products in the surrounding geological formations. Phase N, which ended in June 1999, had three main objectives: i) to assess radionuclide migration and retention processes from the reactor zones to the geological environment, ii) to define the confinement properties and long-term behavior of geological materials; iii) to test models of processes related to radionuclide migration and retention, and eventually to provide suitable data and scenarios for performance assessment of nuclear waste disposal. This paper proposes a synthesis of the main outputs of the Oklo project to the performance assessment of nuclear waste disposal, the study of the long-term evolution of spent fuel and the long-term behavior of geological materials with respect to the containment of actinides and fission products. The Oklo natural analogue displays a number of specific features that make it unique in the world. The Oklo basin is characterized by the occurrence of meter scale uraninite lenses, that were affected by nuclear fission 2 billion years ago. These ''reactor zones'' exist in three sites: Oklo, Okelobondo and Bagombe. By analogy with a repository system, they are considered as representative of the 'Source' term. Numerous isotopic and geochemical tracers are thus available in order to restrict the migration or retention processes of actinides and fission products present in these zones. The near environment of the reactor zones, called ''Near field'' by analogy, is mainly composed of clayey materials (i.e. chlorite, illite, kaolinite). Reactor zones are found at present from the surface (Bagombe under oxidizing and acid conditions, with supergene weathering) to deep (Okelobondo under reducing conditions, with a low groundwater dynamics) conditions. Some reactor zones, e.g. R.Z. 13 in Oklo mine, have been subjected to strong hydrothermal disturbances (with temperatures above 350 deg C), linked to the geological history of the Franceville basin. On the other hand, the old age of the Oklo reactors (2 Ga) implies that pressure, temperature and chemical conditions have evolved during a long geological history, with associated basin scale movements of fluids. The Oklo-natural analogue Phase II project compiled useful information and tools for persons involved in Performance Assessment of waste disposal, wasteform conception or long term behavior [10] in four main areas corresponding to major investigation fields: 1/ ''Source'' term evolution, 2/ Long term containment properties of geological materials, 3/ Migration and retention of actinides and fission or end products, and 4/Geochemical and transport modeling. The main outputs of the European Oklo project to the nuclear waste repository issue are shown. The most important include: - new data on the long-term evolution of spent fuel, suggesting the possible occurrence of a coffinitisation process and measurement of short term leaching rates of Oklo uraninite, with a simplified kinetic model. A thermodynamic and crystallochemical study remains to be carried out on the coffinitisation process. - modeling tools and data useful for ranking and quantitatively describing the interaction of uranium and rare earth elements with a complex clayey material; - important clues on radionuclide trapping in ''generic''mineral phases such as Mn and Fe oxides, chlorite, illite and specific secondary minerals such as phosphates, Zr-silicates, etc; - consistent understanding of redox buffering in a clayey environment from deep to surface conditions. This model is ''generic'' enough to be adapted or applied to other sites. (authors)

  13. Demonstration of the 3D PANTHERE software for the simulation of gamma dose rates for complex nuclear installations; Demonstration du logiciel 3D panthere pour la simulation des debits de doses gamma pour installations nucleaires complexes

    Energy Technology Data Exchange (ETDEWEB)

    Longeot, M.; Dupont, B. [EDFISEPTENITE, 12-14 avenue Dutrievoz, 69628 Villeurbanne Cedex (France); Schumm, A.; Zweers, M. [EDF/R and D/SINETICS, 1 avenue du General de Gaulle, 92141 Clamart Cedex (France); Malvagi, F.; Trama, J.C. [CEA Saclay, SERMA, 91 - Gif-sur-Yvette (France)

    2010-07-01

    The authors present the two successive versions of the PANTHERE simulation software developed by EDF-SEPTEN to determine gamma dose flow rate in complex industrial installations. This software predicts dose rates and thus enables interventions in irradiating environment to be optimized. The authors report the demonstration of the industrial version (PANTHEREv1) and of the currently under development version (PANTHEREv2). They outline the evolutions brought to the first version to develop the second one such as the direct importation of CAD models, ergonomic improvements, etc.

  14. Initial steps of the base excision repair pathway within the nuclear architecture; Les etapes initiales du mecanisme de reparation par excision de bases au sein de l'architecture nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Amouroux, R

    2009-09-15

    Oxidative stress induced lesions threaten aerobic organisms by representing a major cause of genomic instability. A common product of guanine oxidation, 8-oxo-guanine (8- oxoG) is particularly mutagenic by provoking G to T transversions. Removal of oxidised bases from DNA is initiated by the recognition and excision of the damaged base by a DNA glycosylase, initiating the base excision repair (BER) pathway. In mammals, 8-oxoG is processed by the 8-oxoG-DNA-glycosylase I (OGG1), which biochemical mechanisms has been well characterised in vitro. However how and where this enzyme finds the modified base within the complex chromatin architecture is not yet understood. We show that upon induction of 8-oxoG, OGG1, together with at least two other proteins involved in BER, is recruited from a soluble fraction to chromatin. Formation kinetics of this patches correlates with 8-oxoG excision, suggesting a direct link between presence of this chromatin-associated complexes and 8-oxoG repair. More precisely, these repair patches are specifically directed to euchromatin regions, and completely excluded from heterochromatin regions. Inducing of artificial chromatin compaction results in a complete inhibition of the in vivo repair of 8-oxoG, probably by impeding the access of OGG1 to the lesion. Using OGG1 mutants, we show that OGG1 direct recognition of 8-oxoG did not trigger its re-localisation to the chromatin. We conclude that in response to the induction of oxidative DNA damage, the DNA glycosylase is actively recruited to regions of open chromatin allowing the access of the BER machinery to the lesions. (author)

  15. Study of a cohort of Latvian workers having participated to the decontamination of the nuclear site of Chernobyl; Etude d`une cohorte de travailleurs lettons ayant participe a la decontamination du site nucleaire de Tchernobyl

    Energy Technology Data Exchange (ETDEWEB)

    Viel, J.F. [Faculte de Medecine de Besancon, 25 (France)

    1999-11-01

    In the consequences attributable to the accident at the Chernobyl nuclear power plant, it is debated whether post-disaster psycho-pathology is related to the perception of the level of contamination or the level of contamination itself. To address this issue, the authors have assessed the association of various exposure mental and psychosomatic distress, on a sample of 1,1412 Latvian liquidators drawn from the State Latvian Chernobyl clean-up workers registry. The outcome considered was a mixed mental/psychosomatic disorder occurring during the time period 1986-1995. Comparisons between subgroups of the cohort, classified according to exposure type or level, were based on the proportional hazards model. Length of work ({>=} 28 days) in a 10 km radius from the reactor (relative risk (RR) = 1.39, 95 percent confidence interval (CI) 1.14-1.70), work (> 1 time) on the damaged reactor roof (RR 1.46, 95 percent CI 1.02-2.09), forest work (RR 1.41,95 percent CI 1.19-1.68), and fresh fruits consumption ({>=} 1 time/day) (RR 1.72,95 percent CI 1.12-2.65) are risk factors for mixed mental/ psychosomatic disorder. Construction of the sarcophagus (RR 1.82, 95 percent CI 0.89-3.72), is also associated with this outcome, although non significantly. These findings confirm that some exposure variables represent risk factors for mental disorders and suggest some radiation-induced consequences although surely overweight by stress-related effects. (author)

  16. Working of Mo-TiC cermets for 'future nuclear systems'; Mise en forme de cermets Mo-TiC pour les 'Systemes Nucleaires du futur'

    Energy Technology Data Exchange (ETDEWEB)

    Allemand, Alexandre [CEA-Saclay, DRT/LITEN/LTMEx, 91191 Gif-sur-Yvette (France); Le Flem, Marion [CEA-Saclay, DEN/DMN/SRMA, 91191 Gif-sur-Yvette (France); Rousselet, Jerome [UTT Troyes, 10010 Troyes (France)

    2006-07-01

    The nuclear reactor cores (generation IV) will form an extremely severe environment (high temperature, severe and long irradiation...). These drastic criteria and the preoccupation to ensure a higher and higher safety level lead, beyond the preoccupations due to the feasibility of such reactors, to harsh choices in materials able to be used. Innovating materials such as Mo-TiC cermet are the subject of intense researches in the CEA. This study presents and compares two modes of Mo-TiC cermet working: the hot isostatic compression and the extrusion. Different compositions of Mo-TiC cermets are prepared by hot isostatic compression and extrusion, and then characterized in term of microstructural properties. At last, this study concludes to a very satisfying working by hot isostatic compression, nevertheless the extrusion has still to be improved. (O.M.)

  17. 3D asynchronous particle tracking in single and dual continuum matrix-fractures. Application to nuclear waste storage; Modelisation 3D du transport particulaire asynchrone en simple et double continuum matrice-fractures: application au stockage de dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Lam, M.Ph

    2008-06-15

    This PhD research was conducted as a collaboration between Laboratoire National d'Hydraulique et Environnement (LNHE) from EDF R and D and the Institut de Mecanique des Fluides de Toulouse (IMFT) in the frame of a CIFRE contract. This PhD thesis aims at providing LNHE a reliable numerical model to study the feasibility of a nuclear waste storage in deep geological structures. The main focus of the thesis is put on developing and implementing a Random Walk Particle Method (RWPM) to model contaminant transport in 3D heterogeneous and fractured porous media. In its first part, the report presents the Lagrangian particle tracking method used to model transport in heterogeneous media with a direct high resolution approach. The solute plume is discretized into concentration packets: particles. The model tracks each particle based on a time-explicit displacement algorithm according to an advective component and a diffusive random component. The method is implemented on a hydraulic model discretized on a 3D unstructured tetrahedral finite element mesh. We focus on techniques to overcome problems due to the discontinuous transport parameters and the unstructured mesh. First, we introduce an asynchronous time-stepping approach to deal with the numerical and overshoot errors that occur with conventional RWPM. Then, a filtering method is applied to smooth discontinuous transport parameters (pre-processing). Finally, once the particle displacements are computed, we propose several filtering and sampling methods to obtain concentrations from particle positions (post-processing). Applications of these methods are presented with cases of tracer advection-dispersion in homogeneous and heterogeneous media. For dense fracture networks, direct high resolution methods are very time consuming and need a lot of computational resources. So, as an alternative to the discrete approach, a dual-continuum representation is used, in the second part of the report, to describe the porous matrix and the fracture network. Each material is separately represented by a continuous medium with equivalent homogenized parameters and its own system of governing equations coupled by the exchange rate of water and tracer mass between the fractures and the porous matrix. The exchange of tracer is interpreted with particles transitional probabilities to jump from a continuum to the other. The combination of the asynchronous particle tracking method with a double-continuum approach makes the difficulty of the method. The dual-continuum approach in transport in 3D heterogeneous porous media is applied on a regular fracture network. First results show that the model is adequate for low contrast permeability between the matrix and the fractures. (author)

  18. Implemented organisation for subcontracting companies involved in the maintenance of the French nuclear stock - Sheet nr 39; Organisation mise en place pour les entreprises prestataires de la maintenance du parc nucleaire francais - Fiche No. 39

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-30

    Every year, some 20,000 subcontracted salaried employees are mobilised for maintenance operations in the French nuclear reactors. Subcontracting is an answer to different needs: specific abilities, the short delay for maintenance during which a reactor is stopped, and which requires a very important contribution of labour, and specialised labour for some interventions. The document evokes a rigorous selection and certification process, and indicates the different specific training which are organised for anyone intervening in a nuclear power plant. It outlines that radiation protection and safety arrangements are the same for all (dosimetry), and that some measurements are performed on some temporary workers. Some data shows that these controls are efficient and that safety is improving

  19. Schedule of conditions for the personnel formation of category A or B working in nuclear facilities; Cahier des charges pour la formation du personnel de categorie A ou B travaillant dans les installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document describes the main provisions concerning the formation and the radiation and conventional risks protection of A or B category personnel, working in nuclear facilities. It contents the application domain, the applicable documents, the liability, the formation organizations, the formation to the risk prevention, the retraining and the Passerelles formations. (A.L.B.)

  20. Project report about the motives of the future law project 'security and nuclear clearness'; Projet d'expose des motifs du futur projet de loi ''securite et transparence nucleaire''

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-11-01

    This project aims to prevent the hazards in relation with nuclear activities for man and his environment, as well to reinforce information on risks associated to these activities and on measures taken to avoid them. (N.C.)