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Sample records for du combustible nucleaire

  1. Plutonium, nuclear fuel; Le plutonium, combustible nucleaire

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    Grison, E [Commissariat a l' Energie Atomique, Fontenay aux Roses (France). Centre d' Etudes Nucleaires, Saclay

    1960-07-01

    A review of the physical properties of metallic plutonium, its preparation, and the alloys which it forms with the main nuclear metals. Appreciation of its future as a nuclear fuel. (author) [French] Apercu sur les proprietes physiques du plutonium metallique, sa preparation, ses alliages avec les principaux metaux nucleaires. Consideration sur son avenir en tant que combustible nucleaire. (auteur)

  2. Non-Destructive Methods for Determining Burn-Up in Nuclear Fuel; Methodes Non Destructives d'Evaluation du Taux de Combustion dans le Combustible Nucleaire; Metody opredeleniya vygoraniya v yadernom toplive bez razrusheniya obraztsa; Metodos No Destructivos para Determinai el Grado de Combustion de los Elementos Combustibles Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    McGonnagle, W. J. [Illinois Institute of Technology, Chicago, IL (United States)

    1966-02-15

    is of secondary importance and the cooling time is unimportant. Also, there is more precise nuclear data for the stable fission products. Of the stable isotopes produced during the fission process, zirconium, molybdenum, ruthenium, and neodymium appear to be the most useful. The proposed non-destructive methods using stable isotopes will be discussed. (author) [French] Il est a la fois utile et souhaitable d'utiliser des methodes non destructives pour proceder a la mesure quantitative du taux de combustion des elements combustibles d'un reacteur nucleaire. L'ideal serait de pouvoir analyser le combustible a l'aide d'une methode ne necessitant pas de renseignements particuliers sur les spectres des neutrons, le schema d'irradiation ou le temps de refroidissement. Les isotopes radioactifs et les isotopes stables resultant du processus de fission qui sont presents dans un element combustible irradie caracterisent son irradiation. Malheureusement, que l'analyse soit effectuee au moyen de methodes destructives ou non destructives, les resultats obtenus varient en fonction du spectre de neutrons, du schema d'irradiation et du temps de refroidissement. Deplus, l'absence de donnees nucleaires precises, comme les valeurs des section efficaces, influe sur tous les calculs qui peuvent etre effectues. L'analyse non destructive est egalement genee par la presence de champs de rayonnements intenses qui augmentent le bruit de fond. Il est difficile d'etablir des normes utiles et realistes. Bien que, dans l'etat actuel de la technique, les methodes non destructives n'aient pas toute la precision et l'exactitude voulues, elles presentent neanmoins un grand interet' notamment dans les cas ou il faut obtenir rapidement et economiquement une valeur approximative du taux de combustion. Plusieurs methodes non destructives d'evaluation du taux de combustion sont actuellement appliquees, a l'etude ou en projet. Plusieurs types de spectrometres sont utilises pour la mesure du rayonnement

  3. 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

    competitivite, nous considerons deux cas: 1) le tonnage a transporter annuellement est limite; 2) le tonnage a transporter annuellement n'est pas limite. Dans les deux cas, nous recherchons les optima du navire classique et du navire nucleaire, et nous les comparons. Nous construisons les courbes de competitivite en fonction des rapports des couts de combustible nucleaire et classique, et des couts marginaux de la puissance nucleaire et classique. Ces courbes traduisent les valeurs limites des deux rapports ci-dessus pour lesquelles les couts de transport du navire nucleaire et du navire classique sont egaux. Suivant les hypotheses adoptees pour le marche du fret et pour la limite du tonnage transporte annuellement, nous avons des courbes de competitivite tres differentes. De toute facon, c'est l'augmentation de puissance qui favorise le nucleaire. On peut obtenir cette augmentation en accroissant le deplacement ce qui est toujours interessant dans la mesure ou le fret le justifie, et en accroissant la vitesse, mais dans ce cas le modele met en evidence l'existence d'une limite. Le sous-marin peut presenter certains avantages (moindre resistance hydrodynamique de l'eau, possibilite de vitesse plus reguliere, et eventuellement reduction de trajet) qui rendent la competitivite du nucleaire plus aisee. (auteur)

  4. Contribution to the study of the fission-gas release in metallic nuclear fuels; Contribution a l'etude du degagement des gaz de fission dans les combustibles nucleaires metalliques

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

    1969-10-01

    In order to study the effect of an external pressure on the limitation of swelling due to fission-gas precipitation, some irradiations have been carried out at burn-ups of about 35.000 MWd/ton, and at average sample temperatures of 575 Celsius degrees, of non-alloyed uranium and uranium 8 per cent molybdenum gained in a thick stainless steel can. A cylindrical central hole allows a fuel swelling from 20 to 33 per cent according to the experiment. After irradiation, the uranium samples showed two types of can rupture: one is due to the fuel swelling, and the other, to the pressure of the fission gases, released through a network of microcracks. The cans of the uranium-molybdenum samples are all undamaged and it is shown that the gas release occurs by interconnection of the bubbles for swelling values higher than those obtained in the case of uranium. For each type of fuel, a swelling-fission gas release relationship is established. The results suggest that good performances with a metallic fuel intended for use in fast reactor conditions can be obtained. (author) [French] Afin d'etudier l'effet d'une pression exterieure sur la limitation du gonflement due a la precipitation des gaz de fission, on a irradie a des taux de combustion d'environ 35.000 MWj/t et a des temperatures moyennes de 575 degres des echantillons d'uranium non allie et d'uranium-molybdene 8 pour cent contenus dans une gaine en acier inoxydable epaisse. Un trou cylindrique central permet au combustible de gonfler librement de 20 a 33 pour cent suivant les cas. Apres irradiation les echantillons d'uranium presentent deux types de ruptures de gaine: l'une due au gonflement du combustible, l'autre a la pression des gaz degages, ce degagement des gaz etant provoque par un reseau de micro-fissures. Les gaines des echantillons d'alliage uranium-molybdene sont toutes intactes et l'on montre que le relachement des gaz opere par interconnexion des bulles pour des valeurs de gonflement plus elevees que dans

  5. Treatment of effluent at the Saclay Centre d'Etudes Nucleaires (1960); Le traitement des effluents du Centre d'Etudes Nucleaires de Saclay (1960)

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

    1960-07-01

    The Centre d'Etudes Nucleaires at Saclay possesses several installations from which liquid radioactive effluent is rejected, and it has thus been found necessary to construct a station for the purification of radioactive liquids and to settle various chemical, analytical and technological problems. This report describes, in the following order: - the disposal possibilities at the Centre d'Etudes Nucleaires, Saclay, - the effluents produced at the centre, - the set-up for collecting effluent, - treatment of the effluent, - results of these treatments. (author) [French] La presence, au Centre d'Etudes Nucleaires de Saclay, de plusieurs installations susceptibles de rejeter des effluents liquides radioactifs a necessite la construction d'une station d'epuration d'eaux radioactives et la mise au point de differents problemes chimiques, analytiques et technologiques. Dans ce rapport, nous exposerons successivement: - les possibilites de rejet du Centre d'Etudes Nucleaires de Saclay, - les effluents du centre, - le dispositif de collecte des effluents, - le traitement de ces effluents, - les resultats de ces traitements. (auteur)

  6. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

    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 combustibles, une simplification du systeme de

  8. Optimal sizes and siting of nuclear fuel reprocessing plants; Tailles et localisations optimales des usines de retraitement des combustibles nucleaires

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    Thiriet, L; Deledicq, A [Commissariat a l' Energie Atomique, Siege (France). Centre d' Etudes Nucleaires

    1967-07-01

    The expansion of a nuclear economy entails the development of fuel process and reprocessing plant programmes. The model proposed makes it possible to select the size, the site and the start-up schedule of the plants in such a way as to minimize the total freight and reprocessing costs. As an illustration, we have approached the problem of burnt natural uranium processing plants related to natural uranium-graphite as nuclear power stations. The sites and annual output of the reactors, the possible plant sites and cost functions (freight and reprocessing) are supposed to be known. The method consists in first approaching the process plant problem as a Dynamic Programming problem, increasing programme slices (total reactor output) being explored sequentially. When the quantities of burnt natural uranium to be reprocessed are fixed, the minimization of the transport cost is then also carried out as a dynamic programming problem. The neighbourhood of the optimum process cost is explored in order to find the minimum summation of a suboptimal processing cost and corresponding optimal transport cost. As the reprocessing problem can be represented on a sequential graph, in order to compute the sub-optima, we developed and used a 'reflexion algorithm'. The method can be interpreted as a general mechanism for determining the optimum when to a sequential dynamic problem (for example an equipment programme) is added a complementary problem (transport, for instance). It also makes it possible to estimate the economic losses which result from the choice of a non optimal policy for other than economic reasons. (author) [French] L'expansion de l'economie nucleaire se traduit par un developpement des programmes d'usines d'elaboration et de retraitement des combustibles. Le modele propose permet de choisir la taille, la localisation et la cadence de mise en service des usines de maniere a minimiser le total des frais de transport et de retraitement. A titre d'exemple nous avons

  9. Material movement of medium surrounding an underground nuclear explosion; Mouvement materiel du milieu environnant une explosion nucleaire souterraine

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    The results of measurements of the mechanical effects in the, intermediate zone around underground nuclear explosions in Sahara granite are presented. After a description of the main characteristics of the equipment used, the laws drawn up using experimental results for the acceleration, the velocity, and the material displacement are presented. These laws are compared to those published in other countries for nuclear tests in granite, in tuff and in alluvial deposits. (authors) [French] Les resultats de mesures d'effets mecaniques en zone intermediaire autour d'essais nucleaires souterrains dans le granite du Sahara sont exposes. Apres avoir decrit, dans leurs grandes lignes, les materiels utilises, on presente les lois etablies avec les resultats experimentaux pour l'acceleration, la vitesse et le deplacement materiel. Ces lois sont comparees a celles publiees a l'etranger pour des essais nucleaires dans le granite, le tuf et les alluvions. (auteur)

  10. Contribution to the study of nuclear fuel materials with a metallic uranium base; Contribution a l'etude des materiaux combustibles nucleaires a base d'uranium metallique

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

    1957-11-15

    In a power reactor destined to supply industrially recoverable thermal energy, the most economical source of heat still consists of natural metallic uranium. However, the nuclear fuel material, most often employed in the form of rods of 20 to 40 mm diameter, is subjected to a series of stresses which lead to irreversible distortions usually incompatible with the substructure of the reactor. As a result the fuel material must possess at the outset a certain number of qualities which must be determined. Investigations have therefore been carried out, first on the technological characters peculiar to each of the three allotropic phases of pure uranium metal, and on their interactions on the stabilisation of the material which consists of either cast uranium or uranium pile-treated in the {gamma} phase. (author) [French] Dans un reacteur de puissance destine a fournir de l'energie thermique industriellement recuperable, la source de chaleur la plus economique reste constituee par de l'uranium metallique naturel. Or, le materiau combustible nucleaire, employe le plus souvent sous forme de barreaux de 20 a 40 mm de diametre, se trouve soumis a un ensemble de contraintes qui provoque des deformations irreversibles, le plus souvent incompatibles avec l'infrastructure du reacteur. Par consequent, le materiau combustible doit presenter a l'origine un certain nombre de qualites qu'il est necessaire de determiner. Aussi a-t-on d'abord etudie les caracteres technologiques propres a chacune des trois phases allotropiques de l'uranium-metal pur et leurs interactions sur la stabilisation du materiau constitue soit par de l'uranium coule, soit par de l'uranium traite en pile en phase {gamma}. (auteur)

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

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    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 la frequence

  12. Economic consequences of the Swiss 'Sortir du nucleaire' and 'Moratoire-plus' popular initiatives - Analysis using a balanced model

    International Nuclear Information System (INIS)

    Mueller, A.; Wickart, M.; Van Nieuwkoop, R.

    2001-01-01

    This article is a short version of the ENET number 210359. This report for the Swiss Federal Office of Energy (SFOE) presents the results of a study made to assess the economic consequences of two models for the opting out of nuclear energy in Switzerland, as proposed in two popular initiatives. The 'Sortir du nucleaire' (electricity without atomic power) initiative calls for the shutting down of the existing nuclear power stations and the 'Moratoire-plus' initiative calls for a stop on the building of new atomic power stations for 10 years. The method used for assessing the costs and benefits resulting if the initiatives were accepted in a public vote is described. Basic assumptions made on further factors concerning the electricity and energy markets are discussed. Results of analyses made for various scenarios with respect to CO 2 emissions are presented and include discussions on risk costs, effects on employment and welfare aspects

  13. Contribution to the study of thermal mixing between nuclear spin systems; Contribution a l'etude du melange thermique entre systemes de spins nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-02-15

    This work describes methods of dynamic nuclear polarization in solids based on the thermal mixing between nuclear spin systems. The description of the thermal mixing processes involves most of the fundamental aspects of the spin temperature theory. The experiments, conducted with paradichlorobenzene and para-dibromobenzene, yield a detailed confirmation of the theoretical predictions. (author) [French] Ce travail decrit des methodes de polarisation dynamique nucleaire dans les solides basees sur le melange thermique entre systemes de spins nucleaires. La description des processus de melange thermique met en jeu la plupart des aspects fondamentaux de la theorie de la temperature de spin. Les experiences, realisees avec du paradichlorobenzene et du paradibromobenzene, apportent une confirmation detaillee des previsions theoriques. (auteur)

  14. Front end of the nuclear fuel cycle; Amont du cycle du combustible nucleaire

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    Leroux, S.; Gueneau, C.; Le Ny, J.; Camel, D.; Drevet, B.; Granier, J.; Doneddo, F.; Roblin, P.; Van Wambeke, C.; Bouty, O.; Michel, N.; Thro, P.U.; Dupuy, P.; Farcage, D.; Schildknecht, J.; Lompre, L.A.; L' Hermite, D.; Comte, M.; Gobert, O.; De Lamare, J

    1999-07-01

    In this chapter of the DCC 1999 scientific report, the following theoretical studies are detailed: condensation and flow of a binary metallic alloy in a two phase domain, a model of gas centrifuge separative performance called TRYPHON, an estimation of electron gun cathodes erosion. It also provides technological developments and instrumentation studies: a power improvement of diode-pumped solid state lasers, measurement using intracavity near resonant propagation in atomic vapours. (A.L.B.)

  15. 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.)

  16. 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.)

  17. Nuclear magnetic resonance of iron-57 nuclei in local fields in yttrium and iron garnets; Resonance magnetique nucleaire des noyaux du fer 57 dans les champs locaux du grenat d'yttrium et de fer

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    We have demonstrated the nuclear resonance of {sup 57}Fe nuclei in the local field of each of the two magnetic sub-lattices of yttrium and iron garnets. The resonance frequencies and the relaxation times have been measured as a function of the temperature. (author) [French] Nous avons mis en evidence la resonance nucleaire des noyaux de {sup 57}Fe dans le champ local de chacun des deux sous-reseaux magnetiques du grenat d'yttrium et de fer. Les frequences de resonances et les temps de relaxation ont ete mesures en fonction de la temperature. (auteur)

  18. Contribution to the study of nuclear fuel materials with a metallic uranium base; Contribution a l'etude des materiaux combustibles nucleaires a base d'uranium metallique

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-11-15

    In a power reactor destined to supply industrially recoverable thermal energy, the most economical source of heat still consists of natural metallic uranium. However, the nuclear fuel material, most often employed in the form of rods of 20 to 40 mm diameter, is subjected to a series of stresses which lead to irreversible distortions usually incompatible with the substructure of the reactor. As a result the fuel material must possess at the outset a certain number of qualities which must be determined. Investigations have therefore been carried out, first on the technological characters peculiar to each of the three allotropic phases of pure uranium metal, and on their interactions on the stabilisation of the material which consists of either cast uranium or uranium pile-treated in the {gamma} phase. (author) [French] Dans un reacteur de puissance destine a fournir de l'energie thermique industriellement recuperable, la source de chaleur la plus economique reste constituee par de l'uranium metallique naturel. Or, le materiau combustible nucleaire, employe le plus souvent sous forme de barreaux de 20 a 40 mm de diametre, se trouve soumis a un ensemble de contraintes qui provoque des deformations irreversibles, le plus souvent incompatibles avec l'infrastructure du reacteur. Par consequent, le materiau combustible doit presenter a l'origine un certain nombre de qualites qu'il est necessaire de determiner. Aussi a-t-on d'abord etudie les caracteres technologiques propres a chacune des trois phases allotropiques de l'uranium-metal pur et leurs interactions sur la stabilisation du materiau constitue soit par de l'uranium coule, soit par de l'uranium traite en pile en phase {gamma}. (auteur)

  19. Study of the aqueous chemical treatment of uranium zirconium fuels; Etude du traitement chimique des combustibles uraniumzirconium par voie seche

    Energy Technology Data Exchange (ETDEWEB)

    Bourgeois, M; Nollet, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    A dry process has been studied for separating the uranium from the zirconium-either for recovering the enriched uranium from fuel element production waste, or with a view to treating this waste after irradiation. In this process the alloy is treated with hydrochloric acid at 400 deg. C in a fluidized corundum bed which causes the zirconium to volatilize as tetrachloride and the uranium to form the trichloride. This latter is then converted to the hexafluoride by attack with fluorure. After the laboratory tests, a first pilot plant with a capacity of 1 kg of alloy was tried out at the Fontenay-aux-Roses Nuclear Research Centre; this made it possible to fix the operational conditions for the process. An industrial scale plant was then built with the collaboration of the from Kuhlmann, and operated until a satisfactory process had been developed for treating the waste. This installation treats 3 kg/h of alloy with a yield for the hydrochloric acid of about 50 per cent and with a uranium loss in the zirconium tetrachloride of about 0.1 per cent. An active pilot plant capable of treating of treating a few kilos of irradiated alloy is now being studied. (authors) [French] On a etudie un procede de voie seche pour effectuer la separation de l'uranium et du zirconium - soit en vue de la recuperation de l'uranium enrichi contenu dans les dechets de fabrication des elements combustibles - soit en vue du traitement de ceux-ci apres irradiation. Ce procede consiste a attaquer l'alliage par l'acide chlorhydrique a 400 deg. C dans un lit fluidise de corindon, ce qui a pour effet de volatiliser le zirconium sous forme de tetrachlorure et de transformer l'uranium en trichlorure. Ce dernier est ensuite converti en hexafluorure par action du fluor. Apres des essais de laboratoire, un premier pilote a l'echelle de 1 kg d'alliage a ete experimente au Centre d'Etudes Nucleaires de Fontenay-aux-Roses et a permis de determiner les conditions operatoires du procede. En collaboration avec

  20. 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)

  1. 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

    Theoretical study of nuclear magnetic resonance in ferromagnetic metals shows the near dependence of ferromagnetic properties and unusual feature of this nuclear resonance. This results from a strong interaction between nuclei and magnetic electrons. They excite the nuclei, and, in Bloch walls, submit them to a RF field much stronger than those directly applied. The parameters of the resonance are determined from wall movement and depend consequently of ferromagnetic constants. The theory is enable to provide quantitatively some peculiar effects, specially those of a continuous magnetic field and of temperature. Experimental study was made on cobalt powders, and is in good agreement with theory. However one must take the skin-effect into consideration and accordingly adjust, the theory. This can explain some observed divergences, as well as the influence at particles size and magnetic field over the line shape. Original informations have been obtained about some typical ferromagnetic properties of cobalt, when studying magnetic field effect, and it has been able to apply this method to other ferromagnetic materials. In consideration of the peculiar characteristics of this nuclear resonance, which occurs without external magnetic field and whose line width is large, new models of spectrographs have been realized and have permitted accurate measures of the line shape. The weak intensity of the signals obtained in some cases, has induced the elaboration of an original method of extraction whose theory and practical uses are described here. The whole of this experiment reveals the nuclear resonance as a strong way for the study of ferromagnetism, which is able to detect microscopic phenomenons, not easily accessible by classical methods. (author) [French] L'etude theorique de la resonance magnetique nucleaire dans les metaux ferromagnetiques revele l'etroite liaison entre les proprietes ferromagnetiques et l'aspect inhabituel de cette resonance. Ceci resulte du

  2. Transparency associated with the nuclear fuel cycle; Transparence associee au cycle du combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This document presents the different fuel cycle stages with which the CEA is associated, the annual flow of materials and wastes produced at these different stages, and the destiny of these produced materials and wastes. These information are given for the different CEA R and D activities: experimentation hot laboratories (activities, fuel cycle stages, list of laboratories, tables giving annual flows for each of them), research reactors (types of reactors, fuel usage modes, annual flows of nuclear materials for each reactor), spent fuel management (different types of used materials), spent fuels and radioactive wastes with a foreign origin (quantities, processes)

  3. Possibilities and limitations of analogue methods for studying the dynamics of nuclear power stations; Possibilites et limitations du calcul analogique pour les etudes dynamiques de centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Caillet, C; Deat, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    'on decrit en discutant la validite des approximations choisies. 4. Les simulateurs de machines tournantes: on souligne le caractere particulier que presentent les calculs des machines tournantes en raison de la necessite ou l'on est de passer par l'intermediaire d'abaques. On propose l'utilisation d'une memoire a acces aleatoire permettant un traitement analogique de ces problemes. 5. Etude d'une centrale nucleaire: on etudie, sur un exemple, les problemes poses par l'interconnexion d'elements du type precedent pour la simulation de grands ensembles (centrales nucleaires) et on souligne le role des elements ordinaires de calcul. 6. Conclusion: on souligne la necessite pour toutes ces etudes, de disposer d'un materiel de qualite et on discute la signification des resultats ainsi obtenus. (auteur)

  4. 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)

  5. Staff Organization in Nuclear Power Stations; Organisation du personnel des centrales nucleaires; Organizatsiya personala na atomnykh ehlektrostantsiyakh; Organizacion del personal de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Scuricini, G. B. [Comitato Nazionale Energia Nucleare, Roma (Italy)

    1963-10-15

    This paper deals with the organization of operating and maintenance staff at nuclear power stations in Italy and manpower variations, either because the plants themselves differ or are organized in some special way. Staff doing jobs for which a specific training is required are given special consideration in the paper. (author) [French] Dans le memoire, on examine l'organisation du personnel d'exploitation et d'entretien des centrales nucleaires italiennes et les differences existant dans les effectifs, differences dues soit aux caracteristiques des centrales memes, soit aux particularites d'organisation des entreprises. Le personnel charge de fonctions determinees pour lesquelles un entrainement special est requis, fait l'objet d'une attention particuliere. (author) [Spanish] En la memoria se examina la organizacion del personal de explotacion y conservacion de las centrales nucleares italianas y las diferencias que existen entre sus efectivos, diferencias que se deben a las caracteristicas de las mismas centrales o a las particularidades de organizacion de las empresas. El autor dedica especial atencion al personal encargado de funciones que requieren una formacion profesional especial. (author) [Russian] Issleduyutsya voprosy organizatsii personala, zanimayushchegosya ehkspluatatsiej ital'yanskikh atomnykh ehlektrostantsij i ukhodom za nimi, a takkhe razlichiya v sostave personala, vytekayushchie libo iz kharakternykh osobennostej samikh stantsij, libo iz osobennostej organizatsii predpriyatij. Osoboe vnimanie udelyaetsya personalu, kotoromu porucheny opredelennye funktsii, trebuyushchie spetsial'noj pod go tovki. (author)

  6. 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

  7. 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)

  8. SCPRI Emergency Kit for Use in the Event of a Nuclear Accident; Le Dispositif d'Intervention Rapide du SCPRI en Cas d'Accident Nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Ervet, P.; Moroni, J. P.; Pellerin, P. [Service Central de Protection Contre les Rayonnements Ionisants, Ministere des Affaires Sociales, Le Vesinet (France)

    1969-10-15

    In the event of a nuclear accident necessitating implementation of the ORSEC radiation protection plan, the Service central de protection contre les rayonnements ionisants (Central Service for Protection against Ionizing Radiations), in conjunction with the Service national de la protection civile (National Civil Defence Service), has adopted the necessary measures for rapid evaluation of possible contamination as promptly as possible. With this aim in mind the Service has prepared emergency kits, which are permanently stored at airfields in the Paris region; these can be carried by aircraft together with two engineers from the Service, thereby enabling them to reach the site of the incident with the specialized equipment in a few hours at most. This paper describes the monitoring and sampling equipment as well as the conditions under which the kit is carried and used (it operates independently by having a built-in generating unit). It is basically designed to permit an initial assessment of the situation, to furnish local authorities with data on which to base decisions for the safety of the population, and to determine any additional measures that need to be adopted. (author) [French] Dans le cas d'un accident nucleaire impliquant la mise en application du plan ORSEC radiologique, en liaison avec le Service national de la protection civile, le Service central de protection contre les rayonnements ionisants a pris les dispositions necessaires pour faire une evaluation rapide, aussi preooce que possible, des contaminations eventuelles. Dans ce but, il a realise des cantines d'intervention qui sont deposees en permanence sur les aerodromes de la region parisienne, et peuvent etre embarquees par avion avec deux ingenieurs du service qui peuvent etre ainsi sur les lieux de l'incident, avec un materiel specialise, dans un delai qui n'excede pas quelques heures. Le memoire decrit le materiel de mesure et de prelevement, ainsi que les conditions de transport et d

  9. The pulsed neutron method applied to the determination of the nuclear constants of graphite (1961); La methode des neutrons pulses appliquee a la determination des constantes nucleaires du graphite (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    A method for determining the nuclear constants {sigma}{sub a} and {lambda}{sub t} of a moderator is described. The disappearance of a burst of neutrons introduced into a finite medium is studied as a function of time. This decrease in the thermal neutron density is the product of two exponentials; one representing the absorption, the other the leakage. By varying one or other of these factors, the constants of the factor left unvaried can be determined, and from this the nuclear constant values are deduced. (author) [French] On decrit une methode permettant de determiner les constantes nucleaires {sigma}{sub a} et {lambda}{sub t} d'un moderateur. On etudie la decroissance dans le temps d'une bouffee de neutrons introduite dans un milieu fini. Cette decroissance de la densite en neutrons thermiques est le produit de deux exponentielles; l'une represente l'absorption, l'autre les fuites. Par variation de l'un ou l'autre de ces facteurs, on determine les constantes du facteur laisse invariant dont on deduit les valeurs des constantes nucleaires. (auteur)

  10. 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

    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)

  11. Effect of cobalt-60 {gamma} radiation and of thermal neutrons on high resistance P and N silicon. Possibility of obtaining a nuclear compensation for P type silicon; Effects du rayonnement {gamma} du cobalt 60 et de neutrons thermiques sur du silicium P et N de haute resistivite. Possibilite de realiser une compensation nucleaire d'un silicium du type P

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-11-01

    Type P silicon has been compensated by the production of a controlled and uniform amount of donor atoms ({sup 31}P) using thermal neutrons to bring about a nuclear transformation. It is shown that it is possible in this way to reduce by a factor of about one hundred the overall concentration of residual ionised impurities in the purest crystals obtained by floating zone purification (2 x 10{sup 12} atoms/cm{sup 3}). The degree compensation obtained is limited by the initial inhomogeneity of acceptor impurities which have to be compensated. Lattice defects which still remain after prolonged annealings reduce the life-time of the material to about 10 {mu}s approximately. Particle detectors having thicknesses of 2 to 5 mm have been built by this process; they give good results, particularly at low temperatures. A study has also been made of the number and of the nature of lattice defects produced by thermal neutrons in high resistivity P and N type crystals. These defects have been compared to those produced by {gamma} rays from {sup 60}Co. A discussion is given of the validity of the Wertheim model concerning pronounced recombination at low temperatures (77 deg. K - 300 deg. K) of primary defect-interstitial pairs. The nature of the defects introducing energy levels into the lower half of the forbidden band has been studied. (author) [French] On a compense du silicium de type P en produisant, au moyen de neutrons thermiques, par transmutation nucleaire une quantite controlee et uniforme d'atomes donneurs ({sup 31}P). On montre qu'on peut ainsi reduire de cent fois environ la densite nette d'impuretes ionisees residuelles subsistant dans les cristaux les plus purs obtenus par purification par zone flottante (2.10{sup 12} atomes/cm{sup 3}). Le degre de compensation obtenu est limite par i'inhomogeneite initiale des impuretes acceptrices a compenser. Des defauts de reseau qui subsistent meme apres des recuits prolonges reduisent la duree de vie du materiau a 10 {mu

  12. Gas-flow detector for uranium contamination on finned-can surface of a reactor fuel; Detecteur a courant gazeux pour deceler la contamination en uranium des nervures des gaines de combustible nucleaire; Gazopotochnyj detektor zagryazneniya uranom rebristoj poverkhnosti obolochki reaktornykh teplovydelyayushchikh ehlementov; Detector de flujo gaseoso para medir la contaminacion de uranio en la superficie de la vaina de aletas de los elementos combustibles para reactores

    Energy Technology Data Exchange (ETDEWEB)

    Miwa, H; Shiojiri, T; Maeda, Y [Kobe Kogyo Corporation, Okubo, Akashi, Hyogo (Japan)

    1962-04-15

    Calder Hall-type reactor-fuel and all JRR-3 fuels are to be inspected by this counter. (author) [French] Le detecteur a courant gazeux presente par les auteurs est un compteur proportionnel a grille, specialement concu pour deceler la contamination en uranium des nervures des gaines de combustible nucleaire. Un compteur proportionnel classique, compose seulement d'une cathode et d'un collecteur, n'est guere capable de deceler les particules alpha emises par l'uranium contaminant une surface rugueuse telle que les nervures d'une gaine de combustible nucleaire, par suite du manque d'uniformite du champ electrique pres de la surface. C'est pourquoi les auteurs ont construit un compteur proportionnel a grille. Cet appareil, de forme cylindrique, comprend le combustible, une grille, des collecteurs et une cathode, tous les elements etant disposes suivant le meme axe. Le combustible est place au centre de la grille a laquelle on applique une tension negative. L'espace entre le combustible et la grille sert de collecteur d'ions. La grille, faite de fils paralleles minces en tungstene, disposes suivant un cylindre autour du combustible, est reliee a la terre. Les collecteurs sont constitues de 16 minces fils de tungstene disposes de la meme maniere que la grille, mais chaque fil est isole electriquement des autres. Tous les collecteurs sont interconnectes par des resistances de 5 x 10{sup 4} ohms et relies au positif de la haute tension par une resistance. L'espace entre la grille, les collecteurs et la cathode sert a la multiplication du gaz, tout comme dans un compteur proportionnel classique. Chaque resistance de 5 x 10{sup 4} ohms isole la capacite parasite de chaque collecteur. La sortie du detecteur est couplee a un amplificateur a faible impedance d'entree. La faible impedance d'entree diminue aussi l'influence facheuse de la capacite parasite du circuit d'entree. Il en resulte un rapport favorable signal/bruit de fond, ce qui permet une bonne detection des particules

  13. Communication Received from the Permanent Mission of Brazil regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology; Communication recue de la mission permanente du Bresil concernant les Directives de certains Etats Membres applicables a l'exportation de matieres, d'equipements et de technologie nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-12-03

    The Agency has received a Note Verbale from the Permanent Mission of Brazil, dated 22 March 2007, in which it requests that the Agency circulate to all Member States a letter of 12 December 2006 from the Chairman of the Nuclear Suppliers Group, Ambassador Jose Artur Denot Medeiros, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [French] L'Agence a recu une note verbale de la mission permanente du Bresil, en date du 22 mars 2007, lui demandant de diffuser a tous les Etats Membres une lettre du 12 decembre 2006 du president du Groupe des fournisseurs nucleaires, l'ambassadeur Artur Denot Medeiros, adressee au Directeur general au nom des gouvernements des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Chine, Chypre, Croatie, Danemark, Espagne, Estonie, Etats-Unis d'Amerique, Federation de Russie, Finlande, France, Grece, Hongrie, Irlande, Italie, Japon, Kazakhstan, Lettonie, Lituanie, Luxembourg, Malte, Norvege, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Roumanie, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovaquie, Slovenie, Suede, Suisse, Turquie et Ukraine. Cette lettre apporte des informations supplementaires sur les Directives de ces gouvernements applicables aux transferts nucleaires.

  14. The Staffing of Central Electricity Generating Board Nuclear Power Stations; Organigramme des centrales nucleaires du central electricity generating board; Politika v oblasti kadrov na atomnykh ehlektrostantsiyakh CEGB; El personal de las plantas nucleoelectricas de la central electricity generating board.

    Energy Technology Data Exchange (ETDEWEB)

    Bartlett, J. S.; Shepherd, G. T. [Central Electricity Generating Board, Western Division, Bristol (United Kingdom)

    1963-10-15

    An account is given of the staffing requirements and organization at a CEBG nuclear power station. The training of staff and licensing requirements for reactoroperating staff are discussed. Experience gained to data of the outcome of pre-operating training and detailed planning in the operational sphere is given. (author) [French] Le memoire donne un apercu de l'organigramme d'une centrale nucleaire du CEGB et des conditions auxquelles doit satisfaire le personnel (formation, qualifications requises pour la fonction d'operateur). Il rend compte egalement de l'experience acquise a ce jour quant a l'interet qu'il y a a former le personnel au prealable et a etablir des plans d'operation detailles. (author) [Spanish] La memoria informa sobre la organizacion de las centrales nucleoelectricas de la CEGB y sobre la plantilla de personal que estas requieren. Discute la formacion del personal y los requisitos para obtener la licencia de operador de reactores. Describe la experiencia adquirida hasta el presente en materia de formacion previa del personal y de organizacion detallada de las operaciones. (author) [Russian] Daetsya otchet o trebovaniyakh, pred{sup y}avlyaemykh k personalu, i organizatsiya nabora personala na atomnykh ehlektrostantsiyakh Tsentral'nogo upravleniya proizvodstva ehlektroehnergii (CEGB). Obsuzhdayutsya voprosy podgotovki personala i normativnykh trebovanij, pred{sup y}avlyaemykh k ehkspluatatsionnomu personalu. Izlagaetsya opyt, nakoplennyj k nastoyashchemu vremeni v rezul'tate osushchestvleniya predehkspluatatsionnoj podgotovki i podrobnogo planirovaniya v usloviyakh ehkspluatatsii. (author)

  15. 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 des imbrules. Le melange ThO{sub 2}, U{sub 3}O

  16. The Technical Training Programme for Nuclear Power Station Personnel; Programme de formation technique du personnel des centrales nucleaires; Programma tekhnicheskoj podgotovki personala yadernoj ehlektrostantsii; El programa de formacion tecnica del personal de una central nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Howey, G. R. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

    1963-10-15

    .), responsible for maintenance of all mechanical equipment; and (5) Service maintainers: responsible for a wide variety of less skilled tasks requiring lower qualifications. In addition to these general categories a few specialists are required, such as chemists and radiation protection officers. Organization of the NPD staff and training for future nuclear-power needs will be discussed. (author) [French] La centrale nucleaire de demonstration canadienne (NPD), creee par un organisme federal, l'Atomic Energy of Canada Limited, est exploitee par une compagnie provinciale de distribution d'electricite, la Hydro-Electric Power Commission of Ontario, qui pourvoit aussi aux besoins en personnel. Le recrutement et la formation du personnel de la centrale ont ete difficiles du fait que, recemment encore, la plupart des besoins en electricite de l'Ontario pouvaient etre satisfaits par les abondantes ressources hydro-electriques de cette province. La multiplication des centrales thermiques, depuis 1950, a cree une enorme demande de personnel. Pour faire face a cette situation, on a organise la formation de personnel pour les centrales nucleaires de la maniere suivante: a) un groupe initial d'ingenieurs a ete selectionne parmi des specialistes ayant une vaste experience des travaux dans le domaine nucleaire de l 'exploitation des centrales thermiques et de la production d'electricite; b) on a selectionne un autre groupe d'operateurs et d'agents des services d'entretien hautement qualifies; c) ces groupes ont recu une formation systematique comprenant l'exploitation de centrales nucleaires et de centrales thermiques a charbon, un enseignement theorique et pratique et des instructions donnees par les specialistes qui ont concu les plans de NPD ; d) un centre de formation nucleaire a ete cree et charge de la selection et de la formation du personnel supplementaire ainsi que de l 'organisation des examens officiels; il doit s'assurer, d'une maniere generale, de la competence du personnel

  17. 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 brai a ete effectuee. Pour les graphites issus du meme coke et fabriques

  18. Aspects chimiques de la combustion du charbon pulvérisé. Première partie Chemical Aspects of the Combustion of Pulverized Coal. Part One

    Directory of Open Access Journals (Sweden)

    De Soete G. G.

    2006-11-01

    Full Text Available II n'est pas facile de parvenir à une vue complète des multiples phénomènes chimiques dont la flamme de charbon pulvérisé est le siège. La présente étude bibliographique s'efforce de donner plus qu'une juxtaposition des données de la littérature récente, en risquant une tentative de présentation cohérente des mécanismes chimiques clés qui s'affrontent dans cette combustion. Ces mécanismes font intervenir des réactions en phase gazeuse relativement rapides (combustion des produits gazeux de pyrolyse, formation d'oxydes d'azote à partir de l'azote organique ainsi qu'un certain nombre de réactions hétérogènes très importantes (dévolatilisation pyrolysante rapide, oxydation du coke, réduction hétérogène d'oxydes d'azote qui peuvent se dérouler de façon beaucoup plus lente. En ce qui concerne ces dernières, le régime non isotherme, auquel les soumet l'existence de gradients de température dans la flamme industrielle, entraîne souvent des conséquences non négligeables pour le déroulement de ces mécanismes cinétiques complexes : ainsi la quantité et la composition des produits de pyrolyse est fortement tributaire de ces conditions non isothermes. Carrefour de plusieurs mécanismes chimiques complexes, la flamme de charbon est caractérisée chimiquement par un grand nombre de cas de compétition : a compétition entre différentes voies réactionnelles à l'intérieur d'un mécanisme donné ; à titre d'exemple typique : la pyrolyse du charbon ; b compétition entre phénomènes chimiques et physiques, également à l'intérieur d'un même mécanisme, entraînant la transition éventuellement réversible d'un régime cinétique vers un régime diffusionnel, comme c'est le cas dans l'oxydation du coke, avec des conséquences sensibles pour la vitesse réactionnelle globale et sa dépendance par rapport à la température, pouvant même aller jusqu'à l'extinction de la combustion du coke ; c compétition entre

  19. A study of filtering problems of background noise in nuclear spectrometry, improvement of signal-to-noise ratio, and of pulse characteristics produced by the optimum predictor device; Etude de problemes de filtrage de bruit de fond en spectrometrie nucleaire, amelioration du rapport signal sur bruit et des caracteristiques de l'impulsion mise en forme par le dispositif du predicteur optimum

    Energy Technology Data Exchange (ETDEWEB)

    Benda, J [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1967-05-01

    The purpose of nuclear spectrometry is the precise measurement of particles energy. The resolving power of a spectrometer design is an important factor. Two main phenomena are involved in the limitation of this resolving power: The statistical fluctuations of the detector itself, and the background noise. For a given noise, the theory of filters enables the calculation of networks specially designed for the improvement of signal to noise ratio. The proposed system should lead to an improvement of 10.5 per cent of this ratio. Experiments have confirmed this theoretical estimation. The predictor device also makes possible the obtaining of shortened pulses. (author) [French] Les mesures en spectrometrie nucleaire ont pour but la determination precise de l'energie des particules. Le pouvoir de resolution d'une chaine de spectrometrie est une caracteristique importante. Deux phenomenes principaux concourent a limiter ce pouvoir de resolution: les fluctuations statistiques du detecteur et le bruit de fond. Pour un bruit de fond donne, la theorie des filtres permet de calculer des reseaux susceptibles de modifier le rapport signal sur bruit. Le systeme propose permet d'ameliorer de 10.5 pour cent ce rapport lorsqu'on se place dans les conditions optimales. Les resultats experimentaux confirment les previsions. Le dispositif predicteur permet aussi un raccourcissement de l'impulsion dans le temps. (auteur)

  20. Combustion

    CERN Document Server

    Glassman, Irvin

    1987-01-01

    Combustion, Second Edition focuses on the underlying principles of combustion and covers topics ranging from chemical thermodynamics and flame temperatures to chemical kinetics, detonation, ignition, and oxidation characteristics of fuels. Diffusion flames, flame phenomena in premixed combustible gases, and combustion of nonvolatile fuels are also discussed. This book consists of nine chapters and begins by introducing the reader to heats of reaction and formation, free energy and the equilibrium constants, and flame temperature calculations. The next chapter explores the rates of reactio

  1. 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'influx nerveux, on peut mettre en evidence une

  2. Combustion

    CERN Document Server

    Glassman, Irvin

    2008-01-01

    Combustion Engineering, a topic generally taught at the upper undergraduate and graduate level in most mechanical engineering programs, and many chemical engineering programs, is the study of rapid energy and mass transfer usually through the common physical phenomena of flame oxidation. It covers the physics and chemistry of this process and the engineering applications-from the generation of power such as the internal combustion automobile engine to the gas turbine engine. Renewed concerns about energy efficiency and fuel costs, along with continued concerns over toxic and particulate emissions have kept the interest in this vital area of engineering high and brought about new developments in both fundamental knowledge of flame and combustion physics as well as new technologies for flame and fuel control. *New chapter on new combustion concepts and technologies, including discussion on nanotechnology as related to combustion, as well as microgravity combustion, microcombustion, and catalytic combustion-all ...

  3. Resonance quadripolaire nucleaire dans les halogenures d'actinides, ThBr 4, ThCl 4 ET UCl 4. II. Polymorphisme et transition de phase du premier ordre dans ThBr 4. Resonance du Brome dans UBr 4.

    Science.gov (United States)

    Gourdji, M.; Péneau, A.; Genet, M.; Guibé, L.

    1983-12-01

    La poursuite de recherches antérieures a permis de caractériser la résonance quadripolaire du brome dans la phase α de ThBr 4 et d'étudier la variation, en fonction de la température, entre 63 et 295 K, de la fréquence de résonance, ν Q(T), correspondante. Une première analyse des conditions expérimentales du passage de la transition α↔β à 426 C a été faite. La résonance du brome dans UBr 4 a également été observée et l'étude en fonction de la température des fréquences de résonance (il y a deux résonances distinctes pour chacun des deux isotopes du brome dans ce composé) a révélé un comportement inattendu en ce sens que les pentes dν Q/dT des courbes ν Q(T) correspondant aux deux résonances sont de signe contraire.

  4. An Appraisal of Analytical Methods for Plutonium and their Applications to the Analysis of Nuclear Materials; Evaluation des Methodes Analytiques de Dosage du Plutonium et de Leur Application a l'Analyse des Matieres Nucleaires; Otsenka analiticheskikh metodov opredeleniya plutoniya i ikh primenenie dlya analiza yadernykh materialov; Metodos Analiticos de Determinacion del Plutonio y su Empleo en el Analisis de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Milner, G. W.C.; Phillips, G. [Atomic Energy Research Establishment, Harwell, Berks. (United Kingdom)

    1966-02-15

    programmes for new nuclear fuels. (author) [French] Il existe plusieurs methodes de dosage de la teneur en plutonium des matieres nucleaires. Pour les quantites de l'ordre du milligramme, les methodes utilisables sont la spectro- photometiie differentielle fondee sur la couleur de Pu (III), la gravimetrie fondee sur PuO{sub 2}, le comptage gamma et les methodes de reduction/oxydation comprenant les titrages poientiometriques et amperemetriques et la coulombmetrie a potentiel constant. Pour les quantites de Tordre du microgramme, le comptage alpha, la dilution isotopique et les methodes polarigraphiques sont a utiliser. Certaines methodes conviennent mieux que d'autres a des types determines d'echantillons et l'analyste soucieux d'obtenir les meilleurs resultats se heurte a un choix difficile. Les auteurs exposent les avantages et les inconvenients des methodes citees tels qu'ils se sont degages de l'experience acquise au cours des annees a l'Atomic Energy Research Establishment, et ils discutent l'exactitude, la precision, la sensibilite de ces methodes, et d'autres caracteristiques presentant un interet particulier. Certaines methodes ne peuvent etre utilisees si l'on n'a, dans une certaine mesure, separe le plutonium des autres constituants de l'echantillon et le memoire commente l'experience acquise avec l'echange d'anions et les procedes de chromatographie a phase inversee utilises a cette fin, en insistant surtout sur la mesure dans laquelle cette methode convient aux echantillons radioactifs. Les auteurs etudient en outre les nombreux problemes qui se sont poses lors de l'application (d'ailleurs couronnee de succes) de ces methodes a l'analyse des alliages de plutonium, des ceramiques et des cermets dans differentes combinaisons contenant de l'uranium, du thorium, du fer, du chrome, du molybdene, du cerium et du cobalt. Us exposent les difficultes de la dissolution des echantillons et de la reduction du plutonium a l'etat de valence voulu, ainsi que les avantages

  5. Combustion

    CERN Document Server

    Glassman, Irvin

    1997-01-01

    This Third Edition of Glassman's classic text clearly defines the role of chemistry, physics, and fluid mechanics as applied to the complex topic of combustion. Glassman's insightful introductory text emphasizes underlying physical and chemical principles, and encompasses engine technology, fire safety, materials synthesis, detonation phenomena, hydrocarbon fuel oxidation mechanisms, and environmental considerations. Combustion has been rewritten to integrate the text, figures, and appendixes, detailing available combustion codes, making it not only an excellent introductory text but also an important reference source for professionals in the field. Key Features * Explains complex combustion phenomena with physical insight rather than extensive mathematics * Clarifies postulates in the text using extensive computational results in figures * Lists modern combustion programs indicating usage and availability * Relates combustion concepts to practical applications.

  6. Study of the tributyl phosphate - 30% dodecane solvent; Etude du solvant phosphate tributylique - 30 % dodecane

    Energy Technology Data Exchange (ETDEWEB)

    Leroy, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses. Centre d' Etudes Nucleaires, 92 (France)

    1967-07-01

    This study, originating mainly from a literature survey, gives the principal chemical and physical features of the tributyl-phosphate (TBP) agent diluted at 30 volumes per cent in dodecane. The mixture is a very commonly used extractant in nuclear fuel processing. In this paper, the main following points are reported: -) the components (TBP and diluents) -) the TBP-diluents systems (non-loaded), -) the TBP-diluents-water systems, -) TBP-diluents-water-nitric acid systems, and -) industrial solvents. (author) [French] Cette etude, d'origine bibliographique, regroupe les caracteristiques physico-chimiques essentielles du phosphate tributylique (TBP) dilue a 30% en volume dans du dodecane. Ce melange constitue un agent d'extraction tres utilise dans le traitement des combustibles nucleaires. Les principaux points traites sont les suivants: -) les constituants (TBP et diluants), -) les systemes TBP-diluants non charges, -) les systemes TBP-diluants-eau, -) les systemes TBP-diluants-eau-acide nitrique, et -) les solvants industriels. (auteur)

  7. Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

    1966-02-15

    insurance programme. (author) [French] L'uranium, combustible relativement nouveau et extremement interessant pour la production d'electricite, doit faire l'objet d'un controle tres strict depuis le moment ou l'exploitant de la centrale en devient financierement responsable jusqu'a celui oti, sous forme de combustible partiellement epuise, la matiere est transferee dans une autre installation et oti l'on recupere ce qui reste de sa valeur initiale. La plupart des exploitants de centrales nucleaires dirigeaient des centrales alimentees par des combustibles fossiles avant l'avenement de l'energie nucleaire et ils ont etabli depuis longtemps un controle etendu et efficace de ces combustibles fossiles. L'exploitant d'une centrale nucleaire doit exercer un controle non moins efficace sur les matieres nucleaires speciales utilisees dans son installation. La technique de l'exploitation des centrales nucleaires n'est pas ancienne et, au cours de, son existence relativement breve, les ingenieurs et hommes de science des Etats-Unis ont constamment ameliore les plans des centrales et les methodes d'exploitation afin de reduire les couts et de permettre aux centrales nucleaires de concurrencer les centrales classiques. La gestion des matieres nucleaires doit etre aussi moderne et efficace que possible pour assurer que les progres technologiques grace auxquels les prix on pu etre reduits ne soient pas mis en echec par des insuffisances dans la manipulation du combustible nucleaire et la tenue de la comptabilite des stocks. Pour assurer la gestion des matieres nucleaires, il faut que l'exploitant de la centrale etablisse et tienne a jour une comptabilite complete et detaillee, sans etre necessairement complexe pour autant; en fait, la simplicite est extremement souhaitable. Bien que le combustible nucleaire soit nouveau et qu'il n'ait rien de commun avec les combustibles classiques, aucun secret ne doit s'y attacher. Le controle des matieres nucleaires dans le cadre de la gestion des

  8. Dosage of plutonium by isotopic dilution in irradiated fuels; Dosage du plutonium par dilution isotopique dans les combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    Plutonium determination in irradiated fuels has been carried out for several years by isotopic dilution by Sebaci and SSM in collaboration. SECACI has made available to the SSM the necessary space and equipment in its Fontenay laboratories. This work has shown the importance of the valency cycle which should make it possible to obtain a uniform isotopic distribution in sample tracer mixtures, and also a satisfactory U/Pu separation. Now it has been noticed that the presence of an excess of uranium considerably modifies the oxidation-reduction reaction kinetics of the plutonium. We have therefore been led to change certain parts of the operational technique so as to have an efficient cycle and to thereby improve the U/Pu separation; the stability of the thermionic emission of the plutonium, connected to the quantity of residual uranium, has at the same time been improved and we can now carry out more precise isotopic analyses. We have also tried to eliminate as far as possible the isotopic contaminations by:using a more rational operational method; the equipment used has been the object of a special study. The evaporations are carried out so as to prevent the formation of saturated vapours inside the glove box. The material which cannot be changed after each operation is carefully cleaned every time a new sample is treated. With this technique, a second calibration of the tracer T{sub 2} has been undertaken using a new standard solution. This solution has been prepared very carefully by weighing uranium and plutonium of known chemical purity, and we believe that it can be guaranteed to be a good reference solution. The value of the {sup 233}U/{sup 242}Pu ratio of the tracer has been obtained with a relative accuracy of 0,5 per cent. This modified method is now being applied to the analysis of rods irradiated in G-3. (author) [French] La determination du plutonium par dilution isotopique dans les combustibles irradies est pratiquee depuis plusieurs annees en

  9. 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.)

  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. 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.

  12. 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.)

  13. Communications of 15 November 1999 Received from Member States Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material; Communications En Date Du 15 Novembre 1999 Recues D'Etats Membres Concernant L'Exportation De Matieres Nucleaires Et De Certaines Categories D'Equipements Et D'Autres Matieres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-15

    The Director General of the International Atomic Energy Agency has received letters of 17 October 1996 from the Resident Representatives of Argentina, Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, the Netherlands, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, the United Kingdom, and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material [French] Le Directeur general de l'Agence internationale de l'energie atomique a recu des lettres datees du 15 novembre 1999 que les representants permanents des pays suivants lui ont adressees au sujet de l'exportation de matieres nucleaires et de certaines categories d'equipements et d'autres matieres : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belgique, Bulgarie, Canada, Coree (Republique de), Danemark, Espagne, Etats-Unis d'Amerique, Finlande, France, Grece, Hongrie, Irlande, Italie, Japon, Luxembourg, Norvege, Pays-Bas, Pologne, Portugal, Republique slovaque, Republique tcheque, Roumanie, Royaume-Uni, Suede, Suisse, Turquie et Ukraine.

  14. Evolution of nuclear chemical industry in France; Evolution de l'industrie chimique nucleaire en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    'impulsion du CEA, mais aussi de maitres d'oeuvres tels qu'Electricite de France et la Marine Marchande, l'effort nucleaire fran is atteint pour les annees 1957-1961, environ 600 milliards de francs: plus de la moitie de cette somme sera depensee par l'industrie chimique en recherches, installations pilotes, constructions d'usines et livraisons. Faire bien, vite et rentable sont les buts recherches. Ces objectifs sont atteints grace a une collaboration intime des grands services de l'etat et de l'industrie privee. Ce gros effort s'exerce principalement dans les voies suivantes: - Un traitement chimique pousse de tonnages croissants des minerais de l'Union fran ise, visant a produire un uranium pur, abondant et bon marche. - Une preparation soigneuse de combustibles nucleaires economiques et parfaitement adaptes aux divers types de reacteurs en fonctionnement ou en construction. - Un retraitement des combustibles irradies pour en extraire le plutonium de facon complete ainsi que l'uranium et certains produits de fission. - Une fabrication industrielle des materiaux nucleairement purs ou resistants a la corrosion exiges par la technologie des reacteurs producteurs d'energie et de recherches. - La fourniture aux multiples utilisateurs etrangers et fran is d'isotopes et de traceurs radioactifs reclames par la medecine, l'industrie et l'agriculture en nombre toujours croissant. - Un traitement chimique meticuleux des effluents gazeux ou liquides dans des stations au controle rigoureux afin de rendre les reacteurs et leurs annexes parfaitement surs d'emploi. Cet expose aura montre l'ampleur de l'effort deploye par une industrie chimique nucleaire jeune, dynamique et en plein essor. Ayant assure ses techniques, realise de nombreuses installations, elle est largement en etat de faire face au programme atomique fran is. En outre, elle est capable et desireuse d'etre associee aux developpements de l'industrie atomique etrangere notamment dans te cadre de l'Euratom et d

  15. 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

  16. Burnup determination of power reactor fuel elements by gamma spectrometry; Determination par spectrometrie {gamma} du taux d'irradiation des elements combustibles des reacteurs de puissance

    Energy Technology Data Exchange (ETDEWEB)

    Robin, M; Jastrzeb, M; Boisliveau, S; Boyer, R; Vidal, R [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-07-01

    This report describes a method for determining by {gamma} spectrometry the burn up and the specific power of fuel elements irradiated in power reactors. The energy spectrum of {gamma} rays emitted by fission products is measured by means of a simple equipment using a sodium iodide detector and a multichannel analyzer. In order to extract from the spectrum a quantity proportional to the burn up, it is necessary to: - isolate an activity specific of one emitter,- give the same importance to fissions in uranium and plutonium - take into account the radioactive decay during and after irradiation. One hundred fuel elements were studied and burn up values obtained by {gamma} spectrometry are compared to results given by chemical analyses. Preliminary measurements show that the accuracy of the results is greatly increased by the use of a germanium detector, due to its good resolution. (authors) [French] Ce rapport expose une methode de determination par spectrometrie {gamma} du taux d'irradiation et de la puissance specifique des elements combustibles irradies dans les reacteurs de puissance. Une installation simple utilisant un detecteur d'iodure de sodium et un selecteur multicanaux mesure le spectre en energie du rayonnement {gamma} emis par les produits de fission. Afin d'extraire du spectre une quantite proportionnelle au taux de combustion, il faut: - isoler une activite specifique a un emetteur, - donner la meme importance aux fissions survenues dans l'uranium et le plutonium, - prendre en compte la decroissance radioactive pendant et apres l'irradiation. Les mesures ont porte sur une centaine d'elements combustibles et les taux de combustion obtenus par spectrometrie {gamma} sont compares aux resultats des analyses chimiques. Des mesures preliminaires montrent que l'utilisation d'un detecteur de germanium augmente considerablement la precision des resultats, en raison de son excellente resolution. (auteurs)

  17. Piles used for the nuclear control of materials; Empilements pour le controle nucleaire des materiaux

    Energy Technology Data Exchange (ETDEWEB)

    Raievski, V; Sautiez, B; Bailly du Bois, B; Tretiakoff, O; Thome, P; Vidal, R; Koppel Martelly, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The devices which make it possible to check on the nuclear qualities of the materials used in reactor construction are described. These verifications bear on substantial masses of materials, following the last stage of their machining. The components found in all these are a graphite pile into which the material to be investigated is inserted, a source of neutrons made up of an Ra-Be system, and a proportional BF{sub 3} counter. The devices described here bear on checking graphite, beryllium oxide and uranium absorption, as well as on a verification of the {sup 235}U content of fuel elements. (author)Fren. [French] On decrit des dispositifs permettant de controler les qualites nucleaires de materiaux utilises dans la construction des piles. Ce controle s'effectue sur des masses importantes de materiaux apres la phase finale d'usinage. Ces dispositifs ont en commun un empilement de graphite recevant le materiau a etudier, une source de neutrons de Ra-Be et un compteur proportionnel a BF{sub 3}. Les dispositifs decrits concernent le controle de l'absorption du graphite, de la glucine et de l'uranium, ainsi que le controle de la teneur en {sup 235}U des elements de combustion. (auteur)

  18. The reprocessing of irradiated fuels improvement and extension of the solvent extraction process; Le traitement des combustibles irradies amelioration et extension du procede utilisant les solvants

    Energy Technology Data Exchange (ETDEWEB)

    Faugeras, P; Chesne, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    Improvements made in the conventional tri-butylphosphate process are described, in particular. the concentration and the purification of plutonium by one extraction cycle using tri-butyl-phosphate with reflux; and the use of an apparatus working continuously for precipitating plutonium oxalate, for calcining the oxalate, and for fluorinating the oxide. The modifications proposed for the treatment of irradiated uranium - molybdenum alloys are described, in particular, the dissolution of the fuel, and the concentration of the fission product solutions. The solvent extraction treatment is used also for the plutonium fuels utilized for the fast breeder reactor (Rapsodie) An outline of the process is presented and discussed, as well as the first experimental results and the plans for a pilot plant having a capacity of 1 kg/day. The possible use of tn-lauryl-amine in the plutonium purification cycle is now under consideration for the processing plant at La Hague. The flowsheet for this process and its performance are presented. The possibility of vitrification is considered for the final treatment of the concentrated radioactive wastes from the Marcoule (irradiated uranium) and La Hague (irradiated uranium-molybdenum) Centers. Three possible processes are described and discussed, as well as the results obtained from the operation of the corresponding experimental units using tracers. (authors) [French] On decrit les ameliorations apportees au procede classique utilisant le phosphate tributylique, et notamment la concentration et la purification du plutonium par un cycle d'extraction au tributylphosphate avec reflux, l'utilisation d'un appareillage continu de precipitation d'oxalate de plutonium, de calcination de l'oxalate, et de fluoration de l'oxyde. On presente les modifications envisagees pour le traitement des alliages uranium-molybdene irradies, principalement en ce qui concerne la dissolution du combustible et la concentration des solutions de produits de fission

  19. Technique of nuclear reactors controls; Technique des controles des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-12-15

    This report deal about 'Techniques of control of the nuclear reactors' in the goal to achieve the control of natural uranium reactors and especially the one of Saclay. This work is mainly about the measurement into nuclear parameters and go further in the measurement of thermodynamic variables,etc... putting in relief the new features required on behalf of the detectors because of their use in the thermal neutrons flux. In the domain of nuclear measurement, we indicate the realizations and the results obtained with thermal neutron detectors and for the measurement of ionizations currents. We also treat the technical problem of the start-up of a reactor and of the reactivity measurement. We give the necessary details for the comprehension of all essential diagrams and plans put on, in particular, for the reactor of Saclay. (author) [French] Nous avons aborde le probleme de la ''Technique du Controle des reacteurs nucleaires'' dans le but de realiser le controle du reacteur de Saclay. C'est ainsi que nous avons ete amene a etudier le probleme dans son ensemble, tel qu'il se pose pour tout reacteur a uranium naturel. Ce travail traite principalement du domaine des mesures a caractere nucleaire et s'etend dans le domaine des mesures thermodynamque de niveaux, etc... mettant en relief les caracteristiques nouvelles exigees de la part des detecteurs du fait de leur utilisation dans le flux de neutrons thermiques. Dans le domaine de mesures nucleaires, nous indiquons principalement les realisations et les resultats obtenus pour les detecteurs de neutrons thermiques et pour la mesure de courants d'ionisations. Nous traitons egalement du probleme technique du demarrage d'un reacteur et du probleme de la mesure de la reactivite. Nous donnons les details necessaires a la comrehension de tous les schemas et plans de cablages essentiels mis au point, en particulier, pour le reacteur de Saclay. (auteur)

  20. Determining a pool - type reactor fuel policy; Recherche d'une politique de gestion du combustible d'une pile piscine

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-07-01

    Refuelling the 10 to 15 MW pool type reactor considered here will occur frequently (some 10 elements every 3 to 4 weeks). It is therefore necessary to determine the most economic fuel policy. This study proposes to define a strategy that will make it possible to decide on the number and characteristics of the shipment containers, as well as on the means of storage, so as to reduce the risks as much as possible should the basic parameters of the study vary. Among these parameters, the respective influence of which is investigated, chemical reprocessing costs play a vital part. Two examples of optimum fuel management are given according to whether the reprocessing charges applied are those of the old or of the 1961 U.S. AEC base charges for reprocessing highly enriched irradiated fuel. (authors) [French] Les renouvellements du combustible de la pile piscine de 10 a 15 MW consideree ici, seront frequents (quelques 10 elements toutes les 3 ou 4 semaines). Il est donc important de connaitre les meilleures conditions de gestion economique de ce combustible. Cette etude se propose de definir une strategie permettant de choisir le nombre et les caracteristiques des containers de transport, ainsi que les moyens de stockage, de facon a minimiser les risques si les parametres de base de l'etude varient. Parmi ces parametres dont l'influence respective est successivement examinee, le cout du traitement chimique joue un role fondamental. Deux exemples d'optimum de gestion sont donnes selon que le tarif de retraitement est conforme a l'ancien tarif de l'U.S. AEC ou au tarif 1961 de traitement des combustibles irradies tres enrichis. (auteurs)

  1. Professional Nuclear Materials Management; Gestion Industrielle des Matieres Nucleaires; Obrashchenie s yadernymi materialami na professional'nom urovne; Administracion Eficiente de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Forcella, A. A.; O' Leary, W. J. [Allis-Chalmers Manufacturing Company, Bethesda, MD (United States)

    1966-02-15

    . (author) [French] Le memoire expose en quoi consiste la gestion des matieres nucleaires dans une centrale nucleaire type, aux Etats-Unis. Comme le reacteur en question est partiellement finance a l'aide de capitaux prives, l'une des principales obligations de l'exploitant est d'assurer la protection et la rentabilite des investissements. Etant donne que les matieres nucleaires sont d'une valeur intrinseque elevee, il faut constamment proceder a des controles appropries allant au-dela des mesures de securite et de la comptabilite interessant les matieresnucleaires proprement dites afin de reduire les pertes au minimum. Il faut faire preuve de clairvoyance et planifier judicieusement pour prevenir toute perte supplementaire de capital provenant de frais inutiles ou d'un manque a gagner dans divers secteurs de l'exploitation. C'est ainsi que le gestionnaire de matieres nucleaires doit prendre des dispositions pour garantir la bonne marche des operations et assurer le respect des plans d'execution par une liaison et un controle constants, dans les domaines suivants? a) acquisition du combustible et des elements combustibles, b) utilisation des elements combustibles dans le reacteur et c) recuperation, dans le combustible irradie, des produits et matieres presentant de l'interet. Pendant la periode qui precede l'utilisation du reacteur, il faut faire une place importante dans la planification et les travaux preparatoires aux considerations d'economie dans la conception des elements combustibles, en ce qui concerne leur fabrication, leur manutention, leur transport et leur remplacement. Les differentes etapes de la fabrication doivent etre planifiees de facon a reduire au minimum le manque a gagner du a des periodes improductives d'entreposage de matieres tres couteuses. Pendant la marche du reacteur, il faut assurer une combustion maximale de la matiere fissile par des redistributions appropriees du combustible dans le coeur du reacteur. Parallelement, les temps morts dus a

  2. France's nuclear power programme; Le programme nucleaire francais

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    -increasing importance, by using the country's resources of natural uranium, and later plutonium, to the best ends. (authors) [French] Les perspectives d'evolution de la consommation d'energie electrique francaise confirment l'aggravation du deficit des ressources energetiques metropolitaines. Les centrales nucleaires doivent permettre de diminuer ce deficit si un certain nombre d'incertitudes actuelles sont levees. Le premier programme presente par MM AILLERET et TARANGER a la Conference de Geneve en 1955 visait la mise en service pour 1965 de 850 MWe; il a ete consacre au developpement de la filiere uranium naturel - graphite - gaz et s'acheve avec la realisation d'EDF 3, premiere unite capable de 500 MWe engagee dans le monde. Avant de passer du stade des prototypes a celui des duplications, ELECTRICITE DE FRANCE a decide, en accord avec le COMMISSARIAT A L'ENERGIE ATOMIQUE, la realisation d'EDF 4 qui, en reprenant la partie reacteur d'EDF 3 ainsi que l'appareil de chargement et de dechargement, l'ensemble de controle et divers materiels, apporte une innovation importante en incorporant les echangeurs et les soufflantes a l'interieur du caisson en beton precontraint contenant le coeur. En meme temps, les etudes se poursuivent dans cette meme filiere et laissent entrevoir les possibilites d'utiliser un nouvel element combustible annulaire dont l'emploi ameliorerait notablement les performances d'EDF 5. Dans la filiere eau lourde, la realisation d'EL 4 a Brennilis par le COMMISSARIAT A L'ENERGIE ATOMIQUE et ELECTRICITE DE FRANCE se poursuit. Les etudes d'un reacteur de 500 MWe de cette filiere ont deja commence. Dans la filiere a eau pressurisee, la centrale de CHOOZ est realisee en association par ELECTRICITE DE FRANCE et les Producteurs Belges. Enfin, le COMMISSARIAT A L'ENERGIE ATOMIQUE poursuit a Cadarache la realisation du surgenerateur 'Rapsodie' et les etudes d'un reacteur de puissance plus important. Ainsi, les connaissances techniques et economiques acquises dans ces diverses

  3. Mixture preparation and combustion in an optically-accessible HCCI, diesel engine; La preparation du melange et de la combustion dans un moteur Diesel, HCCI a acces optique

    Energy Technology Data Exchange (ETDEWEB)

    Kashdan, J.; Bruneaux, G. [Institut Francais du Petrole, 92 - Rueil-Malmaison (France)

    2006-07-01

    Planar laser-induced fluorescence (LIF) imaging techniques have been applied in order to study the mixture preparation and combustion process in a single cylinder, optically-accessible homogeneous charge, compression ignition (HCCI) engine. In particular, the influence of piston bowl geometry on the in-cylinder mixture distribution and subsequent combustion process has been investigated. A new optically-accessible piston design enabled the application of LIF diagnostics directly within the combustion chamber bowl. Firstly, laser-induced exciplex fluorescence (LIEF) was exploited in order to characterise the in-cylinder fuel spray and vapour distribution. Subsequently a detailed study of the two-stage HCCI combustion process was conducted by a combination of direct chemiluminescence imaging, laser-induced fluorescence (LIF) of the intermediate species formaldehyde (CH{sub 2}O) which is present during the cool flame and LIF of the OH radical which is subsequently present in the reaction and burned gas zones at higher temperature. Finally, spectrometry measurements were performed with the objective of determining the origin of the emitting species of the chemiluminescence signal. The experiments were performed on a single cylinder optical engine equipped with a direct-injection, common rail injection system and narrow angle injector. The experimental results presented reveal the significant role of the combustion chamber geometry on the mixture preparation and combustion characteristics for late HCCI injection strategies particularly in such cases where liquid impingement is unavoidable. Planar LIF 355 imaging revealed the presence of the intermediate species formaldehyde allowing the temporal and spatial detection of auto-ignition precursors prior to the signal observed by chemiluminescence in the early stages of the cool flame. Formaldehyde was then rapidly consumed at the start of main combustion which was marked not only by the increase in the main heat release

  4. 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)

  5. 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.

  6. Mechanics and electronics as auxiliary techniques in nuclear research and exploitation; Mecanique et electronique auxiliaires de la recherche et de l'exploitation nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Weill, J. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre d' Etudes nucleaires de Saclay, Departement Electronique, Groupe Controle des Reacteurs (France)

    1959-07-01

    Electronics and mechanics form the basic techniques used in the field of measurement and control in nuclear physics experiments, and in nuclear machine installations. The delegate describes some instruments typical of the use of these techniques in the fields of calculation, detection, amplification and nuclear Installations. Reprint of a paper published in 'Bulletin S.F.M.' n. 25 (3. quarter 1957) [French] L'electronique et la mecanique constituent les techniques de base utilisees clans le domaine des mesures et du controle effectues dans les experiences de physique nucleaire et dans les installations des engins nucleaires. Le Conferencier decrit plusieurs appareils caracteristiques de l'emploi de ces techniques dans les domaines du calcul, des detecteurs, de l'amplification et des lnstallations nucleaires. Reproduction d'un article publie dans le 'Bulletin S.F.M.' n. 25 (3e trimestre 1957)

  7. Dosage of fission products in irradiated fuel treatment effluents (radio-chemical method); Dosage des produits de fission dans les effluents du traitement des combustibles irradies (methode radiochimique)

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-07-01

    The dosage methods presented here are applicable to relatively long-lived fission products present in the effluents resulting from irradiated fuel treatment processes (Sr - Cs - Ce - Zr - Nb - Ru - I). The methods are based on the same principle: - addition of a carrying-over agent - chemical separation over several purification stages, - determination of the chemical yield by calorimetry - counting of an aliquot liquid portion. (author) [French] Les methodes de dosage presentees concernent les produits de fission a vie relativement longue presents dans les effluents de traitement des combustibles irradies (Sr - Cs - Ce - Zr - Nb - Ru - I). Elles sont toutes basees sur le meme principe: - addition d'entraineur, - separation chimique en plusieurs stades de purification, - determination du rendement chimique par calorimetrie, - comptage d'une aliquote liquide. (auteur)

  8. Natural gas combustion and indoor air quality in domestic premises; Combustion du gaz naturel et qualite de l'air a l'interieur des habitations

    Energy Technology Data Exchange (ETDEWEB)

    Occhio, L.; Riva, A. [Snam, (Italy); Canci, F.; Scevarolli, V. [Italgas, Torino (Italy)

    2000-07-01

    Indoor air quality depends on many factors; combustion appliances are one of the sources of emissions inside dwellings. Their installation is regulated by UNI-CIG standards which also establish the ventilation and aeration requirements needed to guarantee the safety and healthiness of the environment. In order to critically evaluate the effect on indoor air quality of using gas appliances under different operational regimes and in different types of building, Snam and Italgas have developed a research project in co-operation with Enitecnologie and Turin Polytechnic, even to provide theoretical and experimental support for standardisation activities. The results of the presented research include experimental measurements made in real buildings, mathematical modelling and analysis of Italian and international literature. The results show that use of combustion appliances has little influence on indoor air quality and does not affect people's health. (authors)

  9. Experimental and numerical study of the active control of jets inside combustion chambers; Etude experimentale et numerique du controle actif de jets dans des chambres de combustion

    Energy Technology Data Exchange (ETDEWEB)

    Faivre, V

    2003-12-15

    Combustion instabilities occur when the flame heat release couples with the acoustic waves propagating in the combustion chamber. This phenomenon can lead to strong vibrations and noise but also, sometimes, to the complete combustion device failure. That is the reason why so many studies focus on the control of those instabilities. The method chosen in this study consists in an active control device (or set of actuators) having a strong effect on the mixing of the burner exhaust flow with the ambient fluid. The model configuration studied consists in a non reactive jet of air controlled by four small tangential secondary jets. Experiments have been carried out to optimize the control device geometry. The configuration identified as the most efficient, in terms of mixing enhancement, has been simulated through Large Eddy Simulations (LES). The objective of the numerical part of the present work is double. First, the numerical simulations provide a better understanding of the phenomena occurring when the control is on. Then, it is shown that LES can be considered as a tool to predict the effects of a control device on a flow. (author)

  10. Review of safety precautions derived from six-year experience of a spent fuel reprocessing plant - Centre de Marcoule; Elements de securite tires de six annees d'exploitation de l'usine de traitement de combustibles irradies du Centre de Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1964-07-01

    an organization of the work aimed at eliminating the causes of incidents. They investigate the following points in particular: - frequency of entry into forbidden zones during normal functioning - the distribution of exceptional tasks - the prevention of criticality risks - zone contamination incidents - the volume and nature of decontaminated material and eliminated residues - the evolution and distribution of external irradiation doses received by the workers - the frequency of cases of body contamination - internal contamination fixed in the organisms of workers. Conclusions are drawn from the different incidents which have occurred during the years of operating the plant. (author) [French] Dans une usine de traitement de combustibles irradies comme dans toute autre usine, la continuite de la production ne peut etre obtenue que par une recherche constante de la securite. Les auteurs examinent les elements de securite apportes par la conception des installations tant au point de vue de la securite classique que de la securite radiologique. Dans l'industrie nucleaire, il ne suffit pas, en effet, d'adopter seulement les precautions habituelles prises contre les risques d'explosion, d'incendie...; il faut aussi apporter beaucoup d'attention aux problemes poses par le confinement des matieres, la radioactivite et les risques de criticite. Les principes generaux de la prevention technique contre les risques radioactifs sont maintenant bien connus. Leur application doit se traduire des la conception des installations par des dispositions concernant: - la conception et la realisation des installations vis-a-vis des risques deja enumeres, - la division de l'usine en zones, - la circulation du personnel et du materiel, - la ventilation et l'epuration de l'air. Les facteurs techniques de securite ne sont toutefois pas suffisants a eux seuls. Quelle que soit la qualite du materiel et le degre d'automatisme atteint, la continuite de fonctionnement d'une usine implique l

  11. The Text of the Agreement between Belgium, Denmark, the Federal Republic of Germany, Ireland, Italy, Luxembourg, The Netherlands, the European Atomic Energy Community and the Agency in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons; Texte de l'Accord entre la Belgique, le Danemark, la Republique Federale d' Allemagne, l'Irlande, l'Italie, le Luxembourg, les Pays-Bas, la Communaute Europeenne de l'En-Ergie Atomique et L'Agence En Application Du Traite Sur La Non-Proliferation Des Armes Nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-09-14

    The text of the Agreement, and of the Protocol thereto, between Belgium, Denmark, the Federal Republic of Germany, Ireland, Italy, Luxembourg, The Netherlands, the European Atomic Energy Community and the Agency in implementation of Article III (1) and (4) of the Treaty on the Non-Proliferation of Nuclear Weapons (reproduced in document INFCIRC/140) is reproduced in this document for the information of all Members [French] Le texte de l'Accord, ainsi que celui du Protocole qui y est joint, entre la Belgique, le Danemark, la Republique fdrale d'Allemae, l'Irlande, l'Italie, le Luxembourg, les Pays-Bas, la Communaute europenne de l'energie atomique et l'Agence condu en application des paragraphes 1 et 4 de l'article III du Traite sur la non proliferation des armes nucleaires sont reproduits dans le present document pour l'information de tous les Membres.

  12. Nuclear explosion and internal contamination; Explosion nucleaire et contamination interne

    Energy Technology Data Exchange (ETDEWEB)

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

    1956-07-01

    By the study of the conditions of internal contamination due to the radioactive mixture produced by a nuclear explosion, the parts played by the relative weights of the different elements and the mode of expression of the doses are considered. Only the knowledge of the weight composition of the contamination mixture and of its evolution as a function of time can provide the required basis for the study of its metabolism in the organism. The curves which give the composition of the fission product mixture - in number of nuclei - - as a function of time - have been established. These curves are applied to some practical examples, particularly relative to the nature of contamination, radiotoxicity of some elements and assessment of hazards. (author) [French] Etudiant les modalites de la contamination interne par les elements radioactifs apparus lors d'une explosion nucleaire, le role de la 'masse' et le mode d'expression des doses sont envisages. La connaissance de la composition en 'masse' du melange contaminant et de son evolution en fonction du temps peut seule apporter les bases necessaires a l'etude de son comportement dans l'organisme. Les courbes donnant la composition du melange de produits de fission - en nombre de noyaux - - en fonction du temps - ont ete etablies. Quelques applications pratiques, relatives en particulier a la nature de la contamination, a la radiotoxicite de certains elements et a l'evaluation de risque, sont envisagees a titre d'exemple. (auteur)

  13. The formation of scientists and technicians at the 'Centre d'Etudes Nucleaires' at Saclay; Formation des scientifiques et des techniciens au Centre d'Etudes Nucleaires de Saclay

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The considerable needs in research workers and scientists which are asked by the nuclear energy obliged the Commissariat a l'Energie atomique to deal with a particular effort to increase the quantitative and qualitative formation of scientists. Most various ways have been used. 1- A National Institute of Nuclear Sciences and Nuclear Techniques was created, by a joint decree of the Prime Minister and the Minister for National Education (june 18, 1957). This Institute of Higher Teaching (250 students) indulges in the following matters: atomic engineering, quantum mechanics, theory and technic of particle accelerators, special metallurgy, radiobiology, thermic and mechanics of fluids. 2- An associated centre of the 'Conservatoire National des Arts et Metiers' waeated (200 students) for technical assistants, drawers, etc. 3- In contribution with both electronic industry and Ministry of Work, the Centre d'Etudes Nucleaires contributes to an accelerated formation of technical assistants into Professional Centres. Conclusion: Training of scientists and research workers is one of the most important activities of the Centre d'Etudes Nucleaires de Saclay. Without losing its technical efficiency, it has supplied and varied means adapted to the various purposes that we shall reach. (author)Fren. [French] Les besoins considerables actuels et previsibles en chercheurs et scientifiques necessites par l'avevement de l'energie nucleaire imposaient au Commissariat a I'Energie atomique un effort particulier pour augmenter la formation quantitative et qualitative des scientifiques. Les moyens les plus divers ont ete mis en oeuvre: 1- Creation de l'Institut National des Sciences et Techniques Nucleaires par decret de la Presidence du Conseil et de l'Education Nationale en date du 18.6.57. Cet Institut d'Enseignement Superieur (250 etudiants) donne des cours en: genie atomique, mecanique quantique, theorie et technique des Accelerateurs de particules, metallurgie speciale, radiobiologie

  14. Application de l'A.D.L, pour la mesure du champ de vitesses instationnaires de llecoulement a Ilechappement d'un moteur a combustion interne

    Science.gov (United States)

    Boutrif, M. S.; Thelliez, M.

    1993-01-01

    We present experimental results of instantaneous velocity measurement, which were obtained by application of the laser Doppler anemometry (L.D.A.) at the exhaust pipe of a reciprocating engine under real working conditions. First of all, we show that the instantaneous velocity is monodimensional along a straight exhaust pipe, and that the boundary layer develops within a 2mm thickness. We also show that the cylinder discharges in two phases : the blow down period and the final part of exhaust stroke. We also make obvious, that the flow escapes very quickly : its velocity varies between - 100m/s and 200m/s within a period shorter than 1ms ; thereby, we do record the acoustic resonance phenomenon, when the engine speed is greater than 3 000rpm. Finally, we show that in the exhaust pipe the apparent fluctuation - i.e. the cyclic dispersion and the actual turbulence - may reach 15%. Nous présentons des résultats expérimentaux du champ de vitesses instationnaires, obtenus par adaptation et application de la vélocimétrie laser interférentielle communément appelée à effet Doppler (L.D.A.), à l'échappement d'un moteur altematif à combustion inteme en fonctionnement nominal. Tout d'abord, nous montrons que dans un tube d'échappement long et droit, la vitesse instantanée est bien monodimensionnelle et que l'écoulement occupe la quasitotalité de la section droite géométrique du tube (une couche limite d'épaisseur inférieure à 2mm se développe très près de la paroi du tube). Nous pouvons également décrire la vidange du cylindre du moteur étudié en deux phases principales : bouffée d'échappement et refoulement des gaz brûlés par le piston. Nous mettons de même en évidence l'état très pulsé de l'écoulement, puisqu'en un intervalle de temps inférieur à 1ms, la vitesse de l'écoulement varie de - 100m/s à 200m/s ; nous enregistrons ainsi l'apparition du phénomène de résonance acoustique à des vitesses de rotation supérieures à 3 500

  15. Structures and properties of (U,Pu)O{sub 2} containing non-active fission products. A simulation of irradiated nuclear fuel; Structure et proprietes de (U, Pu)O{sub 2} contenant des produits de fission sous forme inactive. Une simulation de combustible nucleaire irradie

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    We have made oxides with the same uranium and plutonium content, the same stoichiometry and the same fission product content as an oxide fuel (U{sub 0,8}PuO{sub 2})O{sub 1,96} after 2 per cent burn up. We have calculated the stoichiometry changes due to irradiation and checked the calculation by X rays parameters measurements. We have calculated and measured the contraction of the oxide lattice due to fission products in solid solution. Microprobe analysis of precipitates have been made and have lead to the identification of non metallic barium containing compounds and have shown the particular behaviour of molybdenum. Some physical properties have been measured especially the electrical resistivity, the thermal diffusivity and the vapour pressure of zirconium in solid solution. (author) [French] Nous avons fabrique des oxydes dont la composition en uranium et plutonium, la stoechiometrie et la teneur en produit de fission, sont identiques a celles d'un oxyde (U{sub 0,8}PuO{sub 2})O{sub 1,96} ayant subi 2 pour cent de combustion. Nous avons calcule les changements de stoechiometrie entraines par l'irradiation et controle ces calculs par des mesures de parametre. Nous avons calcule et mesure la contraction du reseau due aux produits de fissions solubles dans la matrice. Des analyses a la microsonde des precipites de produits de fission insolubles ont ete faites et ont conduit a l'identification de composes non metalliques contenant du baryum et a la mise en evidence du role particulier du molybdene. Certaines proprietes physiques ont ete mesurees sur ces composes, en particulier la resistivite electrique, la diffusivite thermique et la tension de vapeur du zirconium dissout dans la matrice. (auteur)

  16. Thermodynamic modeling of LPG combustion in dual-fuel engines; Modelisation thermodynamique de la combustion du GPL dans les moteurs dual-fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bilcan, A.; Le Corre, O.; Tazerout, M. [Ecole des Mines de Nantes, 44 (France); Ramesh, A. [Indian Institute of Technology Madras (India)

    2002-07-01

    Dual-fuel engines are modified diesel engines burning simultaneously two fuels inside the cylinder: a gaseous one, called the primary fuel and a liquid one, called the pilot fuel. The thermal efficiency of the dual-fuel engine and of the diesel engine are comparable; the level of emissions is lower compared to the diesel one. This article presents a new procedure for the combustion modeling in a LPG-diesel dual-fuel engine. The procedures deals with the ignition delay period and with the rate of heat release inside the cylinder. This procedure is validated using experimental data issued front a collaboration with the Indian Institute of Technology from Madras, India. The used engine is a single-cylinder one, air-cooled. The pilot fuel is direct injected inside the cylinder The engine was run at constant load and with different diesel substitutions, i.e. for different air to fuel ratios of the primary fuel-air mixture. The general error of the procedure is below 10%. (authors)

  17. 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)

  18. 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)

  19. Separation of Graphitic Line in Debyegram of the Reactor Graphite; Separation de la raie graphitique dans le debyegramme du graphite nucleaire; Otdelenie linii grafita v debaiegramme reaktornogo grafita; Separacion de la linea grafitica en el diagrama de debye del grafito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pandic, B. [Institut Rudjer Boskovio, Zagreb, Yugoslavia (Croatia)

    1963-11-15

    The author sets forth a method for the determination of crystallite dimensions L{sub c} in reactor graphite. The method consists of the mathematical correction of the diffraction profile (002) obtained by means of a Philips diffractometer with scintillation counter. During the work CuK{sub {beta}} radiation is used. The convenience of using CuK{sub {beta}} radiation rather than that of a CuK{sub {alpha}} doublet is discussed. All instrumental errors except that of the sample adsorption are eliminated using corresponding slits. Sample adsorption is corrected mathematically. Highly symmetrical lines of graphitic and non-graphitic phase could be analytically separated from such corrected line profiles. Experimental error in the determination of the half-height and half-width of these lines does not exceed 5%. (author) [French] On a elabore une methode pour determiner la hauteur moyenne L{sub c} des cristallites du graphite nucleaire. Il s'agit d'une methode mathematique de correction du profil de la raie de diffraction (002), obtenu par le diffractometre Philips avec un compteur a scintillation. On a discute les avantages des rayons CuK{sub {beta}} par rapport au doublet CuK{sub {alpha}}. Le choix des ouvertures elimine toutes les erreurs, sauf l'erreur d'absorption dans les echantillons, que l 'on ecarte mathematiquement. Les raies de diffraction pures et tres symetriques des phases graphitique et non graphitique peuvent etre separees du profil corrige de cette facon. L'incertitude dans la mesure de la demi-largeur de ces raies n'est pas superieure a 5%. (author) [Spanish] El autor de la memoria expone un metodo para determinar la altura media Lc de las cristalitas del grafito nuclear. Consiste en corregir matematicamente el perfil de la linea de difraccion (002) obtenido con un difractometro Philips y un contador de centelleo. En la memoria se explican las ventajas que la radiacion CuK{sub {beta}} ofrece sobre el doblete CuK{sub {alpha}} Si se elige correctamente la

  20. 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)

  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. Review of Development Status of Nuclear Superheat; Expose sur l'etat actuel des travaux concernant la surchauffe nucleaire; Obzor razrabotki voprosa o yadernykh peregrevatelyakh; Estudio de los progresos realizados en niateria de sobrecalentamiento nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Imhoff, D. H.; Pennington, R. T. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    fuel irradiation performance, in-pile and out-of-pile uniform and localized corrosion evaluations, results from thermal superheat critical experiments, results from experimental heat-transfer testing and a brief appraisal of the economic incentives of the separate superheat reactor, integral superheat reactor, and mixed-spectrum superheat reactor design studies. (b) A brief description is given of the USAEC-Sponsored ESADA-VESR nuclear superheat fuel development programme. The development tasks, the initial core superheat fuel-element design, the range of experimental variables, and the expected results for the three-year fuel development programme are discussed. (author [French] Depuis 1959, la Societe General Electric s'occupe activement de mettre au point la surchauffe nucleaire dans les reacteurs ralentis a l'eau ordinaire. A cette epoque, le ''Superheat Advance Demonstration Experiment'' (SADE), finance par la societe, a permis d'obtenir, pour la premiere fois aux Etats-Unis, de la vapeur surchauffee par un dispositif nucleaire. Les auteurs du memoire font le point de la situation actuelle concernant la surchauffe nucleaire. Ils decrivent, dans une premiere partie, les trois principales installations de surchauffe nucleaire utilisees par la General Electric et, dans la seconde, les deux principaux programmes de recherches sur la surchauffe ainsi que les resultats les plus importants obtenus jusqu'ici dans ce domaine. 1. Principales installations pour les experiences de surchauffe: a) Breve description du SADE utilise dans le reacteur a eau bouillante de Vallecitos (VBWR), avec tableaux des conditions dans lesquelles se deroulent les experiences, et des elements combustibles irradies pendant la periode comprise entre mai 1959 et juin 1962; puis examen critique des resultats les plus importants ainsi obtenus. b) Breve description de l' ''Expanded Superheat Advance Demonstration Experiment'' (E-SADE) installe dans le reacteur de Vallecitos, avec tableaux des

  3. Accidental behaviour of nuclear fuel in a warehousing site under air: investigation of the nuclear ceramic oxidation and of fission gas release; Comportement accidentel du combustible nucleaire dans un site d'entreposage sous air: Etude de l'oxydation de la ceramique nucleaire et du relachement des gaz de fission

    Energy Technology Data Exchange (ETDEWEB)

    Desgranges, L.

    2006-12-15

    After a brief presentation of the context of his works, i.e. the nuclear fuel, its behaviour in a nuclear reactor, and studies performed in high activity laboratory, the author more precisely presents its research topic: the behaviour of defective nuclear fuel in air. Then, he describes the researches performed in three main directions: firstly, the characterization and understanding of fission gas localisation (experimental localisation, understanding of the bubble forming mechanisms), secondly, the determination of mechanisms related to oxidation (atomic mechanisms related to UO{sub 2} oxidation, oxidation of fragments of irradiated fuel, the CROCODILE installation). He finally presents his scientific project which notably deals with fission gas release (from UO{sub 2} to U{sub 3}O{sub 7}, and from U{sub 3}O{sub 7} to U{sub 3}O{sub 8}), and with further high activity laboratory experiments

  4. La coopération internationale et régional concertant la protection de l'environnement et l'apport du droit nucleaire. L'exemple de la Mer Noir

    Directory of Open Access Journals (Sweden)

    Flore POP

    2005-10-01

    Full Text Available This article presents several short components regarding peaceful uses of nuclear energy, the role played by nuclear energy law, and of complementary institutions and programmes in connection to environmental protection. Additionally, this material discusses not only fundamental principles of cooperation directed towards sustainable development but also general principles of international law, within a framework of institutional intergovernmental and/or non governmental cooperation towards environmental protection, based upon global, regional, national or „No State” context. Dans ce bref article, nous voulons présenter quelques éléments ou repères préliminaires de l’utilisation pacifique de l’énergie nucléaire, le rôle du droit nucléaire, des institutions et programmes adjacents par rapport à la protection de l’environnement, les principes fondamentaux de la coopération pour un développement durable sur le plan régional, ainsi que les principes généraux de droit international susceptibles d’orienter la coopération intergouvernementale ou non-gouvernementale, sur la base des initiatives globales, régionales ou d’intérêt national, ou dans le cadre de la coopération “sans Etat”.

  5. Une installation expérimentale pour l'étude du traitement par combustion des fumées industrielles An Experimental Plant for Processing Industrial Fumes by Combustion

    Directory of Open Access Journals (Sweden)

    Morillon R.

    2006-11-01

    Full Text Available Le rejet à l'atmosphère d'effluents gazeux d'origine industrielle entraîne un accroissement sensible de la pollution atmosphérique ; en outre, il s'accompagne souvent d'une perte d'énergie lorsque l'élément polluant est un hydrocarbure. Dans ce cas, l'utilisation du gaz naturel pour le traitement par combustion des fumées industrielles apporte une solution élégante et souvent peu coûteuse grâce à la récupération d'énergie qu'il est possible de faire. La première partie de l'article rappelle les aspects théoriques de ce traitement ; en particulier, l'influence des divers éléments sur son efficacité y est discutée (composition de l'atmosphère polluée, température, temps de séjour, etc.. II apparaît ainsi que diverses conditions doivent être remplies simultanément pour obtenir une efficacité satisfaisante. Afin de disposer d'éléments d'ingénierie permettant de construire les unités de traitement les plus efficaces et les plus sûres possible, au coût le plus bas possible, la Direction des études et techniques nouvelles du Gaz de France a réalisé une installation expérimentale qui est présentée dans la deuxième partie de l'article. Enfin, quelques examples d'utilisation de cette installation expérimentale, qui constitue un nouvel outil de travail mis à la disposition des utisitateurs et des constructeurs, sont décrits dans la troisième partie de l'article. The discharge into the atmosphere of industrial waste gases causes substantially increased air pollution. Moreover, it is often accompanied by loss of energy when the polluting element is a hydrocarbon. In such cases, the use of natural gas for processing industrial fumes by combustion provides an elegant solution, which moy often prove economical too becouse of the recovery of energy it makes possible. The first part of this article reviews the theoretical aspects of such processing. The way in which its effectiveness is affected by various parameters

  6. 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)

  7. The fuel element of the first charge for EL 4; presentation, main problems arising in the research, production problems; L'element combustible du 1. jeu de EL 4; presentation, problemes essentiels poses par l'etude, problemes de fabrication

    Energy Technology Data Exchange (ETDEWEB)

    Ringot, C; Bailly, H; Bujas, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The fuel element making up the first charge for EL-4 is made of slightly enriched uranium oxide canned in stainless steel. This fuel element makes it possible to operate the reactor in the safest conditions awaiting the development of the fuel which will be finally adopted; this will have a low absorption can: beryllium, or a zirconium copper alloy. The 500 mm assembly is made up of 19 small rods placed on 3 rings, inside a graphite jacket. The solution adopted was a solution using completely independent small rods. This report deals with possible problems resulting from their study and production. (authors) [French] L'element combustible du 1er jeu EL-4 est un element combustible a oxyde d'uranium legerement enrichi gaine d'acier inoxydable. C'est un element combustible permettant de faire fonctionner le reacteur EL 4 dans des conditions aussi sures que possible avant de mettre au point le combustible definitif qui sera a gaine peu absorbante: beryllium, ou alliage zirconium-cuivre. L'assemblage de longueur 500 mm est constitue de 19 crayons places sur 3 couronnes, a l'interieur d'une chemise de graphite. La solution adoptee a ete une solution a crayons independants les uns des autres. Ce rapport traite des problemes eventuels poses par leur etude et leur fabrication. (auteurs)

  8. Contribution to the study on the flow rate adjustment for gas cooled power reactors (1964); Contributiom a l'etude de reglage du debit pour les reacteurs industriels refroidis par gaz (1964)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-06-15

    1. This original study firstly defines the problem of the adjustment of the coolant flow rate in a reactor channel as a function of the corresponding heat transfer equations and of the local and temporal neutron flux. The necessity of such an adjustment is pointed out and the modifying parameters are studied. An adjustment study using the envelope of the possible flux curves is developed. A short study on the technology and the economical advantage of this adjustment is presented. Some measurements, made on G-1 and G-2, show the precision one can obtain from adjustment apparatus itself as well as from the complete reactor adjustment system. 2. Evolution of nuclear properties of fuel in an heterogeneous thermal reactor. In the first port of this paper, the phenomena of fuel evolution have been mainly pointed out. Now a bibliographical study more qualitatively than quantitatively has been done. This survey specifies the present theories and relates to a real effective cross section and also yields to the bases of such a nuclear calculation. (author) [French] 1. Cette etude originale definit d'abord le probleme du reglage du debit de refrigerant dans un canal de reacteur en fonction de la formulation du calcul des performances thermodynamiques de ce canal et des variations du flux neutronique dans l'espace et le temps. La necessite du reglage est ensuite mise en evidence et les parametres le modifiant sont etudies. Une methode de reglage, basee sur l'emploi d 'une courbe enveloppe des courbes de flux possibles, est donnee. Une breve etude de la technologie et des incidences economiques du reglage est presentee. Des mesures effectuees sur les reacteurs G-1 et G-2 montrent la precision que l'on peut attendre des dispositifs de reglage comme du reglage d'ensemble du reacteur lui-meme. 2. Evolution des proprietes nucleaires du combustible dans un reacteur heterogene a neutrons thermiques. Les phenomenes d'evolution du combustible

  9. Contribution to the study on the flow rate adjustment for gas cooled power reactors (1964); Contributiom a l'etude de reglage du debit pour les reacteurs industriels refroidis par gaz (1964)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-06-15

    1. This original study firstly defines the problem of the adjustment of the coolant flow rate in a reactor channel as a function of the corresponding heat transfer equations and of the local and temporal neutron flux. The necessity of such an adjustment is pointed out and the modifying parameters are studied. An adjustment study using the envelope of the possible flux curves is developed. A short study on the technology and the economical advantage of this adjustment is presented. Some measurements, made on G-1 and G-2, show the precision one can obtain from adjustment apparatus itself as well as from the complete reactor adjustment system. 2. Evolution of nuclear properties of fuel in an heterogeneous thermal reactor. In the first port of this paper, the phenomena of fuel evolution have been mainly pointed out. Now a bibliographical study more qualitatively than quantitatively has been done. This survey specifies the present theories and relates to a real effective cross section and also yields to the bases of such a nuclear calculation. (author) [French] 1. Cette etude originale definit d'abord le probleme du reglage du debit de refrigerant dans un canal de reacteur en fonction de la formulation du calcul des performances thermodynamiques de ce canal et des variations du flux neutronique dans l'espace et le temps. La necessite du reglage est ensuite mise en evidence et les parametres le modifiant sont etudies. Une methode de reglage, basee sur l'emploi d 'une courbe enveloppe des courbes de flux possibles, est donnee. Une breve etude de la technologie et des incidences economiques du reglage est presentee. Des mesures effectuees sur les reacteurs G-1 et G-2 montrent la precision que l'on peut attendre des dispositifs de reglage comme du reglage d'ensemble du reacteur lui-meme. 2. Evolution des proprietes nucleaires du combustible dans un reacteur heterogene a neutrons thermiques. Les phenomenes d'evolution du combustible tiennent une place importante dans l

  10. Concentration and Storage of Highly-Active Wastes from the First Stages of the United Kingdom Civil Nuclear Power Programme; Concentration et Stockage des Dechets de Haute Activite au Cours des Premiers Stades du Programme Civil de Production d'Energie d'Origine Nucleaire au Royaume-UNL; КОНЦЕНТРИРОВАНИЕ И ХРАНЕНИЕ ВЫСОКОАКТИВНЫХ ОТХОДОВ НА ПЕРВЫХ СТАДИЯХ ОСУЩЕСТВЛЕНИЯ ПРОГРАММЫ СОЕДИНЕННОГО КОРОЛЕВСТВА ПО ПРОИЗВОДСТВУ ЯДЕPHОЙ ЭЛЕКТРОЭНЕРГИИ ДЛЯ ГРАЖДАНСКИХ ЦЕЛЕЙ; Concentracion y Almacenamiento de Desechos de Elevada Radiactividad en las Primeras Etapas del Programa Civil de Energia Nucleoelectrica del Reino Unido

    Energy Technology Data Exchange (ETDEWEB)

    Clelland, D. W. [United Kingdom Atomic Energy Authority, Production Group, Risley, Warrington (United Kingdom)

    1963-02-15

    The general problems of highly-active waste disposal are discussed and in particular the United Kingdom system of concentrating and storing highly-active waste as an acidic liquid concentrate is described. A speculative estimate is made of the amount of highly- active waste which will arise from reprocessing during the first two decades of the United Kingdom Civil Nuclear Power Programme and engineering design and technical problems associated with the safe and economic confinement of this material are examined. (author) [French] L'auteur analyse les problemes generaux que pose l'elimination des dechets de- haute activite; il decrit plus particulierement la methode appliquee au Royaume-Uni pour concentrer et stocker des dechets de haute activite sous forme d'un liquide concentre acide. U evalue la quantite des dechets de haute activite qui seront produits au cours du traitement de combustibles irradies pendant les deux premieres deconnies du programme civil de production d'energie d'orgine nucleaire et il examine les problemes techniques que pose l'isolement economique et sur de ces substances. (author) [Spanish] El autor examina los problemas generales de la evacuacion de desechos de elevada radiactividad y, en particular, el procedimiento que se aplica en el Reino Unido para concentrar y almacenar desechos muy radiactivos en forma de concentrados liquidos de reaccion acida. Efectua un calculo aproximado de la cantidad de desechos de elevada radiactividad que se orginaran en las operaciones de regeneracion de combustibles durante las dos primeras decadas de ejecucion del programa civil de energia nucleoelectrica en el Reino Unido y analiza los problemas tecnicos y constructivos relacionados con el confinamiento seguro y economico de estas sustancias. (author) [Russian] Obsuzhdajutsja obshhie problemy udalenija radioaktivnyh othodov vysokoj aktivnosti i, v chastnosti, prinjatyj v Soedinennom Korolevstve metod koncentrirovanija i hranenija takih othodov v vide

  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. The reprocessing-recycling of spent nuclear fuel. Actinides separation - Application to wastes management; Le traitement-recyclage du combustible nucleaire use. La separation des actinides - Application a la gestion des dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    After its use in the reactor, the spent fuel still contains lot of recoverable material for an energetic use (uranium, plutonium), but also fission products and minor actinides which represent the residues of nuclear reactions. The reprocessing-recycling of the spent fuel, as it is performed in France, implies the chemical separation of these materials. The development and the industrial implementation of this separation process represent a major contribution of the French science and technology. The reprocessing-recycling allows a good management of nuclear wastes and a significant saving of fissile materials. With the recent spectacular rise of uranium prices, this process will become indispensable with the development of the next generation of fast neutron reactors. This book takes stock of the present and future variants of the chemical process used for the reprocessing of spent fuels. It describes the researches in progress and presents the stakes and recent results obtained by the CEA. content: the separation of actinides, a key factor for a sustainable nuclear energy; the actinides, a discovery of the 20. century; the radionuclides in nuclear fuels; the aquo ions of actinides; some redox properties of actinides; some complexing properties of actinide cations; general considerations about treatment processes; some characteristics of nuclear fuels in relation with their reprocessing; technical goals and specific constraints of the PUREX process; front-end operations of the PUREX process; separation and purification operations of the PUREX process; elaboration of finite products in the framework of the PUREX process; management and treatment of liquid effluents; solid wastes of the PUREX process; towards a joint management of uranium and plutonium: the COEX{sup TM} process; technical options of treatment and recycling techniques; the fuels of generation IV reactors; front-end treatment processes of advanced fuels; hydrometallurgical processes for future fuel cycles; the conversion of actinides; fuels re-fabrication; pyrometallurgical processes; strategy of radionuclides management; transmutation principles; general conclusion. (J.S.)

  13. Studies of neo-formed phases occurring during spent nuclear fuel dissolution in geological repository: influence of silicate ions; Etude des phases neoformees lors de la dissolution du combustible nucleaire en condition de stockage geologique: influence des ions silicate

    Energy Technology Data Exchange (ETDEWEB)

    Robit-Pointeau, V

    2005-12-15

    Spent nuclear fuel alteration in deep storage conditions may proceed by local oxidising conditions at the fuel / water interface under influence of alpha irradiation. However, due to the strong redox buffer capacity of the near-field materials (especially the canister and the geological media), most of the near-field environment will remain reducing. Due to the relative high concentration in silica in such system, coffinite USiO{sub 4}.n(H{sub 2}O) may be a relevant phase to consider as it has been suggested from the natural analogues observations (Oklo). The aim of this work was to assess the relevance of coffinitisation of the spent fuel phenomena. The results of the experimental work contest the thermodynamic predictions. Instead of coffinite, a new U(IV)-Si phase has been observed in water simulating storage conditions. The thermodynamic data on coffinite validated by OECD are based on the average concentration of dissolved silica present in natural system containing uraninite and quartz. As the silica concentration in natural groundwaters is more probably controlled by minerals like chalcedony or silica gel, the coffinite present with uraninite in such systems, is probably not in equilibrium even in 2-billion years- old geological sites. Based on the results of this study, coffinitisation of the spent nuclear fuel in deep geological disposal is not anticipated to be a dominant short term process. (author)

  14. 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.)

  15. Fuel location, homogeneity and amount in flat and tubular configurations; Repartition, Homogeneite et Quantite du Combustible dans les Elements a Configuration Plate ou Tubulaire; Polozhenie, gomogennost' i kolichestvo topliva v ploskikh i trubchatykh konfiguratsiyakh; Disposicion, Homogeneidad y Cantidad de Combustibles en Configuraciones Planas y Tubulares

    Energy Technology Data Exchange (ETDEWEB)

    Meester, P. de [Studiecentrum voor Kernenergie, Mol (Belgium)

    1965-10-15

    standards are considered. Accuracy and elimination of errors are discussed. Some possible future improvements in the tests are proposed. (author) [French] Les elements combustibles pour le reacteur d'essai de materiaux BR-2 peuvent etre-realises, soit avec des plaques obtenues par cadrages, soit avec des tubes obtenus par coextrusion. Au cours de la fabrication et avant le chargement dans le reacteur, il faut verifier ou mesurer la repartition, l'homogeneite et la quantite du combustible. Il faut connaitre la repartition du combustible pour le positionnement de l'ame dans les plaques et tubes ainsi que pour une premiere evaluation qualitative du produit du point de vue des specifications geometriques. On a procede a des radiographies 3 80-90 keV, ainsi qu'a des autoradiographies et gammagraphies avec une source au thulium-170. Pour l'examen radiographique des tubes de combustible, on a introduit dans le tube un mandrin en plomb auquel etait fixe un film sensible aux rayons X , puis on a fait des radiographies sous divers angles. En utilisant une source radioactive se deplacant le long de l'axe du tube et un film place autour du tube, on a obtenu des enregistrements avec un tres bon contraste. Il faut controler l'homogeneite du combustible pour assurer la securite du fonctionnement du reacteur, c'est-a-dire pour eviter toute concentration excessive de combustible pouvant donner lieu a des formations de vapeur pendant le fonctionnement du reacteur et pour garantir que le chargement de combustible est suffisant et regulierement reparti. On peut faire appel a des radiographies en vue d'une verification visuelle. Cependant, s'il est necessaire de faire une analyse quantitative, il est preferable d'utiliser un spectrometre g a m m a a scintillation permettant de mesurer le rayonnement propre emis par l'uranium-235. Le memoire contient une' analyse des resultats obtenus pour quelque 400 plaques de combustible et pour un premier lot de tubes de combustible. Il est possible de

  16. The repertory set of nuclear energy; Le repertoire du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-15

    This second documentary form, edited by the national association of local commissions of information about nuclear activities (ANCLI), is a glossary of the main terms used in the nuclear industry domain. (J.S.)

  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. experience du service de medecine nucleaire sahloul sousse dans ...

    African Journals Online (AJOL)

    tics of the tumor and the Tg values of. Conclusion: The ablative efficiency is optimized by 131 cures iodine should be extended until the Tg remains high. Monitoring life is necessary and the thresholds Tg below 2ng/ml is required. Keywords: Differentiated thyroid Cancers, Thyroglobulin, Iodine 131, Prediction, Monitoring.

  19. 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.)

  20. The large nuclear works; Le grand chantier du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Stephan, C. [Institut de Physique Nucleaire, (CNRS) 91 - Orsay (France)

    2010-10-15

    This article comments the present development of nuclear energy in the world. This energy is very attractive because it has no impact on greenhouse effect. The author briefly describes the various types of nuclear reactors, their operation principle, their power, their availability, their reliability, their reinforced safety. He also evokes the technological developments which lead to third generation reactors which are currently operated (the EPR is more particularly described). He comments the waste management issue, the possibility of fuel recycling, evokes the Myrrha reactor project, and the perspective of fourth generation reactors which will have to be both critical and sur-regenerator (or fast breeder): different projects and ideas are presented, notably mini-reactors

  1. 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.)

  2. 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)

  3. The Non-Destructive Testing of Fuel Elements and Their Components for the United Kingdom Power-Reactor Development Programme; Controle Non Destructif des Elements Combustibles et de Leurs Parties Constitutives dans le Cadre du Programme de Developpement des Reacteurs de Puissance au Royaume-Uni; Nedestruktivnoe ispytanie teplovydelyayushchikh ehlementov i ikh komponentov dlya osushchestvleniya programmy soedinennogo korolevstva po razrabotke ehnergeticheskikh reaktorov; Ensayo No Destructivo de Elementos Combustibles y sus Componentes, en el Marco del Programa de Reactores de Potencia del Reino Unido

    Energy Technology Data Exchange (ETDEWEB)

    Mann, C. A.; Campsie, I. C. [U.K.A.E.A., Reactor Fuel Element Laboratories, Springfields, Salwick, Preston, Lancs. (United Kingdom)

    1965-10-15

    pastilles. Diverses methodes mecaniques, pneumatiques, nucleaires et electriques permettant de mesurer les dimensions des tubes font l'objet d'une etude comparative. On decrit les mesures qui sont prises pour ne pas rayer la surface des tubes. Les auteurs exposent les procedes employes pour mesurer le diametre et la circonference des pastilles; pour les tubes a paroi mince, les problemes que pose le rapport entre le volume des pastilles et celui des vides pourraient etre traites de facon plus realiste en comparant les circonferences. La mise au point d'un appareil efficace de rotation des tubes a permis de combiner les methodes decrites ci-dessus et de construire un dispositif d'essai entierement integre dont l'utilisation ne necessite pas un personnel hautement qualifie. Pour que le Laboratoire puisse obtenir rapidement des renseignements precis sur les dimensions des tubes, on procede a l'enregistrement automatique des mesures; on a ainsi supprime l'operation, lente et quelque peu inexacte, d'enregistrement a la main. En ce qui concerne la detection des defauts dans les aiguilles de combustible, les methodes exposees sous le point a) peuvent, en regle generale, servir a examiner les gaines d'aiguilles de combustible apres le chargement du combustible et l'obturation des extremites. En plus, l'etat des bouchons terminaux est verifie par radiographie. On fait normalement des expositions multiples pour examiner convenablement toute la peripherie des soudures. On peut egalement determiner avec precision la repartition du combustible par radiographie panoramique. Le recours a la radiographie en couleurs est egalement etudie. L'etancheite des aiguilles est verifiee apres remplissage d'helium au moyen d'un detecteur de fuites a spectrometre de masse. Les aiguilles ne contenant pas d'helium peuvent etre controlees par immersion dans un milieu sous pression. Pour localiser les fuites, on peut appliquer, le cas echeant, des methodes d'investigation classiques. On utilise aussi le

  4. 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)

  5. Non-Destructive Testing of Plutonium-Enriched Fuel Rods; Controles non Destructifs de Barreaux Combustibles Enrichis au Plutonium; Nedestruktivnyj-kontrol' toplivnykh sterzhnej''obogashchennykh plutoniem; Ensayo no Destructivo de Elementos Combustibles Enriquecidos en Plutonio

    Energy Technology Data Exchange (ETDEWEB)

    Libotte, P.; Inniger, H.; Leblanc, J. M. [Centre D' Etude de l' Energie Nucleaire, Societe Belge pour l' Industrie Nucleaire, S.A. (Belgonucleaire), Mol (Belgium)

    1965-09-15

    ultrasonically by the pulse-echo technique. The respective advantages of the various non-destructive techniques are studied in relation to the required accuracy and to their possible application to the automated inspection of plutonium fuel rods fabricated on an industrial scale. (author) [French] La Societe belge pour l'industrie nucleaire (BelgoNucleaire) et le Centre d'etude de l'energie nucleaire (CEN) etudient sous contrat, en cooperation avec la Commission de l'EURATOM, l'utilisation du plutonium dans les reacteurs de puissance a eau pressurisee. Dans le cadre des recherches entreprises, differentes techniques de controle non destructif ont ete mises au point en vue d'evaluer la qualite des barreaux combustibles fabriques. Les essais non destructifs mis au point et decrits dans le memoire sont utilises essentiellement pour le controle des dimensions et de la qualite des tubes de gainage, de l'integrite des soudures, de l'etancheite des barreaux, de la densite du materiau combustible et de sa repartition, de l'enrichissement en plutonium et de sa distribution radiale et axiale dans le barreau combustible. Les methodes utilisees pour ces essais non destructifs comportent principalement les examens par radiographie, par autoradiographie, par gammagraphie et par les ultrasons. Le document reprend le principe de chacune des mesures realisees, et decrit dans chaque cas l'appareillage utilise et les techniques operatoires appliquees en vue d'obtenir les sensibilites et precisions desirees. La technique utilisee pour la radiographie permet de deceler des defauts de l'ordre de 50 a 60 {mu}m dans les soudures d'extremite des barreaux combustibles. Les combustibles etant densifies par vibration de trois fractions de poudre dense, dont la fraction fine seule comporte l'enrichissement en plutonium, il est essentiel que la repartition de ce dernier, de meme que la distribution de la densite, soient relevees avec precision. Le comptage du rayonnement gamma emergent emis par le plutonium

  6. Energies and media nr 30. Conditions for the nuclear sector. The fuel cycle and wastes. The usefulness of fuel reprocessing. Wastes; Energies et medias no. 30. La conjoncture, pour le nucleaire. Le cycle du combustible et les dechets. L'utilite du retraitement des combustibles. Les dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-10-15

    After some comments on recent events in the nuclear sector in different countries (energy policy and projects in the USA, Europe, China, India, Russia), this issue proposes some explanations on the nuclear fuel cycle and on nuclear wastes: involved processes and products from mining to reprocessing and recycling, usefulness of reprocessing (future opportunities of fast neutron reactors, present usefulness of reprocessing with the recycling of separated fissile materials), impact of reprocessing on the environment in La Hague (gas and liquid releases, release standard definition), and the destiny of wastes

  7. General trends in the use of uranium in the nuclear industry; Tendances generales d'emploi de l'uranium dans les industries nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    It can be seen from a consideration of the development of the military and civil needs for uranium that, in the long run, the main outlet for the metal will be provided by its industrial applications. The technical uncertainties concerning the best method of producing atomic energy are still numerous and in fact reflect the hesitation in choosing one of two classes of fuel: that based on the metal and that based on the oxide. Four main factors should influence the choice: - the neutron reactivity and the enrichment of the uranium; - the operating temperature; - the resistance to radiation effects; - the chemical stability; but in actual fact, when the choice for a particular use has to be made, it will be another type of factor, such as the cost price, and weight and space considerations which will determine the choice of either metallic uranium or uranium oxide reactors. (author) [French] D'apres le developpement des besoins militaires ou civils en uranium, on voit que les usages industriels de ce metal constituent, a long terme, le debouche essentiel. Les incertitudes techniques, sur le procede optimum pour faire de l'energie nucleaire, restent nombreuses, et se traduisent finalement par une hesitation entre deux grandes classes de combustibles: ceux a base de metal et ceux a base d'oxyde: la preference a l'une ou l'autre de ces deux categories doit s'inspirer de quatre considerations: - la reactivite neutronique et l'enrichissement de l'uranium; - la temperature de fonctionnement; - la resistance aux effets du rayonnement; - la stabilite chimique; mais en definitive, lorsqu'il s'agira d'une application determinee, ce seront des considerations d'un autre ordre, comme le prix de revient, le poids et l'encombrement, qui determineront le choix entre piles a uranium metallique et piles a oxyde d'uranium. (auteur)

  8. 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.)

  9. Quantification of hydrogen distribution with the nuclear microprobe of the Pierre Sue Laboratory in the thickness of the PWR fuel cladding in zirconium alloy; Quantification de la repartition de l'hydrogene a la microsonde nucleaire du Laboratoire Pierre Sue dans l'epaisseur du tube de gainage du combustible des REP en alliage de zirconium

    Energy Technology Data Exchange (ETDEWEB)

    Raepsaet, C. [Laboratoire Pierre Sue (DSM/DRECAM/LPS) - CEA Saclay, 91 - Gif-sur-Yvette (France); Bossis, Ph. [CEA Saclay, Dept. des Materiaux pour le Nucleaire (DEN/DANS/DMN/SEMI/LM2E), 91 - Gif sur Yvette (France); Hamon, D.; Bechade, J.L.; Brachet, J.C. [CEA Saclay, Dept. des Materiaux pour le Nucleaire (DEN/DANS/DMN/SRMA/LA2M), 91 - Gif sur Yvette (France)

    2007-07-01

    In a first part of this study, are detailed the general principles of the specific technique ERDA (Elastic Recoil Detection Analysis) used in the Pierre Sue Laboratory. Then, the contribution of this technique is illustrated with two studies examples on the behaviour of PWR nuclear fuel cladding. (O.M.)

  10. Nouveaux critères pour juger de l'efficacité d'un fourneau à la combustion du charbon de bois

    Directory of Open Access Journals (Sweden)

    Ndaysenga, M.

    1994-01-01

    Full Text Available New Criteria to Judge Stove Efficiency in the Charcoal Combustion. The water boil test efficiency for choosing the most economic stove in combustion is estimated on the basis of four stoves. In addition to the heating and boiling energy usually considered as selection criterion, other criteria such as the boiling time and the combustion rate have been taken to indicate efficiency. Strangely, it appeared that the stove which maintains water at its boiling point for a long time and has the lowest combustion rate doesn 't valorize fuel energy efficiently if you only keep to the heating and boiling energy. The cooking test made it possible to explain that apparent contradiction : the fuel energy fraction which doesn't enter in the calculation of the heating and boiling energy isn't really lost. A low combustion rate associated with a long boiling time proved to be the best criteria of choosing the most economic stove in fuel. Therefore, the only water boil test doesn't make it possible to identify the most economically efficient stove. Resorting to the cooking test is compelling.

  11. Study of the chimney produced by an underground nuclear explosion; Etude de la cheminee creee par une explosion nucleaire souterraine

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Underground nuclear explosions lead to the formation of a cavity which is roughly of spherical shape. The roof of this cavity is unstable and collapses in most cases, leading to the formation of a chimney. The height and the diameter depend on the energy of the charge and on the nature of the surroundings. The chronology of the various stages can be determined by seismic observations. The interior of the chimney is filled, either partially or completely, with rubble earth. This phenomenon is of great importance as far as the use of nuclear explosions for industrial applications is concerned. (author) [French] Les explosions nucleaires souterraines creent une cavite de forme grossierement spherique. La voute de cette cavite est instable et s'effondre dans la plupart des cas, donnant lieu a la formation d'une cheminee. La hauteur et le diametre sont fonction de l'energie du tir et de la nature du milieu. La chronologie des evenements peut etre determinee par des observations seismiques. L'interieur des cheminees est occupe, en partie ou en totalite, par des eboulis. Ce phenomene presente un grand interet pour l'utilisation des explosions nucleaires a des fins industrielles. (auteur)

  12. Statistical treatment of data. Application to nuclear electronics; Traitement des informations en regime statistique. Applications a l'electronique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    In this report the data of probability calculations are applied to the analyses of counting losses in experiments on chance events encountered in nuclear physics. The distribution of time intervals according to Poisson's law is studied and various applications of this are given: calculation of counting losses on a scale preceded by a fast de-multiplying circuit, decrease of the counting rate on the multichannel selectors, recording of statistical distribution phenomena on magnetic bands. (author) [French] Ce rapport applique les donnees du calcul des probabilites a l'analyse des pertes de comptage dans les experiences sur des evenements aleatoires rencontres en physique nucleaire. La distribution des intervalles de temps suivant une loi de Poisson est etudiee et differentes applications en sont donnees: calcul des pertes de comptage sur une echelle precedee d'un circuit de demultiplication rapide, diminution du taux de comptage sur les selecteurs multicanaux, enregistrement de phenomenes a distribution statistique sur bandes magnetiques. (auteur)

  13. Experimental apparatus for in-pile studies of: creep of nuclear fuels, and Young's-modulus of structural materials; Dispositifs experimentaux pour etudes en pile du fluage des materiaux combustibles, et du module d'elasticite des materiaux de structure

    Energy Technology Data Exchange (ETDEWEB)

    Gautier, A; Le Bret, P; Alfille, L; Pesenti, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    Creep test under compression: the apparatus described allows to study, in an horizontal beam hole of a research reactor such as EL2, the creep behaviour of nuclear fuel samples under neutron flux. The maximum stress applied on the specimens is a constant compression chooses between 0.200 and 0.400 kg/mm{sup 2} (285 psi and 570 psi). - Young's Modulus measurement: in another horizontal beam hole of such a reactor, an apparatus allows to study the irradiation effect on Young's Modulus of a structural material specimen. (author)Fren. [French] Essai de fluage en compression: l'appareillage decrit permet d'etudier, dans un canal horizontal d'une pile experimentale type EL2, le fluage en compression d'eprouvettes de materiaux fissiles sous le flux de neutrons, sous une contrainte maximum de 500 g/mm{sup 2}. - Mesure du module d'Young: dans un canal identique au precedent, un appareillage permet de suivre l'influence du rayonnement sur le module d'elasticite d'une eprouvette d'un materiau de structure. (auteur)

  14. 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.)

  15. Underground nuclear explosions. Geological survey of the cavities; Explosions nucleaires souterraines etude geologique des cavites

    Energy Technology Data Exchange (ETDEWEB)

    Faure, J [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    A geological survey of underground nuclear explosions makes it possible to determine the main characteristics of the cavity formed. The lower portion is spherical; the same was very likely true of the roof, which collapses in the majority of media with the exception of rock-salt. Its radius, for a given bomb size, can vary by a factor of two according to the type of rock. The lay-out of its contents depends on the characteristics of the solid and liquid products at the moment of the roof collapse; according to the medium involved, mixing of the rubble and the mud-flow occurs (granite) or does not occur (tuff and alluvia). In all media, the average physical properties can be evaluated. (author) [French] L'etude geologique d'explosions nucleaires souterraines permet de determiner les principaux caracteres de la cavite creee. Sa partie inferieure est spherique; il en etait vraisemblablement de meme de sa voute, effondree dans la plupart des milieux a l'exception du sel gemme. Son rayon, a energie d'engin egale, varie selon les roches du simple au double. La disposition de son contenu depend des caracteristiques des produits solides et liquides au moment de la chute du toit; selon le cas, il n'y a pas (tuf et alluvions) ou il y a (granite) melange des eboulis et des laves. Dans tous les milieux, les proprietes physiques moyennes peuvent etre evaluees. (auteur)

  16. Experimental study of a separated jets burner: application to the natural gas-pure oxygen combustion; Etude experimentale du comportement de bruleurs a jets separes: application a la combustion gaz naturel-oxygene pur

    Energy Technology Data Exchange (ETDEWEB)

    Salentey, L.

    2002-04-15

    The evolution of pollution standards and the optimisation of furnaces performances require a development of new burner generation and also the improvement of combustion techniques. Actually, the use of oxy-combustion in separated jets burners offers interesting prospects for NO{sub x} emission reduction and on the modularity of flames properties (lift off, flame front topology, flame length). The complex geometry of those burners leads to several problems like the three-dimensional character of the flow, which may sometimes disturb the flame stability as flames are lifted above the burner. This experimental study deals with a simplified version of that kind of burner constituted with a central natural gas jet surrounded by two oxygen jets. Primary, the study of non-reactive jet was planned in order to understand dynamic and mixture phenomena involved between jets and to provide a database useful for the computer code validation. The reactive flow developed in a furnace, which simulates the real conditions, had been characterised. The studies of the dynamic field using Laser Doppler Velocimetry (LDV) and of the turbulent mixture by conditional Laser tomography were supplemented in combustion by the visualisation of the spontaneous emission of radical OH, in the initial and final zone of the oxy-flames, like by the measurement of pollutants like NO{sub x} and soot. The measurements carried out while varying speeds of injection as well as the gap between the jets made possible the highlight of the influence of these parameters upon the stabilisation of the oxy-flames as well as the modification of the topology and the characteristics of the flows. The comparison of the measurements made in non-reactive and reactive flow shows the influence of oxy-combustion on the dynamic and scalar development of the flow for this type of burners. (author)

  17. A Study on the Role of Reaction Modeling in Multi-phase CFD-based Simulations of Chemical Looping Combustion; Impact du modele de reaction sur les simulations CFD de la combustion en boucle chimique

    Energy Technology Data Exchange (ETDEWEB)

    Kruggel-Emden, H.; Stepanek, F. [Department of Chemical Engineering, South Kensington Campus, Imperial College London, SW7 2AZ, London (United Kingdom); Kruggel-Emden, H.; Munjiza, A. [Department of Engineering, Queen Mary, University of London, Mile End Road, E1 4NS, London (United Kingdom)

    2011-03-15

    Chemical Looping Combustion is an energy efficient combustion technology for the inherent separation of carbon dioxide for both gaseous and solid fuels. For scale up and further development of this process multi-phase CFD-based simulations have a strong potential which rely on kinetic models for the solid/gaseous reactions. Reaction models are usually simple in structure in order to keep the computational cost low. They are commonly derived from thermogravimetric experiments. With only few CFD-based simulations performed on chemical looping combustion, there is a lack in understanding of the role and of the sensitivity of the applied chemical reaction model on the outcome of a simulation. The aim of this investigation is therefore the study of three different carrier materials CaSO{sub 4}, Mn{sub 3}O{sub 4} and NiO with the gaseous fuels H{sub 2} and CH{sub 4} in a batch type reaction vessel. Four reaction models namely the linear shrinking core, the spherical shrinking core, the Avrami-Erofeev and a recently proposed multi parameter model are applied and compared on a case by case basis. (authors)

  18. Effect of Ash on Oxygen Carriers for the Application of Chemical Looping Combustion to a High Carbon Char Effet des cendres sur l’activité des porteurs d’oxygène dans la combustion du charbon en boucle chimique

    Directory of Open Access Journals (Sweden)

    Rubel A.

    2011-02-01

    activity of the OCs and both OCs performed well. The results were promising for the application of CLC directly to solid fuels. L’application de la combustion en boucle chimique (CLC aux combustibles solides est actuellement étudiée à l’Université du Kentucky, au Centre de Recherche de l’Energie Appliquée (CAER dans le but de développer un procédé de gazéification/combustion en boucle chimique pressurisé (PCLC/G afin de générer de l’électricité à partir de charbon. Un des principaux aspects de la combustion en boucle chimique de combustibles solides est la compréhension de l’effet des cendres sur la réactivité des porteurs d’oxygène (OCs. L’effet des cendres sur la capacité de transfert d’oxygène et sur l’aptitude à oxyder le charbon est étudié avec deux porteurs d’oxygène à base d’oxydes de fer. Les cendres utilisées sont des cendres volantes provenant d’une centrale thermique au charbon. Les expériences sont réalisées dans un système composé d’une thermo-balance couplée à un spectrographe de masse (TGMS dans lequel on utilise d’abord 500 mg d’un mélange de cendres/porteurs d’oxygène à différentes concentrations de cendres allant jusqu’à 75 %. Le gaz réducteur est composé de 10 % de H2, 15 % de CO, 20 % de CO2 et de 55 % de Ar; et le gaz oxydant est composé de 20 % de O2 dans Ar. Les réactions d’oxydation/réduction sont quasi totales. D’après ces expériences, les cendres ont une activité propre de porteur d’oxygène, liée à la présence de fer dans les cendres, confirmée par les analyses DRX. Cela génère une augmentation du gain ou de la perte de masse du mélange pendant l’oxydation/réduction. Les vitesses d’oxydation/réduction augmentent avec la concentration des cendres à cause de l’augmentation de la porosité du mélange de porteurs d’oxygène avec les cendres, ce qui permet un meilleur accès des gaz réactifs sur les sites actifs des porteurs d’oxygène. Dans un

  19. The industrial production of fuel elements; La fabrication en france des elements combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Boussard, R [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Nadal, J [Societe Industrielle de Combustible Nucleaire (SICN), 75 - Paris (France); Pellen, A [Compagnie pour l' Etude et la Realisation de Combustibles Atomiques (CERCA), 75 - Paris (France)

    1964-07-01

    indiquent pourquoi et comment l'on est passe de la gaine filee a la gaine usinee et mentionnent quelques caracteristiques de l'appareillage utilise ainsi que les controles effectues. Ils donnent egalement quelques indications sur la fabrication et l'usinage des chemises. Apres avoir rappele comment se presente en France a la mi-1964 l'industrie des combustibles nucleaires, les auteurs insistent sur les aspects economiques de la fabrication des elements combustibles. Ils montrent l'importance relative des investissements sur le prix de revient du combustible proprement dit, dont ils examinent ensuite les differentes pertes. Ils font une analyse du prix de revient de l'element combustible complet en tirant les enseignements actuels. Pour conclure les auteurs indiquent les points particuliers sur lesquels doit porter l'action a venir pour diminuer le cout d'une fabrication assez delicate, mais maintenant bien au point, et supputent le developpement de cette branche industrielle nouvelle. 2eme Partie - FABRICATION INDUSTRIELLE DES ELEMENTS COMBUSTIBLES POUR REACTEURS DU TYPE PISCINE: Les auteurs indiquent comment a ete elude en France le probleme de la fabrication industrielle des elements combustibles obtenue par laminage et les trois phases par lesquelles on est passe: 1 - Assemblage des plaques fabriquees aux U.S.A., 2 - Laminage des noyaux fabriques aux U.S.A. pour obtenir les plaques, 3 - Elaboration de l'alliage U.Al et fabrication des noyaux. Ils rappellent ensuite brievement les caracteristiques des differents elements combustibles actuellement fabriques. Ils decrivent ensuite les differents stades de l'elaboration en donnant des indications sur l'appareillage et en insistant sur l'importance des controles effectues a chaque stade. Pour finir ils examinent le developpement futur de ce type de fabrication, compte tenu des ameliorations prevues ou envisageables. (auteurs)

  20. Formation and destruction mechanisms of nitrogen oxides during coal combustion in circulating fluidized beds; Mecanismes de formation et de destruction des oxydes d`azote lors de la combustion du charbon en lit fluidise circulant

    Energy Technology Data Exchange (ETDEWEB)

    Borrel, G.; Lecuyer, I. [Universite du Haut-Rhin, 68 - Mulhouse (France)

    1997-01-01

    Formation and reduction of nitrogen oxides (NO and N{sub 2}O) during coal combustion in a circulating fluidized bed (CFBC) are very complicated and yet badly known. The aim of the present study was to better characterize these phenomena on a small-sized experimental unit (reactor diameter: 5 cm), with the possibility to re-inject the solids in the bottom of the furnace, as in a real industrial unit. This should allow then to develop a numerical set of chemical reactions involving the nitrogen oxides. The experimental results showed that coal ash plays a great role in reducing nitrogen oxides, the determining parameter being the quantity of unburnt carbon remaining in the ash. The study then detailed the interaction between nitrogen oxides and de-volatilized (char) according to the temperature, NO{sub x} concentration and the mass of solid. In the absence of oxygen small quantities of char can very significantly reduce NO as well as N{sub 2}O. It was possible to establish destruction kinetics on these particles, and orders of reaction could be determined versus the NO{sub x} concentration and the char particle mass (heterogeneous phase chemical reactions). Then, the coal pyrolysis study enabled to identify the products released during coal devolatilization and thermogravimetric analyses displayed several successive weight losses due CO, CO{sub 2} and CH{sub 4} releases, during a linear temperature increase. Lastly coal combustion was studied in the small pilot with variable experimental conditions. Using the previous experimental was studied in the small pilot with variable experimental conditions. Using the previous experimental results, a model was developed to calculate NO{sub x} concentrations during the coal combustion and validated. The NO and N{sub 2}O contents calculated are thoroughly correlated with the experimental data whatever the injection carbon/oxygen ratio is. (author) 96 refs.

  1. Neutron noise in nuclear reactors; Le bruit neutronique des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Blaquiere, A. [Institut National des Sciences et Techniques Nucleaires (France); Pachowska, R. [Universite Technique de Varsovie (Poland)

    1961-06-15

    The power of a nuclear reactor, in the operating conditions, presents fluctuations due to various causes. This random behaviour can be included in the study of 'noises'. Among other sources of noise, we analyse hereafter the fluctuations due: a) to the discontinuous emissions of neutrons from an independent source; b) to the multiplication of neutrons inside the reactor. The method which we present makes use of the analogies between the rules governing a nuclear reactor in operation and a number of radio-electrical systems, in particular the feed-back loops. The reactor can be characterized by its 'passing band' and is described as a system submitted to a sequence of random pulses. In non linear operating condition, the effect of neutron noise is defined by means of a non-linear functional, this theory is thus related to previous works the references of which are given at the end of the present report. This leads us in particular in the case of nuclear reactors to some results given by A. Blaquiere in the case of radio-electrical loops. (author) [French] La puissance d'un reacteur nucleaire, dans les conditions du regime, est affectee de fluctuations dont les causes sont tres diverses. Ce comportement aleatoire rentre dans le cadre general de l'etude des 'bruits'. Entre autres sources ce bruit, nous analysons ici les fluctuations dues: a) a l'emission discontinue des neutrons provenant d'une source autonome; b) a la multiplication des neutrons au sein du reacteur. La methode que nous introduisons exploite les analogies entre les lois qui regissent un reacteur nucleaire au regime et certains systemes radioelectriques, en particulier les circuits a boucle de reaction. Le reacteur est caracterise par sa 'bande passante' et est decrit comme un systeme soumis a une succession d'impulsions aleatoires. Dans les conditions de fonctionnement non lineaires, l'effet du bruit neutronique est precise en utilisant une fonctionnelle non lineaire, ce qui relie cette theorie a

  2. 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.)

  3. 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

  4. 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'amidon, metabolisme glucidique des tubercules irradies, radioresistance des levures

  5. 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.)

  6. 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.)

  7. Visualisation of Gasoline and Exhaust Gases Distribution in a 4-Valve Si Engine; Effects of Stratification on Combustion and Pollutants Visualisation de la répartition du carburant et des gaz brûlés dans un moteur à 4 soupapes à allumage commandé ; effet de la stratification sur la combustion et les polluants

    Directory of Open Access Journals (Sweden)

    Deschamps B.

    2006-12-01

    des dégagements d'énergie et des émissions de polluants très distincts. Le niveau de tumbleet l'emplacement de l'étincelle sont aussi modifiés. L'observation de la stratification telle qu'elle est réellement dans le moteur constitue un moyen pertinent pour expliquer ses performances. Les paramètres permettant d'optimiser les niveaux de NOx et d'HC peuvent en être déduits, de même que l'efficacité des stratégies de recirculation et d'injection du carburant. Les résultats des visualisations ont été confirmés par des mesures obtenues dans un moteur monocylindre muni d'une culasse conventionnelle avec la même géométrie de chambre de combustion.

  8. The Use of Research Reactors and Short-Lived Isotopes in the Study of Nuclear-Reactor Fuel Materials; Emploi de Reacteurs de Recherche et de Radioisotopes de Courte Periode dans l'Etude des Combustibles pour Reacteurs Nucleaires; ИСПОЛЬЗОВАНИЕ ИССЛЕДОВАТЕЛЬСКИХ РЕАКТОРОВ И КОРОТКОЖИВУЩИХ ИЗОТОПОВ ПРИ ИЗУЧЕНИИ ТОПЛИВНЫХ МАТЕРИАЛОВ ДЛЯ ЯДЕРННХ РЕАКТОРОВ; Empleo de Reactores de Investigacion y de Isotopos de Periodo Corto en el Estudio de Combustibles Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Elleman, T. S.; Townley, C. W.; Sunderman, D. N. [Battelle Memorial Institute, Columbus, OH (United States)

    1963-03-15

    can often exhibit preferential release of particular elements, rapid fission- product release during temperature changes, and fission-gas release after reactor shutdown. The use of this technique allows fundamental information to be obtained on the performance of prototype fuel materials without the necessity for large testing reactors or high-level cave facilities for handling irradiated specimens. (author) [French] On peut employer avec profit un reacteur de recherche pour etudier la mobilite des produits de fission dans les prototypes de combustibles nucleaires en creant un milieu analogue a celui dans lequel le combustible est appele a fonctionner normalement, et en controlant rigoureusement les conditions de l'experience, tout en prevoyant une certaine souplesse dans le dispositif d'experimentation. Si l'on fait varier les conditions d'irradiation et que l'on procede a une analyse quantitative des produits de fission de courte periode liberes par l'echantillon, on pourra determiner les mecanismes de la liberation des produits de fission et leurs rapports avec les proprietes physiques et chimiques tant du combustible servant d'echantillon que des produits de fission eux-memes. On pourra en outre obtenir des donnees de technogenie utiles sur la valeur brute de la radioactivite liberee et la duree de vie probable du combustible. En regle generale, on irradie les echantillons dans des capsules a double paroi qu'on chauffe et introduit dans la piscine ou dans les canaux d'irradiation du reacteur, les produits de fission volatils liberes etant elimines de la capsule par un gaz de balayage. Etant donne .que le rapport entre la vitesse de degagement et la periode du radioisotope constitue un indice important du mecanisme, on recueille et analyse les gaz de fission- krypton et xenon - dont la periode va de 1,7 s jusqu'a 5,3 d. On determine les gaz rares de courte periode (krypton-89, krypton-91, krypton-92, xenon-137, xenon-138, xenon-139, xenon-140 et xenon-141) en

  9. Shippingport Atomic Power Station Operating Experience, Developments and Future Plans; La centrale nucleaire de Shippingport, experience de son fonctionnement et plans pour l'avenir; Shippingportskaya atomnaya ehlektrostantsij, opyt ehkspluatatsii, usovershenstvovaniya i plany na budushchee; Central nucleoelectrica de Shippingport; experiencia adquirida con su explotacton y programa de desarrollo

    Energy Technology Data Exchange (ETDEWEB)

    Feinroth, H. [Division of Reactor Development, United States Atomic Energy Commission, Washington, DC (United States); Oldham, G. M. [Shippingport Atomic Power Station, Duquesne Light Company, Pittsburgh, PA (United States); Stiefel, J. T. [Bettis Atomic Power.Labora Tory, Westinghouse Electric Corporation, Pittsburgh, PA (United States)

    1963-10-15

    design rating of 150 MW(e) gross and a first seed life of 10.000 effective full power hours (EFPH), Core 2 will have five and a half times the design energy output and twice the power density of Core 1. The Core 2 design is described and associated major developments in reactor physics, metallurgy, heat transfer and fluid flow, and fuel element manufacture, are summarized. Plans for decontamination of the reactor plant and for performing modifications to the plant in connection with the installation of the higher rated Core 2 are described. (author) [French] Les auteurs font le bilan des cinq annees de fonctionnement et d'essai de la centrale nucleaire de Shippingport; ils examinent les progres techniques actuels et l'avenir du programme de Shippingport. Ce programme vise a mettre au point la technologie fondamentale des reacteurs a eau legere pour permettre une reduction du prix de revient de l'energie d'origine nucleaire. La centrale nucleaire de Shippingport fonctionne depuis plus de 5 ans et s'est integree facilement dans un reseau d'interconnexion comme centrale de base ou comme centrale d'appoint. Les divers elements de la centrale se sont reveles d'un fonctionnement sur. Il n'y a pas eu de probleme de contamination ni d'elimination des dechets. On peut acceder facilement aux elements du circuit primaire de refroidissement pour l'entretien et, ce faisant, on a constate que les cartouches de combustible etaient intactes. Chacune des trois operations de rechargement effectuees depuis le demarrage de la centrale a pris moins de temps que la precedente. Recemment, la troisieme charge de combustible enrichi a ete mise en place en 32 journees de travail, soit environ le quart du temps necessaire pour le premier rechargement. Les auteurs exposent les conditions auxquelles doit satisfaire la formation du personnel et donnent un apercu des instructions ecrites en matiere d'administration, d'exploitation, etc., qui sont autant de facteurs essentiels du succes du programme de

  10. Application of steric exclusion chromatography for the separation of degradation products of the solvent used for the reprocessing of the nuclear fuels; Application de la chromatographie d`exclusion sterique a la separation de produits de degradation du solvant du retraitement des combustibles nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Pozo, C.

    1993-08-01

    The solvent, used in France in Purex reprocessing plants at La Hague is tributylphosphate (TBP) diluted to 30% with a mixture of branched alkanes, for which the main component is branched dodecane (70%). In order to minimize volumes of organic wastes, we have to maintain Purex solvent qualities and to get rid of degradation products. The subject of this memoir concerns among all the degradation products the heaviest molecules. The separation and the identification of these products have been carried out by preparative steric exclusion chromatography, followed by the analysis of the samples by various analytical methods. An inactive residue containing heavy degradation products was prepared according to the process used in the UP3 La Hague plant. The Analysis of this residue using steric exclusion chromatography and GPC/MS methods, shows the presence of three families of compounds heavier than TBP: the ``dimers of TBP`` (provided from the addition of two molecules of TBP), the ``TBP-alkanes`` (the main molecule is the result of the addition of dodecane with TBP), and ``the functionalized TBP`` (hydroxyled TBP, nitrous TBP, nitrated TBP). Plutonium (IV) retention tests were made on the various fractions generated by steric chromatography. They showed that ``the dimers of TBP`` and ``the functionalized TBP`` families are responsible for that retention. These results confirm the good efficiency of the solvent distillation system operated in UP3 plant which allow the elimination of heavy degradation products of the solvent with the residue and then restore excellent extracting properties for the recycled solvent. (author). 35 figs., 69 refs., 15 tabs.

  11. 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.)

  12. Study of molybdenum (VI) complexation and precipitation by zirconium (IV) in strongly acid medium. Application to nuclear spent fuel dissolution; Etude de la complexation et de la precipitation du molybdene (VI) par le zirconium (IV) en milieu tres acide. Application a la dissolution du combustible nucleaire irradie

    Energy Technology Data Exchange (ETDEWEB)

    Esbelin, E

    1999-07-01

    These last years the formation of solid deposits has been observed in the dissolution workshops of the La Hague plant. A sample of the solid was withdrawn for expertise: molybdenum and zirconium are the two major components of the solid, identified as zirconium molybdate. This thesis consisted in the approach of the mechanisms in solution liable to induce precipitate formation. After a bibliographical overview on the chemistry of Mo(VI) in highly acidic solution, this system was studied by absorption spectrophotometry in perchloric medium. The implication of two major forms of Mo(VI) in a dimerization equilibrium was confirmed by this way and by {sup 95}Mo NMR. The principal parameters governing this equilibrium were identified. It is thus shown that the molybdenum dimerization reaction is exothermic. Disturbance of the Mo(VI) system in highly acidic solution by Zr(IV) was also studied. In a restricted experimental field, for which 'conventional' exploitation methodologies had to be adapted to the system, a main complex of stoichiometry 1:1 between Mo(VI) and Zr(IV) was found. The precipitation study of Mo(VI) by Zr(IV) under conditions close to those of the dissolution medium of nuclear spent fuel was undertaken. The main parameters which control precipitation kinetics were identified. The results obtained reveal that precipitation is controlled by a single macroscopic process and therefore can be described by a single equation. The solid obtained is composed of only one phase presenting a Mo:Zr non-stoichiometry when compared to the theoretical formula ZrMo{sub 2}O{sub 7}(OH){sub 2},2H{sub 2}O. At last, on the basis of the research results, a descriptive mechanism of the system is proposed in which intervenes a 1:1 intermediate complex, much more soluble than a probable 2:1 precipitation precursor. (author)

  13. Effect of TiO{sub 2} additive on the sintering of nuclear fuel (U,Pu)O{sub 2}. Contribution of surface diffusion to plutonium distribution; Influence de l`ajout de TiO{sub 2} sur l`aptitude au frittage du combustible nucleaire (U,Pu)O{sub 2}. Contribution de la diffusion de surface a la repartition du plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Bremier, Stephane [CEA Centre d`Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France)

    1997-12-19

    This thesis has as objective the study of the effect of TiO{sub 2} additive on the development of MOX fuel microstructure during sintering in reducing atmosphere. To understand better the mechanisms governing the evolution of microstructure, the behavior of UO{sub 2} in the presence of TiO{sub 2} has been established and the influence of the PuO{sub 2} distribution in the initial state of the material was taken into account. The chapter II is devoted to the bibliographic study of the transport mechanisms responsible of the sintering in the ceramics UO{sub 2} and UO{sub 2}-PuO{sub 2}. The results concerning the influence of TiO{sub 2} upon density, grain size and homogenization are discussed. The following chapter describes the characteristics of initial powder, the procedures and installations of heat treatment, as well as the techniques of characterization used. Then the sintering features of UO{sub 2} alone or in the presence of TiO{sub 2} are presented. It appears that in the last case the surface diffusion becomes sufficient fast so that the distribution of the additive occurs naturally during a slow temperature increase. The fifth chapter treats the effect of UO{sub 2}-PuO{sub 2} preparation upon the initial microstructure of the materials and the role played by the PuO{sub 2} grains in sintering. The potentiality of surface diffusion as a means of PuO{sub 2} spreading in the UO{sub 2} is evaluated and correlated with the reduced capacity of sintering the UO{sub 2} ceramics containing PuO{sub 2}. The last chapter deals with the influence of TiO{sub 2} on the development of microstructure in UO{sub 2}-PuO{sub 2} ceramics. While at temperatures below 1500 deg.C the TiO{sub 2} additive affects the surface diffusion and so the plutonium distribution, at values T{>=} 1600 deg.C the additive gives rise to a dissolution-reprecipitation process taking place in a intergranular liquid phase appeared between UO{sub 2}, PuO{sub 2} and titanium oxide. Thus the objective is the optimizing the temperature conditions, the oxygen potential as sintering gas and the additive concentration in order to obtain a homogeneous (U,Pu)O{sub 2} solid solution independently of the degree of heterogeneity of the initial oxide mixtures 98 refs., 60 figs., 25 tabs.

  14. Quantification of the distribution of hydrogen by nuclear microprobe at the Laboratory Pierre Sue in the width of zirconium alloy fuel clad of PWR reactors; Quantification de la repartition de l'hydrogene a la microsonde nucleaire du Laboratoire Pierre Sue dans l'epaisseur de tubes de gainage du combustible des REP en alliage de zirconium

    Energy Technology Data Exchange (ETDEWEB)

    Raepsaet, C. [CEA Saclay, Dept. de Recherche sur l' Etat Condense, les Atomes et les Molecules (DSM/DRECAM/LPS-CNRS) UMR9956, 91 - Gif sur Yvette (France); Bossis, Ph. [CEA Saclay, Dept. des Materiaux pour le Nucleaire (DEN/DANS/DMN/SEMULM2E), 91 - Gif-sur-Yvette (France); Hamon, D.; Bechade, J.L.; Brachet, J.C. [CEA Saclay, Dept. des Materiaux pour le Nucleaire (DEN/DANS/DMN/SRMALA2M), 91 - Gif-sur-Yvette (France)

    2007-07-01

    Among the analysis techniques by ions beams, the micro ERDA (Elastic Detection Analysis) is an interesting technique which allows the quantitative distribution of the hydrogen in materials. In particular, this analysis has been used for hydride zirconium alloys, with the nuclear microprobe of the Laboratory Pierre Sue. This probe allows the characterization of radioactive materials. The technique principles are recalled and then two examples are provided to illustrate the fuel clad behavior in PWR reactors. (A.L.B.)

  15. Study of physico-chemical release of uranium and plutonium oxides during the combustion of polycarbonate and of ruthenium during the combustion of solvents used in the reprocessing of nuclear fuel; Etude de la mise en suspension physico-chimique des oxydes de plutonium et d'uranium lors de la combustion de polycarbonate et de ruthenium lors de la combustion des solvants de retraitement du combustible irradie

    Energy Technology Data Exchange (ETDEWEB)

    Bouilloux, L

    1998-07-01

    The level of consequences concerning a fire in a nuclear facility is in part estimated by the quantities and the physico-chemical forms of radioactive compounds that may be emitted out of the facility. It is therefore necessary to study the contaminant release from the fire. Because of the multiplicity of the scenarios, two research subjects were retained. The first one concerns the study of the uranium or plutonium oxides chemical release during the combustion of the polycarbonate glove box sides. The second one is about the physico chemical characterisation of the ruthenium release during the combustion of an organic solvent mixture (tributyl phosphate-dodecane) used for the nuclear fuel reprocessing. Concerning the two research subjects, the chemical release, i.e. means the generation of contaminant compounds gaseous in the fire, was modelled using thermodynamical simulations. Experiments were done in order to determine the ruthenium release factor during solvent combustion. A cone calorimeter was used for small scale experiments. These results were then validated by large scale tests under conditions close to the industrial process. Thermodynamical simulations, for the two scenarios studied. Furthermore, the experiments on solvent combustion allowed the determination of a suitable ruthenium release factor. Finally, the mechanism responsible of the ruthenium release has been found. (author)

  16. Determination of the Effectiveness of Control Rods in the VVER Reactor Fuel Assemblies; Determination de l'Efficacite des Barres de Reglage dans les Ensembles Combustibles du reacteur VVER; Opredelenie ehffektivnosti reguliruyushchikh sterzhnej v sborkakh reaktora VVEHR; Determinacion de la Eficacia de las Barras de Control en los Conjuntos de Elementos Combustibles del Reactor VVER

    Energy Technology Data Exchange (ETDEWEB)

    Semenov, V. N.; Lunin, G. L.; Komissarov, L. V.; Kamyshan, A. N.; Halizev, V. I.; Andrianov, G. Ja.; Voznesenskij, V. A.; Kuz' micheva, V. A.; Lebedev, V. I. [Ordena Lenina Institut Atomnoj Energii Im. I.V. Kurchatova, Moskva, SSSR (Russian Federation)

    1964-06-15

    The paper describes experiments done in homogeneous mock-ups of the fuel assemblies from the VVER Reactor (at one level of enrichment) to determine the effectiveness of absorbing systems comprising shim fuel assemblies or water cavities and of absorbing rods clad in jackets made of differing materials. The paper also gives data on some experiments that have been done in mock-ups of assemblies with differing levels of enrichment. These experiments make it possible to verify the methods used in calculation and to evaluate the prospects of using them for heterogeneous reactors. (author) [French] Le memoire decrit les experiences qui ont ete faites pour determiner l 'efficacite des absorbants contenus dans les barres de compensation, l'effet cavitaire et l 'efficacite des absorbants gaines de materiaux divers, au moyen d'assemblages homogenes de cartouches de combustible du reacteur VVER (reacteur de puissance ralenti et refroidi a l 'eau ayant le meme taux d'enrichissement. On y trouve en outre des donnees sur certaines experiences executees a l 'aide d'assemblages de cartouches de combustible taux d'enrichissement differents. Ces travaux permettent de verifier la methode de calcul et d'evaluer ses possibilites d'application aux reacteurs non homogenes. (author) [Spanish] Se describen en la memoria experimentos para determinar la eficacia de los materiales absorbentes contenidos en las barras de compensacion, el efecto de cavitacion y la eficacia de los materiales absorbentes revestidos de diversos materiales, realizados con ayuda de los conjuntos homogeneos de elementos combustibles del reactor VVER (reactor de potencia moderado y refrigerado por agua) con un solo grado de enriquecimiento. Ademas, se exponen datos sobre los experimentos efectuados con ayuda de conjuntos de grados de enriquecimientos; variados. Tales experimentos permiten verificar el metodo de calculo teorico, utilizad o y evaluar la posibilidad de aplicarlo a los reactores no homogeneos. (author

  17. 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

  18. 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 millimetres fonctionnent

  19. The experimental nuclear reactor: AQUILON; Le reacteur nucleaire experimental: AQUILON

    Energy Technology Data Exchange (ETDEWEB)

    Girard, Y; Koechlin, J C; Moreau, J M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    'Aquilon' is an experimental reactor specially designed for the neutronic study of heterogeneous multiplying media with solid fuel and liquid moderator. Since this study is in general incompatible with energy production, the power of the reactor has been limited to a minimum so as to be able to obtain a simple and compact structure, easy access, good handling and great flexibility of operation and utilisation. (author) [French] 'Aquilon' est un reacteur experimental specialement concu pour l'etude neutronique de milieux multiplicateurs heterogenes a combustible solide et ralentisseur liquide. Cette etude etant en general incompatible avec la production d'energie, on a limite au minimum la puissance du reacteur pour pouvoir obtenir une structure simple et peu encombrante, un acces facile, une bonne maniabilite et une grande souplesse de fonctionnement et d'utilisation. (auteur)

  20. Nuclear purity and the production of uranium (1962); La purete nucleaire et la fabrication de l'uranium (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    When the production of 'nuclear grade' uranium is dealt with, it is difficult, the author of this study points out, to separate its chemical, technical, and economical bearings. While recalling the evolution of chemical processes in various countries and describing the technic of uranium manufacture in the plant of the French 'Commissariat a l'Energie Atomique' at Le Bouchet, the author outlines the effect of economical contingencies on the problems the chemists and engineer are faced with. The question of cost price is also considered here with particular attention. (author) [French] Lorsqu'il s'agit de la production d'uranium de 'qualite nucleaire', il est difficile, souligne l'auteur de cette etude, de separer les aspects chimique, technique et economique. Aussi, en retracant l'evolution des procedes chimiques dans divers pays et decrivant les techniques de fabrication de l'uranium a l'usine du Bouchet du Commissariat a l'Energie Atomique, l'auteur ne manque-t-il pas de rappeler les incidences de la conjoncture economique sur les problemes posees au chimiste et a l'ingenieur. La question du prix de revient, egalement, est traitee ici avec une attention particuliere. (auteur)

  1. 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)

  2. Instruments used to measure or check {alpha}, {beta}, {gamma} activity and neutron emission in the course of processing ore or irradiated fuel; Appareils de mesure ou de controle {alpha}, {beta}, {gamma}, n, des circuits des usines de traitement du minerai ou du combustible irradie

    Energy Technology Data Exchange (ETDEWEB)

    Blanc, A; Brunet, M; Kermagoret, M; Labeyrie, J; Roux, G; Vasseur, J; Weil, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-07-01

    One of the methods checking ores in the course of treatment is the rapid quantitative determination of thorium. This measurement is carried out by means of a scintillation instrument which shows the {beta} and {alpha} coincidences of ThC and ThC'. The treatment of irradiated fuel is accompanied by a large number of radioactive checks relative to the performance of the fixation and elution operations of uranium in the ion exchangers, to the concentration of radioactivity of effluent sent from the plant into watercourses. The operations of fixation and elution of the uranium are checked automatically by an instrument which takes a sample of 5 cm{sup 3} of solution, evaporates it and measures its activity every 10 or 20 minutes. Plutonium concentrations are measured: - in the presence of strong {beta} {gamma} activities, by means of rotating cylinder detectors; - in the presence of weak {beta} {gamma} activities, by means of {alpha} detectors scanning a constant level liquid surface; - by means of fission chambers relatively insensitive to {gamma}. Fission product concentrations are measured by chambers, counters or scintillators, according to the amount of {gamma} activity present. Finally, the activity of effluent to be emptied into watercourses is checked by means of a scintillation instrument, which measures the {alpha} activity on the one hand, and on the other hand the {beta} {gamma} activity of residue from a 100 cm{sup 3} sample taken and evaporated in 20 minutes. (author) [French] Parmi les controles relatifs au minerai en cours de traitement, figure le dosage rapide de thorium. Cette mesure est realisee au moyen d'un appareillage a scintillation qui met en evidence la coincidence des emissions {beta} et {alpha} du ThC et du ThC'. Le traitement des combustibles irradies s'accompagne d'un grand nombre de controles radioactifs portant sur le fonctionnement des operations de fixation et d'elution de l'uranium dans les echangeurs d'ions, sur la concentration du

  3. Récupération du platine contenu dans les piles à combustible basse température par voie hydrométallurgique Platinum Recovery from used PEMFC by hydrometallurgy

    Directory of Open Access Journals (Sweden)

    Vincent Denis

    2013-11-01

    Full Text Available La récupération du platine contenu dans la couche catalytique des piles à combustible est nécessaire pour viabiliser cette technologie vers le secteur industriel. Dans cette étude la voie purement hydrométallurgique a été privilégiée au procédé de récupération pyrométallurgique, évitant la destruction des autres constituants de la pile (membrane, … et limitant la formation de gaz toxique. Le procédé mise en œuvre est constitué d'une étape de lixiviation à partir d'un mélange HCl/HNO3, suivie par la précipitation d'un sel de platine (NH42PtCl6 pouvant soit servir à la synthèse d'un nouveau catalyseur soit à l'obtention de platine métallique. Sur l'ensemble de la chaîne un rendement de récupération de plus de 80 % a pu être obtenu mettant en avant le potentiel de cette stratégie. The recovery of platinum in the catalyst layers of PEMFCs (proton exchange membrane fuel cells is required to allow a transfer in industry. In this study, hydrometallurgical route was preferred to pyrometallurgical process, reducing both the destruction of the other components of the cell (membrane, … and the formation of hazardous gas. In this work, the process includes a leaching step from a diluted aqua regia solution, followed by a precipitation step of platinum under the (NH42PtCl6 form. This salt can be used either for the synthesis of a new catalyst or to obtain a metallic platinum. Considering these steps the recovery efficiency has been found to be over 80 %, which bring out the potential of this strategy.

  4. Pointing Out Main Factors from Design, Construction and Operating Experience of Existing Nuclear Plants for Assisting in Shaping Future Nuclear Power Programmes; Les principaux criteres degages de l'etude, de la construction et de l'exploitation des centrales nucleaires existantes et leur interet pour l'elaboration des futurs programmes d'energie d'origine nucleaire; Ukazanie osnovnykh faktorov proektirovaniya, stroitel'stva i opyta ehkspluatatsii sushchestvuyutsikh atomnykh ehlektrostantsij, chto dolzhno pomoch' pri sostavlenii budushchikh programm atomnoj ehnergetiki; Principales consideraciones relativas al diseno, construccion y explotacion de centrales nucleares, encaminadas a facilitar la preparacion de programas futuros de energia nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Dalla Volta, F. [Comitato Nazionale per l' Energia Nucleare, Rome (Italy)

    1963-10-15

    enseignements qui ont ete fournis, aux points de vue technique et economique, par l'etude, la construction et l'exploitation des premieres centrales nucleaires, et qui peuvent etre particulierement utiles pour l'implantation de nouvelles centrales de ce genre dans l'avenir, notamment eu egard aux conditions qui regnent en Italie. La technologie actuelle des reacteurs et les progres qu'elle continue de faire revelent une tendance marquee vers la reduction du cout, non seulement des cycles de combustible, mais aussi des elements de la centrale. Cette evolution se trouve d'ailleurs favorisee par la tendance croissante a construire des centrales plus grandes et par le fait que l'etude du developpement du reseau electrique semble indiquer que, sur le plan economique, il y a plus d' avantage ainstaller des centrales nucleaires plus puissantes que d'augmenter la puissance des centrales classiques. Se fondant sur l'experience acquise concernant l'etu de, la construction et l'essai des divers types de centrales existantes, l'auteur donne un apercu des principaux facteurs dont il convient de tenir compte lors de l'etablissement des programmes futurs. Il insiste sur le probleme de l'isolement, vu les incidences favorables que peut avoir sur le choix du site de la centrale la mise au point d'ecrans de protection tres surs, qui puissent etre construits sans augmentation sensible du prix de revient, en tirant notamment parti, pour resoudre certains aspects de ce probleme, des conditions particulieres qui se trouvent reunies en Italie. Quant a l'experience du fonctionnement de certaines centrales d'un modele eprouve, l'auteur examine dans quelle mesure ces installations peuvent etre construites sans difficulte et satisfaire la demande du reseau; il se refere ici egalement au role croissant qu'il est prevu d'attribuer a l'energie d'origine nucleaire en Italie. Enfin, l'auteur souligne a quel point le rassemblement et l'interpretation des donnees relatives aux trois centrales, qui doivent

  5. Problems to be Expected in Disposing of Fission Products from a Possible Nuclear Power Programme; Problemes Eventuels d'Elimination des Produits de Fission dans les Futures Centrales Nucleaires; 0412 0415 0420 041e 042f 0414 ; Problemas que Puede Plantear la Evacuacion de Productos de Fision Resultantes de la Ejecucion de un Programa de Produccion de Energia de Origen Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Dickson, G. K. [Cenral Technical Services, Engineering and Development Group, United Kingdom Atomic Energy Authority, Risley (United Kingdom)

    1960-07-01

    typical British nuclear power programme covering the next few decades is examined. The types of reactor to be erected and the types of fuel to be initially used in them are well appreciated but of course the author's conclusions will necessarily become less certain with the passage of time. The chemical processes which must be applied to irradiated fuels will depend on the type of fuel, its burn-up etc., and so will change during the period under review. Consideration is therefore given to the quantities of fission products and heavy isotopes which may be produced, the forms in which they may leave the chemical processing streams and the methods available for handling them safely, either by storage or by disposal. (author) [French] L'auteur examine un programme d'energie nucleaire caracteristique pour la Grande-Bretagne et s'etendant sur les prochaines decennies. Il donne une evaluation fort judicieuse des types de reacteurs dont la construction est envisagee et des genres de combustibles qu'il est question d'y utiliser pendant la periode initiale; toutefois, ses conclusions auront avec le temps de moins en moins de valeur. En effet, le traitement chimique auquel on devra soumettre le combustible irradie depend du genre de ce dernier, de son taux de combustion, etc.; il subira inevitablement des modifications au cours de la periode consideree. L'auteur tient donc compte des quantites de produits fissiles et d'isotopes lourds qu'il sera possible de produire, des formes sous lesquelles ils pourront se presenter a la fin du traitement chimique et des methodes existantes permettant d'assurer leur manipulation sans danger en vue de leur stockage ou de leur elimination. (author) [Spanish] Esta memoria estudia un programa britanico caracteristico de produccion de energia nuclear que cubre las proximas decadas. Se sabe con bastante certeza que tipos de reactores se construiran y el tipo de combustible que se empleara en ellos en un principio, pero estos conocimientos son

  6. Chemical Effects of Nuclear Recoil in Organic Halide Systems: A New Theoretical Treatment and Experimental Verification of the Theory; Effets Chimiques du Recul Nucleaire dans des Systemes Organiques Halogenes: Nouveau Traitement Theorique et Verification Experimentale de la Theorie; Khimicheskie vozdejstviya yadernoj otdachi v organicheskikh galoidnykh sistemakh: novoe teoreticheskoe tolkovanie i ehksperimental'noe podtverzhdenie teorii; Efectos Quimicos del Retroceso Nuclear en Sistemas de Haluros Organicos: Nuevo Tratamiento Teorico y Verificacion Experimental de la Teoria

    Energy Technology Data Exchange (ETDEWEB)

    Kontis, S. S.; Sanitwongs, P.; Weston, M. [Londonderry Laboratory for Radiochemistry, University of Durham, Durham (United Kingdom)

    1965-04-15

    mecanisme de la 'boule de billard' pour le marquage par l'atome chaud, auquel Libby a donne son nom, et les retentions sont exprimees en fonction de deux types de parametres, savoir: 1. la probabilite que le choc entre un atome chaud de radiohalogene et une molecule donnee determine la retention de l'atome chaud dans cette molecule; 2. les limites superieure et inferieure des energies pour lesquelles un atome de brome est dit chaud. Les auteurs montrent comment le premier type de parametre peut etre derive d'experiences sur des melanges binaires d'un halogenure organique et de l'halogene libre correspondant; le second type de parametre doit etre deduit des constantes nucleaires et chimiques. Des etudes sur les systemes C{sub 2}H{sub 5}Br/CCl{sub 4}/Br{sub 2} et C{sub 2}H{sub 5}Br/C{sub 6}H{sub 5}Br/Br{sub 2} ont permis de faire l'essai de ces methodes. Les valeurs de retention calculees (en Utilisant des parametres derives d'etudes des systemes C{sub 2}H{sub 5}Br/Br{sub 2}, CCl{sub 4}/Br{sub 2} et C{sub 6}H{sub 5}Br/Br{sub 2}) concordent avec celles qui sont determinees experimentalement dans des melanges ou la fraction molaire de brome est superieure a 0,1 environ. Par consequent, les auteurs considerent que le mecanisme Libby permet d'expliquer les retentions organiques observees dans ces melanges. Lorsque la fraction molaire de brome devient inferieure a 0,1, les retentions observees augmentent progressivement par rapport aux valeurs calculees, ce qui est sans doute du au fait que d'autres modes de marquage par l'atome chaud interviennent lorsque la concentration en brome n'est pas assez elevee pour assurer un bon 'balayage' des radicaux. (author) [Spanish] Los autores elaboraron metodos para calcular la probable retencion organica de los halogenos radiactivos despues de activar con neutrones mezclas de dos haluros organicos y el correspondiente halogeno libre; Los metodos se basan en la teoria del proceso de ' bolas de billar ' de Hbby para la marcacion con atomos

  7. Calculation of the shock-wave in the region close to an underground nuclear explosion (method Cades); Calcul de l'onde de choc en zone proche d'une explosion nucleaire souterraine (methode cades)

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    The outline of a method is presented for calculating the characteristics of a shock wave produced by an underground nuclear explosion (pressure, wave velocity, velocity of the medium, energy left in the medium by the shock, etc.). By means of an application to a granitic medium and of a comparison with results obtained during French nuclear explosions, it has been possible to show the good agreement existing between the calculations and the experimental results. The advantages of such a method for studying the industrial applications of underground nuclear explosions are stressed. (authors) [French] On expose les grandes lignes d'une methode de calcul des caracteristiques de l'onde de choc issue d'une explosion nucleaire souterraine (pression, vitesse de l'onde, vitesse du milieu, energie deposee par le choc dans le milieu...). Une application a un milieu granitique et une comparaison aux resultats obtenus au cours d'explosions nucleaires francaises permet de montrer la bonne concordance entre le calcul et les resultats experimentaux. On souligne l'interet d'une telle, methode pour l'etude d'applications industrielles des explosions nucleaires souterraines. (auteurs)

  8. 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)

  9. Analyse de la dynamique non-linéaire et du contrôle des instabilités de combustion fondée sur la "Flame Describing Function" (FDF)

    OpenAIRE

    Boudy , Frédéric

    2012-01-01

    This thesis is concerned with an investigation of combustion instabilities in premixed combustors. This problem has been the subject of a continuous effort in relation with the many issues encountered in practical systems like those used in propulsion and energy production. Combustion instabilities usually arise from the coupling between combustion and acoustic eigenmodes of the system. In most cases such resonances lead to vibrations, structural fatigue and intensified heat fluxes to the cha...

  10. Optimization of fuel cycles: marginal loss values; Optimisation des cycles de combustibles: valeurs marginales des pertes

    Energy Technology Data Exchange (ETDEWEB)

    Gaussens, J [Commissariat a l' Energie Atomique, 75 - Paris (France); Lasteyrie, B de; Doumerc, J [Compagnie pour l' Etude et la Realisation de Combustibles Atomiques, 75 - Paris (France)

    1965-07-01

    comme definitivement perdue, alors que le reste pourrait etre recupere et recycle. Le cout eleve des pertes, recyclees ou non, d'autant plus eleve que l'uranium est plus enrichi, exige qu'il en soit tenu compte dans l'optimisation generale des cycles de combustible. Il importe donc de determiner leur niveau le plus souhaitable economiquement, aux diverses etapes d'elaboration du combustible nucleaire. Mais en France et dans d'autres pays, la production de matieres fissiles est geree par l'Etat, tandis que la fabrication de l'element combustible est effectuee par l'industrie privee. Les criteres d'optimisation et l'interet economique accorde aux pertes sont donc differents pour les deux parties de la chaine de fabrication. Pour tenter neanmoins d'atteindre un optimum conforme a l'interet collectif sans intervenir dans la politique de prix de l'entreprise, on peut utiliser la propriete des couts marginaux d'etre egaux entre eux a l'optimum, pour un volume de production donne. On peut donc ajuster le niveau des pertes pour realiser cette egalite des couts marginaux dont le calcul est plus facile a obtenir de la firme que la justification des prix eux-memes. On s'apercoit d'ailleurs que, bien qu'axee essentiellement sur les pertes, cette analyse globale peut conduire a une meilleure utilisation d'autres facteurs de production. On donne un expose theorique et des exemples pratiques de cette methode d'optimisation economique dans le cadre de la fabrication d'elements combustibles destines a des reacteurs du type: uranium naturel, moderes au graphite et refroidis par le gaz carbonique. (auteurs)

  11. The Application of Various Nondestructive Testing Methods to Fuel Elements of the Orgel Type; Application des Differentes Methodes d'Essais Non Destructifs aux Elements Combustibles du Type Orgel; Primenenie razlichnykh nedestruktivnykh metodov ispytanij k toplivnym ehlementam tipa ''orgel''; Aplicacion de Distintos Metodos de Ensayo No Destructivo a los Elementos Combustibles de Tipo Orgel

    Energy Technology Data Exchange (ETDEWEB)

    Bonnet, P.; Jansen, J. [EURATOM, C.C.R., Ispra (Italy)

    1965-09-15

    . There is a device making it possible to examine four or six fuel elements simultaneously, or two or three separately. Standard radiographic tests. Particular stress is laid on the study of welds, and the limits of the experimental conditions in order to obtain good definition are given. In conclusion, the authors present a plan for a semi-industrial inspection system, describing the various possibilities for treatment, and try to define a general policy of non-destructive tests applied to fuel elements. (author) [French] Le memoire presente les differentes methodes employees pour la detection des defauts dans les tubes de gaine des elements combustibles (defauts de type dimensionnel ou defauts structuraux). Les auteurs evoquent egalement les tests finaux sur elements combustibles complets, en particulier: radiographie des soudures et tests d'etanchete. Ce sujet a deja ete partiellement traite. La recherche des caracteristiques dimensionnelles sur tube de gaine lisse en poudre d'aluminium frittee (SAP) a fait l'objet de recherches assez poussees. En particulier: 1. Mesures des diametres internes et externes par utilisation de capteurs pneumatiques et enregistrement des resultats; 2. Mesures des epaisseurs par utilisation, soit des ultrasons en methode de resonance, soit des rayons y (contrat EURATOM - Istituto Sperimentale Metalli Leggeri); 3. Controle de la fleche; 4. Tests sur tubes a ailettes. La detection des defauts sur tube de gaine lisse a egalement fait l'objet de travaux et un critere de rejet a ete adopte suivant l'utilisation future des tubes de gaines. a) La creation de defauts artificiels en fonction de la nocivite des defauts reels dans la poudre d'aluminium frittee est expliquee dans le memoire. Cette etude a montre, en effet, une grande sensibilite aux defauts du type longitudinal crees generalement lors de la transformation par de grosses inclusions. b) Tests par ultrasons. Defauts longitudinaux: Une comparaison entre la methode a deux capteurs et la

  12. Notes on the Start-Up of the Latina Power Station; Notes concernant le demarrage de la centrale nucleaire de Latina; Zapusk ehlektrostantsii Latina; Notas sobre la puesta en marcha de la central electrica de Latina

    Energy Technology Data Exchange (ETDEWEB)

    Calabria, G.; Gualtieri, G. [AGIP Nucleare, Milano (Italy)

    1963-10-15

    Information is given on the start-up of the first Italian nuclear power plant, the Latin Power Station, designed for an electrical output of 200 MW, incorporating a natural uranium-gas-graphite reactor. After a brief description of the main characteristics of the station, details are given on die performance of the final tests of the plant, on the fuel loading and on the sequence of commissioning operations, measurements and controls subsequent to the criticality attained. The operations for the start-up and connection of the station to the electrical network are treated. The organization problems relevant to the station operation including personnel preparation and qualification, safety measures, are also illustrated. (author) [French] Le memoire donne des renseignements sur le demarrage de la premiere centrale nucleaire italienne, la centrale de Latina, dont la puissance electrique est de 200 MW et qui fonctionne avec un reacteur du type uranium naturel-gaz-graphite. Apres une breve description des caracteristiques essentielles de la centrale, des explications detaillees sont donnees sur les resultats des derniers essais auxquels elle a ete soumise, sur le chargement du combustible et sur la serie des operations de mise en service, des mesures et des verifications auxquelles il a ete procede lorsque l'etat critique a ete atteint. Les operations de demarrage et de raccordement de la centrale au reseau electrique sont etudiees dans le memoire, ainsi que les problemes d'organisation que pose l 'exploitation de la centrale, notamment en ce qui concerne la formation du personnel et les mesures de securite. (author) [Spanish] Se comunican datos sobre la puesta en marcha de la primera central nucleoelectrica italiana, en Latina, proyectada para desarrollar una potencia de 200 MW (e), que se basa en un reactor de uranio natural moderado por grafito u refrigerado por gas. Despues de describir brevemente las caracteristicas de la central, se dan detalles sobre el

  13. Developpement d'une methode de Monte Carlo dependante du temps et application au reacteur de type CANDU-6

    Science.gov (United States)

    Mahjoub, Mehdi

    La resolution de l'equation de Boltzmann demeure une etape importante dans la prediction du comportement d'un reacteur nucleaire. Malheureusement, la resolution de cette equation presente toujours un defi pour une geometrie complexe (reacteur) tout comme pour une geometrie simple (cellule). Ainsi, pour predire le comportement d'un reacteur nucleaire,un schema de calcul a deux etapes est necessaire. La premiere etape consiste a obtenir les parametres nucleaires d'une cellule du reacteur apres une etape d'homogeneisation et condensation. La deuxieme etape consiste en un calcul de diffusion pour tout le reacteur en utilisant les resultats de la premiere etape tout en simplifiant la geometrie du reacteur a un ensemble de cellules homogenes le tout entoure de reflecteur. Lors des transitoires (accident), ces deux etapes sont insuffisantes pour pouvoir predire le comportement du reacteur. Comme la resolution de l'equation de Boltzmann dans sa forme dependante du temps presente toujours un defi de taille pour tous types de geometries,un autre schema de calcul est necessaire. Afin de contourner cette difficulte, l'hypothese adiabatique est utilisee. Elle se concretise en un schema de calcul a quatre etapes. La premiere et deuxieme etapes demeurent les memes pour des conditions nominales du reacteur. La troisieme etape se resume a obtenir les nouvelles proprietes nucleaires de la cellule a la suite de la perturbation pour les utiliser, au niveau de la quatrieme etape, dans un nouveau calcul de reacteur et obtenir l'effet de la perturbation sur le reacteur. Ce projet vise a verifier cette hypothese. Ainsi, un nouveau schema de calcul a ete defini. La premiere etape de ce projet a ete de creer un nouveau logiciel capable de resoudre l'equation de Boltzmann dependante du temps par la methode stochastique Monte Carlo dans le but d'obtenir des sections efficaces qui evoluent dans le temps. Ce code a ete utilise pour simuler un accident LOCA dans un reacteur nucleaire de type

  14. French achievements in the field of nuclear electronics; Realisations francaises dans le domaine de l'electronique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Doireau, M; Fabre, R; Guillon, H; Guyot, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    Nuclear electronic equipment used by the french Atomic Energy Commission has been developed, with an increasing participation of the radioelectric industry (manufacture under AEC license, contracts for prototypes). The equipment for general use has been standardized and satis the technical specification sheets in which are specified more particularly, the conditions for construction, the choice of the spare parts and the conditions for acceptance by the french AEC at factory. The electronic equipment is classified in nine classes, and a brief description of the principal instruments is given in each class. The reliability of the equipment in use is satisfactory, as it is shown by the mean frequency of faults per 1000 hours operation. (author)Fren. [French] L'appareillage d'electronique nucleaire utilise au Commissariat a l'Energie atomique fran is a ete developpe en demandant un concours de plus en plus important a l'industrie radioelectrique (fabrications sous licence CEA, marches de prototypes, etc...). Le materiel d'emploi courant a ete standardise et repond aux specifications de cahiers des charges ou sont precises en particulier les conditions de realisation du materiel, le choix des pieces detachees et les conditions de recette en usine. L'appareillage electronique est classe en neuf rubriques et une description sommaire des principaux appareils est donnee dans chacune des rubriques. La tenue en service du materiel est satisfaisante, ainsi que le montre la frequence moyenne des pannes observees par 1000 heures de fonctionnement. (auteur)

  15. Thermoluminescent Dosimeter as the Gamma Component of a Nuclear Accident Dosimeter; Utilisation du Dosimetre Thermoluminescent Comme Element Detecteur Gamma d'un Dosimetre pour les cas d'Accident Nucleaire; 0422 0415 0420 041c 0414 ; Los Detectores de Termoluminiscencia Como Elemento Gammametrico de un Dosimetro para Casos de Accidente Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Handloser, J. S. [Edgerton, Germeshausen and Grier, Inc., Santa Barbara, CA (United States)

    1965-06-15

    dans les dosimetres a utiliser en cas d'accident. Il a essaye diverses sortes de dosimetres en verre, de dosimetres a films, de dosimetres chimiques et de dosimetres a polymerisation, mais le dosimetre thermoluminescent est celui qui presente le plus d'avantages. En raison de sa grande etendue de mesure, le dosimetre thermoluminescent peut etre utilise a la fois comme appareil de controle radiologique quotidien et comme dosimetre en cas d'accident. Ce systeme rend inutile remploi d'instruments speciaux pour la dosimetrie des accidents et permet d'utiliser a cette fin les instruments bien calibres d'usage quotidien. Habituellement, l'etendue de mesure d'un dosimetre thermoluminescent est de 5 mr a 100 000 r, avec une reproductibilite de {+-} 10%. L'auteur a concu et fabrique un modele unique de dosimetre a fluorure de calcium avec dispositif de lecture pouvant mesurer de 5 mr a 5000 r. La lecture du dosimetre est realisee par chauffage du phosphore et mesure de la lumiere emise. On dispose d'instruments de lecture a six echelles de graduation et des systemes entierement automatises sont prevus. La lecture a l'aide de chacun de ces appareils ne prend pas plus de 20 s par dosimetre. Un autre avantage du dosimetre thermoluminescent est sa faible reponse aux neutrons. La reponse aux neutrons varie selon le type du support et le type de phosphore. Un modele de dosimetre au fluorure de calcium a une reponse aux neutrons de 0.27 x 10{sup -9} rad/n/cm{sup 2}. L'auteur examine deux formes physiques de dosimetres thermoluminescents. Le premier est un dosimetre a chauffage interne place sous vide dans une capsule de verre; il a approximativement les dimensions suivantes: diametre 1 cm, longueur 6 cm. Le second modele est constitue par un tube de verre de faible section dans lequel le phosphore est scelle. Ce dosimetre a un diametre de 0,8 mm et une longueur de 6 mm. L'auteur a concu des ecrans de correction de la reponse a l 'energie pour ces deux types de dosimetres. (author

  16. Combustion engineering

    CERN Document Server

    Ragland, Kenneth W

    2011-01-01

    Introduction to Combustion Engineering The Nature of Combustion Combustion Emissions Global Climate Change Sustainability World Energy Production Structure of the Book   Section I: Basic Concepts Fuels Gaseous Fuels Liquid Fuels Solid Fuels Problems Thermodynamics of Combustion Review of First Law Concepts Properties of Mixtures Combustion StoichiometryChemical EnergyChemical EquilibriumAdiabatic Flame TemperatureChemical Kinetics of CombustionElementary ReactionsChain ReactionsGlobal ReactionsNitric Oxide KineticsReactions at a Solid SurfaceProblemsReferences  Section II: Combustion of Gaseous and Vaporized FuelsFlamesLaminar Premixed FlamesLaminar Flame TheoryTurbulent Premixed FlamesExplosion LimitsDiffusion FlamesGas-Fired Furnaces and BoilersEnergy Balance and EfficiencyFuel SubstitutionResidential Gas BurnersIndustrial Gas BurnersUtility Gas BurnersLow Swirl Gas BurnersPremixed-Charge Engine CombustionIntroduction to the Spark Ignition EngineEngine EfficiencyOne-Zone Model of Combustion in a Piston-...

  17. 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)

  18. Techniques de combustion Combustin Techniques

    Directory of Open Access Journals (Sweden)

    Perthuis E.

    2006-11-01

    Full Text Available L'efficacité d'un processus de chauffage par flamme est étroitement liée à la maîtrise des techniques de combustion. Le brûleur, organe essentiel de l'équipement de chauffe, doit d'une part assurer une combustion complète pour utiliser au mieux l'énergie potentielle du combustible et, d'autre part, provoquer dans le foyer les conditions aérodynamiques les plus propices oux transferts de chaleur. En s'appuyant sur les études expérimentales effectuées à la Fondation de Recherches Internationales sur les Flammes (FRIF, au Groupe d'Étude des Flammes de Gaz Naturel (GEFGN et à l'Institut Français du Pétrole (IFP et sur des réalisations industrielles, on présente les propriétés essentielles des flammes de diffusion aux combustibles liquides et gazeux obtenues avec ou sans mise en rotation des fluides, et leurs répercussions sur les transferts thermiques. La recherche des températures de combustion élevées conduit à envisager la marche à excès d'air réduit, le réchauffage de l'air ou son enrichissement à l'oxygène. Par quelques exemples, on évoque l'influence de ces paramètres d'exploitation sur l'économie possible en combustible. The efficiency of a flame heating process is closely linked ta the mastery of, combustion techniques. The burner, an essential element in any heating equipment, must provide complete combustion sa as to make optimum use of the potential energy in the fuel while, at the same time, creating the most suitable conditions for heat transfers in the combustion chamber. On the basis of experimental research performed by FRIF, GEFGN and IFP and of industrial achievements, this article describesthe essential properties of diffusion flames fed by liquid and gaseous fuels and produced with or without fluid swirling, and the effects of such flames on heat transfers. The search for high combustion temperatures means that consideration must be given to operating with reduced excess air, heating the air or

  19. A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido

    Energy Technology Data Exchange (ETDEWEB)

    Allday, C. [United Kingdom Atomic Energy Authority, Risley, Warrington, Lancs (United Kingdom)

    1963-10-15

    son programme d'energie d'origine nucleaire sur la filie re des reacteurs a l'uranium naturel et au graphite, refroidis par un gaz. Les reacteurs de Calder Hall et de Chapelcross fonctionnent depuis sept ans; ceux de Berkeley et de Bradwell, qui dependent du Central Electricity Generating Board (CEGB), sont maintenant en service et sept autres reacteurs sont en construction ou en projet. Le combustible destine a ces reacteurs est etudie et fabrique dans l'usine de l'Atomic Energy Authority (AEA) a Springfields, puis transporte jusqu'au reacteur. Apres irradiation et dechargement, le combustible est transporte a l'usine de l'AEA, situee a Windscale, ou l'uranium et le plutonium sont separes des produits de fission. L'auteur decrit l'experience britannique en matiere d'etude et de fabrication du combustible, d'exploitation du reacteur, de transport et de traitement chimique du combustible irradie. Il examine brievement le comportement du combustible dans le reacteur et les differents programmes possibles de chargement et de dechargement, ce sujet etant developpe dans un autre memoire. b) Reacteurs utilisant les combustibles enrichis. Le Royaume-Uni met au point un reacteur perfectionne refroidi par un gaz (Advanced Gas Cooled Reactor = AGR), dont le prototype a ete mis en service en 1963. Le combustible est fabrique a partir d'oxyde d'uranium enrichi gaine d' acier inoxydable; apres irradiation, il sera traite dans une novelle installation qui sera ajoutee a l'usine de separation de Windscale ou est actu ellement traite le combustible gaine de magnox. L'uranium enrichi destine a AGR est produit par l'usine de diffusion situee a Capenhurst. L'oxyde d'uranium naturel enrichi au plutonium peut remplacer, comme combustible, l'oxyde d'uranium enrichi. L'auteur decrit l'experience acquise dans la transformation de l'oxyde destine a AGR et dans le fonctionnement du reacteur et indique comment on envisage de traiter le combustible irradie. Il examine le cas de l'utilisation d

  20. The Use of Fuel Gas as Stripping Medium in Atmospheric Distillation of Crude Oil L’utilisation de gaz combustible comme moyen d’extraction des fractions légères en distillation atmosphérique du pétrole brut

    Directory of Open Access Journals (Sweden)

    Plellis-Tsaltakis C.

    2011-09-01

    Full Text Available Stripping of petroleum fractions aims to remove the light ends that spoil some of their properties, such as the flash point. Stripping usually employs steam for that purpose. Except for steam, other substances can perform the same function, among them light hydrocarbons. In this article, we investigate the use of refinery fuel gas as stripping medium for a crude oil atmospheric distillation unit. L’extraction des fractions légères du pétrole vise à enlever les produits nuisibles à certaines propriétés comme le point d’éclair. Cette opération utilise habituellement de la vapeur d’eau. D’autres substances peuvent remplir la même fonction, comme les hydrocarbures légers. Dans cet article, on étudie l’utilisation du gaz combustible de la raffinerie comme moyen d’extraction des fractions légères dans une unité de distillation atmosphérique.

  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. Communication Received from the Permanent Mission of the Netherlands regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology; Communication recue de la mission permanente des Pays-Bas concernant les Directives de certains Etats Membres applicables a l'exportation de matieres, d'equipements et de technologie nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-05

    The Agency has received a Note Verbale from the Permanent Mission of the Kingdom of the Netherlands, dated 12 July 2011, in which it requests that the Agency circulate to all Member States a letter of 12 July 2011 from the Chairman of the Nuclear Suppliers Group, Ambassador Piet de Klerk, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [French] L'Agence a recu une note verbale de la mission permanente du Royaume des Pays-Bas, en date du 12 juillet 2011, lui demandant de communiquer a tous les Etats Membres une lettre du 12 juillet 2011 du president du Groupe des fournisseurs nucleaires, l'ambassadeur Piet de Klerk, adressee au Directeur general au nom des gouvernements des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Chine, Croatie, Chypre, Danemark, Espagne, Estonie, Etats-Unis d'Amerique, Federation de Russie, Finlande, France, Grece, Hongrie, Irlande, Islande, Italie, Japon, Kazakhstan, Lettonie, Lituanie, Luxembourg, Malte, Norvege, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Roumanie, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovaquie, Slovenie, Suede, Suisse, Turquie et Ukraineb. Cette lettre apporte des informations supplementaires sur les Directives de ces gouvernements applicables aux transferts nucleaires.

  3. 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)

  4. Criteria for Special Nuclear Materials Inventory and Control Procedures; Criteres a Suivre Pour Proceder a l'Inventaire des Matieres Nucleaires Speciales et aux Mesures de Controle; Kriterii dlya inventarizatsii spetsial'nykh yadernykh materialov i metody ucheta; Criterios a Que Deben Ajustarse los Procedimientos de Inventario y Control de los Materiales Nucleares Especiales

    Energy Technology Data Exchange (ETDEWEB)

    Kinderman, E. M.; Tarrice, R. R. [Stanford Research Institute, Menlo Park, CA (United States)

    1966-02-15

    and the total inventory of these special nuclear materials. A matrix of solutions to the management and inventory control of special nuclear materials will be presented. The multiplicity and relative effectiveness of varied techniques at key stages of the materials supply, utilization and recovery are assessed. (author) [French] L'un des plus importants problemes qui, dans le domaine nucleaire et notamment dans l'exploitation commerciale de l'energie d'origine nucleaire, se posera aux societes d'investissement, aux directeursetaux exploitants est celui du controle efficace de l'inventaire des matieres nucleaires dont la valeur depassera, d'ici 1980, 5 milliards de dollars des Etats-Unis. Comparativement a la plupart des matieres utilisees commercialement, les matieres nucleaires speciales sont couteuses; aux Etats-Unis par exemple, l'uranium enrichi a 90%, l'uranium enrichi a 3% sous forme d'hexa- fluorure et l'eau lourde coutent respectivement 10808 dollars, 254 dollars et 61,60 dollars le kilo. En outre, ces matieres sont frequemment soumises, pour des raisons de protection sanitaire et de securite, a des controles gouvernementaux speciaux sans rapport direct avec leur valeur monetaire. En depit de leur prix eleve, ces matieres sont destinees a etre utilisees en grandes quantites; par exemple, on utilisera de 50 a 75 t de combustible enrichi a 3{sup o}{r_brace}o dans un reacteur de 500 MW modere a l'eau ordinaire et 200 a 300 reacteurs de cette puissance fonctionneront vraisemblablement dans le monde en 1980. L'experience acquise a permis la mise au point et l'application de methodes speciales pour le controle commercial de grandes quantites de matieres de faible valeur comme le charbon ou le minerai de fer ou de petites quantites de matieres de grande valeur comme les metaux precieux. Tout en ayant des prix comparables a ces derniers, les matieres nucleaires speciales sont de nature differente et seront utilisees en quantites beaucoup plus importantes que les

  5. Combustion physics

    Science.gov (United States)

    Jones, A. R.

    1985-11-01

    Over 90% of our energy comes from combustion. By the year 2000 the figure will still be 80%, even allowing for nuclear and alternative energy sources. There are many familiar examples of combustion use, both domestic and industrial. These range from the Bunsen burner to large flares, from small combustion chambers, such as those in car engines, to industrial furnaces for steel manufacture or the generation of megawatts of electricity. There are also fires and explosions. The bountiful energy release from combustion, however, brings its problems, prominent among which are diminishing fuel resources and pollution. Combustion science is directed towards finding ways of improving efficiency and reducing pollution. One may ask, since combustion is a chemical reaction, why physics is involved: the answer is in three parts. First, chemicals cannot react unless they come together. In most flames the fuel and air are initially separate. The chemical reaction in the gas phase is very fast compared with the rate of mixing. Thus, once the fuel and air are mixed the reaction can be considered to occur instantaneously and fluid mechanics limits the rate of burning. Secondly, thermodynamics and heat transfer determine the thermal properties of the combustion products. Heat transfer also plays a role by preheating the reactants and is essential to extracting useful work. Fluid mechanics is relevant if work is to be performed directly, as in a turbine. Finally, physical methods, including electric probes, acoustics, optics, spectroscopy and pyrometry, are used to examine flames. The article is concerned mainly with how physics is used to improve the efficiency of combustion.

  6. Proportioning of {sup 79}Se and {sup 126}Sn long life radionuclides in the fission products solutions coming from spent fuels processing; Dosage des radionucleides a vie longue {sup 79}Se et {sup 126}Sn dans les solutions de produits de fission issues du traitement des combustibles nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Comte, J

    2001-11-01

    The determination of radionuclides present in waste resulting from the nuclear fuel reprocessing is a request from the regulatory authorities to ensure an optimal management of the storage sites. Long-lived radionuclides (T{sub 1/2} > 30 years) are particularly concerned owing to the fact that their impact must be considered for the long term. Safety studies have established a list of long-lived radionuclides (LLRN) whose quantification is essential for the management of the disposal site. Among these, several are pure {beta} emitters, present at low concentration levels in complex matrices. Their determination, by radiochemical method or mass spectrometry, involves selective chemical separations from the others {beta}/{gamma} emitters and from the measurement interfering elements. The work undertaken in this thesis relates to the development of analytical methods for the determination of two long-lived radionuclides: selenium 79 and tin 126, in acid solutions of fission products present in nuclear fuel reprocessing plant. For selenium 79, a {beta} emitter with a half live estimated to be 10{sup 6} years, the bibliography describes different chemical separation methods including precipitation, liquid-liquid extraction and chromatography on ionic resins. After optimisation on a synthetic solution, two of these techniques, precipitation by potassium iodine and separation with ion exchange resins were applied to a genuine solution of fission products at Cogema La Hague. The results showed that only the ion exchange method allows us to obtain a solution sufficiently decontaminated (FD{beta}{gamma} = 250) with a significant selenium recovery yield (85%). This separation allows the measurement of the {sup 79}Se by electrothermal vaporization coupled with inductively coupled plasma mass spectrometry (ETV-ICP/MS), after transfer of the samples to CEA/Cadarache. The concentration of {sup 79}Se measured is 0,42 mg/L in the solution of fission products with an isotopic ratio {sup 79}Se/{sup 82}Se equal to that recommended by the modelling codes for this fuel. Further analyses were carried out by liquid scintillation counting after two additional chemical treatment steps for purification. For tin 126, a {beta} emitter with a half-live estimated to 10{sup 5} years, the studies of separation methods described in the literature made it possible to define a liquid-liquid protocol of extraction with N-benzyl-phenylhydroxylamine (BPHA). Its application on genuine solution of fission products was performed with high chemical recovery yield (90%) and decontamination factors (FD{sub {beta}}{sub {gamma}} = 10{sup 5}). The measurements carried out by ICP/MS made it possible to quantify {sup 126}Sn (2,3 mg/L) and to determine the isotopic composition of tin in the fission product solution. The isotopic composition of tin obtained was in good agreement with the data recommended by modelling codes. Complementary measurement on {sup 126}Sn, and its decay products, were carried out by gamma spectrometry. Therefore, it was possible to deduce a value of the half-life of {sup 126}Sn found equal to 2,63.10{sup 5} years. (author)

  7. Nuclear fuel cycle and marine environment. Behavior of the Rhone river effluents in the mediterranean sea and of wastes dumped in the northeast atlantic; Cycle du combustible nucleaire et milieu marin. Devenir des effluents rhodaniens en mediterranee et des dechets immerges en atlantique nord-est

    Energy Technology Data Exchange (ETDEWEB)

    Charmasson, S

    1998-07-01

    Man-made radionuclides released into the marine environment by the installations from the nuclear fuel cycle are used as tracers of various bio-geochemical processes. Several installations belonging to the whole nuclear fuel cycle, except the uranium mining, are set up on the Rhone River Banks. The sea disposal of low and intermediate level radioactive waste has never been authorized in the Mediterranean sea but several sites have been used in the North-East especially in abyssal waters. Radionuclides released by the Rhone river installations are used in order to study the dynamics of the Rhone inputs into the Mediterranean Sea. In the river, freshwater samples reflect quite accurately the discharge composition with a predominance of {sup 106}Ru, a radionuclide mostly released by the spent nuclear fuel reprocessing plant in Marcoule. Conversely, at the Rhone mouth, in the sediment compartment {sup 106}Ru yields to caesium isotopes ({sup 134}Cs and {sup 137}Cs) in importance. As these two isotopes demonstrate very different half-lives (30,2 and 2,1 years respectively), the temporal evolution of their ratio acts as a chronometer enabled to date sediment accumulation near the river mouth. Mean accumulation rates greater than 35 cm y{sup -1} have been determined in the pro-deltaic zone near the Roustan buoys over the period 1983-1991. Accumulation rates decrease rapidly with distance from the mouth and therefore most of the {sup 137}Cs inventory in this part of the Gulf of Lions is limited to the pro-deltaic area. A first study about the part the different {sup 137}Cs sources in the Mediterranean Sea play in this inventory has been carried out. Direct (atmospheric) and indirect (fluviatile) inputs due to fallout from both past nuclear tests and the Chernobyl accident could contribute to this inventory at the highest to 40 % while the industrial releases could contribute at the lowest to 60 %. The last site used for the dumping of low and intermediate level radioactive waste in the North-East Atlantic has been the subject of studies especially as regards the biological compartment. Indeed, the occurrence in abyssal waters of a very motile fauna, i.e. fish (Coryphaenoides armatus) and amphipods (Eurythenes gryllus), able to undertake important vertical migrations into the water column, represents a possible pathway towards the surface for the dumped radionuclides. The ignorance as regards populations inhabiting this site has led to a study of the population structure for the amphipod Eurythenes gryllus. This species is cosmopolite since it is found at all the latitudes in the world ocean both in bathyal and abyssal waters. Well known for its necrophagy and ability to consume baits, it is supposed to feed on carcasses. However, study of a natural radionuclide, i.e. {sup 210}Po, in this species has shown that it is possible that it feeds also on particle fluxes. In order to verify the validity of the data used for the modelling of the radiological assessment of these operations, in situ labelling experiments have been realized on these amphipods as well as on polychaetes from food labelled with radionuclides characterizing the dumped wastes. Though these results are still too few to acknowledge this validity, as expected from studies on coastal species the transfer factors food-organisms are quite low. Analyses carried out for surveillance purposes both on the fish Coryphaenoides armatus and the amphipod Eurythenes gryllus show that in these deep waters the main source of man-made radioactivity is the global fallout due to the atmospheric nuclear testing carried out mainly in the sixties. A transfer via the particle fluxes is necessary to explain the concentrations found for {sup 3}H, {sup 137}Cs, {sup 238}Pu and {sup 239+240}Pu. However, {sup 238}Pu/{sup 239+240}Pu isotopic ratios in some fish samples suggest and influence from the dumped wastes and underline the possible part taken by these necrophagous organisms in the dispersion of radionuclides released form the low and intermediate level radioactive waste dumped in the North-East Atlantic. (author)

  8. Study of the aqueous corrosion mechanisms and kinetics of the AlFeNi aluminium based alloy used for the fuel cladding in the Jules Horowitz research reactor; Etude des mecanismes et des cinetiques de corrosion aqueuse de l'alliage d'aluminium AlFeNi utilise comme gainage du combustible nucleaire de reacteurs experimentaux

    Energy Technology Data Exchange (ETDEWEB)

    Wintergerst, M.

    2009-05-15

    For the Jules Horowitz new material-testing reactor (JHR), an aluminium base alloy, called AlFeNi, will be used for the cladding of the fuel plates. This alloy (Al - 1% Fe - 1% Ni - 1 % Mg), which is already used as fuel cladding, was developed for its good corrosion resistance in water at high temperatures. However, few studies dealing with the alteration process in water and the relationships with irradiation effects have been performed on this alloy. The conception of the JHR fuel requires a better knowledge of the corrosion mechanisms. Corrosion tests were performed in autoclaves at 70 C, 165 C and 250 C on AlFeNi plates representative of the fuel cladding. Several techniques were used to characterize the corrosion scale: SEM, TEM, EPMA, XRD, Raman spectroscopy. Our observations show that the corrosion scale is made of two main layers: a dense amorphous scale close to the metal and a porous crystalline scale in contact with the water. More than the morphology, the chemical compositions of both layers are different. This duplex structure results from a mixed growth mechanism: an anionic growth to develop the inner oxide and a cationic diffusion followed by a dissolution-precipitation process to form the outer one. Dynamic experiments at 70 C and corrosion kinetics measurements have demonstrated that the oxide growth process is controlled by a diffusion step associated to a dissolution/precipitation process. A corrosion mechanism of the AlFeNi alloy in aqueous media has been proposed. Then post-irradiation exams performed on irradiated fuel plates were used to investigate the effects of the irradiation on the corrosion behaviour in the reactor core. (author)

  9. Design of the Small Rods Forming the Fuel Element of the First Charge of the EL4 Reactor. Cladding Problems; Etude des crayons constituant l'element combustible du premier jeu d'EL4 - probleme de la gaine; Problema pokrytiya nebol'shikh steeknej, obrazushchikh toplivnyj ehlement pervoj zagruzki reaktora EL.4; Estudio de las barras que constituyen los elementos combustibles de la primera carga del reactor EL4 - el problema de las vainas

    Energy Technology Data Exchange (ETDEWEB)

    Bailly, H.; Ringot, C.; Weisz, M. [Centre d' Etudes Nucleaires de Saclay (France)

    1963-11-15

    The fuel element for the first charge of EL4 makes use of stainless steel cans. The grade of steel chosen and the can thickness depend on the corrosion resistance and mechanical strength required. The operating stresses and temperatures are such that fabrication of a can lasting throughout the life of the fuel element calls for a highly resistant grade of steel, of thickness greater than 0.5 mm. When the can bears on the fuel as a result of creep, deformation in diametrical clearance may lead to ovalization and folding, while deformation in longitudinal clearance may cause buckling of the can. Numerous tests have been carried out on cans of thickness 0.3 and 0.4 mm to determine type of deformation as a function of clearance. To be certain of avoiding ovalization with the thicknesses proposed and to keep the internal temperature of the fuel as low as possible, the clearance must be reduced to zero in fabrication. (author) [French] L'element combustible du premier jeu EL4 utilise des gaines en acier inoxydable. Le choix de la nuance et de l'epaisseur de la gaine est lie a des considerations de tenue a la corrosion et de tenue mecanique. Les contraintes et les temperatures d'utilisation ne permettent pas de concevoir une gaine resistante pendant toute la vie de l'element combustible a moins d'utiliser une nuance tres resistante et d'epaisseur superieure a 0,5 mm. On admet que la gaine s'applique par fluage sur le combustible: la deformation dans les jeux diametraux peut conduire a la formation d'une ovalisation et d'un pli; la deformation dans les jeux longitudinaux peut conduire a des flambages de la gaine. De nombreux essais ont ete realises sur des gaines d'epaisseurs 0,3 et 0,4 mm pour connaitre le mode de deformation en fonction des jeux. Pour etre certain de ne jamais avoir d'ovalisation avec les epaisseurs envisagees, et pour avoir la temperature a coeur du combustible la plus basse possible, on est conduit a reduire a zero le jeu en fabrication. (author

  10. 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

  11. Study of the combustion of aluminium and magnesium particulates: influence of the composition of the gaseous mixture and of pressure; Etude de la combustion de particules d'aluminium et de magnesium: influence de la composition du melange gazeux et de la pression

    Energy Technology Data Exchange (ETDEWEB)

    Legrand, B.

    2000-07-01

    The combustion of metal particulates has a major interest in the domain of space propulsion. Aluminium is today used as doping material in the solid propellant of Ariane 5 rocket engines. Magnesium represents a possible fuel for propellers allowing a come back from Mars. An electrostatic levitation device has been used to study the combustion in controlled environment of particulates having a size representative of those encountered in propellers. The particulates are ignited with a laser and observed by fast cinematography. The inhibitive property of hydrogen chloride, an important constituent of the propellant atmosphere, on the combustion of aluminium particulates has been evidenced. These results have been compared with those obtained with a kinetic model in gaseous phase. The combustion of magnesium particulates in carbon dioxide has been studied for 53-63 {mu}m and 1-2 mm particulates. It is shown that the ignition of small particulates is controlled by the chemical kinetics and that the limit ignition pressure is reversely proportional to the particulates size. A study on big samples, performed in normal gravity but also in reduced gravity to get rid of the natural convection phenomena, has permitted to show a pulsed combustion regime linked with the presence of heterogenous reactions. The measurement of the combustion durations for the different sizes of particulates has permitted to propose a correlation between these two parameters for the particulate diameters comprised between 50 {mu}m and 2 mm. (J.S.)

  12. 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.)

  13. 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.)

  14. Communication Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material, Software and Related Technology; Communication recue de certains Etats Membres concernant les directives applicables aux transferts d'equipements, de matieres et de logiciels a double usage dans le domaine nucleaire, ainsi que de technologies connexes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-09-09

    The Agency has received a Note Verbale from the Permanent Mission of Hungary, dated 14 June 2010, in which it requests that the Agency circulate to all Member States a letter of 7 May 2010 from the Chairman of the Nuclear Suppliers Group, Ambassador Ms. Gyorgyi Martin Zanathy, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America,1 providing further information on those Governments' Guidelines for Nuclear Transfers [French] L'Agence a recu une note verbale de la mission permanente de la Hongrie, en date du 14 juin 010, lui demandant de communiquer a tous les Etats Membres une lettre du 7 mai 2010 du president du Groupe des fournisseurs nucleaires, l'ambassadeur Gyorgyi Martin Zanathy, adressee au Directeur general au nom des gouvernements des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Chine, Croatie, Chypre, Danemark, Espagne, Estonie, Etats-Unis d'Amerique, Federation de Russie, Finlande, France, Grece, Hongrie, Irlande, Islande, Italie, Japon, Kazakhstan, Lettonie, Lituanie, Luxembourg, Malte, Norvege, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Roumanie, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovaquie, Slovenie, Suede, Suisse, Turquie et Ukraine1. Cette lettre apporte des informations supplementaires sur les Directives de ces gouvernements applicables aux transferts nucleaires.

  15. Effets du milieu sur la propagation des neutrinos dans la matiere nucleaire

    CERN Document Server

    Margueron, J

    2001-01-01

    We study the elementary interactions between neutrinos and dense matter in a proroneutron 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^{tau tau'}_0 (where tau, tau' = proton or neutron)We calculate nthe pure neutron matter response functions with and withoutcharge exchange, describing nuclear correlations in both approaches : non-relativistic and relativistic. At the end we calculate neutrino mean free paths for 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.

  16. 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)

  17. Should we be scared of nuclear energy?; Faut-il avoir peur du nucleaire?

    Energy Technology Data Exchange (ETDEWEB)

    Allegre, C.

    2011-07-01

    The recent accident of the Fukushima daiichi power plant has re-launched the nuclear debate in France. On the one hand, the nuclear power allows the French consumers to benefit by the cheapest electricity in Europe. On the other hand the undeniable accidents spread fears and doubts about the safety of nuclear facilities. Therefore, should we trust the scientists and technical specialists when they claim that the potential danger is weak? The author takes stock of the question without taboos or prejudices and supplies to us the scientific, technical, economical and political elements allowing anyone to make his own opinion based on reason and not on emotion or fear. (J.S.)

  18. 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.)

  19. The control of hospital wastes - 'ACROnic du nucleaire' nr 86, September 2009

    International Nuclear Information System (INIS)

    2009-09-01

    This article first describes how radioactive elements are used in hospital and research departments: in nuclear medicine (for radiotherapy, in vivo diagnosis), in isotopic analysis laboratories, in research laboratories. It indicates the nature and characteristics of frequently used radio-elements (type of emission, maximum energy, percentage of emission, period). It evokes the regulation related to waste management, and comments the assessment of controls of effluents of hospitals as they have been performed by the ACRO (variation in time during the day, technetium activity, iodine 131 activity, indium 111 activity from 2004 to 2008, other detected radionuclides). It discusses the impact on the environment (in waterways)

  20. Tritium: an underestimated health risk- 'ACROnic du nucleaire' nr 85, June 2009

    International Nuclear Information System (INIS)

    Barbey, Pierre

    2009-06-01

    After having indicated how tritium released in the environment (under the form of tritiated water or gas) is absorbed by living species, the author describes the different biological effects of ionizing radiations and the risk associated with tritium. He evokes how the radiation protection system is designed with respect to standards, and outlines how the risk related to tritium is underestimated by different existing models and standards. The author discusses the consequences of tritium transmutation and of the isotopic effect

  1. After Fukushima in the North Contentin - 'ACROnic du nucleaire' nr 95, December 2011

    International Nuclear Information System (INIS)

    Anger, Paulette; Anger, Didier; Autret, Jean-Claude; Barbey, Pierre; Boilley, David; Guillemette, Andre; Rousselet, Yannick; Sene, Monique; Zerbib, Jean-Claude

    2011-12-01

    This document raises questions on the safety and security of nuclear installations in North-Cotentin after the Fukushima accident. These questions concern the responsible authority in case of accident, the problems associated with subcontracting, the existing organisation and measures related to radiation protection and medical monitoring, the way dose limits will be computed and how people will be informed when there is no more electricity or telephone, the actual exposure level when plume effect and food are taken into account, the issue of domestic and industrial waters (how contamination will be stopped), the way huge quantities of contaminated lands and wastes will be managed in France. It also evokes other issues (the distribution of iodine, hacking of computer systems, extreme meteorological events, historic earthquakes), some of them being specific to La Hague AREVA NC plant (storage of fission products, storage pools for irradiated fuels, storage of plutonium oxide and MOX wastes), to the Flamanville power station (location and protection of the control room and of spare systems, hot shutdown of the reactor, failures of steam generator tubes, hydrogen management in case of loss of coolant, toughness of seals in the primary circuit, and so on), and to the EPR (reliability of control clusters, efficiency of corium receptor, sinking of an oil tanker and oil-slick)

  2. 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)

  3. World atlas of nuclear industry: civil and military; Atlas mondial du nucleaire: Civil et militaire

    Energy Technology Data Exchange (ETDEWEB)

    Alexandre, Nicolas

    2011-07-01

    Todays, with the energy supplies and global warming concerns, nuclear energy in making a come-back, witness the numerous nuclear programs launched or re-launched in the US, in Europe, China and India. In parallel, on the military side, the deterrence strategy remains in the center of security politics of big powers. This atlas takes stock of the overall issues linked with the nuclear technology: production, civil applications (power generation, medicine etc..), military usages (naval propulsion, weapons). It answers the main questions of this complex world, often dominated by secrecy: who does what in the nuclear domain in France? Is an accident, like the Chernobyl's one, possible today in Europe? What solutions for radioactive wastes? Do we take risks when we export our reactor technologies to Middle-East countries? Are we at the dawn of a new arms rush? What do international agreements foresee in this domain? Taking into account the costs, the hazards and the advantages of nuclear industry, the atlas shows that it is possible to establish solid technical and legal barriers between its civil and military sides. (J.S.)

  4. Nuclear proliferation in South Asia; La proliferation nucleaire en Asie du Sud

    Energy Technology Data Exchange (ETDEWEB)

    Lamballe, A

    2007-07-15

    Neither India nor Pakistan has signed the Nuclear Non-Proliferation Treaty or the Comprehensive Test Ban Treaty.By carrying out tests in 1998, they therefore violated no international agreement but dealt a severe blow to non-proliferation by inciting other countries, including Iran, to develop nuclear weapons. The purpose of India strike force is to deter China; Pakistan hopes that with a credible strike force it will be able to deter any major attack by India. The nuclear phenomenon is now firmly entrenched in the minds of all those on the subcontinent, where the arms race continues without let-up on all fronts: witness the many launches of ballistic and cruise missiles by both countries. And now that radical Islamist movements are showing an interest in nuclear weapons systems there is a risk of tipping from the rational to the irrational world, with all its attendant dangers. (author)

  5. The renaissance of Italian nuclear power; La renaissance du nucleaire italien

    Energy Technology Data Exchange (ETDEWEB)

    Bouchter, J.C.; Cassuto, A. [CEA/Ambassade de France a Rome (Italy)

    2010-07-15

    In the fifties Italy was an advanced country in terms of nuclear electricity but as a consequence of the Chernobyl accident Italy changed drastically its energy policy and closed definitely all its nuclear plants. Now in order to be less dependent on energy imports and to reduce its CO{sub 2} emission, Italy has changed its mind and welcomes nuclear power in its future energy mix. The aim is to reach the following contributions for the production of electricity in 2030: 50% from fossil fuels, 25% from renewable energies and 25% from nuclear energy (13.000 MWe) and with a first reactor operating in 2020. The main actors of the renaissance of nuclear power in Italy are: -) ENEL (the second electricity producer in Europe), -) SOGIN, a company that is mainly in charge of the dismantling of nuclear plants, -) ENEA a state agency for the development of new technologies, energy and sustainable development, and -) companies working in the nuclear industry like ANSALDO. Various collaboration agreements have been signed between ENEL and EDF or between ENEA and CEA concerning staff training, nuclear safety or radioactive waste management. The main difficulties of this renaissance of the nuclear energy are to get the agreement of the national and local populations as well as that of the political class that is strongly marked by a division in 2 wings. (A.C.)

  6. The world nuclear market and its prospects; Le marche mondial du nucleaire et ses perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2010-07-15

    This market study of the nuclear industry presents: 1 - the dynamics of nuclear markets: organisation of the nuclear industry (fuel cycle, reactors), market analysis and key figures (uranium production, conversion and enrichment, fuel fabrication, reactor manufacturing, spent fuel reprocessing), strengths in presence and competition structure (companies ranking, market shares, positioning); 2 - nuclear renaissance and its basis: a suitable answer to the present day energy and environmental challenges (carbon-free energy and low volatility of fuel price), conjunction of favourable conditions (security of fuel supplies, political support, necessity of plants renewal), three main uncertainties (waste management, safety aspect, public opinion weight); 3 - perspectives of development at the 2030 prospects: data (scope of renaissance, market size), sector reconfiguration scenarios (evolution of competition, reconfiguration paths, concentration trend); 4 - analysis of the strategy of 13 companies, suppliers of the nuclear industry, with their key figures, positioning and strategy (production capacity, partnerships, external growth investments, new technical developments etc.). (J.S.)

  7. Spectrographic determination of lithium in nuclear grade calcium; Determination spectrographique du lithium dans le calcium nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-07-01

    A method is described for the spectrographic determination of lithium in calcium. The samples are converted directly to CaCO{sub 3}. A method of fractional distillation in the arc, using KCl as carrier, makes it possible to detect and measure the Li content to 0,1 ppm. (author) [French] On decrit une methode de determination spectrographique de Li dans Ca. Les echantillons sont transformes d'une facon simple en CO{sub 3}Ca. Une methode de distillation fractionnee dans l'arc utilisant KCl comme entraineur permet la detection et le dosage de teneurs de Li jusqu'a 0,1 ppm. (auteur)

  8. Quality control in nuclear medicine;Mise en oeuvre du controle de qualite en medecine nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Voyant, C. [Hopital de Castelluccio, unite de radiophysique, 20 - Ajaccio (France); Universite de Corse, CNRS UMR SPE 6134, 20 - Corte (France)

    2010-03-15

    Like in many nuclear medicine centers, the A.F.S.S.A.P.S. decision of November 25, 2008, has slightly changed our habits. The centers with medical physicist already made most of these controls, and this concept was not new for them. But what about the other centers? Sometimes, measures were made as expected, other times the manufacturers were expected to do them during the maintenance time, often nothing was formalized, and even in some cases nothing was done. Our experience in quality control in nuclear medicine is relatively recent, but we find interesting to raise some issues, including the duration for all these controls, the possible delegations, the means necessary to build them and difficulties in applying these controls. (author)

  9. Spectral content of seismic movements produced by underground nuclear explosions; Contenu spectral des mouvements seismiques dus aux explosions nucleaires souterraines

    Energy Technology Data Exchange (ETDEWEB)

    Albaret, A; Duclaux, F [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    After a summary of available data, both theoretical and experimental, concerning the spectral content of seismic movements, a description is given of the experiments carried out during the French nuclear explosions in the Sahara, and of the results obtained on the volume waves. A comparison is then made with certain American results. A new method is described for studying the amplitude spectra; it has made it possible to show that the amount of low frequencies in the spectrum increases with the power of the explosion, and decreases with the distance to the zero point and with the filtering effect of the weathered zone. A calculation is then made of the low cut-off ground filter, this giving a better representation of the initial seismic phenomenon. (authors) [French] Apres avoir resume les connaissances disponibles, aussi bien theoriques qu'experimentales, sur le contenu spectral des mouvements seismiques, on decrit les experiences effectuees a l'occasion des explosions nucleaires francaises du Sahara et les resultats obtenus sur les ondes de volume. Puis on les compare avec certains resultats americains. On decrit une nouvelle methode d'etude des spectres d'amplitudes qui montre que le spectre est d'autant plus riche en basses frequences que la puissance de l'explosion est grande, que la distance au point zero est faible et qu'il est moins filtre par la zone alteree superficielle. Puis on calcule le filtre terrain coupe-bas qui permet de donner une representation plus fidele du phenomene seismique initial. (auteurs)

  10. Biofuels combustion.

    Science.gov (United States)

    Westbrook, Charles K

    2013-01-01

    This review describes major features of current research in renewable fuels derived from plants and from fatty acids. Recent and ongoing fundamental studies of biofuel molecular structure, oxidation reactions, and biofuel chemical properties are reviewed, in addition to combustion applications of biofuels in the major types of engines in which biofuels are used. Biofuels and their combustion are compared with combustion features of conventional petroleum-based fuels. Two main classes of biofuels are described, those consisting of small, primarily alcohol, fuels (particularly ethanol, n-butanol, and iso-pentanol) that are used primarily to replace or supplement gasoline and those derived from fatty acids and used primarily to replace or supplement conventional diesel fuels. Research efforts on so-called second- and third-generation biofuels are discussed briefly.

  11. Nuclear raw materials; Matieres premieres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Cameron, J. [Division of Nuclear Power and Reactors, International Atomic Energy Agency, Vienna (Austria)

    1970-01-15

    It is clear that in the next decades there will be a substantial and increasing demand for uranium to fuel nuclear power stations. In a developing country, the discovery and development of uranium resources can be of importance either for the development of national nuclear power or for the commercial export of uranium. As the time taken between the start of a uranium exploration program and the uranium production stage.may be of the order of 6 - 10 years, it is now opportune to start new exploration so that advantage of the increased demand in the mid-1970s may be achieved. Thorium will also be of interest, but in the more distant future when the thorium cycle for advanced converters and breeder reactors is fully developed [French] Il est certain qu' au cours des prochaines décennies la demande d'uranium pour les centrales nucléaires sera importante et ne cessera de croître. Dans un pays en voie de développement, la découverte et la mise en valeur de ressources d'uranium peut avoir une grande importance, soit en vue de produire de l'énergie nucléoélectrique, soit en vue d'exporter l'uranium. Etant donné que les délais entre le démarrage d'un programme de prospection de l'uranium et le début de la production peuvent être de l'ordre de six ans, il est actuellement opportun de commencer les opérations d'exploration pour pouvoir profiter de la demande accrue qui s' affirmera vers le milieu de la prochaine décennie. Le thorium présentera aussi un certain intérêt, mais à plus long terme. Il faut pour cela que le cycle du thorium pour convertisseurs avancés et surgénérateurs ait été pleinement développé. (author)

  12. The Cyrano program. 1 - description and operation of an irradiation device 'Cyrano'. 2 - results of the experiments Cyrano 1 and 2 (study of the EL 4 first-bach pencil); measurement of the thermal conductivity integral for UO{sub 2} sintered up to 2300 deg C; evolution of fission gases at constant power; Programme Cyrano. 1 - description et exploitation d'un dispositif d'irradiation ''cyrano''. 2 - resultats des experiences cyrano 1 et 2 (etude du crayon EL4 1. jeu). Mesure de l'integrale de conductibilite thermique d'UO{sub 2} fritte jusqu'a 2300 deg C. Evolution des gaz de fission a puissance constante

    Energy Technology Data Exchange (ETDEWEB)

    Stora, J P; Chenebault, P [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    Two rods of the type 'EL 4 first score' have been irradiated in 'Cyrano' capsules which are suited for continuous measurement of the nuclear power evolved and equipped with thermocouples. The variations of the integral of conductivity of sintered 96 per cent theoretical dense UO{sub 2} has been established until 2300 deg. C; these variations are coherent with those previously measured out-of-pile. The released fission gases have been recovered at different times during the irradiation: the kinetics of release of stable gases is such that, in the experimental conditions (T{sub surface} = 610 deg. C, {integral}{sub T{sub s}}{sup T{sub c}} kdT = 34.7 W cm{sup -1}) the fraction of released gases is still widely increasing after 12 days of irradiation. Numerous observations have been made on concentrations of rare gases locally present in the irradiated fuel. (authors) [French] L'irradiation de deux crayons combustibles type EL 4, 1er jeu, a ete menee a bien dans des capsules 'Cyrano' equipees de dispositifs de mesure continue de la puissance nucleaire et de plusieurs reperes de temperatures; la variation de l'integrale de conductibilite thermique de l'oxyde d'uranium fritte (96 pour cent d. th.) a ete tracee jusqu'a 2300 deg. C; la courbe representative de ces variations est coherente avec celle obtenue precedemment hors pile. Les gaz de fission apparus hors du combustible ont ete extraits du crayon a plusieurs reprises pendant l'experience: la cinetique d'accumulation des gaz stables est telle que dans les conditions etudiees (T{sub surface} = 610 deg. C, {integral}{sub T{sub s}}{sup T{sub c}} kdT = 34.7 W cm{sup -1}) la fraction des gaz degages est encore largement croissante apres 12 jours d'irradiation. De nombreuses observations ont ete recueillies sur la nature et la concentration des gaz rares presents en differents points du combustible irradie. (auteurs)

  13. Irradiation and development of the nuclear emulsions exposed to intense fluxes of thermal neutrons with {gamma} rays; Irradiation et developpement des emulsions nucleaires exposees a des flux intenses de neutrons thermiques, accompagnes de rayons {gamma}

    Energy Technology Data Exchange (ETDEWEB)

    Faraggi, H; Bonnet, A; Cohen, J [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1952-07-01

    The thermal neutron fluxes provided by nuclear reactors permit the survey of relatively rare phenomenons, and dosage of very weak quantities of some elements. One of the most favorable detection technique are constituted by the use of the nuclear emulsions. one can mention: - the dosage of uranium by counting in the emulsion the number of traces due to fission fragments after irradiation. - The dosage of the lithium and the boron as trace amounts with the help of nuclear reactions (n, {alpha}) and thermal neutrons. - The research of reactions (n, {alpha}) or (n, p) of very weak cross section for middle or heavy elements. These different applications require however important neutrons fluxes. It had therefore obliged us to search for the most favorable irradiation and development of the emulsions conditions, to get the best visibility of the trajectories and decrease the phenomena of fog on the emulsion, which prevents any observation. (M.B.) [French] Les flux de neutrons thermiques fournis par les reacteurs nucleaires permettent l'etude de phenomenes relativement rares, et le dosage de tres faibles quantites de certains elements. Un des moyens de detection les plus favorables est constitue par l'utilisation des emulsions nucleaires. on peut citer: - le dosage de l'uranium par comptage dans l'emulsion du nombre de traces dues aux fragments de fission apres irradiation. - Le dosage du lithium et du bore a l'etat de traces a l'aide des reactions (n, {alpha}) sous l'action des neutrons thermiques. - La recherche de reactions (n,{alpha}) ou (n,p) de tres faible section efficace pour des elements moyens ou lourds. Ces differentes applications necessite cependant des flux de neutrons important. On a donc ete amene a rechercher les conditions les plus favorables d'irradiation et de developpement des emulsions, de maniere a obtenir la meilleure visibilite des trajectoires et diminuer les phenomenes de voile de l'emulsion, qui empeche toute observation. (M.B.)

  14. The design and construction of a nuclear free-precession magnetometer; Etude et realisation d'un magnetometre a precession libre nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-10-15

    After presenting the advantages of nuclear magnetic resonance with respect to electromagnetic processes, as far as the measurement of the earths' magnetic field is concerned, we deal with the macroscopic theory for the Bloch model and analyse Packard and Varions' experiment. The development of a particular absolute free-precession magnetometer is studied, and the conditions are determined for obtaining a maximum amplitude signal as a function of the geometrical form of the detector coil, of the method of cut-off, and of the coupling between various parts of the system. After having described in detail the technology of amplifiers, we consider the problem of the measurement of the frequency of precession for which an original solution, of analogy form, is proposed and discussed. Complete plans of the equipment are given in an appendix. (author) [French] Apres avoir presente les avantages de la resonance magnetique nucleaire relativement aux procedes electromagnetiques, en ce qui concerne la mesure du champ magnetique terrestre, on traite de la theorie macroscopique dans le modele de Bloch et analyse l'experience de Packard et Varian. On etudie une realisation particuliere d'un magnetometre absolu a precession libre et determine les conditions d'obtention d'un signal d'amplitude maximale en fonction de la forme geometrique du bobinage detecteur, de la methode de coupure, et du couplage entre les differents elements du montage. Apres avoir decrit en detail la technologie des amplificateurs, on aborde le probleme de la mesure de la frequence de precession, pour laquelle une solution originale, sous forme analogique, est proposee et discutee. En annexe est joint un dossier complet des plans de la realisation. (auteur)

  15. Contribution to the study of can deformations in the fuel elements of gas-graphite reactors during thermal cycling; Contribution a l'etude des deformations des gaines des elements combustibles de reacteur graphite-gaz au cours du cyclage thermique

    Energy Technology Data Exchange (ETDEWEB)

    Gauthron, M; Boudouresques, B; Delpeyroux, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The cans of fuel cartridges used in reactors of the gas-graphite type have either longitudinal fins of variable thickness, short herring-bone fins, or else a mixture of the two. An important test of the strength of these cartridges is their behaviour during thermal cycling carried out in cells reproducing in-pile conditions. It has been observed during with rapid cooling that there occurs a shortening at the base of the fins which can be accompanied in particular by a compression effect at the fin type, which has a tendency to curl, and by a tractive force acting on the body of the can at the ends of the longitudinal fins; this last phenomenon can result in a fracturing of the welds at the extremities or of the ends of the cartridge. This report presents first of all the way in which the stress diagram can be drawn for a can touching the fuel, and then the effect of the ratchet along a fin fixed to a bar with or without grooves. Finally the importance is shown of the test cycling variables (temperature, heating and cooling rates). (authors) [French] Les gaines des cartouches combustibles des reacteurs de la filiere graphite-gaz comportent soit des ailettes longitudinales plus ou moins epaisses, soit de courtes ailettes a chevrons, soit un ensemble des deux. Un test important de la tenue des cartouches, est la tenue au cyclage thermique en cellule pour reproduire le comportement en pile. On a observe au cours des cyclages a refroidissement rapide, un raccourcissement a la base des ailettes qui peut s'accompagner notamment d'une mise en compression du sommet de l'ailette qui a tendance a friser, et d'une traction exercee sur le corps des gaines au bout des ailettes longitudinales; ce dernier phenomene peut se traduire par des ruptures de soudures d'extremites ou des parties terminales de la cartouche. Ce rapport presente d'abord la maniere dont peut etre trace le diagramme des contraintes dans une gaine liee au combustible, puis l'effet du rochet le long d

  16. 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'importance tres inegale. Ils meritent qu'on les examine

  17. 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

  18. Health problems raised by the elimination of radioactive wastes and nuclear accidents; Problemes sanitaires poses par l'elimination des dechets radioactifs et par les accidents nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Jammet, H; Mechali, D; Dousset, M [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    residus radioactifs produits par les installations nucleaires. L'evaluation du risque encouru par les populations et la fixation des limites admissibles pour les rejets ne peuvent resulter que d'une connaissance exacte du cheminement des radioelements rejetes, depuis leur source d'emission jusqu'a l'homme. L'incorporation des radioelements dans les chaines alimentaires constitue le premier risque a prendre en consideration. Les facteurs de passage doivent etre envisages, dans toutes les etapes de cette transmission, qu'elles interessent les milieux physiques ou les milieux proprement biologiques, du fait de leur continuite et de leur interdependance. Enfin, les donnees de caractere socio-economique et dietetique doivent etre recueillies pour conduire a une evaluation des risques et des niveaux admissibles reposant non sur des donnees theoriques mais sur des bases concretes et experimentales. Le risque d'accidents nucleaires dans l'industrie atomique, bien que de probabilite tres reduite, doit etre pris en consideration du fait de la gravite de leurs consequences. Les problemes sanitaires se posent d'une part dans le domaine de l'hygiene professionnelle, d'autre part dans celui de l'hygiene publique. Le premier domaine implique un risque double: d'irradiation et de contamination. Le domaine public n'est soumis essentiellement qu'au risque de contamination par les substances radioactives liberees accidentellement dans le milieu. Les etudes sanitaires a mener dans ce domaine comprennent, de ce fait, les recherches sur la therapeutique des irradiations ou des contaminations mais aussi celles relatives au transfert des radioelements depuis l'installation accidentee jusqu'a l'homme, principalement a travers les chaines alimentaires, dans leurs composantes physiques comme dans leurs composantes biologiques. De telles etudes sont a la base des decisions d'ordre sanitaire qu'il conviendrait de prendre dans le cas d'un accident. (auteurs)

  19. 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

    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 combustibles refractaires et de graphites speciaux, et l'etude du comportement des liquides organiques sous radiations. Les installations de

  20. Effet de la rugosité de surface sur les performances du contact ...

    African Journals Online (AJOL)

    Effet de la rugosité de surface sur les performances du contact segment- chemise dans un moteur à combustion interne. The effect of surface roughness on the performances of liner-piston ring contact in internal combustion engine. Amar Ayad. *. , Amar Skendraoui & Ammar Haiahem. Laboratoire de Mécanique Industrielle ...

  1. The 'Pole Nucleaire Bourgogne' for developing the nuclear components industry

    International Nuclear Information System (INIS)

    Kottmann, G.

    2012-01-01

    The 'Pole Nucleaire Bourgogne' (PNB) is a high-technology and heavy industries cluster in Burgundy with an international calling. It aims at innovating, educating and federating in order to place the French nuclear industry in a leading position. PNB gathers 76 small-, and medium-sized enterprises, most of them operating in the metal sector, in design and in the control/measuring sector. The aim of PNB is to make enterprises work and cooperate on specific topics according to their sectors of activities and their skills. PNB has identified 3 domains of strategical innovations: -) ecological manufacturing and durability of heavy components, -) controls for high performance components, and -) maintenance and dismantling techniques in hostile environments. The various industry sectors represented in PNB allows a cross-fertilization between high-tech industries (aeronautics, energy, transportation)

  2. The Enrico Fermi Atomic Power Plant; La centrais nucleaire Enrico Fermi; Atomnaya ehlektrostantsiya im Ehnriko Fermi.; La central nucleoelectrica Enrico Fermi

    Energy Technology Data Exchange (ETDEWEB)

    Hartwell, R. W. [Power Reactor Development Company, Detroit, MI (United States)

    1963-10-15

    sodium-water reaction took place in the No. 1 steam generator. The rupture disc, which was installed for such an eventuality, operated correctly. The cause and effect of this failure is currently being investigated. Completion of pre-operational testing. Anticipating the issuance of a low power licence, the final assembly and test programme is being completed in March. (author) [French] La construction de la centrale nucleaire Enrico Fermi, equipee d'un reacteur surgenerateur a neutrons rapides de 100 MWe, a ete virtuellement terminee en decembre 1961. Au cours des derniers 18 mois, on a minutieusement verifie les circuits et les parties constitutives. Ce programme de verifications avant la mise en service a ete tres utile pour verifier les plans et determiner les modifications a y apporter. Tous les problemes ont pu etre resolus. Voici la liste des principales modifications: Bouclier de graphite. En decembre 1960, on a rempli le circuit primaire de sodium liquide et on a procede a des essais tres pousses. Lorsqu'on a rouvert l'enceinte de protection primaire, apres les essais a 540{sup o}C, on a constate que la plus grande partie des blocs de graphite entourant le reacteur s'etait deterioree. Ces blocs, destines a supporter de hautes temperatures, etaient impregnes de bore; ils s'etaient dilates et avaient perdu leur resistance. Une analyse approfondie a montre que le liant du graphite avait cede. On a decide de remplacer tout le graphite, d'utiliser du carbure de bore a la place du bore, d'assujettir les blocs par des dispositifs mecaniques et de maintenir l'humidite a la valeur minimum. Modifications a l'interieur du caisson du reacteur. On a procede a des reparations et modifications pour supprimer la cause du collage des barreaux et les dommages qui en resultaient, et pour prevenir d'autres defaillances du mecanisme de manutention des cartouches. Pour ce faire, on a du retirer le mecanisme de manutention et vider le caisson contenant le sodium. Des specialistes

  3. Tubular combustion

    CERN Document Server

    Ishizuka, Satoru

    2014-01-01

    Tubular combustors are cylindrical tubes where flame ignition and propagation occur in a spatially confined, highly controlled environment, in a nearly flat, elongated geometry. This allows for some unique advantages where extremely even heat dispersion is required over a large surface while still maintaining fuel efficiency. Tubular combustors also allow for easy flexibility in type of fuel source, allowing for quick changeover to meet various needs and changing fuel pricing. This new addition to the MP sustainable energy series will provide the most up-to-date research on tubular combustion--some of it only now coming out of private proprietary protection. Plentiful examples of current applications along with a good explanation of background theory will offer readers an invaluable guide on this promising energy technology. Highlights include: * An introduction to the theory of tubular flames * The "how to" of maintaining stability of tubular flames through continuous combustion * Examples of both small-scal...

  4. Advanced Combustion

    Energy Technology Data Exchange (ETDEWEB)

    Holcomb, Gordon R. [NETL

    2013-03-11

    The activity reported in this presentation is to provide the mechanical and physical property information needed to allow rational design, development and/or choice of alloys, manufacturing approaches, and environmental exposure and component life models to enable oxy-fuel combustion boilers to operate at Ultra-Supercritical (up to 650{degrees}C & between 22-30 MPa) and/or Advanced Ultra-Supercritical conditions (760{degrees}C & 35 MPa).

  5. Checking the sealing of fuel elements by helium sweating - case of the reactors G2 (1960); Controle de l'etancheite des elements combustibles par ressuage d'helium - cas du reacteur G2 (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Blanc, B; D' Orival, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Choumoff, S [Compagnie Francaise Thomson-Houston, 75 - Paris (France)

    1960-07-01

    The G2 slug is a welded, hermetically sealed unit; the seal is checked by placing the fuel element in a helium atmosphere under pressure, then measuring the quantity of helium it releases in a vessel under vacuum. The theoretical aspect and the conditions of industrial application are reviewed, and the installations described. (author) [French] La cartouche G2 se presente comme un ensemble soude, hermetique; le controle d'etancheite s'effectue en immergeant l'element combustible dans une atmosphere d'helium sous pression puis en mesurant la quantite d'helium qu'il restitue dans une enceinte sous vide. L'aspect theorique et les conditions d'exploitation industrielle sont evoques et les installations decrites. (auteur)

  6. 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)

  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. Critical experiments and nuclear calculations - LAMPRE-I; Experiences critiques et calculs nucleaires concernant le LAMPRE-I; Kriticheskie opyty i yadernye raschety - LAMPRE-I; Experimentos criticos u calculos nucleares relativos al LAMPRE-I

    Energy Technology Data Exchange (ETDEWEB)

    Battat, M E [Los Alamos Scientific Laboratory, University of California, Los Alamos, NM (United States)

    1962-03-15

    As part of a programme to develop plutonium fuels for fast-breeder reactors, the Los Alamos Scientific Laboratory has constructed and is operating a 1-MW sodium-cooled test reactor whose core contains a molten alloy of plutonium andiron (90 at. % Pu, 10 at. % Fe, m.p. 410 deg. C). Reactivity control is provided by the use of a stainless-steel reflector and four nickel control-rods located external to the core. Experiments have been performed at core temperatures (isothermal) of 80, 160 and 480 deg. C to determine critical mass and reflector worth at each of these temperatures. Control-rod worths, from period measurements, and temperature coefficient of reactivity were also measured. Calculations have been made, using the S{sub n} method for solving the neutron transport problem, to determine the basic nuclear parameters of the system. The comparison between calculated and measured values of parameters such as temperature coefficient, control-element worths, and critical mass is also of interest in evaluating the reliability of the design calculations. (author) [French] Un reacteur d'essais de 1 MW refroidi au sodium, dont le coeur contient un alliage fondu de plutonium et defer (90 at. % Pu, 10 at. % Fe, p. f. 410 deg. C), a ete construit et est en fonctionnement au Laboratoire scientifique de Los Alamos, dans le cadre d'un programme d'etudes sur les combustibles au plutonium pour reacteurs surgenerateurs a neutrons rapides. Le controle de la reactivite est assure au moyen d'un reflecteur en acier inoxydable et de quatre barres de controle en nickel, a l'exterieur du coeur. On a fait des experiences a des temperatures du coeur de 80, 160 et 480 deg. C afin de determiner la masse critique et la quantite de reflecteur qui correspond a chacune de ces temperatures. On a aussi mesure l'efficacite des barres de controle, a partir de mesures de periode, ainsi que le coefficient thermique de reactivite. Afin de determiner les parametres nucleaires de base du reacteur, on a

  9. Treatment of Radioactive Effluents at the Saclay Nuclear Research Centre; Traitement des Effluents Radioactifs au Centre d'Etudes Nucleaires de Saclay; 041e 0414 ; Tratamiento de los Efluentes Radiactivos en el Centro de Energia Nuclear de Saclay

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    The Report Gives The Account Of Four Years' Experience In Operating The Treatment Plant For Effluents From The Saclay Nuclear Research Centre. It Contains Data Relating To The Origin, Volume And Treatment Of Waste. (author) [French] Ce rapport presente un bilan d'exploitation de l'installation de traitement des effluents du Centre d'etudes nucleaires de Saclay depuis quatre ans. On donne des chiffres concernant l'origine des residus, leur volume, leur traitement. (author) [Spanish] El autor hace un balance de explotacion de la instalacion de tratamiento de efluentes del centro de Saclay desde hace cuatro anos, dando las cifras correspondientes al origen de los residuos, a su volumen y a su tratamiento. (author) [Russian] V jetom dokumente podvoditsja itog chetyrehletnej jekspluatacii ustanovki po obrabotke zhidkih othotov v Centre jadernyh issledovanij v Sakle. V doklade privodjatsja dannye o proishozhdenii othodov, jh ob'eme i obrabotke. (author)

  10. New features of nuclear excitation by {alpha} particles scattering; Nouveaux aspects de l'excitation nucleaire par diffusion de particules {alpha}

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Inelastic scattering of medium energy a particles by nuclei is known to excite preferentially levels of collective character. We have studied the scattering of isotopically enriched targets of Ca, Fe, Ni, Cu, Zn. In part I, we discuss the theoretical features of the interaction. In part II, we describe the experimental procedure. Results are presented and analysed in part III. {alpha} particles scattering by Ca{sup 40} is showed to excite preferentially odd parity levels. In odd nuclei we have observed multiplets due to the coupling of the odd nucleon with the even-even core vibrations. For even-even nuclei, a few levels are excited with lower cross-sections between the well-known first 2{sup +} and 3{sup -} states. Some could be members of the two phonon quadrupole excitation and involve a double nuclear excitation process. (author) [French] On sait que la diffusion inelastique des particules alpha de moyenne energie excite preferentiellement des niveaux de caractere collectif. Nous avons etudie la diffusion des particules alpha de 44 MeV du cyclotron de Saclay par des isotopes separes de Ca, Fe, Ni, Cu, Zn. Dans la premiere partie nous exposons les theories de cette interaction. Dans la seconde nous decrivons le systeme experimental. Les resultats sont donnes dans la troisieme partie. Nous montrons que les niveaux excites preferentiellement pour {sup 40}Ca par diffusion ({alpha},{alpha}') sont de parite negative. Dans les noyaux pair-impair nous avons observe des multiplets dus au couplage du nucleon celibataire avec les vibrations du coeur pair-pair. Pour les noyaux pair-pair nous avons pu etudier entre le premier niveau 2{sup +} et le niveau 3{sup -} deja bien connus certains etats plus faiblement excites. Il semble qu'ils sont dus a une excitation quadrupolaire a deux phonons et impliquent un processus de double excitation nucleaire. (auteur)

  11. Post-Construction Testing of the Elk River, Hallam and Piqua Power Reactor Plants; Essais apres construction des centrales nucleaires d'Elk River, de Hallam et de Piqua; Predehkspluatatsionnoe ispytanie Ehlk-riverskoj, Khehlpemskoj i Pikuaskoj ehnergeticheskikh reaktornykh ustanovok; Ensayos posteriores a la construccion de las centrales nucleoelectricas de Elk River, Hallam y Piqua

    Energy Technology Data Exchange (ETDEWEB)

    Pursel, C. A. [United States Atomic Energy Commission, Argonne, IL (United States)

    1963-10-15

    numerous, observed or suspected, deficiencies or malfunctions of components which led to additional testing and analyses. In some instances, repair or modification of components was necessary to correct fabrication or engineering errors. Major problem areas are discussed: Elk River Reactor. Discovery of cracks in portions of the reactor vessel surface cladding led to extensive investigations and analyses and required some repairs and vessel modifications. Insufficient steam separation capacity required replacement and modification of some reactor vessel internal hardware. Hallam Nuclear Power Facility. Entrainment of the helium cover gas led to modifications of the secondary sodium loops. Failure of a tube in the intermediate (sodium to sodium) heat exchanger led to analyses to determine the cause of failure followed by removal and repair of the heat exchanger. Piqua Nuclear Power Facility. Chemical cleaning of the piping system damaged several valves which required mere repair or replacement. Leaks in the organic coolant and steam tracing systems caused repeated delays. After completion of the necessary repairs and modifications, the actual performance characteristics of each of the three reactors closely matched design predictions. (author) [French] Les resultats des essais apres construction de trois centrales nucleaires, dans le cadre du programme de demonstration des centrales nucleaires de la Commission de l'energie atomique des Etats-Unis (CEA-EU), permettront peut-etre de faire certaines generalisations concernant cette phase de la construction et de l'exploitation des centrales. Ces trois centrales, le reacteur de puissance d'Elk River (ERR), la centrale nucleaire de Hallam (HNPF), et la centrale nucleaire de Piqua (PNPF), appartiennent a trois filieres differentes: reacteur a eau bouillante a circulation naturelle, reacteur a graphite et a sodium et reacteur ralenti et refroidi par un fluide organique. La periode des essais apres construction a commence a la fin

  12. Fiche technique du spermogramme et du spermocytogramme ...

    African Journals Online (AJOL)

    En Afrique la stérilité du couple constitue un drame social. Selon l'OMS, environ 8 à 12 % des couples africains sont touchés par une infertilité. La responsabilité masculine dans la stérilité est comprise entre 30 à 40%. Les causes de l'infertilité masculine peuvent être l'impuissance et/ ou l'altération du sperme. L'étude de ...

  13. Quantitative measurements of small isotopic samples in gaseous mixtures by utilization of some nuclear properties; Etude des possibilites de mesures de faibles quantites de gaz radioactifs dans un melange en utilisant simultanement plusieurs proprietes nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Maragnon, J; Delperie, C

    1967-12-01

    The question is to define the characteristics of a group of measurements allowing the analysis of traces of radioactive rare gases in gas mixtures of different composition. To distinguish the radioactive isotopes from each other and the activity level reaching 10{sup 6} due to their nuclear properties, the method was chosen to use several nuclear properties: gamma radiation energy, beta particle energy, lifetime of excited states. The choice of a plastic scintillator as beta detector allows to answer satisfactorilly to this demand by measurement of nuclear constants because of the short de/excitation time of this detector. Another advantage is that it can be a reservoir for the sample without any destruction nor modification of the sample. The study has been based on the mixture of Kr-85, the analysis of other rare gases follwos immediately from the adopted principle. [French] Les auteurs ont oriente leur recherche vers une solution permettant de distinguer les isotopes radioactifs les uns des autres et dans des rapports d'activite pouvant atteindre 10{sup 6}, grace a plusieurs de leurs proprietes nucleaires, energie de rayonnement gamma, energie de la particule beta, temps de vie des niveaux excites. Le choix d'un scintillateur plastique comme detecteur beta permet de repondre d'une maniere satisfaisante a la mesure des constantes nucleaires en raison du temps de de/excitation rapide de ce scintillateur. Il offre en outre l'avantage de pouvoir servir de reservoir a l'echantillon sans entrainer aucune destruction ni modification de celui-ci. L'etude a ete basee sur la mixture de Kr-85, l'analyse des autre gaz rares decoulant immediatement du principe adopte. (auteur)

  14. Development of mercury porosimeter. Application to nuclear graphite studies (1961); Mise au point d'un porosimetre a mercure. Application a l'etude des graphites nucleaires (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Bocquet, M; Genisson, J; Sailleau, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    A mercury porosimeter, model IFP-CEA, has been developed for application to nuclear graphite studies. The apparatus is based on the capillary depression phenomenon. The relationship between the radius of a pore and the pressure at which mercury fills it is pr = -2 {sigma} cos {theta} ( {sigma} is the surface tension, {theta} the angle of contact of the mercury). After some theoretical consideration, the apparatus is described. The mercury pressure is increased step-wise from 0 to 1000 kg/cm{sup 2} thus yielding the complete distribution of pores from 92 {mu} to 75 A. Results are, then presented concerning nuclear graphites which show the evolution of the porous structure under the effect of bitumen impregnation. In general, the volume of the large pores decreases while that of the small pores increases. The structure of impregnated products appears to depend to a certain extent on that of the starting materials. It has also been possible to study other products with this porosimeter; the range of measurements possible is such that it may be used for the study of the majority of porous materials. (authors) [French] Un porosimetre a mercure modele IFP-CEA a ete mis au point en vue de son application a l'etude de graphites nucleaires. Le fonctionnement de l'appareil repose sur le phenomene de depression capillaire. On etablit la relation existant entre le rayon r d'un pore et la pression p pour laquelle le mercure peut y penetrer: pr = -2 {sigma} cos {theta} ( {sigma} tension superficielle, {theta} angle de contact du mercure). Apres quelques considerations theoriques, l'appareil utilise est decrit. Il permet de faire varier par palier la pression du mercure entre 0 et 1000 kg/cm{sup 2} et d'etablir ainsi la distribution complete des rayons de pores compris entre 92 {mu} et 75 A. Les resultats d'une etude faite sur des graphites nucleaires sont alors presentes faisant apparaitre l'evolution de la structure poreuse sous l'effet des impregnations au brai. D'une facon

  15. 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)

  16. The First Two Years of Operating Experience of the Kahl Nuclear Power Station; Experience acquise pendant les deux premieres annees de fonctionnement de la centrale nucleaire de Kahl; Opyt pervykh dvukh let ehkspluatatsii atomnoj ehlektrostantsii v Kale; Experiencia adquirida en los primeros cuatro anos de funcionamiento de la central nucleoelectrica de Kahl

    Energy Technology Data Exchange (ETDEWEB)

    Bruchner, H. J. [Aeg-Kernenergieanlagen, Frankfurt-am-Main (Germany); Weckesser, A. [Versuchs-Atomkraftwerk Kahl Gmbh, Kahl (Germany)

    1963-10-15

    Kahl, being the first European private atomic power station, has been operating at load since June 1961. Kahl is equipped with a boiling-water reactor, operating in an indirect cycle and with natural circulation. Its electrical net capacity is 15 MW, and the power produced until February 1963 amounts to 140 million kWh. In the paper the operating experience, particularly the extensive testing programme such as concerning transient behaviour and gammascanning, will be reviewed. Results about the operating performance of certain plant components such as control-rod-drive system, off-gas system and turbine will be presented. After this testing programme the plant has been operated at base load for some time in order to obtain realistic experience on fuel performance. After completion of the base-load phase of operation a nuclear superheating test loop will be installed and run in the Kahl reactor. (author) [French] La centrale de Kahl, la premiere en Europe dont l'exploitation soit assuree par une entreprise privee, alimente le secteur depuis juin 1961. Elle est equipee d'un reacteur a eau bouillante, en cycle indirect, a circulation naturelle. Avec une puissance electrique nette de 15 MW, elle avait produit, jusqu'a fevrier 1963, 140 millions de kWh. Le memoire rend compte de l'experience acquise concernant le fonctionnement de la centrale, notamment du programme etendu des essais effectues sur son comportement en regime transitoire et sur la detection gamma. Il donne, en particulier, des renseignements sur le fonctionnement de certains elements de la centrale tels que le mecanisme de commande des barres de controle, le dispositif d'echappement des gaz et la turbine. A la suite de ce programme d'essais, on fait fonctionner depuis quelque temps la centrale comme centrale de base afin de rassembler des donnees pratiques sur les performances du combustible. A l'expiration de la periode prevue pour le fonctionnement comme centrale de base, on amenagera, dans le reacteur

  17. Les Cahiers du CREAD

    African Journals Online (AJOL)

    Admin

    politique de bas prix exercée par la Russie et le Qatar vient confirmer ce constat ; s'ajoute à cela l'entrée éventuelle du gaz non conven- tionnel, dont son prix actuel de 3/4 $US, offre aux USA l'opportunité d'être exportateur de ..... les compagnies à produire en matière du gaz naturel, tels le prix du gaz naturel, le prix des ...

  18. Bulletin du CRDI #124

    International Development Research Centre (IDRC) Digital Library (Canada)

    Les femmes jouent un rôle important dans les exploitations minières artisanales et à petite échelle en Afrique subsaharienne. De concert ... Couverture du livre: Une vie saine pour les femmes et les enfants vulnérables · Couverture du livre: Entre el activismo y la intervención · Couverture du livre: Revitalizing Health for All.

  19. Bulletin du CRDI #125

    International Development Research Centre (IDRC) Digital Library (Canada)

    L'IOSRS remporte le prix de la diplomatie scientifique · GrowInclusive : la plateforme tant attendue est en construction · Toutes les nouvelles. Activités à venir. Semaine du développement international 2018. Le CRDI célébrera la Semaine du développement international du 4 au 10 février 2018. Suivez-nous sur Twitter et ...

  20. Cooperation in the Event of Nuclear Accidents; Cooperation en Matiere d'Accidents Nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Bresson, G. [CEA, Centre d' etudes nucleaires, de Fontenay-aux-Roses (France)

    1969-10-15

    This paper is concerned only with the action to be taken in respect of an individual directly affected by an accident and not with the more general measures relating to the population as a whole. Keeping the same sequence of ideas, the paper deals with nuclear establishments and cites criteria for classifying them; hence only the relationship between the establishment and the hospital, and between the radiation protection experts and medical personnel, is discussed. The complex organization of emergency measures, reception of the victim of the accident, and the treatment possibly required should be based on standard practice and published material, both national and international, allowance being made for the characteristics of each sector. A ''flexible'' plan of co-ordination is given as an illustration. Action must be taken in such cases at the site of the accident, inside and outside the establishment, and above all at the hospital. All categories of persons are involved in the process, i.e. fellow-workers, management, specialized services, and medical personnel, each with their own part to play. The manpower and equipment brought into service therefore vary, and depend upon the internal and external relations maintained by the establishment. The measures envisaged should provide for the transport, reception and treatment of those involved in the accident. An existing organization of this kind is described as an illustration. Finally, no action can be of value without full knowledge of the facts and thorough training of the personnel. Some clearly defined ideas on the.subject are considered under this heading. (author) [French] Le memoire ne traite que de la conduite a tenir envers un accidente et non du probleme, plus general, des mesures relatives a une population. Dans le meme ordre d'idees, l'etude porte sur les etablissements nucleaires et leurs criteres de classement; il ne s'agit donc que des liaisons entre retablissement et l'hopital et entre les

  1. High Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — At NETL's High-Pressure Combustion Research Facility in Morgantown, WV, researchers can investigate new high-pressure, high-temperature hydrogen turbine combustion...

  2. Combustion Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The Combustion Research Laboratory facilitates the development of new combustion systems or improves the operation of existing systems to meet the Army's mission for...

  3. Combustion chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Brown, N.J. [Lawrence Berkeley Laboratory, CA (United States)

    1993-12-01

    This research is concerned with the development and use of sensitivity analysis tools to probe the response of dependent variables to model input variables. Sensitivity analysis is important at all levels of combustion modeling. This group`s research continues to be focused on elucidating the interrelationship between features in the underlying potential energy surface (obtained from ab initio quantum chemistry calculations) and their responses in the quantum dynamics, e.g., reactive transition probabilities, cross sections, and thermal rate coefficients. The goals of this research are: (i) to provide feedback information to quantum chemists in their potential surface refinement efforts, and (ii) to gain a better understanding of how various regions in the potential influence the dynamics. These investigations are carried out with the methodology of quantum functional sensitivity analysis (QFSA).

  4. Biomass Conversion to Hydrocarbon Fuels Using the MixAlcoTM Process Conversion de la biomasse en combustibles hydrocarbonés au moyen du procédé MixAlcoTM

    Directory of Open Access Journals (Sweden)

    Taco-Vasquez S.

    2013-04-01

    Full Text Available The MixAlcoTM process converts biomass to hydrocarbons (e.g., gasoline using the following generic steps: pretreatment, fermentation, descumming, dewatering, thermal ketonization, distillation, hydrogenation, oligomerization and saturation. This study describes the production of bio-gasoline from chicken manure and shredded office paper, both desirable feedstocks that do not require pretreatment. Using a mixed culture of microorganisms derived from marine soil, the biomass was fermented to produce a dilute aqueous solution of carboxylate salts, which were subsequently descummed and dried. The dry salts were thermally converted to raw ketones, which were distilled to remove impurities. Using Raney nickel catalyst, the distilled ketones were hydrogenated to mixed secondary alcohols ranging from C3 to C12. Using zeolite HZSM-5 catalyst, these alcohols were oligomerized to hydrocarbons in a plug -flow reactor. Finally, these unsaturated hydrocarbons were hydrogenated to produce a mixture of hydrocarbons that can be blended into commercial gasoline. Le procédé MixAlcoTM convertit la biomasse en hydrocarbures (par exemple, en essence selon les étapes génériques suivantes : prétraitement, fermentation, écumage, déshydratation, cétonisation thermique, distillation, hydrogénation, oligomérisation et saturation. Cette étude décrit la production de bioessence à partir de fumier de poulet et de papier en lambeaux, ces deux sources étant des matières premières convoitées ne nécessitant pas de prétraitement. À l’aide d’une culture mixte de microorganismes dérivés de sols marins, la biomasse a été soumise à une fermentation de manière à produire une solution aqueuse diluée de sels de carboxylates, ultérieurement écumés et séchés. Les sels séchés ont été thermiquement convertis en cétones brutes, ensuite distillées afin d’éliminer les impuretés. À l’aide du catalyseur à base de nickel de Raney, les c

  5. Separation of zirconium and hafnium; Separation du zirconium et de l'hafnium

    Energy Technology Data Exchange (ETDEWEB)

    Saint-James, D [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    This account is more chemical than metallurgical in character. The reason for this is that so-called 'nuclear metal' must fulfil standards of purity which only chemical processes can attain. This paper must therefore be considered as a preliminary study, from which the metallurgists can form an idea of the treatments leading to the production of the metal. (author) [French] Cet expose a un caractere chimique plutot que metallurgique. La raison en est que le metal dit 'nucleaire' a des exigences de purete que seuls des processus chimiques peuvent satisfaire. Il faut donc considerer cet expose comme un preliminaire, permettant de donner une idee aux metallurgistes des traitements qui aboutissent a l'elaboration du metal. (auteur)

  6. "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…

  7. 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 discussion des resultats experimentaux

  8. 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

  9. Rotary combustion device

    NARCIS (Netherlands)

    2008-01-01

    Rotary combustion device (1) with rotary combustion chamber (4). Specific measures are taken to provide ignition of a combustible mixture. It is proposed that a hollow tube be provided coaxially with the axis of rotation (6), so that a small part of the mixture is guided into the combustion chamber.

  10. Optimization of fuel cycles: marginal loss values; Optimisation des cycles de combustibles: valeurs marginales des pertes

    Energy Technology Data Exchange (ETDEWEB)

    Gaussens, J. [Commissariat a l' Energie Atomique, 75 - Paris (France); Lasteyrie, B. de; Doumerc, J. [Compagnie pour l' Etude et la Realisation de Combustibles Atomiques, 75 - Paris (France)

    1965-07-01

    'uranium doit etre consideree comme definitivement perdue, alors que le reste pourrait etre recupere et recycle. Le cout eleve des pertes, recyclees ou non, d'autant plus eleve que l'uranium est plus enrichi, exige qu'il en soit tenu compte dans l'optimisation generale des cycles de combustible. Il importe donc de determiner leur niveau le plus souhaitable economiquement, aux diverses etapes d'elaboration du combustible nucleaire. Mais en France et dans d'autres pays, la production de matieres fissiles est geree par l'Etat, tandis que la fabrication de l'element combustible est effectuee par l'industrie privee. Les criteres d'optimisation et l'interet economique accorde aux pertes sont donc differents pour les deux parties de la chaine de fabrication. Pour tenter neanmoins d'atteindre un optimum conforme a l'interet collectif sans intervenir dans la politique de prix de l'entreprise, on peut utiliser la propriete des couts marginaux d'etre egaux entre eux a l'optimum, pour un volume de production donne. On peut donc ajuster le niveau des pertes pour realiser cette egalite des couts marginaux dont le calcul est plus facile a obtenir de la firme que la justification des prix eux-memes. On s'apercoit d'ailleurs que, bien qu'axee essentiellement sur les pertes, cette analyse globale peut conduire a une meilleure utilisation d'autres facteurs de production. On donne un expose theorique et des exemples pratiques de cette methode d'optimisation economique dans le cadre de la fabrication d'elements combustibles destines a des reacteurs du type: uranium naturel, moderes au graphite et refroidis par le gaz carbonique. (auteurs)

  11. 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)

  12. 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.

  13. Magnox Fuel Cycles; Cycles des combustibles gaines de magnox; Toplivnye tsikly magnoks; Ciclos de combustible magnox

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, A. [United Kingdom Atomic Energy Authority, Risley, Warrington, Lancs (United Kingdom)

    1963-10-15

    The interaction between reactivity flux and temperature distributions and irradiation patterns caused by different refuelling policies is considered and present calculation methods outlined. Various refuelling schemes for both batch and continuous discharge systems are compared. The problem of the efficient irradiation of the first charge is considered together with delayed onset refuelling and shuffling schemes. The economic advantages and problems of using non-natural uranium in flattened reactors are discussed. The practical consideration of on-load refuelling schemes on new reactors are considered and reference is made to the experience gained on Bradwell and Berkeley. The effect of the variation of fuel cost and endurance on fuel-cycle economics is outlined. (author) [French] L'auteur etudie en premier lieu l'interaction entre les distributions de la temperature du flux et de la reactivite, d'une part, et le regime de l'irradiation, d'autre part, dans le cas de differents programmes de rechargement du combustible et il decrit brievement les methodes de calcul actuelles. Il compare ensuite differents programmes de rechargement du combustible pour le dechargement par lots et le dechargement continu. Il etudie le probleme de l'irradiation effica ce de la premiere charge dans le cadre de programmes de remplacement et de deplacement des cartouches a action retardee. Il analyse les avantages economiques de l'utilisatio n d'uranium non naturel dans les reacteurs a flux aplati et les problemes qu'elle pose. Il examine les aspects pratiques des programmes de rechargement en marche pour les nouveaux reacteurs, en se referant a l'experience acquise au moyen des reacteurs de Bradwell et de Berkeley. Enfin, il decrit brievement les effets des variations du cout et de la resistance du combustible sur l'economie des cycles de combustible. (author) [Spanish] La memoria estudia la interaccion entre el flujo de reactividad y la distribucion de temperaturas, asi como los

  14. Les méthodes thermiques de production des hydrocarbures. Chapitre 5 : Combustion "in situ". Pricipes et études de laboratoire Thermal Methods of Hydrocarbon Production. Chapter 5 : "In Situ" Combustion. Principles and Laboratory Research

    Directory of Open Access Journals (Sweden)

    Burger J.

    2006-11-01

    Full Text Available II existe plusieurs variantes de la combustion in situ, suivant le sens de déplacement du front de combustion, à co-courant ou à contre-courant, et suivant la nature des fluides injectés, air seul ou injection combinée d'air et d'eau. Les réactions de pyrolyse, d'oxydation et de combustion mises en jeu par ces techniques sont discutées, en particulier la cinétique des principaux mécanismes réactionnels, l'importance du dépôt de coke et l'exothermicité des réactions d'oxydation et de combustion. Les résultats d'essais de déplacement unidirectionnel du front de combustion dans des cellules de laboratoire sont présentés et discutés. Enfin on indique les conditions pratiques d'application des méthodes de combustion in situ sur champ. Possible variations of in situ combustion technique ore as follows : forward or reverse combustion depending on the relative directions of the air flow and the combustion front, dry combustion if air is the only fluid injected into the oil-bearing formation, or fixe/woter flooding if water is injected along with air. The chemical reactions of pyrolysis, oxidation and combustion involved in these processes are described. The kinetics of these reactions is discussed as well as fuel availability in forward combustion and the exothermicity of the oxidation and combustion reactions. The results obtained in the laboratory when a combustion front propagates in unidirectional adiabatic tells are described and discussed. This type of experimentation provides extensive information on the characteristics of the processes. Screening criteria for the practical application of in situ combustion techniques are presented.

  15. Combustion 2000

    Energy Technology Data Exchange (ETDEWEB)

    A. Levasseur; S. Goodstine; J. Ruby; M. Nawaz; C. Senior; F. Robson; S. Lehman; W. Blecher; W. Fugard; A. Rao; A. Sarofim; P. Smith; D. Pershing; E. Eddings; M. Cremer; J. Hurley; G. Weber; M. Jones; M. Collings; D. Hajicek; A. Henderson; P. Klevan; D. Seery; B. Knight; R. Lessard; J. Sangiovanni; A. Dennis; C. Bird; W. Sutton; N. Bornstein; F. Cogswell; C. Randino; S. Gale; Mike Heap

    2001-06-30

    . To achieve these objectives requires a change from complete reliance of coal-fired systems on steam turbines (Rankine cycles) and moving forward to a combined cycle utilizing gas turbines (Brayton cycles) which offer the possibility of significantly greater efficiency. This is because gas turbine cycles operate at temperatures well beyond current steam cycles, allowing the working fluid (air) temperature to more closely approach that of the major energy source, the combustion of coal. In fact, a good figure of merit for a HIPPS design is just how much of the enthalpy from coal combustion is used by the gas turbine. The efficiency of a power cycle varies directly with the temperature of the working fluid and for contemporary gas turbines the optimal turbine inlet temperature is in the range of 2300-2500 F (1260-1371 C). These temperatures are beyond the working range of currently available alloys and are also in the range of the ash fusion temperature of most coals. These two sets of physical properties combine to produce the major engineering challenges for a HIPPS design. The UTRC team developed a design hierarchy to impose more rigor in our approach. Once the size of the plant had been determined by the choice of gas turbine and the matching steam turbine, the design process of the High Temperature Advanced Furnace (HITAF) moved ineluctably to a down-fired, slagging configuration. This design was based on two air heaters: one a high temperature slagging Radiative Air Heater (RAH) and a lower temperature, dry ash Convective Air Heater (CAH). The specific details of the air heaters are arrived at by an iterative sequence in the following order:-Starting from the overall Cycle requirements which set the limits for the combustion and heat transfer analysis-The available enthalpy determined the range of materials, ceramics or alloys, which could tolerate the temperatures-Structural Analysis of the designs proved to be the major limitation-Finally the commercialization

  16. Reduced NOX combustion method

    International Nuclear Information System (INIS)

    Delano, M.A.

    1991-01-01

    This patent describes a method for combusting fuel and oxidant to achieve reduced formation of nitrogen oxides. It comprises: It comprises: heating a combustion zone to a temperature at least equal to 1500 degrees F.; injecting into the heated combustion zone a stream of oxidant at a velocity within the range of from 200 to 1070 feet per second; injecting into the combustion zone, spaced from the oxidant stream, a fuel stream at a velocity such that the ratio of oxidant stream velocity to fuel stream velocity does not exceed 20; aspirating combustion gases into the oxidant stream and thereafter intermixing the aspirated oxidant stream and fuel stream to form a combustible mixture; combusting the combustible mixture to produce combustion gases for the aspiration; and maintaining the fuel stream substantially free from contact with oxidant prior to the intermixture with aspirated oxidant

  17. Du Pont de Nemours

    NARCIS (Netherlands)

    Ros JPM; LAE

    1994-01-01

    Dit rapport over Du Pont de Nemours (produktie van o.a. chemische stoffen) is gepubliceerd binnen het Samenwerkingsproject Procesbeschrijvingen Industrie Nederland (SPIN). In het kader van dit project is informatie verzameld over industriele bedrijven of industriele processen ter ondersteuning

  18. Les Cahiers du CREAD

    African Journals Online (AJOL)

    Admin

    6 juil. 2007 ... La problématique du développement du secteur de l'artisanat en. Algérie a été très peu abordée par les chercheurs, qu'ils soient universitaires ou .... La loi a institué une taxe d'apprentissage dont le taux a été fixé à. 1% de la ...

  19. 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.

  20. Bulletin du CRDI #127

    International Development Research Centre (IDRC) Digital Library (Canada)

    La mise à l'échelle de la recherche et de l'innovation en vue de créer un impact social constitue une priorité pour la communauté du développement. Toutefois ... Nous avons renouvelé notre soutien à la recherche auprès du gouvernement de l'Inde ... Des femmes étudient à l'École supérieure d'infotronique d'Haïti.

  1. Irradiation and development of the nuclear emulsions exposed to intense fluxes of thermal neutrons with {gamma} rays; Irradiation et developpement des emulsions nucleaires exposees a des flux intenses de neutrons thermiques, accompagnes de rayons {gamma}

    Energy Technology Data Exchange (ETDEWEB)

    Faraggi, H.; Bonnet, A.; Cohen, J. [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1952-07-01

    The thermal neutron fluxes provided by nuclear reactors permit the survey of relatively rare phenomenons, and dosage of very weak quantities of some elements. One of the most favorable detection technique are constituted by the use of the nuclear emulsions. one can mention: - the dosage of uranium by counting in the emulsion the number of traces due to fission fragments after irradiation. - The dosage of the lithium and the boron as trace amounts with the help of nuclear reactions (n, {alpha}) and thermal neutrons. - The research of reactions (n, {alpha}) or (n, p) of very weak cross section for middle or heavy elements. These different applications require however important neutrons fluxes. It had therefore obliged us to search for the most favorable irradiation and development of the emulsions conditions, to get the best visibility of the trajectories and decrease the phenomena of fog on the emulsion, which prevents any observation. (M.B.) [French] Les flux de neutrons thermiques fournis par les reacteurs nucleaires permettent l'etude de phenomenes relativement rares, et le dosage de tres faibles quantites de certains elements. Un des moyens de detection les plus favorables est constitue par l'utilisation des emulsions nucleaires. on peut citer: - le dosage de l'uranium par comptage dans l'emulsion du nombre de traces dues aux fragments de fission apres irradiation. - Le dosage du lithium et du bore a l'etat de traces a l'aide des reactions (n, {alpha}) sous l'action des neutrons thermiques. - La recherche de reactions (n,{alpha}) ou (n,p) de tres faible section efficace pour des elements moyens ou lourds. Ces differentes applications necessite cependant des flux de neutrons important. On a donc ete amene a rechercher les conditions les plus favorables d'irradiation et de developpement des emulsions, de maniere a obtenir la meilleure visibilite des trajectoires et diminuer les phenomenes de voile de l'emulsion, qui

  2. The atomic energy course of the 'Institut National des Sciences et Techniques nucleaires' at the centre d'Etudes Nucleaires at Saclay; L'enseignement de genie atomique de l'Institut national des Sciences et Techniques nucleaires au Centre d'Etudes nucleaires de Saclay

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    foreign students. 8- Annexe: list of courses, practical work, pile projects drawn up by the 1957 students. (author)Fren. [French] 1- Les raisons de sa creation. L'electricite de France et l'industrie interessee par le developpement de l'Energie atomique ont demande au Commissariat a l'Energie atomique de former des ingenieurs capables d'etudier des projets de piles et de diriger leur construction. 2- Recrutement et Droits d'inscription. Les demandes d'inscription ont toujours depasse les possibilites. Cette annee, les cours sont suivis par 74 eleves permanents, dont 20 etrangers, et une centaine d'auditeurs libres. Tous les elevont deja ingenieurs ou nantis de grades universitaires eleves. Droit d'inscription: 250 000 F pour les eleves, 125 000 F pour les auditeurs. 3- Organisation de l'Enseignement. II comprend deux options: physique et chimie et dans chaque option: une centaine de conferences, une trentaine de travaux pratiques, des stages dans les services, l'etude d'un projet de reacteur par un groupe de 4 ou 5 eleves. L'ensemble occupe l'annee universitaire du 1 novembre au 14 juillet. 4- Sanction. Un examen final combinant les notes de deux epreuves theoriques, des travaux pratiques, du stage, et du projet conduit a un diplome d'ingenieur en genie atomique. Il n'est pas cree en realite de nouveaux ingenieurs; une mention nouvelle est seulement ajoutee a un diplome deja acquis. Les resultats ont toujours ete excellents. Le pourcentage des echecs est tres faible. 5- Placement des Diplomes. Ils reviennent tous dans leurs industries d'origine qui ont paye leurs salaires et les droits d'inscription en se privant de leurs services pendant les neuf mois de duree des cours. 6- Creations analogues. Un cours analogue a ete cree au Centre d'Etudes Nucleaires de Grenoble. Tandis que celui de SACLAY s'adresse plus specialement aux ingenieurs deja en fonctions, celui de Grenoble est, en principe, destine aux jeunes ingenieurs sortant des ecoles. 7- Conclusion. L

  3. Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — For more than 30 years The Combustion Research Facility (CRF) has served as a national and international leader in combustion science and technology. The need for a...

  4. Alcohol combustion chemistry

    KAUST Repository

    Sarathy, Mani; Oß wald, Patrick; Hansen, Nils; Kohse-Hö inghaus, Katharina

    2014-01-01

    . While biofuel production and its use (especially ethanol and biodiesel) in internal combustion engines have been the focus of several recent reviews, a dedicated overview and summary of research on alcohol combustion chemistry is still lacking. Besides

  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. Maximal combustion temperature estimation

    International Nuclear Information System (INIS)

    Golodova, E; Shchepakina, E

    2006-01-01

    This work is concerned with the phenomenon of delayed loss of stability and the estimation of the maximal temperature of safe combustion. Using the qualitative theory of singular perturbations and canard techniques we determine the maximal temperature on the trajectories located in the transition region between the slow combustion regime and the explosive one. This approach is used to estimate the maximal temperature of safe combustion in multi-phase combustion models

  7. The use radioactive tracers in the study of solid transport in water streams; Emploi de traceurs radioactifs pour l'etude du transport solide dans les cours d'eau

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Jaffry, P; Heuzel, M [Laboratoire National d' Hydraulique de Chatou, 78 (France)

    1960-07-01

    riviere, la premiere a ete consacree a l'etude du charriage des galets dans le Rhone, l'autre a l'etude des transports de sables dans le Niger. Cette derniere experience a ete doublee d'experiences identiques, effectuees sur le modele reduit du fleuve Niger exploite par le Laboratoire de Chatou: dans ces experiences, on utilise le rayonnement du {sup 56}Mn et du {sup 24}Na obtenu par activation directe du noyau d'abricot concasse representant sur le modele reduit le sediment naturel du lit du Niger. Les efforts conjugues du Laboratoire de Chatou et du Centre d'Etudes Nucleaires de Saclay portent actuellement sur l'application des traceurs radioactifs aux etudes sur modeles reduits, dans le double but: a) de disposer d'un meme moyen d'investigation en nature et sur modele reduit pour controler la fidelite du modele, dans la phase des essais d'etalonnage; b) de profiter des facilites d'observation et mesures directes offertes par les modeles reduits pour etudier les possibilites d'amelioration de la methode des traceurs, en particulier en ce qui concerne l'obtention de renseignements quantitatifs. (auteur)

  8. 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

  9. 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 ou les moyens technologiques de protection sont multiples et complexes. Les etudes de

  10. Effet du Pediococcus acidilactici sur le bilan lipidique sanguin du ...

    African Journals Online (AJOL)

    Les résultats relatifs aux performances zootechniques ont montré que l'addition du probiotique a amélioré significativement le gain de poids pendant la phase de croissance se traduisant par un indice de consommation meilleur. Les dosages du cholestérol total, des triglycérides, du HDL et du LDL ont été déterminés à la ...

  11. Operating Experience with Indian Point Nuclear Electric Generating Station; Experience d'exploitation de la centrale nucleaire d'Indian point; Opyt ehkspluatatsii Indian-pojntskoj yadernoj ehlektrostantsii; Experiencia adquirida con la explotacion de la central nucleoelectrica de Indian point

    Energy Technology Data Exchange (ETDEWEB)

    Beattie, W. C.; Freyberg, R. H. [Consolidated Edison Company of New York, Inc., New York, NY (United States)

    1963-10-15

    dont un grand nombre avaient leur origine dans le secteur ''classique'' de la centrale. Ce sont surtout des defectuosites du systeme de commande des barres de controle qui, dans le secteur nucleaire, ont contribue a la chute automatique des barres et aux retards dans la remise en marche apres arret. Le 14 novembre 1962, on a arrete la centrale pour proceder aux changements prevus dans les tuyauteries de la partie classique et pour apporter des modifications ou additions aux organes de commande des barres de reglage (installation d'un purgeur a azote sec pour les logements des organes de commande, afin de reduire les effets des fuites d'eau a travers les joints), n semble que c'etait la la cause principale du mauvais fonctionnement du systeme. La centrale a ete remise en service le 1er janvier 1963. Les essais, jusqu'a 100% de la puissance theorique a charge constante, etaient termines le 27 janvier 1963. Les resultats concordent parfaitement avec les previsions. De nouveaux essais pour etudier la maniere dont le reacteur repond a des variations subites de la demande se poursuivront au printemps 1963. (author) [Spanish] El grupo No. 1 de la central de Indian Point consta de un reactor de 585 MW(t), de agua a presion cuatro circuitos refrigerantes primarios con intercambiadores de calor horizontales, dos sobrecalentadores a petroleo de 500 000 kg/h y un turbogenerador de 275 000 kW. El combustible del reactor consiste en una mezcla de oxido de {sup 235}U totalmente enriquecido y de oxido de {sup 232}T. La central se encuentra a orillas del rio Hudson, a uno 40 km al norte de Nueva York. Debido a la proximidad de esa ciudad se adoptaron dispositivos especiales de seguridad intrinseca para evitar saltos bruscos de reactividad y- prevenir sus efectos radiologicos. La construccion quedo terminada en mayo de 1962. Se cargo el combustible en junio y el reactor alcanzo la criticidad inicial el 2 de agosto de 1962. En el curso del mismo mes, se efectuaron los ensayos de baja

  12. The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II

    Energy Technology Data Exchange (ETDEWEB)

    Loewenstein, W. B. [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    ) [French] L'auteur presente les calculs du comportement d'EBR-II statique, dynamique et sous evolution a long terme de la reactivite ainsi que les resultats et l'analyse des experiences critiques seches faites sur EBR-II et en simulation sur ZPR-III. Il insiste particulieremen t sur les problemes de physique des reacteurs qui, dans l'elaboration du projet, suivent le choix du modele theorique et precedent la construction ou la mise en exploitation. L'auteur presente des analyses de la securite des reacteurs ainsi que diverses considerations sur l'evaluation des risques sous l'angle de leur influence sur le projet de reacteur. Il decrit la simulation d'EBR-II, a partir des renseignements fournis par le ZPR-III ainsi que les mesures critiques seches sur EBR-II. Ces experiences, leur analyse et les previsions des calculs servent de bases pour predire le comportement physique du reacteur. L'auteur approfondit quelque peu la validite intrinseque de l'application des donnees experimentales au fonctionnement du reacteur de puissance. Ceci comprend les donnees precises des dimensions du coeur et/ou de l'enrichissement de l'alliagne combustible, le choix convenable des valeurs de la reactivite prevues en exploitation et pendant l'arret, la determination des coefficients de reactivite a la temperature et a la puissance de fonctionnement, et la distribution precise de la puissance et du flux en fonction de la position dans l'ensemble du reacteur. L'auteur decrit le probleme de l'application des renseignements obtenus a partir d'une geometrie simple, ideale, analytique ou experimentale, a la geometrie reelle hexagonale du reacteur. Il compare le rendement nucleaire, y compris la surgeneration, du reacteur reel par rapport a celui du modele theorique. Il decrit la reactivite a long terme et le comportement energetique de la couche fertile du reacteur dans le cadre de l'etude du cyclage propose du combustible et de l'alliage fertile. L'auteur etudie les questions de securite considerant

  13. Uncertainties in hydrogen combustion

    International Nuclear Information System (INIS)

    Stamps, D.W.; Wong, C.C.; Nelson, L.S.

    1988-01-01

    Three important areas of hydrogen combustion with uncertainties are identified: high-temperature combustion, flame acceleration and deflagration-to-detonation transition, and aerosol resuspension during hydrogen combustion. The uncertainties associated with high-temperature combustion may affect at least three different accident scenarios: the in-cavity oxidation of combustible gases produced by core-concrete interactions, the direct containment heating hydrogen problem, and the possibility of local detonations. How these uncertainties may affect the sequence of various accident scenarios is discussed and recommendations are made to reduce these uncertainties. 40 references

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

    Energy Technology Data Exchange (ETDEWEB)

    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 variation continue du taux de vide dans un canal

  15. Les mots du jazz

    OpenAIRE

    Roueff, Olivier

    2007-01-01

    L’ouvrage d’André Schaeffner constitue la première analyse savante du jazz (1926). Il a marqué une étape importante dans le processus de réinvention du jazz en France en contribuant notamment, par sa réception et les polémiques qu’il a suscitées, à transformer l’identification du jazz d’une musique « américaine » à une musique « noire-américaine » (c’est-à-dire aux « racines » africaines). Les analyses proposées dans cet ouvrage, alors qu’elles désignaient des musiques que la critique de jazz...

  16. New class of combustion processes

    International Nuclear Information System (INIS)

    Merzhanov, A.G.; Borovinskaya, I.P.

    1975-01-01

    A short review is given of the results of work carried out since 1967 on studying the combustion processes caused by the interaction of chemical elements in the condensed phase and leading to the formation of refractory compounds. New phenomena and processes are described which are revealed when investigating the combustion of the systems of this class, viz solid-phase combustion, fast combustion in the condensed phase, filtering combustion, combustion in liquid nitrogen, spinning combustion, self-oscillating combustion, and repeated combustion. A new direction in employment of combustion processes is discussed, viz. a self-propagating high-temperature synthesis of refractory nitrides, carbides, borides, silicides and other compounds

  17. fibrosarcome du larynx

    African Journals Online (AJOL)

    pie du lit tumoral est employée comme complément thé- rapeutique [9] alors que la chimiothérapie est générale- ment indiquée dans les formes métastatiques. Le pronos- tic dépend essentiellement du degré de différentiation his- tologique. En fait, le fibrosarcome bien différencié est caractérisé par la fréquence de récidive ...

  18. du Chott Marouane

    African Journals Online (AJOL)

    plancton de 90 µm de vide de maille. Ils ont été conservés dans du formol à 5%. L'identification de l'espèce est basée sur des critères morphologiques [20]: la forme des furcas, les lobes frontaux des antennes des mâles, de l'organe copulateur (pénis) et du sac ovigère. Le comptage des soies furcales a été réalisé. L'étude ...

  19. Combustion modeling in internal combustion engines

    Science.gov (United States)

    Zeleznik, F. J.

    1976-01-01

    The fundamental assumptions of the Blizard and Keck combustion model for internal combustion engines are examined and a generalization of that model is derived. The most significant feature of the model is that it permits the occurrence of unburned hydrocarbons in the thermodynamic-kinetic modeling of exhaust gases. The general formulas are evaluated in two specific cases that are likely to be significant in the applications of the model.

  20. Health problems raised by the elimination of radioactive wastes and nuclear accidents; Problemes sanitaires poses par l'elimination des dechets radioactifs et par les accidents nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Jammet, H.; Mechali, D.; Dousset, M. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    residus radioactifs produits par les installations nucleaires. L'evaluation du risque encouru par les populations et la fixation des limites admissibles pour les rejets ne peuvent resulter que d'une connaissance exacte du cheminement des radioelements rejetes, depuis leur source d'emission jusqu'a l'homme. L'incorporation des radioelements dans les chaines alimentaires constitue le premier risque a prendre en consideration. Les facteurs de passage doivent etre envisages, dans toutes les etapes de cette transmission, qu'elles interessent les milieux physiques ou les milieux proprement biologiques, du fait de leur continuite et de leur interdependance. Enfin, les donnees de caractere socio-economique et dietetique doivent etre recueillies pour conduire a une evaluation des risques et des niveaux admissibles reposant non sur des donnees theoriques mais sur des bases concretes et experimentales. Le risque d'accidents nucleaires dans l'industrie atomique, bien que de probabilite tres reduite, doit etre pris en consideration du fait de la gravite de leurs consequences. Les problemes sanitaires se posent d'une part dans le domaine de l'hygiene professionnelle, d'autre part dans celui de l'hygiene publique. Le premier domaine implique un risque double: d'irradiation et de contamination. Le domaine public n'est soumis essentiellement qu'au risque de contamination par les substances radioactives liberees accidentellement dans le milieu. Les etudes sanitaires a mener dans ce domaine comprennent, de ce fait, les recherches sur la therapeutique des irradiations ou des contaminations mais aussi celles relatives au transfert des radioelements depuis l'installation accidentee jusqu'a l'homme, principalement a travers les chaines alimentaires, dans leurs composantes physiques comme dans leurs composantes biologiques. De telles etudes sont a la base des decisions d'ordre sanitaire qu

  1. NF ISO 7097-1. Nuclear fuel technology - Uranium dosimetry in solutions, in uranium hexafluoride and in solids - Part 1: reduction with iron (II) / oxidation with potassium bi-chromate / titration method; NF ISO 7097-1. Technologie du combustible nucleaire. Dosage de l'uranium dans des solutions, l'hexafluorure d'uranium et des solides. Partie 1: reduction par fer (II) / oxydation par bichromate de potassium / methode par titrage

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-04-01

    This standard document describes the mode of operation of three different methods for the quantitative dosimetry of uranium in solutions, in UF{sub 6} and in solids: reduction by iron (II), oxidation by potassium bi-chromate and titration. (J.S.)

  2. 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.)

  3. Boiler using combustible fluid

    Science.gov (United States)

    Baumgartner, H.; Meier, J.G.

    1974-07-03

    A fluid fuel boiler is described comprising a combustion chamber, a cover on the combustion chamber having an opening for introducing a combustion-supporting gaseous fluid through said openings, means to impart rotation to the gaseous fluid about an axis of the combustion chamber, a burner for introducing a fluid fuel into the chamber mixed with the gaseous fluid for combustion thereof, the cover having a generally frustro-conical configuration diverging from the opening toward the interior of the chamber at an angle of between 15/sup 0/ and 55/sup 0/; means defining said combustion chamber having means defining a plurality of axial hot gas flow paths from a downstream portion of the combustion chamber to flow hot gases into an upstream portion of the combustion chamber, and means for diverting some of the hot gas flow along paths in a direction circumferentially of the combustion chamber, with the latter paths being immersed in the water flow path thereby to improve heat transfer and terminating in a gas outlet, the combustion chamber comprising at least one modular element, joined axially to the frustro-conical cover and coaxial therewith. The modular element comprises an inner ring and means of defining the circumferential, radial, and spiral flow paths of the hot gases.

  4. Economic Aspects of Air and Gas Cleaning for Nuclear Energy Processes; Aspects Economiques de l'Epuration de l'Air et des Gaz au Cours des Operations Nucleaires; 042d 041a 041e 041d 041e 0414 0; Aspectos Economicos de la Depuracion del Aire y de los Gases en los Procesos de Obtencion de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, Leslie [Harvard School of Public Health, Boston, MA (United States)

    1960-07-01

    In this paper the basic requirements for control of gaseous and particulate effluents are given as applied to problems of feed material production, isotope separation, fuel element fabrication, fuel recovery and reactor operation. There are also instances where non-radioactive nuclear materials with toxic or nuisance effluents such as from beryllium and zirconium production are of concern and these too must be controlled at reasonable costs. The factors involved in capital and operating costs of gas cleaning equipment and the types of applications in the United States are described in some detail. Gaseous effluent problems have, of course, been attacked and controlled by several types of device but their performance has been measured on a comparable basis. It is thus possible to judge operating characteristics on an economic basis as related to power consumption, adsorbent costs, space charges, corrosion problems and other operational factors. The United States Atomic Energy Commission through its contract with the Harvard University Air Cleaning Laboratory has initiated an evaluation program with cooperation, from the various facilities and contractors to the Commission. In this study the basic factors necessary to obtain quantitative cost delineation and evaluation have been outlined and some preliminary findings will be presented. The paper also presents a review of other economic studies made in the United States on particular process or facility applications. (author) [French] Le memoire definit les regles fondamentales auxquelles doit obeir le controle des effluents gazeux et particulaires dans les domaines suivants : production des matieres destinees a alimenter les reacteurs, separation des isotopes, fabrication des cartouches de combustible, recuperation du combustible et fonctionnement des reacteurs. De plus - et c'est notamment ce qui se passe avec la production de beryllium et de zirconium -- il y a des cas ou des matieres nucleaires non radioactives

  5. les cahiers du cread

    African Journals Online (AJOL)

    Our Journal “les cahiers du cread” is a quarterly economic review publishing original findings of empirical research and theoretical debates on fields pertaining to our mission coverage (Macro Economics, Industrial Economics and Firms, Human Development & Social Economics, Agriculture & Environment). Other websites ...

  6. Lump wood combustion process

    Science.gov (United States)

    Kubesa, Petr; Horák, Jiří; Branc, Michal; Krpec, Kamil; Hopan, František; Koloničný, Jan; Ochodek, Tadeáš; Drastichová, Vendula; Martiník, Lubomír; Malcho, Milan

    2014-08-01

    The article deals with the combustion process for lump wood in low-power fireplaces (units to dozens of kW). Such a combustion process is cyclical in its nature, and what combustion facility users are most interested in is the frequency, at which fuel needs to be stoked to the fireplace. The paper defines the basic terms such as burnout curve and burning rate curve, which are closely related to the stocking frequency. The fuel burning rate is directly dependent on the immediate thermal power of the fireplace. This is also related to the temperature achieved in the fireplace, magnitude of flue gas losses and the ability to generate conditions favouring the full burnout of the fuel's combustible component, which, at once ensures the minimum production of combustible pollutants. Another part of the paper describes experiments conducted in traditional fireplaces with a grate, at which well-dried lump wood was combusted.

  7. Corrosion by cooling gases in nuclear reactors; la corrosion par les gaz caloporteurs dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Darras, R. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de Saclay, Section d' etude de la corrosion par gaz et metaux liquides (France)

    1960-07-01

    This article begins with a review of the various materials which can be used and the cooling gases in which they may be heated, emphasis being placed on the importance of reaching temperatures as high as possible. This is followed by a few general remarks on the dry oxidation of metals and alloys, particularly with regard to diffusion phenomena and their various possible mechanisms, and also the methods of investigation employed. Finally, the behaviour of the chief nuclear materials heated in the various gases is studied successively. Materials used for fuel (metallic uranium, uranium oxide, carbides and silicides), canning materials (magnesium, aluminium, zirconium, beryllium, stainless and refractory steels), structural materials (ordinary or slightly alloyed steels), and finally moderators (graphite, beryllium oxide) are deal with in this way. This account is backed up both by the results obtained at the CEA and by work published outside or abroad up to the present day. In conclusion, every effort has been made to direct future research on the basis of the foregoing. Reprint of a paper published in Industries Atomiques - no. 9/10, 1959, p. 3-23 [French] Dans cet article, on passe tout d'abord en revue les divers materiaux utilisables et les gaz de refroidissement dans lesquels ils peuvent etre chauffes, en insistant sur l'interet d'atteindre des temperatures aussi elevees que possible. On rappelle ensuite quelques generalites sur l'oxydation seche des metaux et alliages, notamment en ce qui concerne les phenomenes de diffusion et leurs divers mecanismes possibles ainsi que les methodes d'etude. Enfin, le comportement des principaux materiaux nucleaires chauffes dans les divers gaz est etudie successivement. On traita ainsi des materiaux combustibles (uranium metallique, oxyde, carbures et siliciures d'uranium), des materiaux de gainage (magnesium, aluminium, zirconium, beryllium, aciers inoxydables et refractaires), des materiaux de structure (aciers ordinaires

  8. 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)

  9. The Japanese nuclear sector shaken up again. Japanese press review - 'ACROnic du nucleaire' nr 81, June 2008

    International Nuclear Information System (INIS)

    2008-06-01

    After having briefly recalled the earthquake which occurred in July 2007 in the Niigata province, and also some other accidents which occurred in other power plants operated by TEPCO during the previous years, the author reports what were the consequences for Kashinawaki-Kariwa nuclear power station, and how these consequences have been reported by the press and managed by the Japanese operator TEPCO. He indicates the information published by the press after the accident and those given by TEPCO two days after. He describes the problems of organization on the fire brigade side, the fact that the fire risk had been underestimated by the operator. Radioactive leakages et releases have been discovered quite late, and could have been worse because of damages caused by the earthquake to some installations and if the stopped reactors had been operating. The author describes how the storage pools overflowed and how some installations were flooded by radioactive water. He outlines that TEPCO admitted very late that the reactor cores might have been damaged. He also outlines lacks in seismic studies, and notably the fact that TEPCO detected underwater cracks and estimated they were non active. Moreover seismograph recordings have been lost after the earthquake. The author reports the concerns of several scientists about the seismic risk for the region, and about safety margins of the whole Japanese nuclear fleet. He comments the consequences of the closure of the station in terms of lack of electricity supply. He finally notices that Japanese actors of the nuclear sector (industries, public authorities), despite these problems, decided to pursue the activity of a reprocessing plant, and the construction of new reactors

  10. Guides about nuclear energy in South Korea; Reperes sur l'energie nucleaire en Coree du Sud

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-01

    This document summarizes the main information on nuclear energy in South Korea: number of reactors in operation, type, date of commissioning, nuclear facilities under construction, nuclear share in power production, companies and organizations (Korea electric power company (KEPCO), Korea atomic energy institute (KAERI), Korea institute of nuclear safety (KINS), Korea nuclear energy foundation (KNEF), Korea hydro and nuclear power (KHNP), nuclear environment technology institute (NETEC), Korea basic science institute (KBSI)), nuclear fuel fabrication, research works on waste disposal, nuclear R and D in fission and fusion, safety of nuclear facilities, strategies under study (1000 MWe Korea standard nuclear power plant (KSNP), 1400 MWe advanced power reactor (APR), small power water cooled reactors (system-integrated modular advanced reactor (SMART) research program), development of fast reactors (Kalimer research program), development of the process of direct use of PWR fuel in Candu (DUPIC), use of reprocessing uranium, transmutation of trans-uranian and wastes (KOMAC program), first dismantling experience (Triga Mark II and III research reactors). (J.S.)

  11. 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

  12. Radioactive waste: the poisoned legacy of the nuclear industry; Dechets radioactifs: l'heritage empoisonne du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Rousselet, Y. [Campagne Climat/Energie - Greenpeace (France)

    2011-02-15

    The nuclear industry produces a huge amount of radioactive waste from one end to the other of the nuclear cycle: i.e. from mining uranium to uranium enrichment through reactor operating, waste reprocessing and dismantling nuclear power plants. Nuclear power is now being 'sold' to political leaders and citizens as an effective way to deal with climate change and ensure security of energy supplies. Nonetheless, nuclear energy is not a viable solution and is thus a major obstacle to the development of clean energy for the future. In addition to safety and security issues, the nuclear industry is, above all, faced with the huge problem of how to deal with the waste it produces and for which it has no solution. This ought to put a brake on the nuclear industry, but instead, against all expectations, its development continues to gather pace. (author)

  13. 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.)

  14. North-East Asia: a risk of nuclear proliferation; Un risque de proliferation nucleaire en Asie du Nord-Est?

    Energy Technology Data Exchange (ETDEWEB)

    Courmont, B. [Centre d' Etudes Transatlantiques, 75 - Paris (France)

    2009-04-15

    North-East Asia is distinguished by being potentially one of the world's most nuclearised regions. It includes two nuclear powers recognised by the Non-Proliferation Treaty (Russia and China), a proliferating state (North Korea) and three countries that could very quickly complete nuclear programmes (Japan, South Korea and Taiwan). Now that the question of nuclear proliferation has again surfaced on the international strategic scene, and that North Korea's test of October 2006 has introduced a new security paradigm into the region, how real is the risk of nuclear proliferation in North-East Asia? (author)

  15. Corrosion and alteration of materials from the nuclear industry; La Corrosion et l'alteration des materiaux du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Beauvy, M.; Berthoud, G.; Defranceschi, M.; Ducros, G.; Feron, D.; Guerin, Y.; Latge, C.; Limoge, Y.; Madic, C.; Santarini, G.; Seiler, J.M.; Vernaz, E.; Richet, C.

    2010-07-01

    The control of the corrosion phenomenon is of prime importance for the nuclear industry. The efficiency and the safety of facilities can be affected by this phenomenon. The nuclear industry has to face corrosion for a large variety of materials submitted to various environments. Metallic corrosion operates in the hot and aqueous environment of water reactors which represent the most common reactor type in the world. Progresses made in the control of the corrosion of the different components of these reactors allow to improve their safety. Corrosion is present in the facilities of the back-end of the fuel cycle as well (corrosion in acid environment in fuel reprocessing plants, corrosion of waste containers in disposal and storage facilities, etc). The future nuclear systems will widen even more the range of materials to be studied and the situations in which they will be placed (corrosion by liquid metals or by helium impurities). Very often, corrosion looks like a patchwork of particular cases in its description. The encountered corrosion problems and their study are presented in this book according to chapters representing the main sectors of the nuclear industry and classified with respect to their phenomenology. This monograph illustrates the researches in progress and presents some results of particular importance obtained recently. Content: 1 - Introduction: context, stakes and goals; definition of corrosion; a complex science; corrosion in the nuclear industry; 2 - corrosion in water reactors - phenomenology, mechanisms, remedies: A - uniform corrosion: mechanisms, uniform corrosion of fuel cladding, in-situ measurement of generalized corrosion rate by electrochemical methods, uniform corrosion of nickel alloys, characterization of the passive layer and growth mechanisms, the PACTOLE code - an integrating tool, influence of water chemistry on corrosion and contamination, radiolysis impact on uniform corrosion; B - stress corrosion: stress corrosion cracking, testing means, experimental techniques, internal corrosion of zircaloy sheath - the iodine effect, stress corrosion of nickel alloys - hydrogen influence, stress corrosion of stainless steels; C - wear corrosion: a coupled phenomenon, research in the framework of service life extension of the French electronuclear park; 3 - Corrosion in future reactors: A - corrosion in gas reactors: corrosion by helium impurities, oxidation resistance of silicon carbide, corrosion of graphite and carbon-carbon composites; B - corrosion in liquid metal reactors: sodium FBRs, lead and lead alloys reactors; C- corrosion in molten salt reactors: corrosion of Hastelloy N-type nickel alloys by molten fluorides, mass transfer in aniso-thermal fluoride systems, tellurium embrittlement, electrochemical study of pure metals corrosion in molten fluorides; 4 - Materials corrosion and alteration in the back-end of the fuel cycle: A - corrosion in concentrated nitric environment: materials behaviour, self-catalytic mechanism of nitric acid reduction; B - corrosion in unsaturated aqueous environment: metallic corrosion in unsaturated environment - application to the storage of waste containers, bitumens alteration, reinforced concrete behaviour and iron framework corrosion, concrete behaviour in severe thermal environment; C - Corrosion in saturated aqueous environment: metals corrosion in clayey environment, long-term behaviour of glasses, ceramics alteration, underwater concrete durability, clays transformation; D - materials biodegradation: microorganisms and nuclear wastes, biodegradation of bitumen, concretes and steels; 5 - Conclusion, glossary

  16. 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.)

  17. 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.)

  18. Framatome, from the nuclear engineering office to the international group; Framatome, du bureau d'ingenierie nucleaire au groupe international

    Energy Technology Data Exchange (ETDEWEB)

    Lorin, Philippe [Direction de la Communication, FRAMATOME, Tour Framatome, 92084 Paris La Defense Cedex (France)

    1995-07-01

    A simple office of studies by its inceptions, Framatome became during 30 years an international and diversified group, a world nuclear leader, as designer-manufacturer, fuel supplier and servicing provider. It asserts itself also as a foreground actor in the industrial equipment and connections. This book not only presents an exciting and capital episode of the history of nuclear energy in France but it demonstrate also how an company with a little bit of chance, a lot of endeavour, a plenty of talent and a huge firmness succeeded in becoming an incontestable reference authority in its sector. Staking on technological choices, although different from the creeds inspiring the French decision makers, Framatome has obtained its first orders ahead other French companies, much more powerful and prestigious at the time. The impressive Framatome evolution is presented along six chapters entitled as follows: 1. Beginning of nuclear power; 2. Technological challenge; 3. Industrial challenge; 4. Sectorial challenge; 5. Management challenge; 6. Future. The following four witness' papers are inserted with in the main text: 1. Beginning of Framatome (by P. Boulin); 2. The difficult choice for the PWR system (by M. Boiteux); 3. Impossibly is not French (by A. Giraud); 4. A fabulous common effort (by M. Hug). The book is addressed to the public at large but aims also at the Company's personnel, both the people witnessing the Company's beginning and the newcomers who should know the social body they have chosen to join and to the effort of which they have to contribute with their inventiveness and dynamism.

  19. Balance between automation and human actions in nuclear power plant operation. Results of international cooperation; Equilibre entre automatisation et action humaine dans la conduite des centrale nucleaires, resultats de la cooperation internationale

    Energy Technology Data Exchange (ETDEWEB)

    Sun, B [CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d' Analyse de Surete; Bastl, W [Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany); Olmstead, R [Atomic Energy of Canada Ltd, Mississauga (Canada); Oudiz, A [Electric Power Research Inst., Palo Alto, CA (United States); Jenkinson, J [Nuclear Electric PLC, Gloucester (United Kingdom); Kossilov, A [International Atomic Energy Agency, Vienna (Austria)

    1990-07-01

    'est portee sur le concept de reacteurs 'intrinsequement surs', ce qui pourrait simplifier les equipements de securite, et reduire la complexite des systemes d'information et de controle. La repartition des taches entre homme et machine pourrait bien etre l'une des etapes les plus critiques dans la conception d'une centrale nucleaire et l'un des progres les plus sensibles; de ce fait, elle garantit une approche dans la conception qui est commensurable en qualite avec les hauts niveaux de securite et de qualite de production recherches pour les centrales nucleaires. C'est dans ce climat que l'Agence Internationale pour l'Energie Atomique (AIEA) a constitue en 1989 un groupe de recherche auquel participent les pays membres, lequel groupe possede une experience etendue dans le domaine de l'automatisation des centrales nucleaires. La tache de ce groupe etait d'evaluer ou se situait le juste equilibre entre actions manuelles et automatiques dans la conduite des centrales. Se basant sur des recherches anterieures et sur l'experience de ses membres, le groupe a determine que toute solution unique, totalement deterministe, au probleme de la repartition des taches est impossible. Cependant, dans la mesure ou le role de l'operateur est appele progressivement a se transformer, avec le temps, en un role de gestionnaire du systeme, il est imperatif qu'une procedure systematique de repartition des taches soit utilisee par l'equipe chargee de la conception. Le groupe a propose une methodologie qui s'appuie sur des travaux deja publies, mais il adopte une approche pragmatique, adaptee aux besoins reels des projets. Cette methodologie caracterise un certain nombre de facteurs qui relevent des processus de prise de decision, guide une telle prise de decision, et identifie les secteurs dont il considere qu'ils doivent devenir l'objet de recherches ulterieures. (author)

  20. Flameless Combustion Workshop

    National Research Council Canada - National Science Library

    Gutmark, Ephraim

    2005-01-01

    .... "Flameless Combustion" is characterized by high stability levels with virtually no thermoacoustic instabilities, very low lean stability limits and therefore extremely low NOx production, efficient...

  1. Research Combustion Laboratory (RCL)

    Data.gov (United States)

    Federal Laboratory Consortium — The Research Combustion Laboratory (RCL) develops aerospace propulsion technology by performing tests on propulsion components and materials. Altitudes up to 137,000...

  2. Combustion Byproducts Recycling Consortium

    Energy Technology Data Exchange (ETDEWEB)

    Paul Ziemkiewicz; Tamara Vandivort; Debra Pflughoeft-Hassett; Y. Paul Chugh; James Hower

    2008-08-31

    Ashlines: To promote and support the commercially viable and environmentally sound recycling of coal combustion byproducts for productive uses through scientific research, development, and field testing.

  3. Comparaison du filtre adaptatif RIF et du filtre a base de reseau de ...

    African Journals Online (AJOL)

    Comparaison du filtre adaptatif RIF et du filtre a base de reseau de neurones pour le filtrage du courant de reference pour la commande du filtre actif parallele. C Benachaiba, A Bassou, B Mazari ...

  4. Combustion Stratification for Naphtha from CI Combustion to PPC

    KAUST Repository

    Vallinayagam, R.; Vedharaj, S.; An, Yanzhao; Dawood, Alaaeldin; Izadi Najafabadi, Mohammad; Somers, Bart; Johansson, Bengt

    2017-01-01

    This study demonstrates the combustion stratification from conventional compression ignition (CI) combustion to partially premixed combustion (PPC). Experiments are performed in an optical CI engine at a speed of 1200 rpm for diesel and naphtha (RON

  5. 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)

  6. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology; Communications recues de certains Etats Membres concernant les directives applicables aux transferts d'equipements, de matieres et de logiciels a double usage dans le domaine nucleaire, ainsi que de technologies connexes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-10

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology [French] Le Directeur general de l'Agence internationale de l'energie atomique a recu des notes verbales datees du 1er decembre 2006 des representants permanents aupres de l'Agence des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Croatie, Espagne, Estonie, Etats-Unis d'Amerique, Finlande, France, Grece, Hongrie, Irlande, Italie, Japon, Lettonie, Lituanie, Luxembourg, Malte, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovenie, Suede, Suisse, Turquie et Ukraine, au sujet des transferts d'equipements, de matieres et de logiciels e double usage dans le domaine nucleaire, ainsi que de technologies connexes.

  7. 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)

  8. Economic Criteria Applied to Nuclear Materials Management; Criteres Economiques Applicables a la Gestion des Matieres Nucleaires; Ehkonomicheskie kriterii, primenyaemye pri kontrole i uchete yadernykh materialov; Criterios Economicos Aplicados a la Administracion de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Shelley, W. J.; Kuehn, M. N. [Mallinckrodt Chemical Works, St. Charles, MS (United States)

    1966-02-15

    placed upon such personnel to accept, understand and perform the work. Such personnel selected must be thoroughly and minutely trained in the importance of their activity. Those responsible for the management of nuclear materials must be continually alert to the smallest kind of aberration in the quality and performance of the personnel, the process, the systems, procedures and techniques. Only through such alertness and willingness to revise, so as to secure improvement, does one secure the optimum balance of costs and needs. (author) [French] La gestion des matieres nucleaires doit etre subordonnee aux objectifs principaux du traitement de ces matieres, c'est-a-dire la production d'energie ou la fabrication de produits finis. Les responsables de la gestion des matieres nucleaires doivent donc tenir constamment compte des besoins de la production principale et adapter les methodes de gestion aux operations de facon a pouvoir assurer cette gestion avec un minimum de depenses. Le systeme de gestion des matieres nucleaires doit soigneusement tenir compte des divers facteurs qui influent sur son prix de revient. Il vient en complement des operations et doit entrainer le minimum de frais de personnel et d'analyse et provoquer le moins d'interruptions possible dans les operations. U doit etre integre a ces dernieres, de facon que les renseignements d'ordre quantitatif qu'il permet d'obtenir puissent etre communiques rapidement aux responsables du controle des operations. Le systeme d'enregistrement et de preparation des rapports doit fournir une quantite maximale de donnees subsidiaires. Il doit etre compatible avec les systemes utilises par les fournisseurs et les consommateurs et assurer la diffusion, partout ou cela est possible, de renseignements supplementaires concernant les lots de matieres nucleaires. Les donnees a fournir pour le controle des matieres nucleaires doivent se limiter a celles qui sont necessaires pour s'assurer qu'il n'y a pas de pertes importantes, de

  9. Contribution to the study of solid helium-3 by nuclear magnetic resonance; Contribution a l'etude de l'helium trois solide par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    Due to the unusually large zero point motion of helium three atoms in the solid, the overlap of the atomic wave functions is very important. As a consequence, there are exchange interactions, the theoretical calculation and the experimental measurement of which are discussed. Nuclear magnetic resonance is especially well suited for the latter.A detailed theory is given for both exchange narrowing and Zeeman-exchange cross relaxation, which phenomena are used to measure the exchange interaction as a function of molar volume. The alignment temperature is thus known; it goes down when the pressure goes up and is never higher than three milli degrees. An influence of helium four impurities on the exchange interactions between helium three atoms which are neighbours of the substitutional He is shown. (author) [French] Par suite de l'amplitude exceptionnelle des mouvements de point zero dans l'helium trois solide, le recouvrement des fonctions d'onde atomiques est tres important. Il en resulte des interactions d' echange dont on discute l'evaluation theorique et la mise en evidence experimentale. Cette derniere peut se faire par resonance magnetique; on etudie theoriquement les phenomenes de retrecissement par echange et de relaxation Zeeman-echange que l'on met a profit pour determiner les interactions d'echange en fonction du volume molaire. On en deduit que la temperature d'alignement nucleaire diminue quand on comprime le solide et est au plus de 3x10{sup -3} K. L'influence des impuretes d'helium quatre sur les interactions d'echange entre atomes {sup 3}He voisins de {sup 4}He est mise en evidence. (auteur)

  10. An absolute nuclear magnetic resonance magnetometer; Magnetometre absolu a resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-10-15

    After an introduction in which the various work undertaken since the discovery of nuclear magnetic resonance is rapidly reviewed, the author describes briefly In the first chapter three types of NMR magnetometers, giving the advantages and disadvantages of each of them and deducing from this the design of the apparatus having the greatest number of qualities Chapter II is devoted to the crossed coil nuclear oscillator which operates continuously over a wide range (800 gamma). To avoid an error due to a carrying over the frequency, the measurement is carried out using bands of 1000 {gamma}. Chapter III deals with frequency measurements. The author describes an original arrangement which makes possible the frequency-field conversion with an accuracy of {+-} 5 x 10{sup -6}, and the differential measurement between two nuclear oscillators. The report finishes with a conclusion and a few recordings. (author) [French] Apres une introduction rappelant les divers travaux effectues en resonance magnetique nucleaire depuis sa mise en evidence, l'auteur decrit sommairement dans le premier chapitre trois types de magnetometre a R.M.N. enumerant les avantages et les inconvenients de chacun a partir desquels il projet, l'appareillage reunissant le maximum de qualites. Le chapitre II est consacre a l'oscillateur nucleaire a bobines croisees permettant un fonctionnement continu dons une large plage (800 gamma). Pour eviter une erreur due a l'entrainement de frequence, la mesure s'effectue par bandes de 1000 {gamma} chacune. Le chapitre III traite la mesure de frequence. L'auteur expose un montage original permettant la traduction frequence-champ avec une precision egale a {+-} 5.10{sup -6}, et la mesure differentielle entre deux oscillateurs nucleaires. Une conclusion et quelques enregistrements terminent ce travail. (auteur)

  11. A Method of Identification and Inspection for Inventory Control of Irradiated Fuel Elements; Methode d'Identification et d'Inspection Permettant de Proceder a l'Inventaire des Elements Combustibles Irradies; Metod identifikatsii i proverki pri inventarnom kontrole obluchennykh toplivnykh ehlementov; Metodos de Identificacion e Inspeccion para el Control de las Existencias de Elementos Combustibles Irradiados

    Energy Technology Data Exchange (ETDEWEB)

    Kinderman, E. M.; Mills, J. S. [Stanford Research Institute, Menlo Park, CA (United States)

    1966-02-15

    The reactor discharge and irradiated fuel storage locations should be examined in any complete special nuclear materials inventory. They present, however, special physical difficulties to the auditor or inventory control manager. In these locations the distance between object and observer and the poor illumination and optical distortion caused by the shielding media (water, lead glass) contribute to the difficulties of materials inventory. In an attempt to overcome these difficulties and to provide a system for positive identification of reactor discharged fuel, we have developed a compact and convenient optical examination system utilizing a fixed examination station, a periscope, a telescope, and a camera. This system has been tested in a cobalt irradiation pool by examination of test coupons which were marked in various ways, and then treated in a hot, circulating water loop. In the test system, a water-filled periscope, 11-ft long, a catadioptric telescope placed 16 ft from the periscope, and a 35-mm camera for recording the observations were used. The telescope, camera and mountings are all readily portable since they weigh in total less than 22 lb and have maximum dimensions of 29 in. Photographic observations of test resolution charts in air 20 ft away from the object lens of the telescope have demonstrated that the system can resolve markings 22 {mu}m in width. This corresponds to a resolution of 0.8 second of arc. Tests performed on the water system have shown that resolution in this system is better than 50 {mu}m at 20 ft. This corresponds to a resolution of about 1 second of arc. It is clear that the resolution can never be better than the air path system. The present system used in an actual fuel inventory should adequately reproduce any inventory markings. (author) [French] Tout inventaire complet des matieres nucleaires speciales exige un controle au point de dechargement du reacteur et au point de stockage du combustible irradie. Or, ce controle pose

  12. Le ministre du Commerce international du Canada rencontre des ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    17 juil. 2017 ... La promotion de l'entrepreneuriat, la façon dont le commerce peut profiter aux femmes et à leur famille, et la création d'emplois pour les plus vulnérables étaient au coeur de la discussion en table ronde du ministre du Commerce international du Canada, l'honorable François-Philippe Champagne, et des ...

  13. EPA/IFP EUROPEAN WORKSHOP ON THE EMISSION ON NITROUS OXIDE FROM FOSSIL FUEL COMBUSTION

    Science.gov (United States)

    The report summarizes the proceedings of an EPA/Institut Francais du Petrole (IFP) cosponsored workshop addressing direct nitrous oxide (N2O) emission from fossil fuel combustion. The third in a series, it was held at the IFP in Rueil-Malmaison, France, on June 1-2, 1988. Increas...

  14. 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.)

  15. Material balance of the nuclear sector in 1997. Press conference of 18 March 1998; Bilan du parc nucleaire en 1997. Conference de presse du 18 mars 1998

    Energy Technology Data Exchange (ETDEWEB)

    Dupraz, Bernard; Lecocq, Pierre [Electricite de France (EDF), 75 - Paris (France)

    1998-03-18

    This press report of EDF about the material balance on 1997 presents the global figures stressing upon the effects of the competition policy conducted by the company in the last five years. A 11.2% reduction in the actual expenses of the PWR sector exploitation was recorded in the period 1992 - 1997. Good results were obtained in 1997 in the field of safety and new incentives have been recorded. The principles of a preventive maintenance are stipulated. The cooperation with servicing companies is reported, stressing, particularly, the issues like: the professionalism and safety culture; the amelioration of the economical transparency of enterprises; individual dosimetry - significant advances; regional cooperation; emergency exercises to correct dysfunctions; a better medical surveillance of the intervening servicing enterprises; new regulations foreseen to be in force in 1998. Issues like radioprotection and environmental protection, fuel management, the status of EPR (European Pressurized water Reactor) project are also presented. The technical assistance mission related to the developing in China of two 1000 MW nuclear projects is mentioned as well as the problems posed by the Super Phenix Reactor decommissioning.

  16. [Present conceptions of the C.E.A. concerning] the development of fast neutron reactors in France; [Les conceptions actuelles du C.E.A. concernant] la filiere des reacteurs a neutrons rapides en France

    Energy Technology Data Exchange (ETDEWEB)

    Vendryes, G; Gaussens, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Pasquer, R [Electricite de France (EDF), 75 - Paris (France)

    1964-07-01

    . (authors) [French] 1 - Situation des reacteurs a neutrons rapides dans le programme d'energie nucleaire francais. En developpant un programme base sur l'uranium naturel, la France se trouvera dotee d'un stock important de plutonium riche on isotopes superieurs. L'existence de ce plutonium et de l'uranium appauvri provenant des memes reacteurs a pour consequence logique leur emploi dans des reacteurs a neutrons rapides. Justifiee par cet interet a court terme, la mise au point de reacteurs a neutrons rapides repond par ailleurs a une necessite pour l'avenir. 2 - Enonce des caracteristiques d'une centrale a neutrons rapides de 1000 MW el. Nous indiquons les caracteristiques d'une future centrale a neutrons rapides chargee au plutonium et refroidie au sodium. Si incertaines qu'elles soient, elles constituent un guide necessaire a l'orientation de nos travaux. 3 - Etudes effectuees a ce jour: Nous donnons un apercu des etudes souvent tres preliminaires qui ont permis de retenir les caracteristiques citees plus haut. Les principaux domaines techniques abordes sont les suivants: - Neutronique (masses critiques, taux de regeneration, enrichissements, aplatissement du flux de neutrons, coefficients de reactivite, evolution de la reactivite en fonction de l'irradiation), - Dynamique, controle et surete, - Combustible, - Technologie (conception du bloc-pile, des circuits de sodium, des dispositifs pour la manutention des assemblages). Ces etudes techniques se completent de considerations economiques. Le choix de caracteristiques optimales est lie a l'existence de programmes de production d'electricite et, dans ces programmes, a celle des reacteurs a neutrons thermiques producteurs de plutonium. On montre comment il y a lieu de tenir compte de l'existence du plutonium dans ce contexte, et quels sont les mecanismes qui rattachent l'economie de ce plutonium au choix des parametres essentiels des reacteurs surgenerateurs. 4 - Reacteur prototype: On justifie l'interet d'une etape

  17. Strobes: An oscillatory combustion

    NARCIS (Netherlands)

    Corbel, J.M.L.; Lingen, J.N.J. van; Zevenbergen, J.F.; Gijzeman, O.L.J.; Meijerink, A.

    2012-01-01

    Strobe compositions belong to the class of solid combustions. They are mixtures of powdered ingredients. When ignited, the combustion front evolves in an oscillatory fashion, and flashes of light are produced by intermittence. They have fascinated many scientists since their discovery at the

  18. Catalytically enhanced combustion process

    International Nuclear Information System (INIS)

    Rodriguez, C.

    1992-01-01

    This patent describes a fuel having improved combustion efficiency. It comprises a petroleum based liquid hydrocarbon; and a combustion catalyst comprising from about 18 to about 21 weight percent naphthalene, from about 75 to about 80 weight percent toluene, and from about 2.8 to about 3.2 weight percent benzyl alcohol

  19. Fifteenth combustion research conference

    International Nuclear Information System (INIS)

    1993-01-01

    The BES research efforts cover chemical reaction theory, experimental dynamics and spectroscopy, thermodynamics of combustion intermediates, chemical kinetics, reaction mechanisms, combustion diagnostics, and fluid dynamics and chemically reacting flows. 98 papers and abstracts are included. Separate abstracts were prepared for the papers

  20. Portage vaginal du streptocoque du groupe B chez la femme ...

    African Journals Online (AJOL)

    Introduction: le streptocoque du groupe B est le principal agent impliqué dans les infections materno-fœtales, les septicémies et les méningites du nouveau-né à terme. L'objectif est de déterminer le taux de portage maternel du streptocoque du groupe B (SGB) à terme. Méthodes: un prélèvement vaginal a été réalisé de ...

  1. 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)

  2. 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).  

  3. Hepatiques du Surinam

    NARCIS (Netherlands)

    Jovet-Ast, S.

    1957-01-01

    Il n’existe pas, actuellement, de catalogue des Hépatiques du Surinam. Les Hépatiques de ce pays restent très peu connues. Cependant, certaines ont attiré l’attention des Bryologues et ont été citées dans quelques ouvrages anciens ou récents. Je ne ferai pas ici une révision complète de ces

  4. (l.) Medik du Maroc

    African Journals Online (AJOL)

    PR BOKO

    Résumé. Dipcadi serotinum (L.) Medik, est une plante de la famille des Hyacinthaceae, elle est largement utilisée comme réchauffant et aussi pour combattre la jaunisse. Cette plante trouve une large utilisation par la population de la région côtière du Maroc. À notre connaissance l'huile essentielle de cette espèce n'a ...

  5. Fuels and Combustion

    KAUST Repository

    Johansson, Bengt

    2016-08-17

    This chapter discusses the combustion processes and the link to the fuel properties that are suitable for them. It describes the basic three concepts, including spark ignition (SI) and compression ignition (CI), and homogeneous charge compression ignition (HCCI). The fuel used in a CI engine is vastly different from that in an SI engine. In an SI engine, the fuel should sustain high pressure and temperature without autoignition. Apart from the dominating SI and CI engines, it is also possible to operate with a type of combustion: autoignition. With HCCI, the fuel and air are fully premixed before combustion as in the SI engine, but combustion is started by the increased pressure and temperature during the compression stroke. Apart from the three combustion processes, there are also a few combined or intermediate concepts, such as Spark-Assisted Compression Ignition (SACI). Those concepts are discussed in terms of the requirements of fuel properties.

  6. Fuels and Combustion

    KAUST Repository

    Johansson, Bengt

    2016-01-01

    This chapter discusses the combustion processes and the link to the fuel properties that are suitable for them. It describes the basic three concepts, including spark ignition (SI) and compression ignition (CI), and homogeneous charge compression ignition (HCCI). The fuel used in a CI engine is vastly different from that in an SI engine. In an SI engine, the fuel should sustain high pressure and temperature without autoignition. Apart from the dominating SI and CI engines, it is also possible to operate with a type of combustion: autoignition. With HCCI, the fuel and air are fully premixed before combustion as in the SI engine, but combustion is started by the increased pressure and temperature during the compression stroke. Apart from the three combustion processes, there are also a few combined or intermediate concepts, such as Spark-Assisted Compression Ignition (SACI). Those concepts are discussed in terms of the requirements of fuel properties.

  7. PDF Modeling of Turbulent Combustion

    National Research Council Canada - National Science Library

    Pope, Stephen B

    2006-01-01

    .... The PDF approach to turbulent combustion has the advantages of fully representing the turbulent fluctuations of species and temperature, and of allowing realistic combustion chemistry to be implemented...

  8. 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 ...

  9. Imminent perspectives for industrial application of atomic energy; Perspectives imminentes de l'application industrielle de l'energie atomique

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    This conference raises an inventory of industrial applications and their perspectives for the year 1955. The speaker extrapolate for the forthcoming years the evolution of the role of the nuclear, the nuclear fuel, the different, types of atomic reactors and the state of advancement for different countries. (M.B.) [French] Cette conference dresse un etat des lieux des applications industrielles et de leurs perspectives pour l'annee 1955. L'orateur aborde entre autre l'evolution du role du nucleaire dans les annees a venir, le combustible nucleaire, les differents types de piles atomiques et l'etat d'avancement des differents pays. (M.B.)

  10. Fuel Combustion Laboratory | Transportation Research | NREL

    Science.gov (United States)

    Fuel Combustion Laboratory Fuel Combustion Laboratory NREL's Fuel Combustion Laboratory focuses on designs, using both today's technology and future advanced combustion concepts. This lab supports the combustion chamber platform for fuel ignition kinetics research, was acquired to expand the lab's

  11. 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)

  12. The formation of scientists and technicians at the 'Centre d'Etudes Nucleaires' at Saclay

    International Nuclear Information System (INIS)

    Debiesse, J.

    1958-01-01

    The considerable needs in research workers and scientists which are asked by the nuclear energy obliged the Commissariat a l'Energie atomique to deal with a particular effort to increase the quantitative and qualitative formation of scientists. Most various ways have been used. 1- A National Institute of Nuclear Sciences and Nuclear Techniques was created, by a joint decree of the Prime Minister and the Minister for National Education (june 18, 1957). This Institute of Higher Teaching (250 students) indulges in the following matters: atomic engineering, quantum mechanics, theory and technic of particle accelerators, special metallurgy, radiobiology, thermic and mechanics of fluids. 2- An associated centre of the 'Conservatoire National des Arts et Metiers' was created (200 students) for technical assistants, drawers, etc. 3- In contribution with both electronic industry and Ministry of Work, the Centre d'Etudes Nucleaires contributes to an accelerated formation of technical assistants into Professional Centres. Conclusion: Training of scientists and research workers is one of the most important activities of the Centre d'Etudes Nucleaires de Saclay. Without losing its technical efficiency, it has supplied and varied means adapted to the various purposes that we shall reach. (author) [fr

  13. 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)

  14. 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)

  15. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors; Etudes relatives au comportement physico-chimique de l'eau lourde dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J; Dirian, G; Roth, E; Vignet, P; Platzer, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1959-07-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [French] Parmi les degradations subies par l'eau lourde dans les reacteurs nucleaires, les deux plus importantes sont la pollution chimique et isotopique et la decomposition radiolytique. La pollution chimique a conduit a mettre au point pour le cas particulier des reacteurs, des circuits d'epuration par echange d'ions. On decrit ici en detail la mise en oeuvre de cette methode dans les reacteurs de recherche du CEA; les controles qu'elle necessite, les resultats obtenus et leur interpretation. En ce qui concerne la dissociation radiolytique de l'eau, les renseignements obtenus sur ces memes reacteurs sont communiques, ainsi que les details des dispositifs de recombinaison et des moyens de controle. Enfin, on fait le point des etudes poursuivies au CEA sur ces memes problemes de recombinaison dans le cas des reacteurs de puissance. (auteur)

  16. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors; Etudes relatives au comportement physico-chimique de l'eau lourde dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J.; Dirian, G.; Roth, E.; Vignet, P.; Platzer, R. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1959-07-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [French] Parmi les degradations subies par l'eau lourde dans les reacteurs nucleaires, les deux plus importantes sont la pollution chimique et isotopique et la decomposition radiolytique. La pollution chimique a conduit a mettre au point pour le cas particulier des reacteurs, des circuits d'epuration par echange d'ions. On decrit ici en detail la mise en oeuvre de cette methode dans les reacteurs de recherche du CEA; les controles qu'elle necessite, les resultats obtenus et leur interpretation. En ce qui concerne la dissociation radiolytique de l'eau, les renseignements obtenus sur ces memes reacteurs sont communiques, ainsi que les details des dispositifs de recombinaison et des moyens de controle. Enfin, on fait le point des etudes poursuivies au CEA sur ces memes problemes de recombinaison dans le cas des reacteurs de puissance. (auteur)

  17. A study of the fluorescence of the rare gases excited by nuclear particles. Use of the principle for the detection of nuclear radiation by scintillation; Etude de la fluorescence des gaz rares excites par des particules nucleaires. Utilisation pour la detection des rayonnements nucleaires par scintillation

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-12-15

    composantes, l'une tres breve due a la desexcitation directe du gaz rare, l'autre relativement plus lente, due au transfert d'energie sur les impuretes. La mesure des durees de vie des etats excites a confirme l'hypothese precedente, la partie breve de l'impulsion est extremement courte: inferieure a 2,25.10{sup -9} s dans le cas du xenon, la partie plus lente a une duree qui depend etroitement de la concentration d'azote, l'azote etant l'impurete dont le role est preponderant dans tous les cas. L'etude des gaz rares soumis a un champ electrique a permis de montrer que la quantite de lumiere produite par une particule {alpha} peut etre multipliee (par 60 dans un champ de 600 V/cm par exemple) ce qui correspond a un rendement de luminescence superieur a celui de INa TI. Dans la deuxieme partie on a etudie les caracteristiques des gaz rares comme scintillateurs, la plus importante est l'absence de saturation de la fluorescence lorsque la densite d'excitation transmise au gaz devient tres grande. Ceci joint au temps de scintillation tres court a permis d'etudier un certain nombre d'applications a la physique nucleaire (mesure d'energie des particules lourdes, etude cinetique des reacteurs nucleaires, spectroscopie des neutrons...). (auteur)

  18. Sandia Combustion Research: Technical review

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report contains reports from research programs conducted at the Sandia Combustion Research Facility. Research is presented under the following topics: laser based diagnostics; combustion chemistry; reacting flow; combustion in engines and commercial burners; coal combustion; and industrial processing. Individual projects were processed separately for entry onto the DOE databases.

  19. Nuclear Materials Management and its Relationship to Nuclear Safety and Criticality Control; La Gestion des Matieres Nucleaires et ses Rapports avec la Securite Nucleaire et le Controle de la Criticite; Obrashchenie s yadernymi materialami i ego svyaz' s yadernoj bezopasnost'yu i kontrolem nad kritichnost'yu; La Administracion de Materiales Nucleares y sus Relaciones con la Seguridad Nuclear y el Control de la Criticidad

    Energy Technology Data Exchange (ETDEWEB)

    Tingey, F. H. [Phillips Petroleum Company, Idaho Falls, ID (United States)

    1966-02-15

    dictated by the technical considerations and familiar with the operational limitations. The administrative problems are solved through procedural restrictions placed by the supervisor. The NMM office can be most valuable in further support to the supervisor in these activities. The primary responsibility of this office is to alert responsible supervision to potentially hazardous situations as indicated either from information made available through the routine processing of accountability data or from material balance calculations. Any information pertaining to criticality studies as requested from the NMM office must be accurate and precise. A vigorous inventory management policy must be pursued to lessen the problems presented by accumulation of fissile materials. Internal audit by the NMM staff of inventory holdings can also serve to verify adherence to safeguard procedures. A vigorous orientation programme can be implemented by the NMM staff in its dealing with those individuals handling nuclear materials to make them more aware of the hazards involved. The integration of the NMM group into the general criticality safeguard problems at the NRT and has provided an effective system for assisting the line supervision in discharging this very important responsibility. (author) [French] Il est essentiel pour tous ceux qui travaillent dans l'industrie nucleaire de savoir comment eviter que des matieres nucleaires ne se trouvent rassemblees en quantites, selon une geometrie ou dans un milieu tels qu'elles puissent donner lieu a une reaction neutronique en chaine. Ceci interesse tout particulierement ceux qui, dans l'exercice de leurs fonctions, sont responsables de la manipulation, du transfert et de l'entreposage des matieres fissiles. Ces memes personnes participent au systeme de gestion des matieres nucleaires. Elles ont au premier chef la responsabilite de fournir et de recevoir les donnees comptables par l'intermediaire du service de gestion des matieres nucleaires

  20. Archives: les cahiers du cread

    African Journals Online (AJOL)

    Items 1 - 24 of 24 ... Archives: les cahiers du cread. Journal Home > Archives: les cahiers du cread. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register · Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives. 1 - 24 of 24 Items. 2016 ...

  1. Le commerce du Nord

    OpenAIRE

    Pourchasse, Pierrick; Bouëdec, Gérard Le

    2015-01-01

    Au XVIIIe siècle, la France s'approvisionne abondamment dans les pays du Nord : bois, chanvre et goudron de la Baltique, tonnellerie de Poméranie, pêche de rogue de Norvège, graines de lin de Courlande, barres de fer suédois… Sa balance commerciale est pourtant positive grâce aux sels, aux vins et surtout des nouvelles marchandises coloniales. Or, la plupart des transactions passent par l’incontournable intermédiaire hollandais. Les explications sur l’absence des Français dans le Nord sont re...

  2. La voie du Centre

    OpenAIRE

    2017-01-01

    Après avoir quelque peu louvoyé dans un discours apparemment anarchique où les souvenirs semblent se bousculer sans autre fil conducteur que la référence obsédante au mal satanique, brusquement le narrateur annonce un événement primordial : Foi um fato que se deu, um dia, se abriu. O primeiro. Depois o senhor verá por quê, me devolvendo minha razão (79). Cette introduction situe la rencontre du Menino comme fondatrice d’un destin dont il reviendrait au narrataire de dégager les enchaînements....

  3. Bulletin du CRDI #126

    International Development Research Centre (IDRC) Digital Library (Canada)

    26 févr. 2018 ... Dans ce numéro, découvrez comment la recherche financée par le CRDI permet d'améliorer la santé des mères et des enfants dans les pays du Sud et comment les innovations techniques et sociales de l'initiative SEARCH permettent de surmonter les défis liés à la cybersanté. N'oubliez pas non plus de ...

  4. Shale oil combustion

    International Nuclear Information System (INIS)

    Al-dabbas, M.A.

    1992-05-01

    A 'coutant' carbon steel combustion chamber cooled by water jacket was conslructed to burn diesel fuel and mixlure of shale oil and diesel fuels. During experimental work nir fuel ratio was determined, temperaturces were measured using Chromel/ Almel thermocouple, finally the gasous combustion product analysis was carricd out using gas chromatograph technique. The constructed combustion chamber was operating salisfactory for several hours of continous work. According to the measurements it was found that: the flame temperature of a mixture of diesel and shale oil fuels was greater than the flame temperature of diesel fuel. and the sulfer emissious of a mixture of diesel and shale oil fuels was higher than that of diesel fuel. Calculation indicated that the dry gas energy loss was very high and the incomplete combustion energy loss very small. (author). 23 refs., 35 figs

  5. Shale oil combustion

    Energy Technology Data Exchange (ETDEWEB)

    Al-dabbas, M A

    1992-05-01

    A `coutant` carbon steel combustion chamber cooled by water jacket was conslructed to burn diesel fuel and mixlure of shale oil and diesel fuels. During experimental work nir fuel ratio was determined, temperaturces were measured using Chromel/ Almel thermocouple, finally the gasous combustion product analysis was carricd out using gas chromatograph technique. The constructed combustion chamber was operating salisfactory for several hours of continous work. According to the measurements it was found that: the flame temperature of a mixture of diesel and shale oil fuels was greater than the flame temperature of diesel fuel. and the sulfer emissious of a mixture of diesel and shale oil fuels was higher than that of diesel fuel. Calculation indicated that the dry gas energy loss was very high and the incomplete combustion energy loss very small. (author). 23 refs., 35 figs.

  6. Indoor combustion and asthma.

    Science.gov (United States)

    Belanger, Kathleen; Triche, Elizabeth W

    2008-08-01

    Indoor combustion produces both gases (eg, nitrogen dioxide, carbon monoxide) and particulate matter that may affect the development or exacerbation of asthma. Sources in the home include both heating devices (eg, fireplaces, woodstoves, kerosene heaters, flued [ie, vented] or nonflued gas heaters) and gas stoves for cooking. This article highlights the recent literature examining associations between exposure to indoor combustion and asthma development and severity. Since asthma is a chronic condition affecting both children and adults, both age groups are included in this article. Overall, there is some evidence of an association between exposure to indoor combustion and asthma, particularly asthma symptoms in children. Some sources of combustion such as coal stoves have been more consistently associated with these outcomes than other sources such as woodstoves.

  7. Decree no. 2001-1199 of the 10 december 2001 publishing the resolution MSC. 88 (71) notifying adoption of the international compilation of safety rules for the spent nuclear fuels, plutonium and high level radioactive wastes transport in casks on ships (compilation INF) (annexes), adopted at London the 27 may 1999; Decret no. 2001-1199 du 10 decembre 2001 portant publication de la resolution MSC.88 (71) portant adoption du recueil international de regles de securite pour le transport de combustible nucleaire irradie, de plutonium et de dechets hautement radioactifs en colis a bord de navires (recueil INF) (ensemble une annexe), adoptee a Londres le 27 mai 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This legislative text concerns the safety rules of spent nuclear fuels, plutonium and high level radioactive wastes transport, in casks on ships. Rules, fire prevention, temperature control of casks, electric supply, radioprotection, management and emergency plans are detailed. (A.L.B.)

  8. Development of a software for a multi-processor system aimed at the on-line control of nuclear physics experiments; Developpement de logiciel pour un systeme multiprocesseur destine au controle en ligne d'experiences de physique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Poggioli, Jean Renaud

    1984-03-02

    This research thesis reports the development of a software for an acquisition computer aimed at the on-line control of nuclear physics experiments. An original architecture, based on the assignment of a processor to each fundamental task, enables the implementation of a high performance system. In order to make the user free of programming constraints, the author developed a software for dynamic generation of acquisition and processing codes. These codes are created from a data base which is programmed by the user by using a language close to the physical reality. Procedures of interactive control of the experiment are thus simplified by displaying function menus on the operator terminal. The author evokes possible hardware improvements and possible extensions of the system [French] Cette these rend compte du developpement logiciel realise pour un calculateur d'acquisition destine au controle en ligne d'experiences de Physique Nucleaire. Une architecture originale, basee sur l'attribution d'un processeur a chacune des taches fondamentales permet de facon simple la mise en oeuvre d'un systeme a hautes performances. Le souci de liberer l'utilisateur des contraintes de programmation a conduit a l'elaboration d'un logiciel de generation dynamique des codes acquisition et traitement; ces derniers sont crees a partir d'une base de donnees que l'experimentateur programme a l'aide d'un langage approchant la realite physique. Les procedures de controle interactif de l'experience se trouvent simplifiees par l'affichage de menus de fonctions sur la console operateur. En conclusion sont evoquees les ameliorations materielles et les extensions possibles du systeme. (auteur)

  9. Sandia Combustion Research Program

    Energy Technology Data Exchange (ETDEWEB)

    Johnston, S.C.; Palmer, R.E.; Montana, C.A. (eds.)

    1988-01-01

    During the late 1970s, in response to a national energy crisis, Sandia proposed to the US Department of Energy (DOE) a new, ambitious program in combustion research. Shortly thereafter, the Combustion Research Facility (CRF) was established at Sandia's Livermore location. Designated a ''user facility,'' the charter of the CRF was to develop and maintain special-purpose resources to support a nationwide initiative-involving US inventories, industry, and national laboratories--to improve our understanding and control of combustion. This report includes descriptions several research projects which have been simulated by working groups and involve the on-site participation of industry scientists. DOE's Industry Technology Fellowship program, supported through the Office of Energy Research, has been instrumental in the success of some of these joint efforts. The remainder of this report presents results of calendar year 1988, separated thematically into eleven categories. Referred journal articles appearing in print during 1988 and selected other publications are included at the end of Section 11. Our traditional'' research activities--combustion chemistry, reacting flows, diagnostics, engine and coal combustion--have been supplemented by a new effort aimed at understanding combustion-related issues in the management of toxic and hazardous materials.

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  11. Prospects for the Use of Plutonium in Reactors; Prospective d'Utilisation du Plutonium dans les Reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Fossoul, E.; Haubert, P. [BELGONUCLEAIRE (Belgium); Hirschberg, D.; Morlet, E. [International Business Machines of Belgium, Bruxelles (Belgium)

    1967-09-15

    The introduction, at an increasing rate, of power reactors using slightly enriched uranium will inevitably lead to the production of considerable quantities of plutonium over the next decade. Fast reactors will not be capable of absorbing this material before 1980. The question thus arises of whether one should store the plutonium far future use in fast reactors, recycle it in existing thermal reactors, or try to sell it. The problem has been studied for an electric power generating system that does not foresee selling the plutonium produced by its reactors and does not buy plutonium outside, which enables a good approximation to be made and eliminates the major unknown quantity represented by the future market price of plutonium. Assuming within this system a programme that provides for the construction of power reactors of a given type and capacity at specific dates, the utilization of the plutonium produced can be optimized by linear programming techniques so as to minimize the discounted total cost of the power generated over a given period. A later stage consists in optimizing, by various techniques, not only the utilization but also the production of plutonium by appropriate selection of the power reactor types to be constructed. (author) [French] L'implantation, a un rythme croissant, de centrales nucleaires a uranium legerement enrichi entrainera la production ineluctable d'une quantite importante de plutonium au cours de la prochaine decennie. Les reacteurs a neutrons rapides ne seront capables d'absorber cette production qu'apres 1980. La question se pose donc de savoir s'il est preferable de stocker le plutonium en vue de son utilisation ulterieure dans les reacteurs a neutrons rapides plutot que de le recycler dans les reacteurs actuels a neutrons thermiques ou d'essayer de le vendre. Ce probleme a ete etudie dans le cadre d'un systeme de production d'energie electrique qui ne prevoirait pas la vente du plutonium produit par ses reacteurs nucleaires ni

  12. Choeur du CERN : Concert

    CERN Multimedia

    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...

  13. 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�...

  14. Electrically fired incineration of combustible radioactive waste

    International Nuclear Information System (INIS)

    Charlesworth, D.; Hill, M.

    1985-01-01

    Du Pont Company and Shirco, Inc. are developing a process to incinerate plutonium-contaminated combustible waste in an electrically fired incineration system. Preliminary development was completed at Shirco, Inc. prior to installing an incineration system at the Savannah River Laboratory (SRL), which is operated by Du Pont for the US Department of Energy (DOE). The waste consists of disposable protective clothing, cleaning materials, used filter elements, and miscellaneous materials exposed to plutonium contamination. Incinerator performance testing, using physically representative nonradioactive materials, was completed in March 1983 at Shirco's Pilot Test Facility in Dallas, TX. Based on the test results, equipment sizing and mechanical begin of a full-scale process were completed by June 1983. The full-scale unit is being installed at SRL to confirm the initial performance testing and is scheduled to begin in June 1985. Remote operation and maintenance of the system is required, since the system will eventually be installed in an isolated process cell. Initial operation of the process will use nonradioactive simulated waste. 2 figs., 2 tabs

  15. Nuclear Materials Management in a Recovery Facility for Unirradiated Enriched Uranium; Gestion des Matieres Nucleaires dans une Installation de Recuperation d'Uranium Enrichi Non Irradie; Administrativno-khozyajstvennyj uchet yadernykh materialov na ustanovke po regeneratsii neobluchennogo obogashchennogo urana; Administracion de Materiales Nucleares en una Planta de Recuperacion para Uranio Enriquecido No Irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Jasny, G. R. [Union Carbide Corporation, Oak Ridge, TN (United States)

    1966-02-15

    poussee du personnel charge des operations. Le transfert des informations au service de comptabilite des matieres nucleaires est assure au moyen d'un systeme de fiches qui accompagnent les matieres: chaque lot est identifie par une fiche individuelle et la livraison du lot est signalee par transfert de la fiche au service de comptabilite des matieres nucleaires{sup .} La plupart des operations comptables sont executees sur des appareils electroniques de traitement de l'information; outre les dossiers et calculs necessaires pour l'etablissement des bilans matieres, on enregistre regulierement des donnees sur la retention et la concentration afin de faciliter la detection des anomalies dans les bilans entree/sortie ou dans les inventaires. L'analyse statistique est largement utilisee pour verifier les mesures et reduire au minimum le nombre d'analyses chimiques. Toutefois, l'application des statistiques n'a pas donne de bons resultats pour l'evaluation des erreurs d'inventaire. Le memoire etudie de maniere detaillee les methodes de controle des matieres indiquees plus haut et certains des problemesiqu'elles posent. (author) [Spanish] Desde hace mas de veinte anos, la planta Y-12 de la Comision de Energia Atomica, situada en Oak Ridge, Tennessee, viene tratando y recuperando diversas formas de uranio enriquecido no irradiado. El proceso de recuperacion consiste en un tren semicontinuo de operaciones unitarias: disolucion, combustion, evaporacion, extraccion, desnitrificacion e hidrofluoracion. El equipo de tratamiento y almacena - miento es de dimensiones restringidas para evitar la criticidad y tiene una capacidad combinada de varios centenares de kg de uranio enriquecido al mes. El material sometido a las operaciones de recuperacion proviene tanto de la planta como de otras instalaciones que la CEA posee en los Estados Unidos. Este material incluye practicamente todos los tipos de residuos de uranio enriquecido sin irradiar. El control fisico se ejerce satisfactoriamente

  16. High-Volume Non-Destructive Test Applications at the Hanford Atomic Products Operation; Applications Industrielles des Essais Non Destructifs a l'Etablissement Nucleaire de Hanford; Provedenie bol'shogo chisla nedestruktivnykh ispytanii v ''khenford atomik prodakts opereishen''; Ensayos No Destructivos en Gran Escala Aplicados en Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Worlton, D. C. [Pacific Northwest Laboratory, Battelle Memorial Institute, Richland, WA (United States)

    1965-10-15

    patterns whose size and shape reveal defect magnitude, location within the tube wall, and depth. Probe wobble and harmless tube kinks and bends are plotted with a characteristic pattern readily distinguishable from genuine defects. Results of applying the test to 750 000 ft of installed tubing under difficult field conditions are summarized. (author) [French] On a recours a des essais non destructifs - rapides, surs et automatiques - pour assurer la securite et l'efficacite des operations critiques a Hanford. On utilise couramment des methodes de controle tres sensibles, fondees sur les courants de Foucault et les ultrasons, pour verifier avec le maximum d'assurance et dans le minimum de temps la qualite d'importants volumes de matieres et produits. Le memoire decrit les appareils de controle utilises pour s'assurer de la qualife de la fabrication des combustibles nucleaires a Hanford. Ces appareils, qui font partie integrante de l'equipement de fabrication, appliquent le principe de l'attenuation des ondes ultrasonores pour controler la structure granulaire de barreaux d'uranium non gaine, les ultrasons et les courants de Foucault pour controler la liaison entre l'uranium et sa gaine en aluminium ainsi que l'epaisseur de cette derniere (1 mm), et une nouvelle methode ultrasonore (large bande, haute resolution) pour la detection des defauts dans les soudures aux extremites des cartouches de combustible. Des methodes combinees (courants de Foucault et ultrasons) sont appliquees simultanement pour l'inspection complete d'un element combustible en neuf secondes; les elements defectueux sont rejetes automatiquement. Le memoire expose en detail les methodes ultrasonores perfectionnees pour le controle des gaines de combustible a parois minces. Des traducteurs speciaux a forte focalisation sont utilises avec un circuit a bande large pour produire des ondes de rotation pures dans un tube de 0,37 mm d'epaisseur. Les ondes de Lamb et autres mouvements ondulatoires complexes sont

  17. The control equipment of the Melusine II reactor; L'equipement de controle du reacteur Melusine II

    Energy Technology Data Exchange (ETDEWEB)

    Cordelle, M; Delcroix, V; Denis, P; Gariod, R

    1963-07-01

    Melusine II, low-power reactor, used for the study of Siloe core has diverged at the CEA Grenoble, the 23. May 1962; its monitoring board studied and carried out in this center is the first in France to be entirely transistorized. The first months of running have justified the hope put in the new electronics to improve the stability and the safety of running. The article describes the design of the control and gives the main characteristics of the measurement chains and of the actions on reactivity. (O.M.) [French] Melusine II, reacteur de faible puissance destine a l'etude du coeur de Siloe a diverge au Centre d'Etudes Nucleaires de Grenoble, le 23 mai 1962, son tableau de controle etudie et realise dans ce Centre est le premier en France a etre entierement transistorise. Les premiers mois de fonctionnement ont justifie l'espoir mis dans la nouvelle electronique pour ameliorer la stabilite et la surete de fonctionnement. L'article decrit la conception du controle et donne les principales caracteristiques des chaines de mesure et des actions sur la reactivite. (auteurs)

  18. The control of the radioactive pollution of milk (1962); Comment concevoir une surveillance des pollutions radioactives du lait (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Milk, an essential foodstuff, is the object of a supervision and vigilant controls governed by numerous laws which protect its commercial and sanitary qualities. The development of the use of nuclear energy poses and will pose new problems of hygiene and the milk should benefit from controls concerning its possible contamination. Grass-eating animals are particularly subjected to radioactive contaminations and the milk which they produce does not escape contamination because of of its saline composition and of the particular metabolism of the mammary gland. As a result, milk is a contamination integrator and its analysis makes it possible to detect radioelements which can only be detected with great difficulty in an average size plant sample. (author) [French] Le lait, aliment essentiel, fait l'objet d'une surveillance et de controles vigilants regis par de nombreux textes legislatifs qui protegent ses qualites marchandes et sanitaires. Le developpement de l'utilisation de l'energie nucleaire pose et posera de nouveaux problemes d'hygiene et le lait doit beneficier de controles portant sur sa pollution radioactive eventuelle. Les, animaux herbivores sont particulierement exposes aux contaminations radioactives et les laits qu'ils produisent, du fait de leurs compositions salines et du metabolisme particulier de la glande mammaire, n'echappent point aux pollutions. De ce fait, le lait est un integrateur de contamination et son analyse permet de retrouver des radioelements que l'on ne decele qu'avec beaucoup de difficultes sur un echantillon vegetal de taille moyenne. (auteur)

  19. Study methods for the drillings around the underground nuclear explosions in the Sahara. Part 1. study of rock samples; Methodes d'etude des forages realises autour des explosions nucleaires souterraines au Sahara. Premiere partie: etude des echantillons de roche

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    An examination of the mechanical effects produced on rocks by an underground nuclear explosion calls for the use of particular means of exploration which are described in this report, special attention being paid to the equipment used in connection with the French nuclear tests in the Sahara. The drilling methods used (rotary and turbo-drilling) are adapted to the particular conditions of the sampling programme, to the radioactivity and to the temperature in the region of the explosion. A study of the samples makes it possible to obtain the new characteristics of the rock and to assess the chemical and mechanical transformations which it has undergone. An examination of the core obtained from the drilling, together with a knowledge of the drilling parameters (depth of the probe, sample recovery, etc...), makes it possible to study the extent and the characteristics of the zones which have been damaged to different degrees according to their distance from the zero point: cavity, strongly powdered zone, fractured zone, chimney, zones containing high stresses leading to a particular type of fracture of the cores. The problems connected with the interpretation of the results are also presented. (author) [French] L'examen des effets mecaniques provoques par une explosion nucleaire souterraine sur la roche necessite la mise en oeuvre de moyens d'exploration particuliers dont l'expose fait l'objet de ce rapport, essentiellement pour les moyens utilises autour des essais nucleaires francais au Sahara. Les methodes de forage (rotary et turboforage) sont adaptees aux conditions particulieres dues au programme d'echantillonnage, a la radioactivite et a la temperature regnant a proximite du point de tir. L'etude des echantillons permet la determination des nouveaux caracteres de la roche et de ses transformations chimique et mecanique. L'examen des carottes et l'utilisation des parametres de forage (cotes sondeurs, recuperation des echantillons, etc...) permettent d'etudier l

  20. 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.

  1. Deliberations of the 29. of December 2010 bearing opinion of the order project setting electricity purchase conditions; Deliberation du 29 decembre 2010 portant avis sur le projet d'arrete fixant les conditions d'achat de l'electricite produite par les installations utilisant a titre principal l'energie degagee par la combustion de matieres non fossiles d'origine vegetale ou animale telles que visees au 4 de l'article 2 du decret n 2000-1196 du 6 decembre 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document reports deliberations of the Energy Regulation Commission about purchase conditions of electricity produced by installations using mainly the energy released by the combustion of vegetal or animal non fossil materials. As this project aims at decreasing by 3,6% the current purchase tariffs, this document discusses the profitability analysis of projects of more than 5 MW for which the projected decrease still leaves some profitability margin. It comments the case of projects from 1 to 5 MW aimed at supplying sawmills with heat, comments the possible adoption of a winter-summer pricing principle and the impact of the tariff structure on public service expenses

  2. Preparation and study of the properties of lead telluride and cadmium telluride diodes for use in nuclear spectrometry; Preparation et etude des proprietes de diodes au tellurure de plomb et au tellurure de cadmium en vue d'une utilisation en spectrometrie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    This work studies the possibility of using high atomic number compound semiconductors, like lead telluride and cadmium telluride as to realize nuclear radiation detectors, specially in gamma ray spectrometry because of their high absorption coefficient. The problems related to the preparation of binary compounds are exposed. Experiments on PbTe show the influence of the conditions of preparation on the electrical properties of the semiconductor which are greatly dependent on the stoichiometry of the compound. PbTe surface-barrier diodes were realized and have been used to study the surface properties of this semiconductor. These diodes cannot detect nuclear radiations because of the too weak resistivity of our material. Different types of devices made of Cd Te have been studied. One of these diodes has been used as an alpha particle detector. We explain the relative poor performances of that detector by the presence of lattice defects in Cd Te where charge carriers may recombine themselves. By analysing the properties of gold diffused Cd Te diodes we identified this defect, the cadmium vacancy, the presence of which is due to the deviation from stoichiometry during the preparation of the material. (author) [French] Ce travail etudie la possibilite d'utiliser des semiconducteurs composes d'elements a numero atomique eleve, tels que le tellurure de plomb et le tellurure de cadmium pour la realisation de detecteurs de rayonnements nucleaires, grace notamment a la section efficace de capture elevee qu'ils presentent vis-a-vis des rayons gamma. On souligne les problemes relatifs a la preparation des composes binaires. Les experiences realisees sur PbTe mettent en evidence l'influence des conditions de preparation sur les proprietes electriques du semiconducteur qui dependent fortement de la stoechiometrie du compose. Nous avons realise des diodes au PbTe a barriere de surface qui ont permis de preciser les proprietes de surface de ce semiconducteur. La trop faible

  3. Burn up physics; Physique des combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    requires samples of the order of several kilograms only. The relationships between these measurements and the investigations of lattices are discussed, and an outline is given of the way of carrying out the systematic study of fuels of various compositions. The method has been successfully applied to the systematic study of irradiated fuels (analysed independently by the methods mentioned above) thus giving the possibility of measuring in situ the absorption of fission products. (author) [French] Cette communication expose un ensemble d'etudes theoriques et d'experiences, effectuees au CEA et destinees a faire progresser la connaissance de l'evolution de la reactivite (au cours de l'irradiation du combustible) dans les reacteurs a uranium naturel ou faiblement enrichi.,. On rappelle les difficultes de l'experimentation directe sur des masses importantes de combustible irradie - en particulier dans les reacteurs de puissance en fonctionnement - et on souligne la necessite d'experiences a caractere fondamental distinguant: d'une part l'evolution de la composition des combustibles (chaines de noyaux lourds, produits de fission), d'autre part l'effet des modifications de composition sur le bilan de neutrons. Avant de presenter trois categories d'experiences que l'on est conduit a entreprendre, on rappelle l'importance des problemes lies aux spectres de neutrons et on decrit rapidement les methodes pratiques de calcul utilisees. L'irradiation systematique de quelques types de combustibles, suivie de leur analyse chimique et isotopique est en cours depuis plusieurs annees. On donne un apercu de l'ensemble du programme experimental et on decrit les moyens et les methodes mis en oeuvre: chaine {alpha}, {beta}, {gamma} pour la preparation des echantillons, dosage du Plutonium par coulommetrie et double dilution isotopique, separation du Bore utilise dans certains cas pour la mesure des densites de neutrons integrees. On discute sur quelques exemples l'interpretation des mesures

  4. Transient flow combustion

    Science.gov (United States)

    Tacina, R. R.

    1984-01-01

    Non-steady combustion problems can result from engine sources such as accelerations, decelerations, nozzle adjustments, augmentor ignition, and air perturbations into and out of the compressor. Also non-steady combustion can be generated internally from combustion instability or self-induced oscillations. A premixed-prevaporized combustor would be particularly sensitive to flow transients because of its susceptability to flashback-autoignition and blowout. An experimental program, the Transient Flow Combustion Study is in progress to study the effects of air and fuel flow transients on a premixed-prevaporized combustor. Preliminary tests performed at an inlet air temperature of 600 K, a reference velocity of 30 m/s, and a pressure of 700 kPa. The airflow was reduced to 1/3 of its original value in a 40 ms ramp before flashback occurred. Ramping the airflow up has shown that blowout is more sensitive than flashback to flow transients. Blowout occurred with a 25 percent increase in airflow (at a constant fuel-air ratio) in a 20 ms ramp. Combustion resonance was found at some conditions and may be important in determining the effects of flow transients.

  5. Combustion and regulation; Combustion et reglementation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This conference was organized after the publication of the French by-law no 2010 relative to combustion installations and to the abatement of atmospheric pollution. Five topics were discussed during the conference: the new regulations, their content, innovations and modalities of application; the means of energy suppliers to face the new provisions and their schedule; the manufacturers proposals for existing installations and the new equipments; the administration control; and the impact of the new measures on exploitation and engineering. Twenty papers and 2 journal articles are reported in these proceedings. (J.S.)

  6. La grammaticalisation du monde.

    Directory of Open Access Journals (Sweden)

    Etienne Pingaud

    2010-01-01

    Full Text Available Ouvrage atypique par le fond comme par la forme, Le devoir et la grâce rend compte du minutieux travail d’élaboration théorique auquel s’attelle Cyril Lemieux depuis plusieurs années. Et le résultat final se veut pour le moins ambitieux : l’auteur propose un système total supposé dépasser d’un même élan le relativisme, le mentalisme, l’universalisme ethnocentrique, l’historicisme, le naturalisme et l’herméneutisme, tout en réconciliant les sciences sociales avec le ...

  7. 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...

  8. 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...

  9. Integration of the nuclear energy among the production facilities of energy in France; Integration de l'energie nucleaire parmi les moyens de production de l'energie en france

    Energy Technology Data Exchange (ETDEWEB)

    Ailleret, P [Electricite de France (EDF), 75 - Paris (France). Direction des Etudes et Recherches; Taranger, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The present report gives an overview of the present facilities of energy productions in France and their perspectives. the electric production comes for half about power stations hydraulics and for half of thermal power stations. However due to the increase of the energy consumption, France is particularly interested by the atomic energy that appears to bring a supply in due time to the hydraulics and to limit a development of the thermal power stations to which the natural resources of France in classic fuel would not permit to cope presumably. The integration of the nuclear plants to the other production facilities will make itself gradually according to the evolution of the energy needs. (M.B.) [French] Le present rapport donne un apercu des moyens actuels de productions energetiques en France et de ses perspectives. la production electrique provient pour moitie environ de centrales hydraulique et pour moitie de centrales thermiques. Cependant face a l'augmentation de la consommation energetique, la France est tres particulierement interessee par l'energie atomique qui parait devoir apporter en temps utile la releve a l'hydraulique et limiter un developpement des centrales thermiques auxquels les ressources naturelles de la France en combustible classique ne permettraient vraisemblablement pas de faire face. L'integration des centrales nucleaires aux autres moyens de production se fera graduellment en fonction de l'evolution des besoins energetiques. (M.B.)

  10. (Sorghum bicolor (L.) Moench) du Nord du Burkina Faso

    African Journals Online (AJOL)

    SARAH

    29 déc. 2014 ... sorghos à grains sucrés ont un cycle court et arrivent donc à maturité avant les autres sorghos et le mil d'où leur exploitation comme aliment de soudure par les paysans. L'organisation de la diversité morphologique des accessions de sorghos à grains sucrés du Nord du. Burkina autour principalement des ...

  11. Direct interaction in nuclear reactions: a theory; L'interaction directe dans les reactions nucleaires: theorie

    Energy Technology Data Exchange (ETDEWEB)

    Dominicis, C.T. de [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    General treatment of the foundations of direct interaction in nuclear reactions; representation of the instantaneous elastic scattering amplitude by the scattering amplitude due to a complex potential; expansion of the instantaneous inelastic scattering amplitude and discussion of the 1. Bohr approximation (distorted waves) contribution to individual and collective states of excitation. (author) [French] Expose general sur les fondements de l'interaction directe dans les reactions nucleaires; representation de l'amplitude de diffusion instantanee elastique par celle due a un potentiel complexe; developpement de l'amplitude de diffusion instantanee inelastique et discussion de la contribution de la premiere approximation de Bohr (sur des distendues) a l'excitation d'etats individuels et collectifs. (auteur)

  12. The 1989 annual report of the Institut de Physique Nucleaire-Orsay

    International Nuclear Information System (INIS)

    1989-01-01

    The activity report of the Institut de Physique Nucleaire (Orsay-France) from 1 Sep 1988 to 1 Aug 1989 is presented. Theoretical and experimental investigations were carried out in the following fields: light and medium exotic nuclei, on line spectroscopy, discrete high spin states, new radioactivities, thermal fission, detection systems, giant resonances, high excitation energy structure, reaction mechanisms at energies below 10 MeV/u and at 200 MeV/u and their evolution between 10 and 100 MeV/u, meson production, transfer reactions, spin modes in nuclei, dibaryonic resonances, inelastic scattering of polarized protons. Research programs in the field of radiochemistry and relating to inter-disciplinary fields are included. The activities involving teaching, the lists of publications conferences, seminars and theses are presented [fr

  13. 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.

  14. Alimentation du nouveau-ne et du nourrisson dans la region ...

    African Journals Online (AJOL)

    Alimentation du nouveau-ne et du nourrisson dans la region centrale du togo : pratiques familiales et communautaires avant la mise en oeuvre de la strategie « prise en charge integree des maladies de l'enfant »

  15. Combustible structural composites and methods of forming combustible structural composites

    Science.gov (United States)

    Daniels, Michael A.; Heaps, Ronald J.; Steffler, Eric D.; Swank, W. David

    2013-04-02

    Combustible structural composites and methods of forming same are disclosed. In an embodiment, a combustible structural composite includes combustible material comprising a fuel metal and a metal oxide. The fuel metal is present in the combustible material at a weight ratio from 1:9 to 1:1 of the fuel metal to the metal oxide. The fuel metal and the metal oxide are capable of exothermically reacting upon application of energy at or above a threshold value to support self-sustaining combustion of the combustible material within the combustible structural composite. Structural-reinforcing fibers are present in the composite at a weight ratio from 1:20 to 10:1 of the structural-reinforcing fibers to the combustible material. Other embodiments and aspects are disclosed.

  16. Optical Tomography in Combustion

    DEFF Research Database (Denmark)

    Evseev, Vadim

    spectral measurements at several line-of-sights with a view to applications for tomographic measurements on full-scale industrial combustion systems. The system was successfully applied on industrial scale for simultaneous fast exhaust gas temperature measurements in the three optical ports of the exhaust......D project, it was also important to investigate the spectral properties of major combustion species such as carbon dioxide and carbon monoxide in the infrared range at high temperatures to provide the theoretical background for the development of the optical tomography methods. The new software....... JQSRT 113 (2012) 2222, 10.1016/j.jqsrt.2012.07.015] included in the PhD thesis as an attachment. The knowledge and experience gained in the PhD project is the first important step towards introducing the advanced optical tomography methods of combustion diagnostics developed in the project to future...

  17. Internal combustion engine

    Science.gov (United States)

    Baker, Quentin A.; Mecredy, Henry E.; O'Neal, Glenn B.

    1991-01-01

    An improved engine is provided that more efficiently consumes difficult fuels such as coal slurries or powdered coal. The engine includes a precombustion chamber having a portion thereof formed by an ignition plug. The precombustion chamber is arranged so that when the piston is proximate the head, the precombustion chamber is sealed from the main cylinder or the main combustion chamber and when the piston is remote from the head, the precombustion chamber and main combustion chamber are in communication. The time for burning of fuel in the precombustion chamber can be regulated by the distance required to move the piston from the top dead center position to the position wherein the precombustion chamber and main combustion chamber are in communication.

  18. Fuel and combustion stratification study of Partially Premixed Combustion

    OpenAIRE

    Izadi Najafabadi, M.; Dam, N.; Somers, B.; Johansson, B.

    2016-01-01

    Relatively high levels of stratification is one of the main advantages of Partially Premixed Combustion (PPC) over the Homogeneous Charge Compression Ignition (HCCI) concept. Fuel stratification smoothens heat release and improves controllability of this kind of combustion. However, the lack of a clear definition of “fuel and combustion stratifications” is obvious in literature. Hence, it is difficult to compare stratification levels of different PPC strategies or other combustion concepts. T...

  19. The Use of Fuel Gas as Stripping Medium in Atmospheric Distillation of Crude Oil L’utilisation de gaz combustible comme moyen d’extraction des fractions légères en distillation atmosphérique du pétrole brut

    OpenAIRE

    Plellis-Tsaltakis C.; Lygeros A.I.

    2011-01-01

    Stripping of petroleum fractions aims to remove the light ends that spoil some of their properties, such as the flash point. Stripping usually employs steam for that purpose. Except for steam, other substances can perform the same function, among them light hydrocarbons. In this article, we investigate the use of refinery fuel gas as stripping medium for a crude oil atmospheric distillation unit. L’extraction des fractions légères du pétrole vise à enlever les produits nuisibles à cer...

  20. Aerosols from biomass combustion

    Energy Technology Data Exchange (ETDEWEB)

    Nussbaumer, T

    2001-07-01

    This report is the proceedings of a seminar on biomass combustion and aerosol production organised jointly by the International Energy Agency's (IEA) Task 32 on bio energy and the Swiss Federal Office of Energy (SFOE). This collection of 16 papers discusses the production of aerosols and fine particles by the burning of biomass and their effects. Expert knowledge on the environmental impact of aerosols, formation mechanisms, measurement technologies, methods of analysis and measures to be taken to reduce such emissions is presented. The seminar, visited by 50 participants from 11 countries, shows, according to the authors, that the reduction of aerosol emissions resulting from biomass combustion will remain a challenge for the future.

  1. High Gravity (g) Combustion

    Science.gov (United States)

    2006-02-01

    UNICORN (Unsteady Ignition and Combustion with Reactions) code10. Flame propagation in a tube that is 50-mm wide and 1000-mm long (similar to that...turbine engine manufacturers, estimating the primary zone space heating rate. Both combustion systems, from Company A and Company B, required a much...MBTU/atm-hr-ft3) Te m pe ra tu re R is e (K ) dP/P = 2% dP/P = 2.5% dP/P = 3% dP/P = 3.5% dP/P = 4% Company A Company B Figure 13: Heat Release Rate

  2. Alcohol combustion chemistry

    KAUST Repository

    Sarathy, Mani

    2014-10-01

    Alternative transportation fuels, preferably from renewable sources, include alcohols with up to five or even more carbon atoms. They are considered promising because they can be derived from biological matter via established and new processes. In addition, many of their physical-chemical properties are compatible with the requirements of modern engines, which make them attractive either as replacements for fossil fuels or as fuel additives. Indeed, alcohol fuels have been used since the early years of automobile production, particularly in Brazil, where ethanol has a long history of use as an automobile fuel. Recently, increasing attention has been paid to the use of non-petroleum-based fuels made from biological sources, including alcohols (predominantly ethanol), as important liquid biofuels. Today, the ethanol fuel that is offered in the market is mainly made from sugar cane or corn. Its production as a first-generation biofuel, especially in North America, has been associated with publicly discussed drawbacks, such as reduction in the food supply, need for fertilization, extensive water usage, and other ecological concerns. More environmentally friendly processes are being considered to produce alcohols from inedible plants or plant parts on wasteland. While biofuel production and its use (especially ethanol and biodiesel) in internal combustion engines have been the focus of several recent reviews, a dedicated overview and summary of research on alcohol combustion chemistry is still lacking. Besides ethanol, many linear and branched members of the alcohol family, from methanol to hexanols, have been studied, with a particular emphasis on butanols. These fuels and their combustion properties, including their ignition, flame propagation, and extinction characteristics, their pyrolysis and oxidation reactions, and their potential to produce pollutant emissions have been intensively investigated in dedicated experiments on the laboratory and the engine scale

  3. Combustibility of tetraphenylborate solids

    International Nuclear Information System (INIS)

    Walker, D.D.

    1989-01-01

    Liquid slurries expected under normal in-tank processing (ITP) operations are not ignitible because of their high water content. However, deposits of dry solids from the slurries are combustible and produce dense, black smoke when burned. The dry solids burn similarly to Styrofoam and more easily than sawdust. It is the opinion of fire hazard experts that a benzene vapor deflagration could ignite the dry solids. A tetraphenylborate solids fire will rapidly plug the waste tank HEPA ventilation filters due to the nature of the smoke produced. To prevent ignition and combustion of these solids, the waste tanks have been equipped with a nitrogen inerting system

  4. Studies in combustion dynamics

    Energy Technology Data Exchange (ETDEWEB)

    Koszykowski, M.L. [Sandia National Laboratories, Livermore, CA (United States)

    1993-12-01

    The goal of this program is to develop a fundamental understanding and a quantitative predictive capability in combustion modeling. A large part of the understanding of the chemistry of combustion processes comes from {open_quotes}chemical kinetic modeling.{close_quotes} However, successful modeling is not an isolated activity. It necessarily involves the integration of methods and results from several diverse disciplines and activities including theoretical chemistry, elementary reaction kinetics, fluid mechanics and computational science. Recently the authors have developed and utilized new tools for parallel processing to implement the first numerical model of a turbulent diffusion flame including a {open_quotes}full{close_quotes} chemical mechanism.

  5. Combustion stratification for naphtha from CI combustion to PPC

    NARCIS (Netherlands)

    Vallinayagam, R.; Vedharaj, S.; An, Y.; Dawood, A.; Izadi Najafabadi, M.; Somers, L.M.T.; Johansson, B.H.

    2017-01-01

    This study demonstrated the change in combustion homogeneity from conventional diesel combustion via partially premixed combustion towards HCCI. Experiments are performed in an optical diesel engine at a speed of 1200 rpm with diesel fuel. Single injection strategy is employed and the fuel is

  6. Toxicology of Biodiesel Combustion products

    Science.gov (United States)

    1. Introduction The toxicology of combusted biodiesel is an emerging field. Much of the current knowledge about biological responses and health effects stems from studies of exposures to other fuel sources (typically petroleum diesel, gasoline, and wood) incompletely combusted. ...

  7. Underground treatment of combustible minerals

    Energy Technology Data Exchange (ETDEWEB)

    Sarapuu, E

    1954-10-14

    A process is described for treating oil underground, consisting in introducing several electrodes spaced one from the other in a bed of combustibles underground so that they come in electric contact with this bed of combustibles remaining insulated from the ground, and applying to the electrodes a voltage sufficient to produce an electric current across the bed of combustibles, so as to heat it and create an electric connection between the electrodes on traversing the bed of combustibles.

  8. Le plurilinguisme du perroquet

    Directory of Open Access Journals (Sweden)

    Manuel Mühlbacher

    2012-05-01

    Full Text Available La figure du perroquet occupe une position ambiguë face à la question de la traduction. Il est capable d’imiter des paroles en toutes les langues, mais il n’est capable d’en comprendre aucune — il ne peut que répéter des sons, c’est-à-dire des signifiants. Le traducteur semble faire le contraire quand il passe d’une langue à une autre en tâchant de transmettre une signification semblable par d’autres signes. L’article vise à discuter le rôle du traducteur et sa relation, éventuellement équivoque, au perroquet, en analysant la traduction allemande de Trois Contes par André Stoll et Cora van Kleffens. Un décalage au niveau sémantique peut éclairer l’interprétation du texte, par exemple en explicitant des allusions sous-jacentes, tandis que le transfert de la syntaxe française en allemand pose souvent des problèmes considérables. Comment le traducteur peut-il reproduire des structures syntaxiques qui n’existent pas en allemand, mais qui ne cessent de revenir dans le texte français ? Que faire si le texte se met à jouer au perroquet et finit par se singer lui-même ? André Stoll et Cora van Kleffens ont su trouver des stratégies pour affronter ces difficultés.The figure of the parrot holds an ambiguous position towards the question of translation. It is able to imitate all languages, but it will never understand any of them – its only skill is to mimic sounds, i.e. mere signifiers. On the contrary, the translator seems to be the antithesis of the parrot when he moves from one language to another. He endeavours to convey a similar meaning, but by different signs. The article aims at discussing the role of the translator and his or her eventually equivocal relation to the parrot by means of analysing the German translation of Trois Contes by André Stoll and Cora van Kleffens. Whereas a semantic divergence can result in a different tendency on the level of interpretation, as in the case of an underlying

  9. Supersonic Combustion Ramjet Research

    Science.gov (United States)

    2012-08-01

    was in collaboration with Prof. R. Bowersox (Texas A&M University) and Dr. K. Kobayashi ( Japanese Aerospace Exploration Agency, JAXA). 4.2 Ignition... cinema stereoscopic PIV system for the measurement of micro- and meso-scale turbulent premixed flame dynamics,” Paper B13, 5th US Combustion

  10. Infrared monitoring of combustion

    International Nuclear Information System (INIS)

    Bates, S.C.; Morrison, P.W. Jr.; Solomon, P.R.

    1991-01-01

    In this paper, the use of Fourier Transform Infrared (FT-IR) spectroscopy for combustion monitoring is described. A combination of emission, transmission, and reflection FT-IR spectroscopy yields data on the temperature and composition of the gases, surfaces and suspended particles in the combustion environment. Detection sensitivity of such trace exhaust gases as CO, CO 2 , SO 2 , NO x , and unburned hydrocarbons is at the ppm level. Tomographic reconstruction converts line-of-sight measurements into spatially resolved temperature and concentration data. Examples from various combustion processes are used to demonstrate the capabilities of the technique. Industrial measurements are described that have been performed directly in the combustion zone and in the exhaust duct of a large chemical recovery boiler. Other measurements of hot slag show how FT-IR spectroscopy can determine the temperature and optical properties of surfaces. In addition, experiments with water droplets show that transmission FT-IR data yield spectra that characterize particle size and number density

  11. Combustible dust tests

    Science.gov (United States)

    The sugar dust explosion in Georgia on February 7, 2008 killed 14 workers and injured many others (OSHA, 2009). As a consequence of this explosion, OSHA revised its Combustible Dust National Emphasis (NEP) program. The NEP targets 64 industries with more than 1,000 inspections and has found more tha...

  12. Induction of the lambda bacteriophage synthesis in Escherichia coli K 12 by polonium alpha rays; Induction de la synthese du bacteriophage lambda chez Escherichia coli K 12 par les rayons alpha du polonium

    Energy Technology Data Exchange (ETDEWEB)

    Devoret, Raymond

    1958-06-15

    This research thesis reports the study of the inducing action of polonium alpha radiations in Escherichia Coli K 12 by using an external irradiation device. This work comprised the development of a method to spread bacteria in layer with a thickness less than 20 microns, and the measurement of the number of α particles falling on the irradiated surface. This measurement has been performed by using a nuclear emulsion and a simple photographic film. It appears that alpha radiations have an inducing action, and that at most 15 per cent of bacteria can be induced. The comparison of the induction curve with the survival curves of lysogen and sensitive stains shows that there is no abortive induction. Thus, it appears that this inducing action is not due to an indirect effect of the irradiated medium [French] Dans ce travail on a etudie l'action inductrice des rayons alphas du polonium chez Escherichia Coli K 12 par un diapoaitif d'irradiation externe. Son utilisation necessitait: - une methode d'etalement des bacteries en couche de moins de 20 microns d'epaisseur; - une mesure du nombre des particules alpha tombant sur la surface etendue irradiee. Les mesures ont ete faites a l'aide d'une emulsion nucleaire et d'un film photographique ordinaire. 1) Les rayons alphas ont une action inductrice. Au plus 15 pc des bacteries peuvent etre induites. 2) La oomparaison de la courbe d'induction et des courbes de survie des souches lysogene et sensible montre qu'il n'y a pas d'inductions abortives. 3) Cette action inductrice n'est pas due a un effet indirect du milieu irradie. (auteur)

  13. Etat Du Magnesium Dans Quelques Sols Sales Du Sud Et Du ...

    African Journals Online (AJOL)

    étude a été réalisée sur 86 échantillons de sols provenant du Centre et du Sud de l´Irak. L\\'expérimentation a consisté, d´une part, à calculer les différents sels dominants dans les sols salés par la méthode de combinaison hypothétique et, ...

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

    African Journals Online (AJOL)

    Une analyse sédimentologique et minéralogique réalisée sur un cycle hydrologique entre octobre 2004 et août 2005 a permis d\\'évaluer les charges solides en suspension et de caractériser les sédiments du lac du barrage de Taabo. La concentration moyenne en matières en suspension (12 mg.L-1) et la turbidité ...

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

    African Journals Online (AJOL)

    Administrateur

    Une analyse sédimentologique et minéralogique réalisée sur un cycle hydrologique entre octobre 2004 et août 2005 a permis d'évaluer les charges solides en suspension et de caractériser les sédiments du lac du barrage de Taabo. La concentration moyenne en matières en suspension (12 mg.L-1) et la turbidité ...

  16. The use of polarized deuterons beams and the determination of the optical model parameters; Utilisation de faisceaux de deutons polarises et determination des parametres du modele optique

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-06-15

    entraine des relations entre les parametres adoptes. Les limitations de ces parametres sont etudiees specialement dans le cas d'un faisceau de particules de spin 1 ayant un plan de symetrie. Les reactions nucleaires a deux corps sont decrites dans le formalisme de l'helicite. A l'aide des coefficients de polarisation adoptes, on etudie la polarisation dans l'etat final avec etat initial polarise. Un potentiel optique pour deutons pout comprendre une partie scalaire, un couplage L.S et des potentiels tensoriels formes avec la distance du deuton au noyau, son moment angulaire ou son impulsion relative. Des calculs ont ete faits avec les deux premieres sortes de potentiels tensoriels. Plusieurs auteurs ont calcule un potentiel pour deutons a partir du modele optique nucleon oyau. Ces calculs sont repris en considerant l'onde S et l'onde D du deuton. Les differentes parties du potentiel ont ete calculees avec plusieurs fonctions d'onde intrinseque. L'utilisation de potentiels non uniquement scalaires permet d'obtenir de bons accords pour la section efficace avec des rayons nucleaires plus eleves que ceux necessaires avec un potentiel purement central. Les mesures experimentales de polarisation faites a Saclay pour la diffusion elastique de deutons sur le calcium sont en desaccord avec l'existence d'un potentiel tensoriel important ; elles peuvent etre reproduites en utilisant un couplage L.S. independant du potentiel central, mais avec des rayons tres faibles. (auteur)

  17. Determination of radioactive risks connected with the working of a nuclear plant; Evaluation des risques radioactifs lies au fonctionnement d'une installation nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Lavie, J M; Doury, A [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Numerous problems which are posed by the evaluation of the radioactive risks linked to the working of a nuclear plant are new problems which have not yet been satisfactorily solved. In these conditions this study must be considered only as a preliminary approach whose essential aims are the following: - development and synthesis of the existing data; - rapid determination of conservative and usable orders of greatness for the security factors, both for normal working and in the case of an accident. The most probable typical accidents are reviewed together with the nature of the resulting risks and the principal factors on which these risks depend. Among these factors, one of the most important is atmospheric diffusion which is studied in some detail using the analytic model due to Sutton. A logical graphical presentation increasing the flexibility in the use of the results and presents the responsible authorities with a flexible, practical and rapid means of evaluating the risks involved starting from a sufficiently general system of initial and simultaneously valid conditions (types of accident, atmospheric conditions). (author) [French] De nombreux problemes souleves par l'evaluation des risques radioactifs lies au fonctionnement d'une installation nucleaire sont des problemes nouveaux qui n'ont pas encore recu de solution satisfaisante. Dans ces conditions cette etude ne doit etre consideree que comme une premiere approche dont les objectifs essentiels sont les suivants: - mise au point et synthese de donnees existantes; - determination rapide d'ordres de grandeur conservatifs et utilisables de valeurs de securite, tant en fonctionnement normal qu'en cas d'accident. Les accidents types les plus probables sont passes en revue ainsi que la nature des risques qui en decoulent et les principaux facteurs dont dependent ces risques. Parmi ces facteurs, l'un des plus importants est la diffusion atmospherique qui fait l'objet d'une etude particuliere a l'aide du modele

  18. 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

  19. 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 fonctionnement et le

  20. Some aspects of nuclear graphite production in France; Etude generale sur les graphites nucleaires produits en France

    Energy Technology Data Exchange (ETDEWEB)

    Gueron, J; Hering, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legendre, A [Pechiney, 75 - Paris (France)

    1958-07-01

    1) Manufacturing: A summary and results on the CEA-Pechiney purification process are given. Variations in the preparation of green pastes and their effects on graphitized material are described. 2) Physical and mechanical properties: Results are given on: - Statistics of dimensional variatior products having square cross-section. - Statistical variation of thermal expansion coefficients and of electrical conductivity. - Density of normals to carbon layer planes and their connexion with thermal expansion. - Stress-strain cycles and conclusions drawn therefrom. - Mechanical resistance and gas permeability of items for supporting fuel elements. 3) Behaviour under radiation: Alteration under radiation of French graphites irradiated either in G1 pile or in experimental piles, and thermal annealing of those alterations, are given. (author)Fren. [French] 1) Fabrication: On resume le procede d'epuration CEA-PECHINEY, ainsi que diverses modalites de preparation des pates et on expose les resultats obtenus. 2) Proprietes physiques et mecaniques: On indique le resultat d'etudes sur: - la statistique des dimensions de produits a section carree. - celle des variations des coefficients de dilatation thermique et de la conductibilite electrique. - la densite des normales aux plans graphitiques et leur connexion avec la dilatation thermique. - la compression mecanique du graphite. - la solidite mecanique et la permeabilite aux gaz de pieces destinees a supporter des cartouches de combustible. 3) Tenue sous rayonnement: Modification sous rayonnement des graphites fran is irradies soit dans la pile G1, soit dans des piles experimentales, et guerison thermique de ces modifications. (auteur)

  1. 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...

  2. Simulation numérique du transfert de chaleur dans un moteur-fusée à propergol liquide

    Directory of Open Access Journals (Sweden)

    B. KHELIDJ

    2015-03-01

    Full Text Available Ce travail est une contribution à l'étude du refroidissement d'un moteur-fusée à propergol liquide. En effet pour protéger la paroi de la chambre propulsive, un système de refroidissement est nécessaire, car la température des gaz de combustion du propergol liquide dans la chambre de combustion, est très élevée. C'est pour montrer l'intérêt du refroidissement de la paroi de la chambre propulsive qu'une étude de simulation numérique, des phénomènes de combustion et de refroidissement dans la chambre propulsive, a été réalisée en régime permanent à l'aide du code de calcul Fluent. Les résultats de simulation, notamment ceux relatifs aux températures des parois le long de la chambre propulsive ont été confrontés à ceux trouvés dans la littérature.

  3. Low emission internal combustion engine

    Science.gov (United States)

    Karaba, Albert M.

    1979-01-01

    A low emission, internal combustion compression ignition engine having a cylinder, a piston movable in the cylinder and a pre-combustion chamber communicating with the cylinder near the top thereof and in which low emissions of NO.sub.x are achieved by constructing the pre-combustion chamber to have a volume of between 70% and 85% of the combined pre-chamber and main combustion chamber volume when the piston is at top dead center and by variably controlling the initiation of fuel injection into the pre-combustion chamber.

  4. Hydrogen assisted diesel combustion

    Energy Technology Data Exchange (ETDEWEB)

    Lilik, Gregory K.; Boehman, Andre L. [The EMS Energy Institute, The Pennsylvania State University, University Park, PA 16802 (United States); Zhang, Hedan; Haworth, Daniel C. [Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, PA 16802 (United States); Herreros, Jose Martin [Escuela Tecnica Superior de Ingenieros Industriales, Universidad de Castilla La-Mancha, Avda. Camilo Jose Cela s/n, 13071 Ciudad Real (Spain)

    2010-05-15

    Hydrogen assisted diesel combustion was investigated on a DDC/VM Motori 2.5L, 4-cylinder, turbocharged, common rail, direct injection light-duty diesel engine, with a focus on exhaust emissions. Hydrogen was substituted for diesel fuel on an energy basis of 0%, 2.5%, 5%, 7.5%, 10% and 15% by aspiration of hydrogen into the engine's intake air. Four speed and load conditions were investigated (1800 rpm at 25% and 75% of maximum output and 3600 rpm at 25% and 75% of maximum output). A significant retarding of injection timing by the engine's electronic control unit (ECU) was observed during the increased aspiration of hydrogen. The retarding of injection timing resulted in significant NO{sub X} emission reductions, however, the same emission reductions were achieved without aspirated hydrogen by manually retarding the injection timing. Subsequently, hydrogen assisted diesel combustion was examined, with the pilot and main injection timings locked, to study the effects caused directly by hydrogen addition. Hydrogen assisted diesel combustion resulted in a modest increase of NO{sub X} emissions and a shift in NO/NO{sub 2} ratio in which NO emissions decreased and NO{sub 2} emissions increased, with NO{sub 2} becoming the dominant NO{sub X} component in some combustion modes. Computational fluid dynamics analysis (CFD) of the hydrogen assisted diesel combustion process captured this trend and reproduced the experimentally observed trends of hydrogen's effect on the composition of NO{sub X} for some operating conditions. A model that explicitly accounts for turbulence-chemistry interactions using a transported probability density function (PDF) method was better able to reproduce the experimental trends, compared to a model that ignores the influence of turbulent fluctuations on mean chemical production rates, although the importance of the fluctuations is not as strong as has been reported in some other recent modeling studies. The CFD results confirm

  5. Effets de la microdose sur la production du niébé, du mil et du ...

    African Journals Online (AJOL)

    Effets de la microdose sur la production du niébé, du mil et du sorgho en fonction la toposéquence. Fatimata Saba, Sibiri Jean Baptiste Taonda, Idriss Serme, Alimata A. Bandaogo, Augustin P. Sourwema, Adama Kabre ...

  6. Dynamique des populations du foreur des tiges du cacaoyer ...

    African Journals Online (AJOL)

    SARAH

    30 nov. 2014 ... déprédateur dans la région du Haut-Sassandra, la deuxième plus grande région de production de cacao en. Côte d'ivoire. Méthodologie et résultats : L'étude a été réalisée de 2009 à 2013 dans les plantations villageoises de la région du Haut-Sassandra en Côte d'Ivoire. Les variations des taux d'attaques ...

  7. Dynamique des populations du foreur des tiges du cacaoyer ...

    African Journals Online (AJOL)

    Objectif : Le foreur de tiges du cacaoyer, Eulophonotus myrmeleon Felder cause aujourd'hui d'énormes dégâts dans les cacaoyères ivoiriennes. La présente étude vise à déterminer les périodes de fortes attaques de ce déprédateur dans la région du Haut-Sassandra, la deuxième plus grande région de production de ...

  8. Combustion strategy : United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Greenhalgh, D. [Heriot-Watt Univ., Edingburgh, Scotland (United Kingdom). School of Engineering and Physical Sciences

    2009-07-01

    The United Kingdom's combustion strategy was briefly presented. Government funding sources for universities were listed. The United Kingdom Research Councils that were listed included the Arts and Humanities Research Council (AHRC) and the Biotechnology and Biological Sciences Research Council (BBSRC); the Engineering and Physical Sciences Research Council (EPSRC); the Economic and Social Research Council; the Medical Research Council; the Natural Environment Research Council; and the Science and Technology Facilities Council. The EPSRC supported 65 grants worth 30.5 million pounds. The combustion industry was noted to be dominated by three main players of which one was by far the largest. The 3 key players were Rolls-Royce; Jaguar Land Rover; and Doosan Babcock. Industry and government involvement was also discussed for the BIS Technology Strategy Board, strategy technology areas, and strategy application areas.

  9. Aerosols from biomass combustion

    Energy Technology Data Exchange (ETDEWEB)

    Nussbaumer, T.

    2001-07-01

    This report is the proceedings of a seminar on biomass combustion and aerosol production organised jointly by the International Energy Agency's (IEA) Task 32 on bio energy and the Swiss Federal Office of Energy (SFOE). This collection of 16 papers discusses the production of aerosols and fine particles by the burning of biomass and their effects. Expert knowledge on the environmental impact of aerosols, formation mechanisms, measurement technologies, methods of analysis and measures to be taken to reduce such emissions is presented. The seminar, visited by 50 participants from 11 countries, shows, according to the authors, that the reduction of aerosol emissions resulting from biomass combustion will remain a challenge for the future.

  10. 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.

  11. Plasma Assisted Combustion

    Science.gov (United States)

    2007-02-28

    Tracking an individual streamer branch among others in a pulsed induced discharge J. Phys. D: Appl. Phys. 35 2823--9 [29] van Veldhuizen E M and Rutgers...2005) AIAA–2005–0405. [99] E.M. Van Veldhuizen (ed) Electrical Discharges for Environmental Purposes: Fun- damentals and Applications (New York: Nova...Vandooren J, Van Tiggelen P J 1977 Reaction Mechanism and Rate Constants in Lean Hydrogen–Nitrous Oxide Flames Combust. Flame 28 165 [201] Dean A M, Steiner

  12. Fluid-bed combustion

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, G.; Schoebotham, N.

    1981-02-01

    In Energy Equipment Company's two-stage fluidized bed system, partial combustion in a fluidized bed is followed by burn-off of the generated gases above the bed. The system can be retrofitted to existing boilers, and can burn small, high ash coal efficiently. It has advantages when used as a hot gas generator for process drying. Tests on a boiler at a Cadbury Schweppes plant are reported.

  13. Combustion science and engineering

    CERN Document Server

    Annamalai, Kalyan

    2006-01-01

    Introduction and Review of Thermodynamics Introduction Combustion Terminology Matter and Its Properties Microscopic Overview of Thermodynamics Conservation of Mass and Energy and the First Law of Thermodynamics The Second Law of Thermodynamics Summary Stoichiometry and Thermochemistry of Reacting Systems Introduction Overall Reactions Gas Analyses Global Conservation Equations for Reacting Systems Thermochemistry Summary Appendix Reaction Direction and Equilibrium Introduction Reaction Direction and Chemical Equilibrium Chemical Equilibrium Relations Vant Hoff Equation Adi

  14. Le Developmental Entrepreneurship Program du Massachusetts ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Faire en sorte que les étudiants venant des pays en développement pour étudier au MIT retournent ensuite dans leurs pays respectifs afin d'y concrétiser leurs idées est un souci majeur du MIT, des bailleurs de fonds et du milieu du développement. Ce projet palliera à ce souci en soutenant la formation des fellows du ...

  15. Issues in waste combustion

    Energy Technology Data Exchange (ETDEWEB)

    Gustavsson, Lennart; Robertson, Kerstin; Tullin, Claes [Swedish National Testing and Research Inst., Boraas (Sweden); Sundquist, Lena; Wrangensten, Lars [AaF-Energikonsult AB, Stockholm (Sweden); Blom, Elisabet [AaF-Processdesign AB, Stockholm (Sweden)

    2003-05-01

    The main purpose of this review is to provide an overview of the state-of-the-art on research and development issues related to waste combustion with relevance for Swedish conditions. The review focuses on co-combustion in grate and fluidised bed furnaces. It is primarily literature searches in relevant databases of scientific publications with to material published after 1995. As a complement, findings published in different report series, have also been included. Since the area covered by this report is very wide, we do not claim to cover the issues included completely and it has not been possitile to evaluate the referred studies in depth. Basic knowledge about combustion issues is not included since such information can be found elsewhere in the literature. Rather, this review should be viewed as an overview of research and development in the waste-to-energy area and as such we hope that it will inspire scientists and others to further work in relevant areas.

  16. Les dispositifs du Net art

    OpenAIRE

    Fourmentraux, Jean-Paul

    2010-01-01

    La pratique du Net art radicalise la question du potentiel communicationnel d’un média —Internet— qui constitue tout à la fois le support technique, l’outil créatif et le dispositif social de l’œuvre. Les technologies de l’information et de la communication (TIC) placent en effet l’œuvre d’art au cœur d’une négociation socialement distribuée entre l’artiste et le public. L’article est focalisé sur cette construction collective du Net art et sur ses mises en scènes. Il montre le travail artist...

  17. L'administration du travail et la production du droit du travail (1906-1960). : Note de synthèse du rapport de recherche

    OpenAIRE

    Le Crom , Jean-Pierre

    2007-01-01

    Synthèse d'un rapport de recherche dont l'objectif est d'appréhender le rôle de l'administration centrale du travail dans la production du droit du travail. Deux dimensions sont explorées : le profil des rédacteurs et l'organisation des structures.

  18. The Diesel Combustion Collaboratory: Combustion Researchers Collaborating over the Internet

    Energy Technology Data Exchange (ETDEWEB)

    C. M. Pancerella; L. A. Rahn; C. Yang

    2000-02-01

    The Diesel Combustion Collaborator (DCC) is a pilot project to develop and deploy collaborative technologies to combustion researchers distributed throughout the DOE national laboratories, academia, and industry. The result is a problem-solving environment for combustion research. Researchers collaborate over the Internet using DCC tools, which include: a distributed execution management system for running combustion models on widely distributed computers, including supercomputers; web-accessible data archiving capabilities for sharing graphical experimental or modeling data; electronic notebooks and shared workspaces for facilitating collaboration; visualization of combustion data; and video-conferencing and data-conferencing among researchers at remote sites. Security is a key aspect of the collaborative tools. In many cases, the authors have integrated these tools to allow data, including large combustion data sets, to flow seamlessly, for example, from modeling tools to data archives. In this paper the authors describe the work of a larger collaborative effort to design, implement and deploy the DCC.

  19. Internal combustion engine using premixed combustion of stratified charges

    Science.gov (United States)

    Marriott, Craig D [Rochester Hills, MI; Reitz, Rolf D [Madison, WI

    2003-12-30

    During a combustion cycle, a first stoichiometrically lean fuel charge is injected well prior to top dead center, preferably during the intake stroke. This first fuel charge is substantially mixed with the combustion chamber air during subsequent motion of the piston towards top dead center. A subsequent fuel charge is then injected prior to top dead center to create a stratified, locally richer mixture (but still leaner than stoichiometric) within the combustion chamber. The locally rich region within the combustion chamber has sufficient fuel density to autoignite, and its self-ignition serves to activate ignition for the lean mixture existing within the remainder of the combustion chamber. Because the mixture within the combustion chamber is overall premixed and relatively lean, NO.sub.x and soot production are significantly diminished.

  20. Development of flameless combustion; Desarrollo de la combustion sin flama

    Energy Technology Data Exchange (ETDEWEB)

    Flores Sauceda, M. Leonardo; Cervantes de Gortari, Jaime Gonzalo [Universidad Nacional Autonoma de Mexico, Mexico, D.F. (Mexico)]. E-mail: 8344afc@prodigy.net.mx; jgonzalo@servidor.unam.mx

    2010-11-15

    The paper intends contribute to global warming mitigation joint effort that develops technologies to capture the CO{sub 2} produced by fossil fuels combustion and to reduce emission of other greenhouse gases like the NO{sub x}. After reviewing existing combustion bibliography is pointed out that (a) touches only partial aspects of the collective system composed by Combustion-Heat transfer process-Environment, whose interactions are our primary interest and (b) most specialists think there is not yet a clearly winning technology for CO{sub 2} capture and storage. In this paper the study of combustion is focused as integrated in the aforementioned collective system where application of flameless combustion, using oxidant preheated in heat regenerators and fluent gas recirculation into combustion chamber plus appropriated heat and mass balances, simultaneously results in energy saving and environmental impact reduction. [Spanish] El trabajo pretende contribuir al esfuerzo conjunto de mitigacion del calentamiento global que aporta tecnologias para capturar el CO{sub 2} producido por la combustion de combustibles fosiles y para disminuir la emision de otros gases invernadero como NOx. De revision bibliografica sobre combustion se concluye que (a) trata aspectos parciales del sistema compuesto por combustion-proceso de trasferencia de calor-ambiente, cuyas interacciones son nuestro principal interes (b) la mayoria de especialistas considera no hay todavia una tecnologia claramente superior a las demas para captura y almacenaje de CO{sub 2}. Se estudia la combustion como parte integrante del mencionado sistema conjunto, donde la aplicacion de combustion sin flama, empleando oxidante precalentado mediante regeneradores de calor y recirculacion de gases efluentes ademas de los balances de masa y energia adecuados, permite tener simultaneamente ahorros energeticos e impacto ambiental reducido.

  1. Use of the helium-3 proportional counter for neutron spectrometry; Utilisation du compteur proportionnel a helium 3 pour la spectrometrie des neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Vialettes, H; Le Thanh, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    Up to now, two methods have been mainly used for neutron spectrometry near nuclear installations: - photographic emulsion spectrometry - the so-called, 'multisphere' technique spectrometry. The first method, which is fairly difficult to apply, has a threshold energy of about 500 keV; this is a big disadvantage for an apparatus which has to be used for spectrometry around nuclear installations where the neutron radiation is very much degraded energetically. The second method does not suffer from this disadvantage but the results which it yields are only approximate. In order to extend the energy range of the neutron spectra studied with sufficient accuracy the use of a helium-3 proportional counter has been considered. This report presents the principles of operation of the helium-3 spectrometer, and the calculation methods which make it possible to take into account the two main effects tending to deform the spectra obtained: - energy absorption by the walls of the counter, - energy loss of the incident neutrons due to elastic collisions with helium-3 nuclei. As an example of the application, the shape of the neutron spectrum emitted by a polonium-lithium source is given; the results obtained are in excellent agreement with theoretical predictions. (authors) [French] Jusqu'ici deux methodes ont ete utilisees principalement pour la spectrometrie des neutrons autour des installations nucleaires: - la spectrometrie par emulsions photographiques - la spectrometrie par la technique dite des multispheres. La premiere methode, d'un emploi assez delicat presente un seuil en energie d'environ 500 keV qui est un obstacle serieux a la spectrometrie autour des installations nucleaires ou le rayonnement neutronique est tres degrade en energie. La deuxieme methode ne presente pas cet inconvenient mais les resultats qu'elle permet d'obtenir ne sont qu'approches. Pour etendre la gamme d'energie des spectres de neutrons etudies avec une precision suffisante, l'utilisation du

  2. 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.

  3. Sulfur Chemistry in Combustion I

    DEFF Research Database (Denmark)

    Johnsson, Jan Erik; Glarborg, Peter

    2000-01-01

    of the sulphur compounds in fossil fuels and the possibilities to remove them will be given. Then the combustion of sulphur species and their influence on the combustion chemistry and especially on the CO oxidation and the NOx formation will be described. Finally the in-situ removal of sulphur in the combustion...... process by reaction between SO2 and calcium containing sorbents and the influence on the NOx chemistry will be treated....

  4. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  5. Pulsating combustion - Combustion characteristics and reduction of emissions

    Energy Technology Data Exchange (ETDEWEB)

    Lindholm, Annika

    1999-11-01

    In the search for high efficiency combustion systems pulsating combustion has been identified as one of the technologies that potentially can meet the objectives of clean combustion and good fuel economy. Pulsating combustion offers low emissions of pollutants, high heat transfer and efficient combustion. Although it is an old technology, the interest in pulsating combustion has been renewed in recent years, due to its unique features. Various applications of pulsating combustion can be found, mainly as drying and heating devices, of which the latter also have had commercial success. It is, however, in the design process of a pulse combustor, difficult to predict the operating frequency, the heat release etc., due to the lack of a well founded theory of the phenomenon. Research concerning control over the combustion process is essential for developing high efficiency pulse combustors with low emissions. Natural gas fired Helmholtz type pulse combustors have been the experimental objects of this study. In order to investigate the interaction between the fluid dynamics and the chemistry in pulse combustors, laser based measuring techniques as well as other conventional measuring techniques have been used. The experimental results shows the possibilities to control the combustion characteristics of pulsating combustion. It is shown that the time scales in the large vortices created at the inlet to the combustion chamber are very important for the operation of the pulse combustor. By increasing/decreasing the time scale for the large scale mixing the timing of the heat release is changed and the operating characteristics of the pulse combustor changes. Three different means for NO{sub x} reduction in Helmholtz type pulse combustors have been investigated. These include exhaust gas recirculation, alteration of air/fuel ratio and changed inlet geometry in the combustion chamber. All used methods achieved less than 10 ppm NO{sub x} emitted (referred to stoichiometric

  6. Molten salts in nuclear reactors; Les sels fondus dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Dirian, J; Saint-James, [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    Collection of references dealing with the physicochemical studies of fused salts, in particular the alkali and alkali earth halides. Numerous binary, ternary and quaternary systems of these halides with those of uranium and thorium are examined, and the physical properties, density, viscosity, vapour pressure etc... going from the halides to the mixtures are also considered. References relating to the corrosion of materials by these salts are included and the treatment of the salts with a view to recuperation after irradiation in a nuclear reactor is discussed. (author) [French] Bibliographie regroupant l'etude physico-chimique des sels fondus, en particulier des halogenures alcalins et alcalino-terreux. On etudie de nombreux systemes binaires, ternaires et quaternaires de ces halogenures avec des halogenures d'uranium, et de thorium. On etudie egalement les proprietes physiques des halogenures ou des melanges d'halogenures (densite, viscosite, tension de vapeur, etc...). On donne egalement des references quant a la corrosion des materiaux par ces sels, et le traitement de ceux-ci en vue de recuperation, apres irradiation dans un reacteur nucleaire. (auteur)

  7. Combustion from basics to applications

    CERN Document Server

    Lackner, Maximilian; Winter, Franz

    2013-01-01

    Combustion, the process of burning, is defined as a chemical reaction between a combustible reactant (the fuel) and an oxidizing agent (such as air) in order to produce heat and in most cases light while new chemical species (e.g., flue gas components) are formed. This book covers a gap on the market by providing a concise introduction to combustion. Most of the other books currently available are targeted towards the experienced users and contain too many details and/or contain knowledge at a fairly high level. This book provides a brief and clear overview of the combustion basics, suitable f

  8. Mathematical Modeling in Combustion Science

    CERN Document Server

    Takeno, Tadao

    1988-01-01

    An important new area of current research in combustion science is reviewed in the contributions to this volume. The complicated phenomena of combustion, such as chemical reactions, heat and mass transfer, and gaseous flows, have so far been studied predominantly by experiment and by phenomenological approaches. But asymptotic analysis and other recent developments are rapidly changing this situation. The contributions in this volume are devoted to mathematical modeling in three areas: high Mach number combustion, complex chemistry and physics, and flame modeling in small scale turbulent flow combustion.

  9. Un Nouveau Monde du Savoir

    International Development Research Centre (IDRC) Digital Library (Canada)

    Si les effets de la mondialisation sur l'économie, la politique ou encore les ..... Il souligne l'importance cruciale d'un plan stratégique d'internationalisation, ...... Lors du recrutement de nouveaux professeurs ( lorsque cette situation est ...

  10. rive gauche du fleuve Rimac

    International Development Research Centre (IDRC) Digital Library (Canada)

    tégée du fleuve et les terrains vagues d'une zone industrielle. .... Ces deux diagnostics sont d'importants outils qui contri- bueront à une meilleure planification ... conditions et instruments nécessaires pour améliorer la situation financière des ...

  11. Voorwoord Forward | du Plessis | Lexikos

    African Journals Online (AJOL)

    J.CM.D. du Plessis. Abstract. No Abstract. Full Text: EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT · DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT · AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's Partners · Terms and Conditions ...

  12. Charte du Conseil des Gouverneurs

    International Development Research Centre (IDRC) Digital Library (Canada)

    Office 2004 Test Drive User

    7. favoriser des communications ouvertes et franches entre le personnel, la direction ..... de dresser le procès-verbal des réunions du Conseil et de ses comités et de veiller à ce ... et des résultats qu'il obtient, et non de sa gestion quotidienne.

  13. Bases biologiques du comportement social

    CERN Document Server

    Laborit, H

    1994-01-01

    Pour bien comprendre le comportement humain dans un environnement social,il est necessaire de comprendre comment fonctionne le systÂ?me nerveux central. L'une des principales fonctions du cerveau est de crÂ?er des relations entre leshumains.. .................

  14. Combustion Byproducts Recycling Consortium

    Energy Technology Data Exchange (ETDEWEB)

    Ziemkiewicz, Paul; Vandivort, Tamara; Pflughoeft-Hassett, Debra; Chugh, Y Paul; Hower, James

    2008-08-31

    Each year, over 100 million tons of solid byproducts are produced by coal-burning electric utilities in the United States. Annual production of flue gas desulfurization (FGD) byproducts continues to increase as the result of more stringent sulfur emission restrictions. In addition, stricter limits on NOx emissions mandated by the 1990 Clean Air Act have resulted in utility burner/boiler modifications that frequently yield higher carbon concentrations in fly ash, which restricts the use of the ash as a cement replacement. Controlling ammonia in ash is also of concern. If newer, “clean coal” combustion and gasification technologies are adopted, their byproducts may also present a management challenge. The objective of the Combustion Byproducts Recycling Consortium (CBRC) is to develop and demonstrate technologies to address issues related to the recycling of byproducts associated with coal combustion processes. A goal of CBRC is that these technologies, by the year 2010, will lead to an overall ash utilization rate from the current 34% to 50% by such measures as increasing the current rate of FGD byproduct use and increasing in the number of uses considered “allowable” under state regulations. Another issue of interest to the CBRC would be to examine the environmental impact of both byproduct utilization and disposal. No byproduct utilization technology is likely to be adopted by industry unless it is more cost-effective than landfilling. Therefore, it is extremely important that the utility industry provide guidance to the R&D program. Government agencies and privatesector organizations that may be able to utilize these materials in the conduct of their missions should also provide input. The CBRC will serve as an effective vehicle for acquiring and maintaining guidance from these diverse organizations so that the proper balance in the R&D program is achieved.

  15. 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

  16. The combustion of sodium

    International Nuclear Information System (INIS)

    Newman, R.N.

    1978-01-01

    The burning rates of sodium in the form of vapour jets, droplets, sprays and unconfined and confined pools have been reviewed. Attention has been paid to assessing the value of models in the various combustion modes. Additional models have been constructed for the descriptions of laminar and turbulent vapour jets, stationary droplets, forced convection over ambient pool fires together with correlations for peak pressures in confined pool environments. Where appropriate experiments with sodium have not been conducted, the likely behaviour is predicted by comparison with the burning of other fuels, particularly in the field of large free ambient fires. Some areas where further knowledge is required are highlighted. (author)

  17. Alternate fuels; Combustibles alternos

    Energy Technology Data Exchange (ETDEWEB)

    Romero Paredes R, Hernando; Ambriz G, Juan Jose [Universidad Autonoma Metropolitana. Iztapalapa (Mexico)

    2003-07-01

    In the definition and description of alternate fuels we must center ourselves in those technological alternatives that allow to obtain compounds that differ from the traditional ones, in their forms to be obtained. In this article it is tried to give an overview of alternate fuels to the conventional derivatives of petroleum and that allow to have a clear idea on the tendencies of modern investigation and the technological developments that can be implemented in the short term. It is not pretended to include all the tendencies and developments of the present world, but those that can hit in a relatively short term, in accordance with agreed with the average life of conventional fuels. Nevertheless, most of the conversion principles are applicable to the spectrum of carbonaceous or cellulosic materials which are in nature, are cultivated or wastes of organic origin. Thus one will approach them in a successive way, the physical, chemical and biological conversions that can take place in a production process of an alternate fuel or the same direct use of the fuel such as burning the sweepings derived from the forests. [Spanish] En la definicion y descripcion de combustibles alternos nos debemos centrar en aquellas alternativas tecnologicas que permitan obtener compuestos que difieren de los tradicionales, al menos en sus formas de ser obtenidos. En este articulo se pretende dar un panorama de los combustibles alternos a los convencionales derivados del petroleo y que permita tener una idea clara sobre las tendencias de la investigacion moderna y los desarrollos tecnologicos que puedan ser implementados en el corto plazo. No se pretende abarcar todas las tendencias y desarrollos del mundo actual, sino aquellas que pueden impactar en un plazo relativamente corto, acordes con la vida media de los combustibles convencionales. Sin embargo, la mayor parte de los principios de conversion son aplicables al espectro de materiales carbonaceos o celulosicos los cuales se

  18. Fluidised bed combustion system

    International Nuclear Information System (INIS)

    McKenzie, E.C.

    1976-01-01

    Fluidized bed combustion systems that facilitates the maintenance of the depth of the bed are described. A discharge pipe projects upwardly into the bed so that bed material can flow into its upper end and escape downwardly. The end of the pipe is surrounded by an enclosure and air is discharged into the enclosure so that material will enter the pipe from within the enclosure and have been cooled in the enclosure by the air discharged into it. The walls of the enclosure may themselves be cooled

  19. Fuel and combustion stratification study of Partially Premixed Combustion

    NARCIS (Netherlands)

    Izadi Najafabadi, M.; Dam, N.; Somers, B.; Johansson, B.

    2016-01-01

    Relatively high levels of stratification is one of the main advantages of Partially Premixed Combustion (PPC) over the Homogeneous Charge Compression Ignition (HCCI) concept. Fuel stratification smoothens heat release and improves controllability of this kind of combustion. However, the lack of a

  20. Combustion Stratification for Naphtha from CI Combustion to PPC

    KAUST Repository

    Vallinayagam, R.

    2017-03-28

    This study demonstrates the combustion stratification from conventional compression ignition (CI) combustion to partially premixed combustion (PPC). Experiments are performed in an optical CI engine at a speed of 1200 rpm for diesel and naphtha (RON = 46). The motored pressure at TDC is maintained at 35 bar and fuelMEP is kept constant at 5.1 bar to account for the difference in fuel properties between naphtha and diesel. Single injection strategy is employed and the fuel is injected at a pressure of 800 bar. Photron FASTCAM SA4 that captures in-cylinder combustion at the rate of 10000 frames per second is employed. The captured high speed video is processed to study the combustion homogeneity based on an algorithm reported in previous studies. Starting from late fuel injection timings, combustion stratification is investigated by advancing the fuel injection timings. For late start of injection (SOI), a direct link between SOI and combustion phasing is noticed. At early SOI, combustion phasing depends on both intake air temperature and SOI. In order to match the combustion phasing (CA50) of diesel, the intake air temperature is increased to 90°C for naphtha. The combustion stratification from CI to PPC is also investigated for various level of dilution by displacing oxygen with nitrogen in the intake. The start of combustion (SOC) was delayed with the increase in dilution and to compensate for this, the intake air temperature is increased. The mixture homogeneity is enhanced for higher dilution due to longer ignition delay. The results show that high speed image is initially blue and then turned yellow, indicating soot formation and oxidation. The luminosity of combustion images decreases with early SOI and increased dilution. The images are processed to generate the level of stratification based on the image intensity. The level of stratification is same for diesel and naphtha at various SOI. When O concentration in the intake is decreased to 17.7% and 14

  1. Some Factors Affecting Combustion in an Internal-Combustion Engine

    Science.gov (United States)

    Rothrock, A M; Cohn, Mildred

    1936-01-01

    An investigation of the combustion of gasoline, safety, and diesel fuels was made in the NACA combustion apparatus under conditions of temperature that permitted ignition by spark with direct fuel injection, in spite of the compression ratio of 12.7 employed. The influence of such variables as injection advance angle, jacket temperature, engine speed, and spark position was studied. The most pronounced effect was that an increase in the injection advance angle (beyond a certain minimum value) caused a decrease in the extent and rate of combustion. In almost all cases combustion improved with increased temperature. The results show that at low air temperatures the rates of combustion vary with the volatility of the fuel, but that at high temperatures this relationship does not exist and the rates depend to a greater extent on the chemical nature of the fuel.

  2. Preliminary assessment of combustion modes for internal combustion wave rotors

    Science.gov (United States)

    Nalim, M. Razi

    1995-01-01

    Combustion within the channels of a wave rotor is examined as a means of obtaining pressure gain during heat addition in a gas turbine engine. Several modes of combustion are considered and the factors that determine the applicability of three modes are evaluated in detail; premixed autoignition/detonation, premixed deflagration, and non-premixed compression ignition. The last two will require strong turbulence for completion of combustion in a reasonable time in the wave rotor. The compression/autoignition modes will require inlet temperatures in excess of 1500 R for reliable ignition with most hydrocarbon fuels; otherwise, a supplementary ignition method must be provided. Examples of combustion mode selection are presented for two core engine applications that had been previously designed with equivalent 4-port wave rotor topping cycles using external combustion.

  3. 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

  4. Path planning during combustion mode switch

    Science.gov (United States)

    Jiang, Li; Ravi, Nikhil

    2015-12-29

    Systems and methods are provided for transitioning between a first combustion mode and a second combustion mode in an internal combustion engine. A current operating point of the engine is identified and a target operating point for the internal combustion engine in the second combustion mode is also determined. A predefined optimized transition operating point is selected from memory. While operating in the first combustion mode, one or more engine actuator settings are adjusted to cause the operating point of the internal combustion engine to approach the selected optimized transition operating point. When the engine is operating at the selected optimized transition operating point, the combustion mode is switched from the first combustion mode to the second combustion mode. While operating in the second combustion mode, one or more engine actuator settings are adjusted to cause the operating point of the internal combustion to approach the target operating point.

  5. AIR EMISSIONS FROM SCRAP TIRE COMBUSTION

    Science.gov (United States)

    The report discusses air emissions from two types of scrap tire combustion: uncontrolled and controlled. Uncontrolled sources are open tire fires, which produce many unhealthful products of incomplete combustion and release them directly into the atmosphere. Controlled combustion...

  6. Plasma igniter for internal-combustion engines

    Science.gov (United States)

    Breshears, R. R.; Fitzgerald, D. J.

    1978-01-01

    Hot ionized gas (plasma) ignites air/fuel mixture in internal combustion engines more effectively than spark. Electromagnetic forces propel plasma into combustion zone. Combustion rate is not limited by flame-front speed.

  7. Some equipment for graphite research in swimming pool reactors; Quelques dispositifs d'etude du graphite dans les piles piscines

    Energy Technology Data Exchange (ETDEWEB)

    Seguin, M; Arragon, Ph; Dupont, G; Gentil, J; Tanis, G [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    The irradiation devices described are used for research concerning reactors of the natural uranium type, moderated by graphite and cooled by carbon dioxide. The devices are generally designed for use in swimming pool reactors. The following points have been particularly studied: - maximum use of the irradiation volume, - use of the simplest technological solutions, - standardization of certain constituent parts. This standardization calls for precision machining and careful assembling; these requirements are also true when a relatively low irradiation temperature is required and the nuclear heating is pronounced. Finally, the design of these devices is suitable for the irradiation of other fissile or non-fissile materials. (authors) [French] Les dispositifs d'irradiation decrits servent aux etudes relatives a la filiere des reacteurs a uranium naturel, moderes au graphite et refroidis par le gaz carbonique. Ils sont generalement concus pour etre utilises dans des piles piscines. L'accent a ete mis sur: - l'utilisation au maximum du volume d'irradiation, - le recours aux solutions technologiques les plus simples, - la standardisation de certaines parties constitutives. Cette standardisation impose un usinage precis et un montage soigne, lesquels sont egalement necessaires lorsqu'on doit obtenir une temperature d'irradiation relativement basse alors que l'echauffement nucleaire est important. Enfin, la conception de ces dispositifs est valable pour irradier d'autres materiaux non fissiles ou fissiles. (auteurs)

  8. Study and installation of concrete shielding in the civil engineering of nuclear construction (1960); Etude et mise en place des betons de protection dans le genie civil des ouvrages nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    sont decrites telles qu'elles ont ete realisees au Centre d'Etudes Nucleaires de Saclay. Des specifications sont donnees pour les betons de barytine et pour la fabrication des blocs de protection du synchrotron a protons 'Saturne'. (auteur)

  9. Study and installation of concrete shielding in the civil engineering of nuclear construction (1960); Etude et mise en place des betons de protection dans le genie civil des ouvrages nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    etudes, deux applications pratiques sont decrites telles qu'elles ont ete realisees au Centre d'Etudes Nucleaires de Saclay. Des specifications sont donnees pour les betons de barytine et pour la fabrication des blocs de protection du synchrotron a protons 'Saturne'. (auteur)

  10. 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.

  11. 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.

  12. Bassins versants du Loup, de la Cagne et du Malvan

    OpenAIRE

    Lepère, Cédric; Lautier, Laurence; Pellegrino, Emmanuel

    2013-01-01

    Identifiant de l'opération archéologique : 8453 Date de l'opération : 2007 (PC) ; 2007 (PI) Inventeur(s) : Lepère Cédric (AUT) ; Lautier Laurence (AUT) ; Pellegrino Emmanuel (AUT) Une campagne de prospection inventaire a été effectuée pendant trois mois, dans les bassins-versants de la Cagne, du Loup et du Malvan qui regroupent les communes de Cagnes-sur-Mer, Villeneuve-Loubet, La Colle-sur-Loup, Saint-Paul-de-Vence, Vence, Saint-Jeannet, Bezaudun, Tourrettes-sur-Loup, Roquefort-les-Pins, Le ...

  13. Manifold methods for methane combustion

    Energy Technology Data Exchange (ETDEWEB)

    Yang, B.; Pope, S.B. [Cornell Univ., Ithaca, NY (United States)

    1995-10-01

    Great progresses have been made in combustion research, especially, the computation of laminar flames and the probability density function (PDF) method in turbulent combustion. For one-dimensional laminar flames, by considering the transport mechanism, the detailed chemical kinetic mechanism and the interactions between these two basic processes, today it is a routine matter to calculate flame velocities, extinction, ignition, temperature, and species distributions from the governing equations. Results are in good agreement with those obtained for experiments. However, for turbulent combustion, because of the complexities of turbulent flow, chemical reactions, and the interaction between them, in the foreseeable future, it is impossible to calculate the combustion flow field by directly integrating the basic governing equations. So averaging and modeling are necessary in turbulent combustion studies. Averaging, on one hand, simplifies turbulent combustion calculations, on the other hand, it introduces the infamous closure problems, especially the closure problem with chemical reaction terms. Since in PDF calculations of turbulent combustion, the averages of the chemical reaction terms can be calculated, PDF methods overcome the closure problem with the reaction terms. It has been shown that the PDF method is a most promising method to calculate turbulent combustion. PDF methods have been successfully employed to calculate laboratory turbulent flames: they can predict phenomena such as super equilibrium radical levels, and local extinction. Because of these advantages, PDF methods are becoming used increasingly in industry combustor codes.

  14. Interesting Developments in UO{sub 2} Technology; Progres interessants dans la technologie du bioxyde d'uranium; Interesnye usovershenstvovaniya tekhnologii UO{sub 2}; Recientes progresos en la tecnologia del UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Robertson, J. A.L. [Atomic Energy of Canada Ltd., Chalk River, Ontario (Canada)

    1963-11-15

    }. With the ability to perform in-reactor measurements a new phase of more meaningful experiments is just starting. These will determine whether any potential economic advantage lies in novel forms of fuel. Meanwhile, continuing development of sintered UO{sub 2} in the simple rod geometry will provide stiff competition. (author) [French] Maintenant que plusieurs reacteurs alimentes au bioxyde d'uranium sont en exploitation normale, on peut considerer que les performances nucleaires de cette matiere sont satisfaisantes et il faut se rejouir de voir se realiser encore de nouveaux progres dans cette branche de la technologie. L'evenement le plus remarquable dans ce domaine est assurement la decouverte des chercheurs de Battelle qui ont observe recemment qu'a haute temperature un monocristal de UO{sub 2} etait doue d'une tres forte conductivite thermique. A la suite d'une controverse sur ce point, une experience d' irradiation faite a Chalk River a montre que les grains de grande dimension formes dans des elements combustibles en fonctionnement ne presentent pas necessairement cette conductivite accrue. Les experiences de laboratoire ont revele que cette augmentation de la conductivite ne se presente que dans les compositions hypostoechiometriques et ne depend guere de l'absence de joint de grain. En fait, la forte conductivite peut etre obtenue dans des frittes polycristallins, si l'on maintient la composition stoechiometrique optimum. On sait depuis longtemps qu' il est possible de reduire rallongement des gaines en menageant des depressions sur chacune des bases des pastilles de UO{sub 2}; on a montre par la suite que si on laissait un vide aux extremites de l'empilement des pastilles, la tendance du combustible a remplir ce vide etait entravee par la dilatation diametrale des pastilles et leur interaction mecanique avec la gaine. On a realise un tres grand progres en vue de reduire los distensions de la gaine lorsqu'on s'est rendu compte que les dilatations longitudinales

  15. Marche du foncier urbain et promotion du logement au Benin ...

    African Journals Online (AJOL)

    Le marché du foncier urbain au Bénin est un secteur qui met en jeu l'intervention de plusieurs acteurs publics et privés mais également de l'informel. La notion de « foncier urbain » utilisée dans cet article englobe les acceptions et les utilisations faites en architecture, en urbanisme, en aménagement et en gestion urbaine.

  16. Gestion du parc agroforestier du terroir de Vipalogo (Burkina Faso ...

    African Journals Online (AJOL)

    Au Burkina Faso, l'arbre rural fait partie des systèmes de production. Le choix des espèces, leur densité, les modes de gestion ainsi que les besoins à satisfaire, obéissent à des critères propres aux producteurs. C'est pour comprendre ces logiques paysannes de la gestion du parc agroforestier que la présente étude a été ...

  17. Malformations du tube neural en chirurgie pediatrique du chu de ...

    African Journals Online (AJOL)

    encéphalocèle et 6 cas de sipina bifida. La cure chirurgicale a été le principal mode de prise en charge des patients. Seuls 91,38% des cas ont été opérés. Pour toutes les malformations du tube neural, nous avons enregistré 7 décès dont 2 décès ...

  18. 3d Modeling of Combustion for Di-Si Engines Modélisation 3D de la combustion dans les moteurs à injection directe d'essence

    Directory of Open Access Journals (Sweden)

    Duclos J. P.

    2006-12-01

    Full Text Available Direct injection of gasoline is a promising concept to reduce fuel consumption of SI engines. The development of GDI engines is difficult and 3D CFD is a way to support its design. It requires models able to describe the spray and its evaporation and combustion. This paper presents a model, the ECFM, that enables to compute combustion for stratified load in the GDI engines. This model is a development of the Coherent Flame Model which includes thermal expansion effects, and is coupled with a burnt/unburnt gases conditionnal thermodynamic properties description. The model is validated by comparing measurements and computations on the GDI Mitsubishi engine in production. L'injection directe d'essence (IDE est un concept prometteur pour les moteurs à allumage commandé. La mise au point de ce type de moteur est néanmoins délicate, et le calcul 3D des chambres de combustion est un moyen d'aider à leur conception. Ceci nécessite cependant de disposer de modèles adaptés, à même de décrire le jet d'essence, son évaporation et la combustion du mélange créé. Cet article présente un modèle ECFM de simulation de la combustion dans les moteurs IDE, y compris en fonctionnement stratifié. C'est un développement du modèle flamme cohérente qui comprend des effets d'expansion thermique et est couplé avec une description conditionnelle gaz frais/gaz brûlés des grandeurs thermodynamiques. Ce modèle a été validé par rapprochement de mesures et simulations sur le moteur GDI Mitsubishi.

  19. Combustion & Laser Diagnostics Research Complex (CLDRC)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: The Combustion and Laser Diagnostics Research Complex (CLRDC) supports the experimental and computational study of fundamental combustion phenomena to...

  20. Numerical and Experimental Study on the Combustion and Emission Characteristics of a Dimethyl Ether (DME Fueled Compression Ignition Engine Études numériques et expérimentales sur les caractéristiques de combustion et d’émissions d’un éther diméthylique (EDM- moteur à auto-allumage rempli de combustible

    Directory of Open Access Journals (Sweden)

    Kim Hyung Jun

    2012-05-01

    Full Text Available A numerical investigation was carried out to study on the combustion and emission characteristics of dimethyl ether (DME with wide ranges of injection timings in compression ignition engines. In order to simulate DME combustion processes, a KIVA-3V code coupled with a chemistry solver was used to solve the detailed chemical kinetics model of DME oxidation. In addition, the Kelvin-Helmholtz-Rayleigh-Taylor (KH-RT hybrid breakup model and Renormalization Group (RNG k-ε  models were applied to analyze the spray characteristics and turbulent flow, respectively. To predict the NOx formation during DME combustion, a reduced Gas Research Institute (GRI NO mechanism was used. From these results on the combustion and emission, the calculated results were compared with experimental ones for the same operating conditions. In the combustion characteristics, the calculated combustion pressure and heat release rates agreed well with experimental results. The levels of experimental NOx emissions was reduced as the start of the injection timing retarded, and also these trends appeared in calculated emission characteristics. Additionally, the calculated CO and HC emissions show an increasing trend as the start of the injection is retarded. Dans cette étude, nous considérons la simulation de la combustion du dimethyl ether (DME dans un moteur à allumage par compression. Les caractéristiques de la combustion ainsi que les émissions polluantes sont analysées sur une large gamme d’avance à l’injection. Afin de simuler le processus de combustion du EDM, le code KIVA-3V couplé à un solveur chimique a été utilisé pour résoudre la cinétique détaillée de l’oxydation du EDM. Le modèle de rupture de Kelvin-Helmholtz-Rayleigh- Taylor (KH-RT ainsi que le modèle de turbulence k-ε  RNG ont été appliqués pour analyser respectivement les caractéristiques du jet et l’écoulement turbulent. Pour prévoir la formation de NOx pendant la combustion

  1. Combustion instability control in the model of combustion chamber

    International Nuclear Information System (INIS)

    Akhmadullin, A N; Ahmethanov, E N; Iovleva, O V; Mitrofanov, G A

    2013-01-01

    An experimental study of the influence of external periodic perturbations on the instability of the combustion chamber in a pulsating combustion. As an external periodic disturbances were used sound waves emitted by the electrodynamics. The purpose of the study was to determine the possibility of using the method of external periodic perturbation to control the combustion instability. The study was conducted on a specially created model of the combustion chamber with a swirl burner in the frequency range from 100 to 1400 Hz. The study found that the method of external periodic perturbations may be used to control combustion instability. Depending on the frequency of the external periodic perturbation is observed as an increase and decrease in the amplitude of the oscillations in the combustion chamber. These effects are due to the mechanisms of synchronous and asynchronous action. External periodic disturbance generated in the path feeding the gaseous fuel, showing the high efficiency of the method of management in terms of energy costs. Power required to initiate periodic disturbances (50 W) is significantly smaller than the thermal capacity of the combustion chamber (100 kW)

  2. The control of the radioactive pollution of milk (1962); Comment concevoir une surveillance des pollutions radioactives du lait (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Milk, an essential foodstuff, is the object of a supervision and vigilant controls governed by numerous laws which protect its commercial and sanitary qualities. The development of the use of nuclear energy poses and will pose new problems of hygiene and the milk should benefit from controls concerning its possible contamination. Grass-eating animals are particularly subjected to radioactive contaminations and the milk which they produce does not escape contamination because of of its saline composition and of the particular metabolism of the mammary gland. As a result, milk is a contamination integrator and its analysis makes it possible to detect radioelements which can only be detected with great difficulty in an average size plant sample. (author) [French] Le lait, aliment essentiel, fait l'objet d'une surveillance et de controles vigilants regis par de nombreux textes legislatifs qui protegent ses qualites marchandes et sanitaires. Le developpement de l'utilisation de l'energie nucleaire pose et posera de nouveaux problemes d'hygiene et le lait doit beneficier de controles portant sur sa pollution radioactive eventuelle. Les, animaux herbivores sont particulierement exposes aux contaminations radioactives et les laits qu'ils produisent, du fait de leurs compositions salines et du metabolisme particulier de la glande mammaire, n'echappent point aux pollutions. De ce fait, le lait est un integrateur de contamination et son analyse permet de retrouver des radioelements que l'on ne decele qu'avec beaucoup de difficultes sur un echantillon vegetal de taille moyenne. (auteur)

  3. 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. Ces resultats ont permis d'etablir un mode

  4. 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...

  5. Les vicissitudes du fret ferroviaire

    OpenAIRE

    DABLANC, L

    2010-01-01

    Dans beaucoup de pays européens, et plus encore en Amérique du Nord et en Asie, le transport de marchandises par le train a augmenté depuis dix ans. Cette activité réduit la part des marchandises acheminées par la route et contribue ainsi au développement durable : un camion émet 8 à 30 fois plus de dioxyde de carbone que le train, pour une distance et une quantité transportée équivalentes. Pourtant, la France a raté ce renouveau. Filiale du groupe public SNCF, la Société Fret SNCF, qui assur...

  6. Study of atmospheric emissions from liquid and solid fuels burning facilities and from raw phosphate chemical treatment in Sfax City (Tunisia); Etude des residus de combustion des fuels liquide et solide et de traitement chimique du phosphate brut dans la ville de Sfax (Tunisie)

    Energy Technology Data Exchange (ETDEWEB)

    Azri, Ch; Tili, A.; Serbaji, M.M. [Faculte des Sciences de Sfax, Dept. des Sciences de la Terre, Sfax (Tunisia); Medhioub, K. [Institut Preparatoire aux Etudes d' Ingenieurs de Sfax (IPEIS), Sfax (Tunisia)

    2002-07-01

    Study of atmospheric emissions from solid and liquid fuels burning facilities and from chemical treatment processes of raw phosphate in Sfax City (Tunisia) shows different forms of pollution concerning mainly sulfur oxides (SO{sub x}), sulfuric and phosphoric acid mists, fluorinated compounds and dust. Limited performances of amortized and/or over used de-pollution systems can explain high atmospheric emissions above emission limits. Gaseous pollution has been shown as coming mainly from phosphate treatment processes inside the chemical complex 'SIAPE' while particulate pollution is coming from all specific industries (SIAPE, charcoal facilities and weaving and soap factories). Calculated emission factors of these industries for some heavy metals (Pb, Cd, Ni, Cu, Zn) are very different. They are ranging from 0.3 to 9.5 g/t for phosphate treatment residues. Excepted Ni with 15.5 g/t, they are rather small for heavy fuels combustion residues. It, nevertheless, exceeds the emission factor of Ni for the phosphate treatment process. Volumes of emissions and calculated annual fluxes of metals are showing that 'SIAPE' could be a potential source of atmospheric pollution in the city. Its contribution to metal emissions is really exceeding emissions from well identified heavy fuels burning facilities in the city. Just to compare, Ni emissions from its processes are equal to emissions from 38 heavy fuels burning facilities of 4.8 t/day capacity (Ni 1 046 kg/year instead of 27 kg/year). Such a fact is clearly pointing out the high level of anthropogenic pollution from chemical processes adopted for primary matter transformation. They hence should be fitted with suitable de-pollution systems. (authors)

  7. Nuclear Materials Management in Relation to Safety and Criticality Control: A Study of Non-Inherently Safe Systems; La Gestion des Matieres Nucleaires dans ses Rapports avec la Securite et le Controle de la Criticite; Etude des Systemes a Securite Non Inherente; Obrashchenie s yadernymi materialami s uchetom bezopasnosti i kontrolya za kritichnost'yu. izuchenie sistem dopolnitel'noj avarijnoj zashchity; La Administracion de Materiales Nucleares y sus Relaciones con la Seguridad y el Control de la Criticidad; Estudio de los Sistemas de Seguridad No Inherente

    Energy Technology Data Exchange (ETDEWEB)

    Fruchard, Y. [Commissariat a l' Energie Atomique, Marcoule (France)

    1966-02-15

    a securite inherente. Toutefois, les systemes a securite non inherente restent nombreux dans les installations nucleaires et le recours a l'une ou l'autre des deux premieres methodes devient necessaire. Ces methodes sont liees a la gestion des matieres nucleaires. Dans les installations ou sont manipulees de petites quantites de matieres fissiles, il est souvent possible d'assurer la securite nucleaire en admettant dans chaque salle une masse de matiere fissile inferieure a la masse ciritique minimale. Pour des installations plus importantes, un tel controle, qui repose entierement sur la gestion des matieres, devient impossible. L'auteur examine, dans le cas particulier d'une usine oe traitement de combustibles irradies par voie aqueuse (les combustibles sont a base d'uranium naturel), comment se presente la liaison entre gestion et securite nucleaire. Une telle usine comprend grossierement trois parties au point de vue du controle de la criticite: Dans la premiere partie, traitant des solutions assez diluees, le controle qui s'impose est celui de la concentration. Si ce controle est aise (analyse et compteurs neutrons), il est difficile de s'assurer qu'il ne se forme pas de depots: bien que l'experience ait montre qu'ils n'etaient pas tellement a craindre, le fait bien connu d'un bilan matieres deficitaire reste un souci en matiere de criticite. Dans cette partie, la gestion des matieres, encore imparfaitement realisee, est de premiere importance pour la securite. La deuxieme partie traite des solutions concentrees et des precipites humides. C'est le domaine de la geometrie sure. La gestion des matieres l'interesse moins directement mais reste un facteur de securite important (en cas d'intervention, de nettoyage des appareils, etc.). Un controle par la masse s'impose dans la troisieme partie qui traite des produits secs. La gestion ne presente pas de difficulte particuliere. A ce schema se superpose une partie moins spectaculaire mais qui sur le plan surete est de

  8. 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).

  9. Revision des Symphurus du Siboga

    NARCIS (Netherlands)

    Chabanaud, Paul

    1955-01-01

    Ce m’est un devoir particulièrement agréable que de saisir l’occasion de ce petit mémoire pour remercier M. L. F. DE BEAUFORT, M. H. ENGEL, Directeur du Zoologisch Museum, ainsi que M. J. J. HOEDEMAN de l’accueil qu’à diverses reprises, j’ai reçu de leur part, au Zoölogisch Museum, et aussi des

  10. Space Station Freedom combustion research

    Science.gov (United States)

    Faeth, G. M.

    1992-01-01

    Extended operations in microgravity, on board spacecraft like Space Station Freedom, provide both unusual opportunities and unusual challenges for combustion science. On the one hand, eliminating the intrusion of buoyancy provides a valuable new perspective for fundamental studies of combustion phenomena. On the other hand, however, the absence of buoyancy creates new hazards of fires and explosions that must be understood to assure safe manned space activities. These considerations - and the relevance of combustion science to problems of pollutants, energy utilization, waste incineration, power and propulsion systems, and fire and explosion hazards, among others - provide strong motivation for microgravity combustion research. The intrusion of buoyancy is a greater impediment to fundamental combustion studies than to most other areas of science. Combustion intrinsically heats gases with the resulting buoyant motion at normal gravity either preventing or vastly complicating measurements. Perversely, this limitation is most evident for fundamental laboratory experiments; few practical combustion phenomena are significantly affected by buoyancy. Thus, we have never observed the most fundamental combustion phenomena - laminar premixed and diffusion flames, heterogeneous flames of particles and surfaces, low-speed turbulent flames, etc. - without substantial buoyant disturbances. This precludes rational merging of theory, where buoyancy is of little interest, and experiments, that always are contaminated by buoyancy, which is the traditional path for developing most areas of science. The current microgravity combustion program seeks to rectify this deficiency using both ground-based and space-based facilities, with experiments involving space-based facilities including: laminar premixed flames, soot processes in laminar jet diffusion flames, structure of laminar and turbulent jet diffusion flames, solid surface combustion, one-dimensional smoldering, ignition and flame

  11. Synthesis and purification of some alkyl phenanthrenes and presentation of their infrared, ultraviolet, nuclear magnetic resonance and mass spectra; Synthese et purification de quelques alcoylphenanthrenes et presentation ds leurs spectres d'absorption infrarouge, ultraviolette, de resonance magnetique nucleaire et de masse

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-01-01

    We have carried out the synthesis of: - phenanthrene - its five monomethyl derivatives - three dimethyl derivatives - two trimethyl derivatives. We have then purified these products as well as a certain number of others obtained from various sources. We have been able to obtain in the majority of cases, a purity of 99.5 per cent or over, these figures being obtained by low voltage mass spectrometry. Finally we have recorded the infrared, ultraviolet, nuclear magnetic resonance and mass spectra of these products for which an atlas has been drawn up. (author) [French] Nous avons realise la synthese: - du phenanthrene - de ses cinq derives monomethyles - de trois de ses derives dimethyles - de deux de ses derives trimethyles. Nous avons ensuite purifie ces produits ainsi qu'un certain nombre d'autres que nous avons obtenus de sources differentes. Nous avons pu atteindre, dans la plupart des cas, une purete egale ou superieure a 99,5 pour cent, chiffres determines par la spectrometrie de masse a basse tension. Enfin, nous avons enregistre les spectres infrarouges, ultraviolets, de resonance magnetique nucleaire et de masse de ces produits dont nous avons fait un atlas. (auteur)

  12. Actes des 5èmes Journées Scientifiques du GDR3544 Sciences du Bois. Journées Annuelles du GDR 3544 Sciences du Bois

    OpenAIRE

    CHAPLAIN, Myriam; CARE, Sabine; GRIL, Joseph

    2016-01-01

    Le Groupement de Recherche en Sciences du bois (GDR3544 Sciences du Bois) a été créé en 2012 par le CNRS et renouvelé en 2016 pour 5 ans. La mission de ce groupement est : (1) de structurer la recherche sur le bois en France pour lui donner une visibilité nationale, (2) de contribuer au développement de la formation en sciences du bois et (3) de servir de relai aux réseaux internationaux de sciences du bois. Les 5èmes journées annuelles du GDR Bois ont été organisées à Bordeaux, au domaine du...

  13. 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. .... (Canada) et du. Ministère de la Santé du Bénin. Le consentement éclairé écrit a été obtenu de chaque participant avant leur recrutement dans.

  14. Use of tri-laurylamine during the retreatment of irradiated fuels; Utilisation de la trilaurylamine au retraitement des combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

    Bathellier, A; Koehly, G; Perez, J J; Chesne, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    The purification of aqueous solutions of plutonium can be made by extraction of the Pu (IV) nitrate complex using trilaurylamine in dodecane. The principal physical properties of this solution are considered along with its extractive properties and the influence of foreign ions on the extraction. The application of this method of extraction in a processing cycle for irradiated material is proposed: either for a final purification process or for auxiliary cycles for recovering plutonium from metal production wastes, oxalate precipitation supernatants, or any general aqueous plutonium waste solution. Also proposed are clean-up procedures for regeneration of an extractive solution which has undergone chemical or radiolytic degradation. (authors) [French] La purification du plutonium contenu dans des solutions aqueuses peut etre effectuee par extraction du nitrate de l'ion tetravalent par la trilaurylamine diluee dans du dodecane. Les principales proprietes physiques de ce solvant sont passees en revue ainsi que ses proprietes extractives et l'influence des ions etrangers sur celles-ci. L'application de cette methode d'extraction dans le cycle de traitement des combustibles irradies est envisagee: soit dans le traitement de purification finale, soit dans les cycles annexes ayant trait a la recuperation de plutonium a partir des scories d'elaboration du metal, des eaux-meres oxaliques et d'une facon generale des solutions aqueuses contenant du plutonium. Des traitements de regeneration du solvant ayant subi des degradations chimique ou radiolytique, sont proposes. (auteurs)

  15. Use of tri-laurylamine during the retreatment of irradiated fuels; Utilisation de la trilaurylamine au retraitement des combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

    Bathellier, A.; Koehly, G.; Perez, J.J.; Chesne, A. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    The purification of aqueous solutions of plutonium can be made by extraction of the Pu (IV) nitrate complex using trilaurylamine in dodecane. The principal physical properties of this solution are considered along with its extractive properties and the influence of foreign ions on the extraction. The application of this method of extraction in a processing cycle for irradiated material is proposed: either for a final purification process or for auxiliary cycles for recovering plutonium from metal production wastes, oxalate precipitation supernatants, or any general aqueous plutonium waste solution. Also proposed are clean-up procedures for regeneration of an extractive solution which has undergone chemical or radiolytic degradation. (authors) [French] La purification du plutonium contenu dans des solutions aqueuses peut etre effectuee par extraction du nitrate de l'ion tetravalent par la trilaurylamine diluee dans du dodecane. Les principales proprietes physiques de ce solvant sont passees en revue ainsi que ses proprietes extractives et l'influence des ions etrangers sur celles-ci. L'application de cette methode d'extraction dans le cycle de traitement des combustibles irradies est envisagee: soit dans le traitement de purification finale, soit dans les cycles annexes ayant trait a la recuperation de plutonium a partir des scories d'elaboration du metal, des eaux-meres oxaliques et d'une facon generale des solutions aqueuses contenant du plutonium. Des traitements de regeneration du solvant ayant subi des degradations chimique ou radiolytique, sont proposes. (auteurs)

  16. 35 Typologie des eaux de surface du bassin du Sebou par multi ...

    African Journals Online (AJOL)

    PR BOKO

    2Service de protection de la qualité de l'eau, Agence du Bassin Hydraulique du ... pour montrer l'évolution de la qualité biologique des eaux de surface du ..... Biological Indicators of Freshwater Pollution and Environmental Management,.

  17. Régionalisation du recrutement du personnel de santé au Burkina ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Régionalisation du recrutement du personnel de santé au Burkina Faso ... le ministère a adopté une politique de recrutement régionalisé de certaines catégories du ... de comprendre le contexte dans lequel une telle stratégie a été formulée, ...

  18. Catalytic Combustion of Gasified Waste

    Energy Technology Data Exchange (ETDEWEB)

    Kusar, Henrik

    2003-09-01

    This thesis concerns catalytic combustion for gas turbine application using a low heating-value (LHV) gas, derived from gasified waste. The main research in catalytic combustion focuses on methane as fuel, but an increasing interest is directed towards catalytic combustion of LHV fuels. This thesis shows that it is possible to catalytically combust a LHV gas and to oxidize fuel-bound nitrogen (NH{sub 3}) directly into N{sub 2} without forming NO{sub x} The first part of the thesis gives a background to the system. It defines waste, shortly describes gasification and more thoroughly catalytic combustion. The second part of the present thesis, paper I, concerns the development and testing of potential catalysts for catalytic combustion of LHV gases. The objective of this work was to investigate the possibility to use a stable metal oxide instead of noble metals as ignition catalyst and at the same time reduce the formation of NO{sub x} In paper II pilot-scale tests were carried out to prove the potential of catalytic combustion using real gasified waste and to compare with the results obtained in laboratory scale using a synthetic gas simulating gasified waste. In paper III, selective catalytic oxidation for decreasing the NO{sub x} formation from fuel-bound nitrogen was examined using two different approaches: fuel-lean and fuel-rich conditions. Finally, the last part of the thesis deals with deactivation of catalysts. The various deactivation processes which may affect high-temperature catalytic combustion are reviewed in paper IV. In paper V the poisoning effect of low amounts of sulfur was studied; various metal oxides as well as supported palladium and platinum catalysts were used as catalysts for combustion of a synthetic gas. In conclusion, with the results obtained in this thesis it would be possible to compose a working catalytic system for gas turbine application using a LHV gas.

  19. Multi-Dimensional Modeling of the Aerodynamic and Combustion in Diesel Engines Modélisation multidimensionnelle de l'aérodynamique et de la combustion dans les moteurs diesel

    Directory of Open Access Journals (Sweden)

    Delhaye B.

    2006-12-01

    Full Text Available The purpose of this paper is to present an overview of Computational Fluid Dynamics (CFD and combustion simulation applications to automotive power train development, and the methodologies we developed at PSA to integrate numerical simulation into the development process. We illustrate these methodologies with some applications concerning the development of PSA HDI engines. Dans cet article, on présente un panorama des applications de la mécanique des fluides numérique et de la simulation de la combustion pour le développement des groupes motopropulseurs, ainsi que les méthodologies que nous avons conçues au sein du groupe PSA pour intégrer la simulation numérique dans ce processus de développement. Nous illustrons cette démarche par des exemples d'applications issues du développement des moteurs HDI injection directe common rail de PSA.

  20. La disparition du temps en gravitation quantique

    OpenAIRE

    Saint-Ours, Alexis de

    2012-01-01

    Le but de ce travail est d’examiner l’incidence philosophique de la gravitation quantique sur le concept de temps. Je cherche à montrer qu’elle conduit à une disparition du temps comme dimension et ouvre la voie à une compréhension du temps comme variation et même à l’idée de variation pure. En l’absence de temps mécanique, il est cependant possible de définir un temps d’origine thermodynamique. Je montre en quoi cette dissociation du temps mécanique et du temps thermodynamique, fait écho à l...

  1. 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

  2. Producer for vegetal combustibles for internal-combustion motors

    Energy Technology Data Exchange (ETDEWEB)

    1943-12-28

    A producer is described for internal-combustion motors fed with wood or agricultural byproducts characterized by the fact that its full operation is independent of the degree of wetness of the material used.

  3. Reducing emissions from diesel combustion

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This paper contains information dealing with engine design to reduce emissions and improve or maintain fuel economy. Topics include: Observation of High Pressure Fuel Spray with Laser Light Sheet Method; Determination of Engine Cylinder Pressures from Crankshaft Speed Fluctuations; Combustion Similarity for Different Size Diesel Engines: Theoretical Prediction and Experimental Results; Prediction of Diesel Engine Particulate Emission During Transient Cycles; Characteristics and Combustibility of Particulate Matter; Dual-Fuel Diesel Engine Using Butane; Measurement of Flame Temperature Distribution in D.I. Diesel Engine with High Pressure Fuel Injection: and Combustion in a Small DI Diesel Engine at Starting

  4. Magnesium and uranium ignition in different gaseous atmospheres; Inflammabilite du magnesium et de l'uranium dans l'air et le gaz carbonique

    Energy Technology Data Exchange (ETDEWEB)

    Darras, R; Baque, P; Leclercq, D [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Magnesium, uranium and some of their alloys burning temperatures have been systematically determined in an air or carbon dioxide atmosphere, either dry or wet. Two different ways of heating have been used: either continuously rising up the temperature, or heating to and then maintaining a constant temperature. The results are clearly different in the two cases. Besides, if moisture has little effect on the magnesium burning temperatures in air, it does lower them by about 130-140 deg. C in CO{sub 2}. The differences of sight between the burning of magnesium and uranium have been noticed; this leads to distinguish between an 'ignition' and an 'inflammation'. (author) [French] Les temperatures auxquelles apparait la combustion vive du magnesium, de l'uranium et certains de leurs alliages ont ete determinees systematiquement dans l'air et le gaz carbonique, soit secs, soit humidifies. On a mis en evidence l'influence du mode de chauffage sur les resultats: soit montee en temperature continue, soit stabilisation a partir d'une certaine temperature. En outre, si la presence d'humidite affecte peu les temperatures de combustion vive du magnesium dans l'air, elle les abaisse de 130 a 140 deg. C dans le gaz carbonique. Les differences d'aspect entre la combustion vive du magnesium et de l'uranium ont egalement ete remarquees, ce qui amene notamment a distinguer une 'ignition' d'une 'inflammation'. (auteur)

  5. 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

  6. 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

  7. Computational Modeling of Turbulent Spray Combustion

    NARCIS (Netherlands)

    Ma, L.

    2016-01-01

    The objective of the research presented in this thesis is development and validation of predictive models or modeling approaches of liquid fuel combustion (spray combustion) in hot-diluted environments, known as flameless combustion or MILD combustion. The goal is to combine good physical insight,

  8. Measures for a quality combustion (combustion chamber exit and downstream); Mesures pour une combustion de qualite (sortie de chambre de combustion et en aval)

    Energy Technology Data Exchange (ETDEWEB)

    Epinat, G. [APAVE Lyonnaise, 69 (France)

    1996-12-31

    After a review of the different pollutants related to the various types of stationary and mobile combustion processes (stoichiometric, reducing and oxidizing combustion), measures and analyses than may be used to ensure the quality and efficiency of combustion processes are reviewed: opacimeters, UV analyzers, etc. The regulation and control equipment for combustion systems are then listed, according to the generator capacity level

  9. Fuels and Combustion | Transportation Research | NREL

    Science.gov (United States)

    Fuels and Combustion Fuels and Combustion This is the March 2015 issue of the Transportation and , combustion strategy, and engine design hold the potential to maximize vehicle energy efficiency and performance of low-carbon fuels in internal combustion engines with a whole-systems approach to fuel chemistry

  10. Combustion modeling in waste tanks

    International Nuclear Information System (INIS)

    Mueller, C.; Unal, C.; Travis, J.R.; Forschungszentrum Karlsruhe

    1997-01-01

    This paper has two objectives. The first one is to repeat previous simulations of release and combustion of flammable gases in tank SY-101 at the Hanford reservation with the recently developed code GASFLOW-II. The GASFLOW-II results are compared with the results obtained with the HMS/TRAC code and show good agreement, especially for non-combustion cases. For combustion GASFLOW-II predicts a steeper pressure rise than HMS/TRAC. The second objective is to describe a so-called induction parameter model which was developed and implemented into GASFLOW-II and reassess previous calculations of Bureau of Mines experiments for hydrogen-air combustion. The pressure time history improves compared with the one-step model, and the time rate of pressure change is much closer to the experimental data

  11. Environmental sensing and combustion diagnostics

    International Nuclear Information System (INIS)

    Santoleri, J.J.

    1991-01-01

    This book contains proceedings of Environmental Sensing and Combustion Diagnostics. Topics covered include: Incineration Systems Applications, Permitting, And Monitoring Overview; Infrared Techniques Applied to Incineration Systems; Continuous Emission Monitors; Analyzers and Sensors for Process Control And Environmental Monitoring

  12. Sodium nitrate combustion limit tests

    International Nuclear Information System (INIS)

    Beitel, G.A.

    1976-04-01

    Sodium nitrate is a powerful solid oxidant. Energetically, it is capable of exothermically oxidizing almost any organic material. Rate-controlling variables such as temperature, concentration of oxidant, concentration of fuel, thermal conductivity, moisture content, size, and pressure severely limit the possibility of a self-supported exothermic reaction (combustion). The tests reported in this document were conducted on one-gram samples at atmospheric pressure. Below 380 0 C, NaNO 3 was stable and did not support combustion. At moisture concentrations above 22 wt percent, exothermic reactions did not propagate in even the most energetic and reactive compositions. Fresh resin and paraffin were too volatile to enable a NaNO 2 -supported combustion process to propagate. Concentrations of NaNO 3 above 95 wt percent or below 35 wt percent did not react with enough energy release to support combustion. The influence of sample size and confining pressure, both important factors, was not investigated in this study

  13. 75 FR 3881 - Combustible Dust

    Science.gov (United States)

    2010-01-25

    ..., rubber, drugs, dried blood, dyes, certain textiles, and metals (such as aluminum and magnesium..., furniture manufacturing, metal processing, fabricated metal products and machinery manufacturing, pesticide... standard that will comprehensively address the fire and explosion hazards of combustible dust. The Agency...

  14. Modeling of microgravity combustion experiments

    Science.gov (United States)

    Buckmaster, John

    1995-01-01

    This program started in February 1991, and is designed to improve our understanding of basic combustion phenomena by the modeling of various configurations undergoing experimental study by others. Results through 1992 were reported in the second workshop. Work since that time has examined the following topics: Flame-balls; Intrinsic and acoustic instabilities in multiphase mixtures; Radiation effects in premixed combustion; Smouldering, both forward and reverse, as well as two dimensional smoulder.

  15. Quantifying emissions from spontaneous combustion

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-09-01

    Spontaneous combustion can be a significant problem in the coal industry, not only due to the obvious safety hazard and the potential loss of valuable assets, but also with respect to the release of gaseous pollutants, especially CO2, from uncontrolled coal fires. This report reviews methodologies for measuring emissions from spontaneous combustion and discusses methods for quantifying, estimating and accounting for the purpose of preparing emission inventories.

  16. Combustion Modeling with the G-Equation Modélisation de la combustion avec l'équation de G

    Directory of Open Access Journals (Sweden)

    Peters N.

    2006-12-01

    Full Text Available Numerical investigations concerning the turbulent flame front propagation in Gasoline Direct Injection (GDI engines were made by implementing a flamelet model in the CFD code Fire. The advantage of this combustion model is the decoupling of the chemistry from the turbulent flow. For this purpose the combustion chamber has to be divided into a burned and an unburned area, which is realized by transporting a scalar field (G-Equation. The reference value defines the present averaged flame position. The complete reaction kinetics is calculated interactively with the CFD code in a one dimensional Representative Interactive Flamelet (RIF code. This combustion model was verified by simulating a 2. 0 l-2 V gasoline engine with homogeneous combustion where a parameter study was conducted to check the flamelet model for plausibility. Finally, the potential of this combustion model was investigated by simulating a hypothetical 2. 0 1-4 V GDI engine. Une investigation numérique relative à la propagation des fronts de flammes turbulents dans les moteurs à essence à injection directe (GDI a été menée en implantant un modèle de flameletdans le code 3D Fire. L'avantage de ce modèle de combustion est de découpler la chimie de l'écoulement turbulent en divisant la chambre de combustion en deux zones : brûlée et imbrûlée, à l'aide d'une équation de transport d'un scalaire (équation de G. Une valeur de référence de ce scalaire définit la position moyenne de la flamme. Une chimie complète est calculée interactivement avec le calcul 3D à l'aide d'un code monodimensionnel RIF (Representative Interactive Flamelet. Le modèle de combustion a été validé sur la simulation d'un moteur 2 litres à 2 soupapes en combustion homogène pour vérifier la représentativité de l'approche flamelet . Puis, le potentiel du modèle de combustion a été étudié en simulant un moteur modèle 2 litres 4 soupapes GDI.

  17. Combustion means for solid fuels

    Energy Technology Data Exchange (ETDEWEB)

    Murase, D.

    1987-09-23

    A combustion device for solid fuel, suitable for coal, coke, charcoal, coal-dust briquettes etc., comprising:- a base stand with an opening therein, an imperforate heat resistant holding board locatable to close said opening; a combustion chamber standing on the base stand with the holding board forming the base of the combustion chamber; a wiper arm pivoted for horizontal wiping movement over the upper surface of the holding board; an inlet means at a lower edge of said chamber above the base stand, and/or in a surrounding wall of said chamber, whereby combustion air may enter as exhaust gases leave the combustion chamber; an exhaust pipe for the exhaust gases; generally tubular gas-flow heat-exchange ducting putting the combustion chamber and exhaust pipe into communication; and means capable of moving the holding board into and out of the opening for removal of ash or other residue. The invention can be used for a heating system in a house or in a greenhouse or for a boiler.

  18. 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.

  19. 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.

  20. 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: Zeamatin; Chai...eta Sandwich SWS:ZEAM_MAIZE,P33679|EMBL; U06831; AAA92882.1; -.|PIR; T02075; T02075.|PDB; 1DU5; X-ray; A/B=22-227.|Mai

  1. les cahiers du cread: About this journal

    African Journals Online (AJOL)

    les cahiers du cread: About this journal. Journal Home > les cahiers du cread: About this journal. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register · Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives. People. » Contact. Policies.

  2. Les figures multiples du maire.

    Directory of Open Access Journals (Sweden)

    Olivier Lebraud

    2004-06-01

    Full Text Available Alors même que l’ensemble du personnel gouvernemental et parlementaire est sujet à une relative désaffection de la part des citoyens, les maires français jouissent, on le sait, d’une popularité qui fait d’eux les figures centrales de la scène politique. Au-delà de la décentralisation, qui a souvent renforcé leur image de décideurs, ils ont su tirer parti de la dimension identitaire qui caractérise l’échelon communal pour devenir les acteurs indispensables de la vie locale. ...

  3. Vers une anthropologie du Confucianisme

    OpenAIRE

    Rieu , Alain-Marc

    2010-01-01

    Research in Anthropology developed in France by Jean-Pierre Vernant, Marcel Détienne and Philippe Descola opens the possibility to reframe the debate and research on the function of Confucianism in Chinese culture, history and society. This paper shows how Confucianism can be studied as a "mythology"; La fonction du Confucianisme dans l'histoire de la société et de la culture chinoise, les débats et les reconstructions dont il est l'objet et l'enjeu, ouvre la possibilité de l'étudier d'un poi...

  4. Description of computer code PRINS, Program for Interpreting Gamma Spectra, developed at ENEA

    Energy Technology Data Exchange (ETDEWEB)

    Borsari, R. [ENEA, Centro Ricerche `E. Clementel`, Bologna (Italy). Dip. Energia

    1995-11-01

    The computer code PRINS, program for interpreting gamma Spectra, has been developed in collaboration with CENG/SECC (Centre Etude Nucleaire Grenoble / Service Etude Comportement du Combustible). Later it has been updated and improved at ENEA. Properties of the PRINS code are: (1) A powerful algorithm to locate the peaks; (2) An accurate evaluation of the errors; (3) Possibility of an automatic channels-energy calibration.

  5. Description of computer code PRINS, Program for Interpreting Gamma Spectra, developed at ENEA

    International Nuclear Information System (INIS)

    Borsari, R.

    1995-12-01

    The computer code PRINS, PRogram for INterpreting gamma Spectra, has been developed in collaboration with CENG/SECC (Centre Etude Nucleaire Grenoble / Service Etude Comportement du Combustible). Later it has been updated and improved at ENEA. Properties of the PRINS code are: I) A powerful algorithm to locate the peaks; 2) An accurate evaluation of the errors; 3) Possibility of an automatic channels-energy calibration

  6. 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

  7. 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. (