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Sample records for belleville sur loire-2 reactor

  1. Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Belleville-sur-Loire nuclear power plant (INB no. 127 - Belleville 1 and no. 128 - Belleville 2, Belleville-sur-Loire and Sury-pres-Lere - Cher (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  2. Study of the radiological and chemical quality of sediments and water of the Loire river at the vicinity of the Belleville-sur-Loire CNPE. Study performed on the request of the Belleville-sur-Loire Local Information Commission

    International Nuclear Information System (INIS)

    Rougier, G.; Josset, M.; Bernollin, A.; Barbey, P.; Boilley, D.; Festoc, S.; Dunand, E.

    2017-01-01

    This study reports an assessment of the influence of present and previous releases of the Belleville-sur-Loire nuclear site, as well as of the persistence of other pollutions in the environment. The report first recalls authorised annual levels for liquid and gaseous radioactive releases and for chemical releases. It describes the strategy and method adopted to assess the radiological and chemical influence of the nuclear power plant on the environment: studied area, sampling locations and samples, examined radiological and chemical parameters. It indicates the adopted strategy and comments results obtained for radiological measurements in waters, in sediments, and in aquatic plants. Results are notably discussed in terms of natural and artificial radioactivity. Chemical measurements are then reported in the same way: strategy, measurements and discussion of results obtained in water and in sediments. Additional information on radionuclides and on sampling and analysis methodologies are given in appendix

  3. Project of Particular intervention plan of the Belleville-sur-Loire NPP. Special provisions of the ORSEC plan

    International Nuclear Information System (INIS)

    2015-01-01

    The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the project of Particular intervention plan for the Belleville-sur-Loire Nuclear Power Plant (Cher, France)

  4. Expertise on the file of declaration of modifications related to releases and to water samplings of the Belleville-sur-Loire C.N.P.E. Study performed on the request of the Bellevile-sur-Loire Local Information Commission

    International Nuclear Information System (INIS)

    Migeon, A.; Barbey, P.; Guillemette, A.; Josset, M.

    2013-01-01

    After a recall of the regulatory framework regarding the safety of nuclear installations and transport of radioactive substances, this document reports an expertise study of the content of a file (Declaration of modification related to releases and water samplings of the Nuclear Centre of Electricity Production (CNPE) of Belleville-sur-Loire) which is being examined by concerned authorities. It first proposes some information on sources of hazard (others than radiological) such as pathogen agents (legionella, amoebae), dangerous chemical agents (hydrazine, morpholine, ethanol-amine, nitrites and nitrates, and so on). It more particularly analyses, comments, explains and discusses four issues of the request for change: evolution of the chemical conditioning of the primary circuit, implementation of a processing of condenser cooling circuits by massive chlorination under controlled pH, evolution of water sampling and release authorisations, and modification of regulatory texts. For these four issues, notably the first three ones, the authors provide detailed comments and discussion on technical and chemical issues. The fourth part of the report addresses the regulatory monitoring of the environment of the nuclear power plant: monitoring of chemical releases (in the Loire river, in its sediments, fauna and flora), of biological pathogen agents, of tritium in water and in the atmosphere. For these various issues, the authors propose a presentation of the situation, and give some explanations and comments on the measured and available data

  5. Belleville-sur-Loire plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

    International Nuclear Information System (INIS)

    2011-01-01

    This CSA (Complementary Safety Assessment) analyses the robustness of the Belleville-sur-Loire plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

  6. Nuclear safety and radiation protection report of Belleville-Sur-Loire nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  7. Loire Classics: Reviving Classicism in some Loire Poets

    Directory of Open Access Journals (Sweden)

    Wim Verbaal

    2017-06-01

    Full Text Available The term 'Loire poets' has come to refer to a rather undefinable group of poets that in the second half of the eleventh century distinguishes itself through its refined poetics. They are often characterized as medieval humanists thanks to their renewed interest in the classics. Sometimes their movement is labelled a 'classicist' one. But what does this 'classicism' mean? Is it even permitted to speak of medieval 'classicisms'? This contribution approaches the question of whether we can apply this modern label to pre-modern phenomena. Moreover, it explores the changes in attitude towards the classics that sets the Loire poets off from their predecessors and contemporaries. The article focuses on poems by Hildebert of Lavardin, Baudri of Bourgueil, Marbod of Rennes, and Geoffrey of Reims. They are compared with some contemporary poets, such as Reginald of Canterbury and Sigebert of Gembloux.

  8. Stiffness and design for strength of trapezoidal Belleville springs

    DEFF Research Database (Denmark)

    Pedersen, Niels Leergaard; Pedersen, Pauli

    2011-01-01

    in this paper. Finite element results are compared with analytical predictions and critically analysed in terms of the effect of Poisson ratio, overall stiffness, and stress distribution in the spring. This is done in order to verify the range of validity of design standards. Finite element analysis emerges......Belleville springs or coned disc springs are commonly used in machine design. The geometric dimensions of the spring and the determination of non-linear force–displacement curve are regulated by different standards. However, the theory behind Belleville spring design standards is founded on a study...... published in 1936. Furthermore, the common spring design with cross-sections of uniform thickness poses problems in terms of non-uniformity of stress distribution. In view of this, non-linear three-dimensional finite element analyses of spring designs including uniform or variable thickness are carried out...

  9. Experiments with the SUR 100 training reactor

    International Nuclear Information System (INIS)

    Milicic, B.

    1984-06-01

    This paper contains a compilation of various experiments using the SUR - 100 reactor for training purposes, which have been widly proved in practical work at the School for Nuclear Technology of the Karlsruhe Research Center. (orig.) [de

  10. Zinc and Its Isotopes in the Loire River Basin, France

    Science.gov (United States)

    Millot, R.; Desaulty, A. M.; Bourrain, X.

    2014-12-01

    The contribution of human activities such as industries, agriculture and domestic inputs, becomes more and more significant in the chemical composition of the dissolved load of rivers. Human factors act as a supplementary key process. Therefore the mass-balance for the budget of catchments and river basins include anthropogenic disturbances. The Loire River in central France is approximately 1010 km long and drains an area of 117,800 km2. In the upper basin, the bedrock is old plutonic rock overlain by much younger volcanic rocks. The intermediate basin includes three major tributaries flowing into the Loire River from the left bank: the Cher, the Indre and the Vienne rivers; the main stream flows westward and its valley stretches toward the Atlantic Ocean. Here, the Loire River drains the sedimentary series of the Paris Basin, mainly carbonate deposits. The lower Loire basin drains pre-Mesozoic basement of the Armorican Massif and its overlying Mesozoic to Cenozoic sedimentary deposits. The Loire River is one of the main European riverine inputs to the Atlantic ocean. Here we are reporting concentration and isotope data for Zn in river waters and suspended sediments from the Loire River Basin. In addition, we also report concentration and isotope data for the different industrial sources within the Loire Basin, as well as data for biota samples such as mussels and oysters from the Bay of Biscay and North Brittany. These organisms are known to be natural accumulators of metal pollutants. Zinc isotopic compositions are rather homogeneous in river waters with δ66Zn values ranging from 0.21 to 0.39‰. This range of variation is very different from anthropogenic signature (industrial and/or agriculture release) that displays δ66Zn values between 0.02 to 0.14‰. This result is in agreement with a geogenic origin and the low Zn concentrations in the Loire River Basin (from 0.8 to 6 µg/L).

  11. Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  12. Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  13. Redécouverte d’un milliaire romain. La borne de Chaspuzac (Haute-Loire, cité des Vellaves (province d’Aquitaine The rediscovery of a Roman milestone. The stone of Chaspuzac (Haute-Loire, city of the Vellaves (Aquitaine

    Directory of Open Access Journals (Sweden)

    Marion Dacko

    2010-11-01

    Full Text Available Les recherches initiées dans le cadre d’une thèse en archéologie sur les voies romaines en territoire arverne et vellave ont récemment conduit à la redécouverte d’une borne milliaire, perdue dans la réserve du musée Crozatier au Puy-en-Velay (Haute-Loire depuis la fin du xixe s. Le réexamen approfondi de l’inscription permet de réviser les précédentes lectures à la lumière de données nouvelles. Complément pour la série des milliaires de l’empereur Maximin, cette borne constitue un témoin des vastes travaux de réfection entrepris sur la voie “ Bolène ” tout au long du iiie siècle.The research started as part of a thesis on Roman roads in the Arverne and Vellave territory has recently led to the rediscovery of a milestone, lost in the storerooms of the Crozatier museum at Puy-en-Velay (Haute-Loire since the end of the 19th century. A thorough reexamination of the inscription has enabled a revision of previous writings in the light of new information. An addition to the series of milestones of the Emperor Maximinus, this stone is evidence of the great repair works undertaken on the Bolène Way throughout the 3rd century.

  14. Pb-Zn-Cd-Hg multi isotopic characterization of the Loire River Basin, France

    Science.gov (United States)

    Millot, R.; Widory, D.; Innocent, C.; Guerrot, C.; Bourrain, X.; Johnson, T. M.

    2012-12-01

    The contribution of human activities such as industries, agriculture and domestic inputs, becomes more and more significant in the chemical composition (major ions and pollutants such as metals) of the dissolved load of rivers. Furthermore, this influence can also be evidenced in the suspended solid matter known to play an important role in the transport of heavy metals through river systems. Human factors act as a supplementary key process. Therefore the mass-balance for the budget of catchments and river basins include anthropogenic disturbances. The Loire River in central France is approximately 1010 km long and drains an area of 117,800 km2. Initially, the Loire upstream flows in a south to north direction originating in the Massif Central, and continues up to the city of Orléans, 650 km from the source. In the upper basin, the bedrock is old plutonic rock overlain by much younger volcanic rocks. The Loire River then follows a general east to west direction to the Atlantic Ocean. The intermediate basin includes three major tributaries flowing into the Loire River from the left bank: the Cher, the Indre and the Vienne rivers; the main stream flows westward and its valley stretches toward the Atlantic Ocean. Here, the Loire River drains the sedimentary series of the Paris Basin, mainly carbonate deposits. The lower Loire basin drains pre-Mesozoic basement of the Armorican Massif and its overlying Mesozoic to Cenozoic sedimentary deposits. The Loire River is one of the main European riverine inputs to the Atlantic ocean. Here we are reporting concentration and isotope data for heavy metals Zn-Cd-Pb-Hg in river waters and suspended sediments from the Loire River Basin. In addition, we also report concentration and isotope data for these metals for the different industrial sources within the Loire Basin, as well as data for biota samples such as mussels and oysters from the Bay of Biscay and North Brittany. These organisms are known to be natural accumulators of

  15. La fouille du fort Saint-Georges à Chinon (Indre-et-Loire. Premiers résultats The excavation of fort Saint-Georges at Chinon (Indre-et-Loire. First results

    Directory of Open Access Journals (Sweden)

    Bruno Dufaÿ

    2006-05-01

    Full Text Available Cette note présente les premiers résultats des fouilles menées en 2003 et 2004 sur la quasi-totalité du fort Saint-Georges à Chinon (Indre-et-Loire. Celui-ci est l’un des trois éléments de la forteresse médiévale qui domine la ville. La fouille a permis de préciser la fonction du fort, construit dans la deuxième moitié du XIIe s., à l’époque où Chinon est le centre administratif des possessions continentales des Plantagenêt, rois d’Angleterre. Du point de vue militaire, il formait une fortification avancée, protégeant le château principal, selon une structure que Richard Cœur de Lion appliquera au Château Gaillard. À l’intérieur, de vastes bâtiments constituaient des logis, conçus peut-être au départ pour héberger la chancellerie royale.This article presents the first results of the excavations undertaken in 2003 and 2004 over almost all of the Fort Saint-Georges at Chinon (Indre-et-Loire, one of three elements of the medieval fortress which dominates the town. The excavation enabled us to clarify the function of the fort, built in the 2nd half of the 12th century at a time when Chinon was the administrative centre of the continental possesions of the Plantagenet King of England. From a military point of view, it formed an advanced fortification protecting the main castle, within a structure that Richard the Lionheart would apply to the Chayeau Gaillard. Inside, some vast buildings made up the dwellings, designed perhaps initially to house the royal chanceller.

  16. La nécropole gauloise de “ Vaugrignon ” à Esvres-sur-Indre (Indre-et-Loire The gaulish burial ground of “ Vaugrignon ” at Esvres-sur-Indre (Indre-et-Loire

    Directory of Open Access Journals (Sweden)

    Sandrine Riquier

    2006-05-01

    Full Text Available Situé à 15 km au sud de Tours, au cœur de l’Indre-et-Loire, le village d’Esvres-sur-Indre est implanté sur le versant nord et le rebord d’un plateau qui domine la vallée de l’Indre. Suite à un projet de lotissement, au lieu-dit “ Vaugrignon ”, un diagnostic archéologique, réalisé en octobre 1998 sous la direction d’O. Ranger, a mis au jour deux inhumations de la fin de l’époque gauloise, dont l’une accompagnée d’une amphore complète (Ranger 1998. La fouille qui a suivi, en été 1999 a confirmé qu’elles étaient intégrées à un ensemble funéraire, composé d’au moins une trentaine de tombes, dont trois avec amphore et arme, datées du milieu du IIe s. av. J.-C. à l’époque augustéenne. Cette nécropole constitue le premier ensemble funéraire connu et étudié à ce jour en territoire turon, situé à la marge occidentale du secteur biturige et de ses tombes aristocratiques (Ferdière, Villard 1993.Utilisée du milieu du IIe s. av. J.-C. à l’époque augustéenne, cette nécropole se compose de 29 tombes, dont une incinération. Elle permet de suivre l’évolution des pratiques funéraires (des tombes les plus modestes à celles pourvues d’amphore et d’arme et d’aborder le statut des enfants. L’analyse des objets met en évidence des dépôts originaux, comme ces trois fibules dans des sacs, les fragments de boucliers dans des tombes de bébés, de menus objets en référence à la métallurgie du fer, des monnaies et des “ services funéraires ” spécifiques à l’âge des défunts. Des épandages de mobilier calciné illustrent des pratiques funéraires post-inhumatoires. La mise en perspective de ces tombes par rapport aux prestigieuses sépultures bituriges (groupe de Fléré-la-Rivière, situées à proximité, est l’occasion d’établir une hiérarchisation sociale à travers les assemblages de mobilier et d’illustrer une partie jusque-là méconnue de la population

  17. A Belleville-spring-based electromagnetic energy harvester

    International Nuclear Information System (INIS)

    Castagnetti, Davide

    2015-01-01

    Energy harvesting from kinetic ambient energy is particularly effective to power autonomous sensors. This work proposes an innovative energy converter based on two counteracting Belleville springs and exploiting their peculiarity, for a height to thickness ratio equal to 1.414, of nearly zero stiffness over a wide deflection range. After analytical and numerical modelling a prototype is developed and experimentally investigated. The sub-optimal geometry of the commercial springs used in the prototype, together with a non-ideal response, makes the operating frequency for the prototype higher than in analytical and numerical predictions. Nevertheless, the harvester exhibits a significantly large bandwidth, together with a high output power, compared to similar solutions in the literature, for all the examined configurations and input excitations. (paper)

  18. Natural radioactivity of Loire river sediments: relations with the lithology

    International Nuclear Information System (INIS)

    Patryl, L.

    2000-01-01

    This study has been carried out on request of the Loire-Bretagne water agency by the Laboratory of geology of Tours univ. (EA2100 GeEAC) in collaboration with CEA-Le Ripault. The main objective was the study of the nature and distribution of natural radioactivity in the Loire river alluvial deposits, its origin in the rocks of the surrounding basins and its links with the alluvial petrography. The radioactive flux linked with the sediments of the bottom of the river has been also determined. The Loire river and its main affluents have been the object of radiological and petrographic analyses (grain size, sands and clays mineralogy, organic matter content). The average radioactivities of 40 K, 238 U and 228 Ac in the alluvial deposits are 934.3 ± 164.7 Bq.kg -1 , 50.6 ± 30.8 Bq.kg -1 and 28.8 ± 18.1 Bq.kg -1 , respectively. The average radioactivity of 238 U, 228 Ac and their daughter products is statistically higher in Loire superieure (Massif Central mounts) than in Loire moyenne (Paris basin). The activities of 238 U and 228 Ac are mainly influenced by the grain size of the alluvial deposits and by the mineralogical composition of the sand fraction. The alluvial deposits are mainly sandy and the coarse fraction is the most abundant. The primary radioactivity is carried by the few zircons of the sediments. The activity of the uranium and thorium families increase with the feldspars content. The fixation of radioactivity seems to be linked with the presence of clay minerals inside the weathered feldspar grains which are abundant in the sands. The radioactivity of the Loire river alluvial deposits shows no important changes with respect to the substratums because of a smoothing due to the predominance of longitudinal fluxes with respect to the lateral ones. The impact of an old uranium mine on the alluvial deposits of the Besbre river is detectable along about a tenth of km s downstream only. Because of the strong variations of radioactivity with granularity, a

  19. Use of small reactors as an alternative to supply electricity to Baja California Sur; Uso de reactores pequenos como alternativa de suministro de electricidad para Baja California Sur

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, G.; Portes, E.; Ramirez, J. R. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Ortega, G., E-mail: gustavo.alonso@inin.gob.mx [Comision Federal de Electricidad, Rio Rodano No. 14, 06500 Ciudad de Mexico (Mexico)

    2016-09-15

    The state of Baja California Sur (Mexico) does not form part of the national interconnected electrical system of the country, reason why is local its electrical power supply; one of the alternatives to cover future demands is the use of gas-based combined cycles, which presents the additional problem of including a high price for gas transportation in its costs. In order to reduce total costs, including investment, fuels and operation and maintenance in the operation of the Baja California Sur state electricity system in the coming years, mainly due to the estimated natural gas cost order of $11.50 dollars per million BTU, a proposal is presented to reduce the costs of the electrical system by replacing the necessary combined cycles with the new Small Modular Reactor type nuclear reactors, this alternative is economically competitive. (Author)

  20. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Migaud, D.; Hutin, J.P.; Jouette, I.; Eymond, P.; Devie, P.; Cudelou, C.; Magnier, S.; Frydman, M.

    2016-01-01

    This document gathers different articles concerning the maintenance of the French nuclear power plants. The first article analyses the impact of the recent law on the energetic transition that sets the share of nuclear power at 50% of the electricity produced by 2025. A consequence may be the decommissioning of 17 to 20 reactors by 2025 and the huge maintenance program called 'Grand Carenage' whose aim is to extend operating life over 40 years will have to be re-considered in order to avoid useless expenses. The second article shows that in 2015 the French nuclear reactor fleet got very good results in terms of availability and safety. There were 49 scheduled outages and among them some ended ahead of time. The third article describes the specificities of the maintenance of a nuclear power plant, for instance the redundancy of some systems implies that maintenance has to deal with systems that have never functioned but must be ready to operate at any moment. Another specificity is the complexity of a nuclear power plant that implies an essential phase of preparation for maintenance operations. Because of safety requirements any maintenance operation has to be controlled, checked and may provide feedback. The fourth article presents the 'Grand Carenage' maintenance program that involves the following operations: the replacement of steam generators, the re-tubing of condensers, the replacement of the filtering drums used for cooling water, the testing of the reactor building, the hydraulic test of the primary circuit and the inspection of the reactor vessel. The fifth article focuses on the organization of the work-site for maintenance operations and the example of the Belleville-sur-Loire is described in the sixth article. Important maintenance operations like 'Grand Carenage' requires a strong collaboration with a network of specialized enterprises and as no reactor (except Flamanville EPR) is being built in France, maintenance

  1. Use of small reactors as an alternative to supply electricity to Baja California Sur

    International Nuclear Information System (INIS)

    Alonso, G.; Portes, E.; Ramirez, J. R.; Ortega, G.

    2016-09-01

    The state of Baja California Sur (Mexico) does not form part of the national interconnected electrical system of the country, reason why is local its electrical power supply; one of the alternatives to cover future demands is the use of gas-based combined cycles, which presents the additional problem of including a high price for gas transportation in its costs. In order to reduce total costs, including investment, fuels and operation and maintenance in the operation of the Baja California Sur state electricity system in the coming years, mainly due to the estimated natural gas cost order of $11.50 dollars per million BTU, a proposal is presented to reduce the costs of the electrical system by replacing the necessary combined cycles with the new Small Modular Reactor type nuclear reactors, this alternative is economically competitive. (Author)

  2. Assessing the contribution of the main aquifer of Loire basin to the river discharge during low flow

    International Nuclear Information System (INIS)

    Monteil, C.

    2011-01-01

    The evolution of the Loire river low flows is a key issue for various uses such as water supply, irrigation or industrial needs. Power production is a major activity in the Loire basin with four nuclear power plants using the river water for the cooling system. To estimate the evolution of long term in-stream low flow distribution, it is necessary to have a good estimate of the contribution of a complex aquifer system to the river discharge. Three main overlaying aquifer units covering an area of 38000 km 2 are considered: Beauce Limestones (Oligocene), Chalks (Seno-Turonian) and Sands (Cenomanian). A distributed hydrogeological model (Eau-Dyssee) is implemented with the coupling of five modules: surface water budget, watershed routing, river routing, unsaturated zone transfer, and groundwater flow. The model is calibrated over a 10-yr period, validated over another 10-yr period, and then a test simulation is run over 35 years. A hybrid fitting methodology, based on an automated inverse method and a trial-error one, has been developed for the fitting of the Beauce aquifer unit. The other units are calibrated by trial and error. The fitted model simulates properly both discharges and piezometric heads over the whole domain, with a global RMSE between simulated and observed piezometric heads of 2.86 m, and all Nash efficiency at the Loire discharge gauging stations over 0.9. The fitted model has then been used to quantify the hydro-system mass balance at different time scales. Mean aquifer contribution to Loire river discharge during low flow between 1975 and 2008 is estimated at 15 m 3 /s. First results of simulations under four different climate change projections indicate an averaged decrease of these contributions reaching 8 to 50% in 2100. (author)

  3. Physical measurements in Marcoule reactors (1962); Mesures physiques sur les reacteurs de Marcoule (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    A brief description of the physical measurements in Marcoule reactors is given here. During commissioning and subsequent years of operation, various experiments ha been carried out to check design data, and improve the operating conditions and also test theoretical models for kinetic studies. (author) [French] On presente une rapide description des mesures physiques effectuees sur les reacteurs de Marcoule. Au cours du demarrage et pendant les premieres annees de fonctionnement de G-2 - G-3, de nombreuses experiences ont ete effectuees pour verifier les donnees du projet, ameliorer les conditions de fonctionnement et eprouver des modeles theoriques de calculs de cinetique. (auteur)

  4. Natural uranium-graphite system. Critial experiments on the G1 reactor; Systeme uranium naturel-graphite. Experiences critiques sur le reacteur G1

    Energy Technology Data Exchange (ETDEWEB)

    Schmitt, A P; Tanguy, P; Teste du Bailler, A; Zaleski, C P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    A number of experiments have been performed during the start up period of the G1 (1956) and G2 (1958) reactors in Marcoule, both on their lattices and on different lattices (hollow rods, clusters, under moderated lattices). The first chapter gives a thorough description of the two reactors. The second chapter deals with buckling measurements, both absolute (flux plots) and relative by the method of progressive substitution. The experimental results are summarised in Table VI. The third chapter contains a number of other measurements performed on G1. (author)Fren. [French] Le demarrage des reacteurs G1 (1956) et G2 (1958) de Marcoule nous a permis d'effectuer une serie d'experiences tant sur les reseaux de ces piles que sur des reseaux differents (elements tubulaires ou divises, reseaux sous-moderes, etc...). Dans une premiere partie, nous donnons une description detaillee des deux reacteurs. Dans la deuxieme partie, relative aux mesures de laplaciens, nous decrivons d'abord les mesures absolues de laplaciens (cartes de flux), puis les mesures relatives effectuees par la methode originale de remplacement progressif. Les resultats experimentaux sont rassembles dans le tableau VI. Dans la troisieme partie, nous rappelons un certain nombre d'autres mesures effectuees sur G1. (auteur)

  5. Les prairies de l’estuaire de la Loire : étude de la dynamique de la végétation de 1982 à 2014

    Directory of Open Access Journals (Sweden)

    Mathieu Le Dez

    2017-01-01

    Full Text Available L’analyse diachronique de cartes de végétation est réalisée pour caractériser les dynamiques de la végétation de l’estuaire de la Loire à différentes échelles spatiales et temporelles. Le modèle des matrices de transition est utilisé pour décrire quantitativement les dynamiques observées. Les analyses révèlent notamment la régression des prairies, le développement des roselières et des boisements ainsi que la progression des végétations halophiles. Ces résultats sont mis en relation avec l’évolution des usages sur ce territoire et les modifications du fonctionnement hydro-sédimentaire de l’estuaire.

  6. The Creys Malville FBR Super Phenix steam generators

    International Nuclear Information System (INIS)

    Baque, P.; Zuber, T.; Saur, J.M.; Cambillard, E.

    1980-08-01

    After briefly recalling the French experience on sodium steam generators, the authors describe the design concepts of the Superphenix units and give their main characteristics. A short summary of the realized R and D program precedes the description of the four 750-MWt steam generators, the fabrication of which is in progress by Creusot-Loire at Chalon sur Saone (France). The studies started for the next French fast breeder reactors and their steam generators are mentioned

  7. Some particular aspects of control in nuclear power reactors; Conception de la surete en france et influence des imperatifs de surete sur la conception des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Vathaire, F de; Vernier, Ph; Pascouet, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    This paper reviews the experience acquired in France on the question, of reactor safety. Since a special paper is being presented on reactors of the graphite gas type, the safety of the other types studied in France is discussed here: - heavy water-gas reactors, - fast neutron reactors, - water research reactors of the swimming-pool and tank types. The safety rules peculiar to the different types are explained, with emphasis on their influence on the reactor designs and on the power limits they impose. The corresponding safety studies are presented, particular stress being placed on the original work developed in these fields. Special mention is made of the experimental systems constructed for these studies: the reactor CABRI, pile loop for depressurization tests, loops outside the pile, mock-ups etc. (authors) [French] La presente communication propose une synthese de l'experience acquise en France en matiere de surete des reacteurs. Les reacteurs de la filiere graphite-gaz faisant l'objet d'une communication particuliere, on examine ici la surete des autres types de reacteurs etudies en France: - reacteurs eau lourde-gaz, - reacteurs a neutrons rapides, - reacteurs de recherche a eau des types piscines et tank. Les imperatifs de surete propres aux differentes filieres sont developpes, en mettant l'accent sur leur influence sur la conception des reacteurs et sur les limitations de puissance qu'ils entrainent. Les etudes de surete correspondantes sont presentees, en insistant plus particulierement sur les travaux originaux developpes dans ces domaines. On indique notamment les moyens d'essais qui ont ete construits pour ces etudes: le reacteur CABRI, boucle en pile pour essais de depressurisation, boucles hors pile, maquettes, etc. (auteurs)

  8. Kir6.2 activation by sulfonylurea receptors: a different mechanism of action for SUR1 and SUR2A subunits via the same residues

    Science.gov (United States)

    Principalli, Maria A; Dupuis, Julien P; Moreau, Christophe J; Vivaudou, Michel; Revilloud, Jean

    2015-01-01

    ATP-sensitive potassium channels (K-ATP channels) play a key role in adjusting the membrane potential to the metabolic state of cells. They result from the unique combination of two proteins: the sulfonylurea receptor (SUR), an ATP-binding cassette (ABC) protein, and the inward rectifier K+ channel Kir6.2. Both subunits associate to form a heterooctamer (4 SUR/4 Kir6.2). SUR modulates channel gating in response to the binding of nucleotides or drugs and Kir6.2 conducts potassium ions. The activity of K-ATP channels varies with their localization. In pancreatic β-cells, SUR1/Kir6.2 channels are partly active at rest while in cardiomyocytes SUR2A/Kir6.2 channels are mostly closed. This divergence of function could be related to differences in the interaction of SUR1 and SUR2A with Kir6.2. Three residues (E1305, I1310, L1313) located in the linker region between transmembrane domain 2 and nucleotide-binding domain 2 of SUR2A were previously found to be involved in the activation pathway linking binding of openers onto SUR2A and channel opening. To determine the role of the equivalent residues in the SUR1 isoform, we designed chimeras between SUR1 and the ABC transporter multidrug resistance-associated protein 1 (MRP1), and used patch clamp recordings on Xenopus oocytes to assess the functionality of SUR1/MRP1 chimeric K-ATP channels. Our results reveal that the same residues in SUR1 and SUR2A are involved in the functional association with Kir6.2, but they display unexpected side-chain specificities which could account for the contrasted properties of pancreatic and cardiac K-ATP channels. PMID:26416970

  9. River Loire levees hazard studies – CARDigues’ model principles and utilization examples on Blois levees

    Directory of Open Access Journals (Sweden)

    Durand Eduard

    2016-01-01

    Full Text Available Along the river Loire, in order to have a homogenous method to do specific risk assessment studies, a new model named CARDigues (for Levee Breach Hazard Calculation was developed in a partnership with DREAL Centre-Val de Loire (owner of levees, Cerema and Irstea. This model enables to approach the probability of failure on every levee sections and to integrate and cross different “stability” parameters such topography and included structures, geology and material geotechnical characteristics, hydraulic loads… and observations of visual inspections or instrumentation results considered as disorders (seepage, burrowing animals, vegetation, pipes, etc.. This model and integrated tool CARDigues enables to check for each levee section, the probability of appearance and rupture of five breaching scenarios initiated by: overflowing, internal erosion, slope instability, external erosion and uplift. It has been recently updated and has been applied on several levee systems by different contractors. The article presents the CARDigues model principles and its recent developments (version V28.00 with examples on river Loire and how it is currently used for a relevant and global levee system diagnosis and assessment. Levee reinforcement or improvement management is also a perspective of applications for this model CARDigues.

  10. Common floor system vertical earthquake-proof structure for reactor equipment

    International Nuclear Information System (INIS)

    Morishita, Masaki.

    1996-01-01

    In an LMFBR type reactor, a reactor container, a recycling pump and a heat exchanger are disposed on a common floor. Vertical earthquake-proof devices which can be stretched only in vertical direction formed by laminating large-sized bellevilles are disposed on a concrete wall at the circumference of each of reactor equipments. A common floor is placed on all of the vertical earthquake-proof devices to support the entire earthquake-proof structure simultaneously. If each of reactor equipments is loaded on the common floor and the common floor is entirely supported against earthquakes altogether, since the movement of each of the reactor equipments loaded on the common floor is identical, relative dislocation is not exerted on the main pipelines which connect the equipments. In addition, since the entire earthquake structure has a flat common floor and each of the reactor equipments is suspended to minimize the distance between a gravitational center and a support point, locking vibration is less caused to the horizontal earthquake. (N.H.)

  11. Tiempo de Dios. Tiempo de los Hombres: El Breviario de Belleville

    Directory of Open Access Journals (Sweden)

    Ofelia Manzi

    2012-11-01

    Full Text Available Las imágenes cristianas, herederas de los sistemas narrativos romanos, expresaron visualmente los contenidos escriturarios. Uno de los elementos notables lo constituye la manera de representar la secuencia temporal en sus dos posibles dimensiones: humana y divina. Un recorrido por el arte cristiano tardo antiguo y medieval permite establecer de qué manera se generó una iconografía que permitió visualizar el mensaje que, de acuerdo con la correspondiente exégesis literaria, se quiso privilegiar en momentos históricos diversos. El objetivo de este trabajo es establecer de qué manera la imagen acompaña una concepción del tiempo en su doble dimensión. El Breviario de Belleville (París, siglo XIV ofrece un ejemplo en el que se conjugan ambas concepciones del transcurrir de la vida del hombre en una particular interpretación iconográfica.  

  12. High resolution modelling of the biogeochemical processes in the eutrophic Loire River (France)

    Science.gov (United States)

    Minaudo, Camille; Moatar, Florentina; Curie, Florence; Gassama, Nathalie; Billen, Gilles

    2016-04-01

    A biogeochemical model was developed, coupling a physically based water temperature model (T-NET) with a semi-mechanistic biogeochemical model (RIVE, used in ProSe and Riverstrahler models) in order to assess at a fine temporal and spatial resolution the biogeochemical processes in the eutrophic Middle Loire hydrosystem (≈10 000 km², 3361 river segments). The code itself allows parallelized computing, which decreased greatly the calculation time (5 hours for simulating 3 years hourly). We conducted a daily survey during the period 2012-2014 at 2 sampling stations located in the Middle Loire of nutrients, chlorophyll pigments, phytoplankton and physic-chemical variables. This database was used as both input data (upstream Loire boundary) and validation data of the model (basin outlet). Diffuse and non-point sources were assessed based on a land cover analysis and WWTP datasets. The results appeared very sensible to the coefficients governing the dynamic of suspended solids and of phosphorus (sorption/desorption processes) within the model and some parameters needed to be estimated numerically. Both the Lagrangian point of view and fluxes budgets at the seasonal and event-based scale evidenced the biogeochemical functioning of the Loire River. Low discharge levels set up favorable physical conditions for phytoplankton growth (long water travel time, limited water depth, suspended particles sedimentation). Conversely, higher discharge levels highly limited the phytoplankton biomass (dilution of the colony, washing-out, limited travel time, remobilization of suspended sediments increasing turbidity), and most biogeochemical species were basically transferred downstream. When hydrological conditions remained favorable for phytoplankton development, P-availability was the critical factor. However, the model evidenced that most of the P in summer was recycled within the water body: on one hand it was assimilated by the algae biomass, and on the other hand it was

  13. Metal Chemical and Isotope Characterisation in the Upper Loire River Basin, France

    Science.gov (United States)

    Widory, D.; Nigris, R.; Morard, A.; Gassama, N.; Poirier, A.; Bourrain, X.

    2016-12-01

    The Water Framework Directive (WFD) elaborated by the European Commission regulates water resources in the EC based on five years management plans. A new management plan that started in 2016 imposes strict water quality criteria to its member states, including good status thresholds for metallic contaminants. The Loire River, the most important river in France, flows through areas with lithologies naturally containing high metal concentrations in the upper part of its basin. Understanding these metal fluxes into the river is thus a prerequisite to understand their potential impact on the quality of its water in regards to the criteria defined by the WFD. The Massif Central, a residue of the Hercynian chain, is composed of granitic and volcanic rocks. Both its upstream position in the Loire basin and its numerous metal mineralizations made this region a good candidate for characterizing the natural metal geochemical background of its surface waters. To fulfill this objective we focused on the Pb, Cd and Zn chemical and isotope characteristics of selected non-anthropized small watersheds. The investigated small watersheds were selected for supposedly draining a single lithology and undergoing (as far as possible) negligible to no anthropogenic pressure. Results showed that although the high metal potential of the upper part of the Loire River basin has been highly exploited by humans for centuries, metal concentrations during the hydrological cycle are still under the guidelines defined by the WFD. Isotope compositions/ratios are strongly related to the corresponding lithologies along the rivers and help precisely define the local geochemical background that can then be used to identify and quantify any anthropogenic inputs downstream.

  14. Spatial distribution of trace elements in the surface sediments of a major European estuary (Loire Estuary, France): Source identification and evaluation of anthropogenic contribution

    Science.gov (United States)

    Coynel, Alexandra; Gorse, Laureline; Curti, Cécile; Schafer, Jörg; Grosbois, Cécile; Morelli, Guia; Ducassou, Emmanuelle; Blanc, Gérard; Maillet, Grégoire M.; Mojtahid, Meryem

    2016-12-01

    Assessing the extent of metal contamination in estuarine surface sediments is hampered by the high heterogeneity of sediment characteristics, the spatial variability of trace element sources, sedimentary dynamics and geochemical processes in addition to the need of accurate reference values for deciphering natural to anthropogenic contribution. Based on 285 surface sediment samples from the Loire Estuary, the first high-resolution spatial distributions are presented for grain-size, particulate organic carbon (POC) and the eight metals/metalloids identified as priority contaminants (Cd, Zn, Pb, Cu, As, Cr, Ni, Hg) plus Ag (an urban tracer). Grain-size and/or POC are major factors controlling the spatial distribution of trace element concentrations. The V-normalized trace metal concentrations divided by the V-normalized concentrations in the basin geochemical background showed the highest Enrichment Factors for Ag and Hg (EF; up to 34 and 140, respectively). These results suggest a severe contamination in the Loire Estuary for both elements. Intra-estuarine Ag and Hg anomalies were identified by comparison between respective normalized concentrations in the Loire Estuary surface sediments and those measured in the surface sediments at the outlet of the Loire River System (watershed-derived). Anthropogenic intra-estuarine Ag and Hg stocks in the uppermost centimetre of the sediment compared with rough annual fluvial flux estimates suggest that the overall strong Enrichment Factors for Ag (EFAg) and and Hg (EFHg) in the Loire Estuary sediments are mainly due to watershed-derived inputs, highlighting the need of high temporal hydro-geochemical monitoring to establish reliable incoming fluxes. Significant correlations obtained between EFCd and EFAg, EFCu and POC and EFHg and POC revealed common behavior and/or sources. Comparison of trace element concentrations with ecotoxicological indices (Sediment Quality Guidelines) provides first standardized information on the

  15. Radioactivity monitoring within the environment of the Loire basin. A partnership between the IRSN and the Dampierre-en-Burly and Saint-Laurent CLIs at the service of citizen vigilance

    International Nuclear Information System (INIS)

    2008-01-01

    The first part of this report presents the Loire basin and its environment, discusses the physical-chemical quality control of its waters and the main usages of the Loire waters. It also presents the nuclear installations present in the Loire basin (electricity production nuclear power stations and other installations), the actors involved in radioactivity measurement in the Loire basin environment (IRSN, EDF, AREVA, associations for the monitoring of water quality, public services), and the national network for radioactivity measurement in the environment. The second part describes and reports the radioactivity monitoring of the environment in the Loire basin, i.e. in the atmosphere, in rain waters and in continental waters, and in the food chain. Addressing this monitoring activity, a last part discusses the evolution of measurements, the importance of the plurality of actors involved in sampling and measurement (in order to guarantee the monitoring system transparency), the variety of sources, the assessment of health impact

  16. [Fetal and neonatal mortality from 22 weeks of amenorrhea in the Loire area].

    Science.gov (United States)

    Branger, B; Beringue, F; Nomballais, M F; Bouderlique, C; Brossier, J P; Savagner, C; Seguin, G; Boog, G; Rozé, J C

    1999-07-01

    The Pays de Loire has a low perinatal mortality indicators among French regions but this could be due to under-notification. To explore this hypothesis we undertook a survey in order to identify all fetal and neonatal deaths occurring at a gestionnal age of 22 weeks or more. We also tried to examine and analyze the causes of death. All maternity (26) and neonatal wards (5) in the region took part in the survey in 1995. Clinicians were asked to fill out a questionnaire for all deaths occurring from gestational age (GA) 22 weeks and/or concerning a birthweight of a least 500 g. Only perinatal deaths related to parents living in the Pays de Loire were included in the study. Two hundred and sixty seven perinatal deaths were identified out of a total 29,440 births (9.1 /1000). Eighty three (2.8 /1000) were termination of pregnancy for medical reasons, of which 82% were motivated by chromosomic illness. Ninety-nine stillbirths fell (3.4 /1000) into two GA periods: 24 to 27 weeks (20%) and 38 to 41 weeks (2%). The cause of stillbirths remained unknown in 50% of cases despite a post-mortem examination rate of 87%. There were 29 deaths (1 /1000) in the immediate per and post-partum, 40% of which occurred at GA 22 to 25 weeks. Another 38% occurred at GA 36 to 40 weeks and these were related to undectected malformations or infections. Neonatal and intensive care units reported 56 neonatal deaths (1.9 /1000). GA was under 33 weeks for 44% of them. Deaths were caused by usual complications of severe prematurity, neurologic diseases and malformations. Thirty-two percent of total deaths were not notified to the French Authority: 25% of deaths for termination of pregnancy for medical reasons and 7% for stillbirths and per and post partum deaths. This survey suggests that the Pays de Loire perinatal mortality indicators remained low compared with other French regions, even after adjustment for this under notification. This casts doubts on the validity of perinatal mortality

  17. Radioactivity monitoring within the environment of the Loire basin. A partnership between the IRSN and the Dampierre-en-Burly and Saint-Laurent CLIs at the service of citizen vigilance; Surveillance de la radioactivite dans l'environnement du bassin de la Loire. Un partenariat entre l'IRSN et les CLI de Dampierre-en-Burly et de Saint-Laurent-des-Eaux au service de la vigilance citoyenne

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The first part of this report presents the Loire basin and its environment, discusses the physical-chemical quality control of its waters and the main usages of the Loire waters. It also presents the nuclear installations present in the Loire basin (electricity production nuclear power stations and other installations), the actors involved in radioactivity measurement in the Loire basin environment (IRSN, EDF, AREVA, associations for the monitoring of water quality, public services), and the national network for radioactivity measurement in the environment. The second part describes and reports the radioactivity monitoring of the environment in the Loire basin, i.e. in the atmosphere, in rain waters and in continental waters, and in the food chain. Addressing this monitoring activity, a last part discusses the evolution of measurements, the importance of the plurality of actors involved in sampling and measurement (in order to guarantee the monitoring system transparency), the variety of sources, the assessment of health impact

  18. The radioactivity measurement in the Loire catchment basin. Actors, networks, data inventory

    International Nuclear Information System (INIS)

    2008-01-01

    The objective of this report on the Loire watershed was to broaden at all the nuclear installations of the watershed the method of synthesis made for Saint-Laurent-des-Eaux nuclear power plant, by resting on the whole of actors doing the radioactivity measurements in environment. This report shows that these actors are numerous. The measurement plans implemented have for objective to establish the radiological situation of environment, near or not the nuclear facilities, to detect the abnormal increase of radioactivity, to evaluate the exposure of populations to the ambient radioactivity, or to check the conformity of practices (nuclear activities) and products. This assessment enlightens the lack of a real global strategy in the organisation of the radioactivity measurement at the level of the watershed. The inventory of available data for the Loire watershed allowed to show the diversity of measurements realised. The I.R.S.N. is face to a complex situation of data return in the frame of the implementation of an information system of the national network of radioactivity measurement in environment. (N.C.)

  19. Static seals and their application in water-cooled nuclear reactor systems

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    Information relative to six types of static seals commonly used in the primary cooling systems of nuclear reactors is compiled. This information includes a description of each type of seal, its material of construction, design features, operating experience, and advantages and disadvantages. The types covered include spiral-wound asbestos-filled gaskets, hollow metallic O-rings, Belleville spring type of gasketed joints, integrated elastomer and metal retainer gaskets, and solid metal gaskets with heavy cross sections. Omega, canopy, and lip seals are discussed briefly, and information on flange design for gasketing is also presented

  20. The impact of trauma on the psyche of the individual using the film Belleville Rendez-vous as an illustrative vehicle.

    Science.gov (United States)

    Waldron, Sharn

    2008-09-01

    Using the film Belleville Rendez-vous as a vehicle for discussion, this paper argues that whilst a traumatic complex may bring about dissociation of the psyche, this is not the only possibility, nor is dissociation necessarily to be seen solely as a difficulty to be overcome. If trauma is experienced within the context of support and validation, the experience of trauma may generate integration not only of the trauma but also of the growth potential that the trauma has previously inhibited.

  1. Un établissement du début du premier âge du Fer en Eure-et-Loir : Sours, Les Ouches A settlement from the first Iron Age in Eure-et-Loir: Sours, Les Ouches

    Directory of Open Access Journals (Sweden)

    Frédéric Dupont

    2012-01-01

    Full Text Available La fouille du site des Ouches à Sours (28 a permis la mise au jour d’une importante occupation du Néolithique ancien et la découverte, dans la partie nord de l’emprise, de plusieurs structures datables du début de l’âge du Fer (Hallstatt C. Elles correspondent à des structures domestiques (un bâtiment et des fosses et à une entité “ cultuelle ”: un double enclos en “ U ”.L’habitation et ses annexes sont représentées par un bâtiment de plan quadrangulaire sur poteaux et une grande fosse riche en mobilier (céramiques, ossements et silex taillés. Cette structure peut être associée au fonctionnement d’un four de type “ polynésien ” et avoir servi de fosse de rejet.Le double enclos, ouvert vers le nord, est localisé au nord-est du site.Même si trois céramiques entières ont été trouvées dans son fossé externe, l’essentiel du mobilier céramique (177 individus sur 192 est issu de la grande fosse. Il s’agit principalement de coupes, de jattes parfois incisées, de petits gobelets à panse globulaire typiques du Hallstatt C ou de vases servant au stockage. Ils sont dotés de manière régulière de cordons digités.Ce petit établissement du début de l’âge du Fer a livré un bon échantillon des céramiques en usage en Eure-et-Loir à cette époque ainsi que des vestiges archéozoologiques et lithiques en quantité intéressante. Ces découvertes donnent de nouvelles informations sur les affinités culturelles à la transition entre l’âge du Bronze et l’âge du Fer, période peu documentée dans le Nord de la région Centre.The excavation of the site of Ouches at Sours (28 has enabled the updating of an important settlement from the early Neolithic and the discovery, in the northern part of the site, of several structures datable to the beginning of the Iron Age (Hallstatt C. They correspond to domestic structures (a building and some ditches and a “worship” entity: a double

  2. Vg mRNA induction in an endangered fish species (Anguilla anguilla) from the Loire estuary (France).

    Science.gov (United States)

    Blanchet-Letrouvé, Isabelle; Lafont, Anne-Gaëlle; Poirier, Laurence; Baloche, Sylvie; Zalouk-Vergnoux, Aurore; Dufour, Sylvie; Mouneyrac, Catherine

    2013-11-01

    Estuarine zones are extremely fragile due to increasing stress from anthropogenic activities. Among those, the Loire estuary (France) is potentially exposed to various contaminants including Endocrine Disruptors Compounds (EDCs) able to impact the reproduction physiology of fish. The European eel (Anguilla anguilla), endangered fish species, is apparently not relevant, in its yellow stage, to monitor the effects of endocrine disruption. Despite this weakly responsiveness, this study aimed to investigate whether European eel from the Loire estuary may still be the subject of estrogenic disruption quantifying the hepatic Vg gene expression according to gender and sexual stage. Vitellogenin (Vg) appears as a valuable biomarker of EDCs, as well as for exposure and effects. Quantitative real-time Reverse Transcription Polymerase Chain Reaction (q RT PCR) was used in this study to amplify responses of hepatic Vg transcripts. European eels were sampled in May 2009 (N=57) and November 2010 (during the downstream migration, N=10) in two sites of the Loire estuary with different ecological conditions and contamination pressures (upstream: Varades; downstream: Nantes). Reproductive (gender, sexual maturity stage) and biometric parameters of collected eels were determined. A laboratory exposure of silver male to steroid hormones (Testosterone (T), 11-KetoTestosterone (11-KT), Estradiol (E2)) was conducted in parallel to validate the q RT PCR approach on hepatic Vg mRNA. Results demonstrated the responsiveness of exposed silver male eels, since hepatic mRNA Vg induction was observed in E2 treated males compared to control specimens. In the field, results of female silver eels reflected large inter-individual differences in the activation of hepatic Vg at silvering. However, while only female silver eels should express hepatic Vg mRNA, quantifiable levels were also detected in a proportion of 38% of the other individuals sampled, normally not inclined to express it, those being

  3. Les structures et le mobilier du site d’habitat Hallstatt final-La Tène ancienne d'Allaines Mervilliers (Eure-et-Loir Buildings and effects from the hallstatt D-Early La Tène site of Allaines Mervilliers (Eure-et-Loir

    Directory of Open Access Journals (Sweden)

    Diane Casadei

    2006-12-01

    Full Text Available Découverte de structures d’habitat sur poteaux et d’une fosse Hallstatt final-La Tène ancienne dans le cadre d’une opération d’archéologie préventive en 1998, à Allaines Mervilliers (Eure-et-Loir. Il s’agit de deux bâtiments rectangulaires à six trous de poteau, d’un bâtiment rectangulaire à trois nefs et d’un bâtiment circulaire. Ces deux derniers sont inédits pour cette époque en région Centre. Le bâtiment rectangulaire à trois nefs est composé de deux rangées centrales de trois trous de poteau et de deux rangées latérales de quatre trous de poteau. Les trous de poteau centraux présentent un remplissage stratifié dont la couche supérieure a livré l’essentiel de l’abondant mobilier découvert. On décompte par exemple dans les vestiges en céramique 56 individus-vases différents. Le bâtiment circulaire est composé d’une couronne de neuf trous de poteau présentant également un remplissage stratifié. On a découvert moins de mobilier dans cette structure que dans le bâtiment précédent, mais il se singularise aussi par la présence d’ossements humains.The discovery of settlement structureson posts and of a pit Hallstatt D-early La Tène during a rescue archaeology operation in 1998, in Allaines Mervilliers (Eure-et-Loir. It concerned two rectangular buildings of six post holes, a rectangular building in three naves and a circular building. The latter two are new for this period in the Centre region.The rectangular building in three naves consisted of two central rows of three post holes and two lateral rows of four post holes. The central holes of post introduce a stratified fill, the upper layer of which produced the majority of the abundant finds. From the ceramic remains it was estimated that there were fifty-six individuals in different vases. The circular building consisted of a ring of nine post holes also producing a stratified fill. Fewer articles were discovered in this structure than

  4. Considerations concerning the reliability of reactor safety equipment; Considerations sur la fiabilite des ensembles de securite de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Furet, J; Guyot, Ch [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    A review is made of the circumstances which favor a good collection of maintenance data at the C.E.A. The large amount of data to be treated has made necessary the use of a computer for analyzing automatically the results collected. Here, only particular aspects of the reliability from the point of view of the electronics used for nuclear reactor control will be dealt with: sale and unsafe failures; probability of survival (in the case of reactor safety); availability. The general diagrams of the safety assemblies which have been drawn up for two types of reactor (power reactor and low power experimental reactor) are given. Results are presented of reliability analysis which could be applied to the use of functional modular elements, developed industrially in France. Improvement of this reliability appears to be fairly limited by an increase in the redundancy; on the other hand it is shown how it may be very markedly improved by the use of automatic tests with different frequencies for detecting unsafe failures rates of measurements for the sub-assemblies and for the logic sub-assemblies. Finally examples are given to show the incidence of the complexity and of the use of different technologies in reactor safety equipment on the reliability. (authors) [French] On rappelle les circonstances qui favorisent au C.E.A. la collecte d'une information valable des resultats de la maintenance. L'importance des donnees a traiter a rendu necessaire l'utilisation d'une calculatrice poux l'analyse automatique des resultats recueillis. On se limitera ici aux aspects particuliers de la fiabilite du point de vue de l'electronique pour le controle et la commande de reacteurs nucleaires: pannes sures et pannes non sures; probabilite de survie dans le cas de la securite des reacteurs; facteur de disponibilite. Les schemas de principe des ensembles de securite definis pour deux types de reacteurs (reacteur de puissance et reacteur experimental de faible puissance) sont indiques. On

  5. Nutrient inputs and hydrology together determine biogeochemical status of the Loire River (France): Current situation and possible future scenarios.

    Science.gov (United States)

    Garnier, Josette; Ramarson, Antsiva; Billen, Gilles; Théry, Sylvain; Thiéry, Dominique; Thieu, Vincent; Minaudo, Camille; Moatar, Florentina

    2018-05-10

    The Grafs-Seneque/Riverstrahler model was implemented for the first time on the Loire River for the 2002-2014 period, to explore eutrophication after improvement of wastewater treatments. The model reproduced the interannual levels and seasonal trends of the major water quality variables. Although eutrophication has been impressively reduced in the drainage network, a eutrophication risk still exists at the coast, as shown by the N-ICEP indicator, pointing out an excess of nitrogen over silica and phosphorus. From maximum biomass exceeding 120 μgChla l -1 in the 1980's, we observed decreasing maximum values from 80 to 30 μgChla l -1 during the period studied. Several scenarios were explored. Regarding nutrient point sources, a low wastewater treatment scenario, similar to the situation in the 1980's, was elaborated, representing much greater pollution than the reference period (2002-2014). For diffuse sources, two agricultural scenarios were elaborated for reducing nitrogen, one with a strict application of the agricultural directives and another investigating the impact of radical structural changes in agriculture and the population's diet. Although reduced, a risk of eutrophication would remain, even with the most drastic scenario. In addition, a pristine scenario, with no human activity within the basin, was devised to assess water quality in a natural state. The impact of a change in hydrology on the Loire biogeochemical functioning was also explored according to the effect of climate change by the end of the 21st century. The EROS hydrological model was used to force Riverstrahler, considering the most pessimistic SRES A2 scenario run with the ARPEGE model. Nutrient fluxes all decreased due to a >50% reduction in the average annual discharge, overall reducing the risk of coastal eutrophication, but worsening the water quality status of the river network. The Riverstrahler model could be useful to help water managers contend with future threats in the

  6. Spectral analysis of detector signals and the effect of gas and vapor bubbles in the core of the SUR-100 reactor

    International Nuclear Information System (INIS)

    Song, P.S.

    1981-01-01

    A series of experiments was performed in the SUR-100 reactor, Hanover, and evaluated by means of statistical analysis methods in order to extend the knowledge about the influence of voids on the neutron flux and facilitate the interpretation of spectra of neutron flux fluctuations measured in power reactors. The investigations were performed in a relatively low frequency band, because the neutron flux spectra generated by air bubbles crossing the reactor core without any essential change in velocity and shape show the typical features of global reactivity effects. A strong relation between the spectra shapes and the transit times of bubbles through the core can be observed. Concerning the experiments with boiling coolant, pronounced neutron flux oscillations were measured originating from periodical flow instabilities in the coolant channel. The neutron flux oscillations depend upon the subcooling of the water and upon the heating power and have evidently the same frequency like the flow oscillations. (orig.) [de

  7. The zero power reactor SUR and its application

    International Nuclear Information System (INIS)

    Wesser, U.

    1986-01-01

    This low-power reactor, rated nominally at 100 milliwatts, has a cylindrical core of 26 cm in diameter and 24 cm high consisting of U 3 O 8 powder in a polyethylene matrix. The fuel is 20 percent enriched and the critical mass about 700 g. The excess reactivity is about 3 mk. The reactivity is controlled by two cadmium sheets in addition to a back-up system that drops the inner reflector. The reactor has no active cooling system. Personnel costs include a supervisor and an operator. The reactor is used for training in Reactor Theory (including use of a neutron chopper), reactor kinetics, nuclear technology, reactor operations and for doctoral thesis research. (author)

  8. Airborne gamma-ray spectrometer and magnetometer survey: Peoria, Decater, Belleville Quadrangles, (IL). Final report

    International Nuclear Information System (INIS)

    1981-01-01

    An airborne combined radiometric and magnetic survey was performed for the Department of Energy (DOE) over the area covered by the Peoria, Decatur, and Belleville, 1:250,000 National Topographic Map Series (NTMS), quadrangle maps. The survey was part of DOE's National Uranium Resource Evaluation (NURE) program. Data were collected by a helicopter equipped with a gamma-ray spectrometer with a large crystal volume, and with a high sensitivity proton procession magnetometer. The radiometric system was calibrated at the Walker Field Calibration pads and the Lake Mead Dynamic Test Range. Data quality was ensured during the survey by daily test flights and equipment checks. Radiometric data were corrected for live time, aircraft and equipment background, cosmic background, atmospheric radon, Compton scatter, and altitude dependence. The corrected data were statistically evaluated, plotted, and contoured to produce anomaly maps based on the radiometric response of individual geological units. The anomalies were interpreted and an interpretation map produced. Volume I contains a description of the systems used in the survey, a discussion of the calibration of the systems, the data collection procedures, the data processing procedures, the data presentation, the interpretation rationale, and the interpretation methodology. A separate Volume II for each quadrangle contains the data displays and the interpretation results

  9. UN OUTIL D’AIDE Á LA GESTION DE L’ANGUILLE : LE TABLEAU DE BORD ANGUILLLE DU BASSIN LOIRE

    Directory of Open Access Journals (Sweden)

    BAISEZ A.

    2005-10-01

    Full Text Available L’anguille européenne (Anguilla anguilla, L. est longtemps apparue comme une espèce commune, représentant une composante majeure des milieux littoraux et des eaux continentales. La prise de conscience de la diminution de son abondance est réelle et engendre l’émergence de processus de gestion. Ce constat situe l’enjeu du Tableau de Bord Anguille du Bassin Loire mis en place en avril 2002 sous l’égide du COmité de GEstion des POissons MIgrateurs du Bassin de la Loire, des Côtiers Vendéens et de la Sèvre Niortaise. Son objectif in fine est de contribuer à une gestion et à un développement durable de l’espèce et de ses habitats. Il vise à surveiller les caractéristiques des stocks locaux présents et des habitats disponibles au moyen d’une collecte régulière et objective de données synthétisées sous forme d’indicateurs de population et de milieu. Le concept, le fonctionnement actuel et les applications de ce tableau de bord sont ici présentés.

  10. Landscape trajectories during the Lateglacial and the Holocene in the Loir River Valley (France) : the contribution of Geoarchaeology

    Science.gov (United States)

    Piana, Juliene

    2015-04-01

    A multidisciplinary research has been initiated in the Loir River valley where investigations revealed high-potential fluvial records and landforms for environmental and socio-environmental reconstructions. Investigations provide the opportunity to reconstruct landscape trajectories between climate, environmental and societal changes during the last 16000 years, using geoarchaeological and archaeogeographical approaches: sedimentology, soil micromorphology, geochemistry, archaeology, geomatics, geochronology (AGES Program: Ancient Geomorphological EvolutionS of Loire Basin hydrosystem). In the sector of Vaas (Sarthe, France) the research on the Lateglacial and the Holocene sedimentary sequences from the alluvial plain leads to a general overview of the valley evolution from the end of the Weichselian Upper Pleniglacial to the Present. Joined to archaeological (Protohistoric and Antic sites) and historical data (engineering archives, 18th century cadastral registers) this research highlights the importance of anthropogenic and geomorphological heritages in the current fluvial landscape (microtopography, wetlands, archaeological remains, land use). This knowledge constitutes a basis for skills transfer to planners and managers, in sustainable management of hydrological resources (reducing the vulnerability to flooding and low flows), preservation of biodiversity (wetlands protection) and valorization of landscapes (cultural tourism development).

  11. methanization development scheme in the Maine-et-Loire district - Synthesis June 2016

    International Nuclear Information System (INIS)

    2016-06-01

    After a presentation of the situation of methanization in France and in the Pays-de-la-Loire region, this report proposes an overview of the situation of methanization in the district and recalls objectives defined in its methanization development scheme. Then, it describes methanization principles (definition, operation and techniques, project typology, project development steps), proposes an overview of conditions for a successful methanization project development (substrate typology, biogas energetic valorisation, digestate valorisation, project financial and economic impact, social acceptability of methanization projects), gives an assessment of methanization development potential in the district through an assessment of methanizable resources and of energy outlets. It presents and comments a map of methanization development opportunities in the district

  12. Generalities on the dynamic behaviour of rapid reactors. Preliminary studies on Rapsodie; Generalites sur le comportement dynamique des piles rapides. Etudes preliminaires de rapsodie

    Energy Technology Data Exchange (ETDEWEB)

    Campan, J L; Chaumont, J P; Clauzon, P P; Ghesquiere, G; Leduc, J; Schmitt, A P; Zaleski, C P [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1963-07-01

    The study of the dynamic behaviour of fast reactors may be divided into three section: 1. Stability studies around equilibrium power only the linear case was examining. S. Transient studies in the case of usual reactor operation (shut down, scram, etc.) with thermal shocks evaluation, for instance. 3. Explosion studies, for the maximum credible accidents. This report presents the status of the studies performed at the 'Physics Research Department' at Cadarache. Methods used are detailed and illustrated with the results obtained on a preliminary metallic core of the Rapsodie Reactor. (authors) [French] Le comportement dynamique des piles rapides, se presente tout naturellement sous trois aspects: 1. Etude de stabilite autour d'un regime d'equilibre (nous nous sommes bornes ici au cas lineaire). 2. Etude de regimes transitoires lors des operations normales de pile (arret, arret d'urgence, etc.) avec evaluation des chocs thermiques par exemple. 3. Etude des regimes transitoires de caractere explosif lors des accidents les plus graves possibles. Ce rapport presente l'etat des etudes a la date du 20 decembre 1961 a la Section d'Etudes de Piles Rapides a CADARACHE. Les methodes employees ont ete detaillees et illustrees a partir des resultats obtenus sur une premiere version 'combustible metallique' de Rapsodie. (auteurs)

  13. Surveillance of the radioactivity in the environment of the Loire basin

    International Nuclear Information System (INIS)

    2008-12-01

    The surveillance of the radioactivity in environment in the Loire catchment basin rests on the measurement of radioactivity in atmosphere, in the rain waters and continental waters as well as the follow up of radioactivity in food chain. Concerning the air radiation monitoring, that is the dose rate measurement of ambient gamma radiation, the radon measurement and the measurement of particulates and radioactive aerosols. Concerning the food chain, the follow up is made on drinking water, milk, fishes and the special case of strontium 90. The actors of this campaign are the institute of radiation protection and nuclear safety (I.R.S.N.), Electricite de France (E.D.F.) Areva NC, the associations qualified for the surveillance of air quality (A.A.S.Q.A.) and the government services. (N.C.)

  14. Notes on a homogeneous reactor project; Idees sur un projet de reacteur homogene

    Energy Technology Data Exchange (ETDEWEB)

    Benveniste, J; Bernot, J; Eidelman, D; Grenon, M; Portes, L; Raspaud, G; Tachon, J; Vendryes, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Berthod, L; Cohen de Lara, G; Delachanal, M; Fontanet, P; Halbronn, G [Societe Grenobloise d' Etudes et d' Applications Hydrauliques, 38 (France)

    1958-07-01

    An attempt has been made to develop certain ideas concerning homogeneous reactors. The project under consideration is based on the simultaneous use of a suspension of uranium dispersed in heavy or light water and of boiling in the reactor for heat extraction. However, the studies of suspensions and of boiling are relatively independent and can also be developed for reactors of different types using one or the other. Our aim is a minimum investment in fissile material; for this we propose to extract the steam directly from the core and to make use of a cyclone to accelerate this extraction; a cyclone-type circulation creating a field of increasing tangential velocities of the fluid towards the axis causes the droplets of vapour to accelerate towards the axial vortex in which they are collected; the steam output is then evacuated to the external heat utilisation system, for example an exchanger of the condenser-boiler type. The input speed of water into the reactor being one of the important parameters in the running of the pile, a spiral supply input chamber is used, allowing this speed to be regulated in amount and direction. (author)Fren. [French] Nous nous sommes attaches a developper certaines idees relatives aux piles homogenes. Le projet que nous etudions est base sur l'emploi simultane d'une suspension contenant de l'uranium disperse dans l'eau legere ou lourde et de l'ebullition dans le reacteur pour l'extraction de chaleur. Neanmoins, les etudes de suspensions et d'ebullition sont relativement independantes et peuvent egalement etre developpees pour des reacteurs de type different utilisant l'une ou l'autre. Le but que nous cherchons a atteindre est un investissement minimum en matiere fissile; pour cela, nous proposons d'extraire directement la vapeur dans le coeur et de recourir a un dispositif cyclone pour accelerer cette extraction; une circulation type cyclone creant un champ de vitesses tangentielles du fluide croissantes veraxe a pour effet d

  15. Application of directional solidification ingot (LSD) in forging of PWR reactor vessel heads

    International Nuclear Information System (INIS)

    Benhamou, C.; Poitrault, I.

    1985-09-01

    Creusot-Loire Industrie uses this type of ingot for manufacture of Framatome 1300 and 1450 MW 4-loop PWR reactor vessel heads. This type of ingot offers a number advantages: improved internal soundness; greater chemical, structural and mechanical homogeneity of the finished part; simplified forging process. After a brief description of the pouring and solidification processes, this paper presents an analysis of the results of examinations performed on the prototype forging, as well as review of results obtained during industrial fabrication of dished heads from LSD ingots. The advantages of the LSD ingot over conventional ingots are discussed in conclusion

  16. Dynamics of intertidal flats in the Loire estuary

    Science.gov (United States)

    Kervella, Stephane; Sottolichio, Aldo; Bertier, Christine

    2014-05-01

    Tidal flats form at the edges of many tidal estuaries, and are found in broad climatic regions. Their evolution plays a fundamental role in maintaining the morphodynamic equilibrium of an estuary. The Loire estuary is one of the largest macrotidal systems of the french atlantic coast. Since 200 years, its geometry has been drastically modified through channeling, deepening, embanking, infilling of secondary channels, etc. These works altered many intertidal areas. In the recent years, efforts for the rectification of the morphology have been made in order to restore the ecology of the estuary. In this context, it is crucial to better understand the dynamics of intertidal flats, still poorly understood in this estuary. The aim of this work is to analyse a series of original observations conducted for the first time in two intertidal flats of the central Lore estuary between 2008 and 2010. The tidal flats are situated in the northern bank, at 12 and 17 km upstream from the mouth respectively. Six Altus altimeters were deployed at two cross shore transects, measuring continuously and at a high-frequency bed altimetry and water level, providing information on tide and waves. At the semi-diurnal tidal scale, the surficial sediment of intertidal flats is permanently mobilized. Altimetry variations are low, and their amplitude varies as a function of tides and river flow. At the scale of several months, the sedimentation is controlled by the position of the turbidity maximum (and therefore by the river flow) and also by the tidal amplitude. During low river flow periods, altimetry variations are only due to tidal cycles. During decaying tides, suspended sediment settle mainly on the lower part of the tidal flats, forming fluid mud layers of several cm thick, which can consolidate rapidly; under rising tides, the increasing of tidal currents promotes erosion. During periods of high river flow, the turbidity maximum shifts to the lower estuary. The higher suspended sediment

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-07-01

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

  18. Measurements of reactivity of reactor G1; Mesures de reactivite sur reacteur G1

    Energy Technology Data Exchange (ETDEWEB)

    Bernot, J; Koechlin, J C; Portes, L; Teste du Bailler, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    The various methods used during the physical study of the reactor G1 to determine the variations of the effective multiplication factor consecutive to a given change in the geometry of the multiplying medium, are presented and discussed. The comparison of the results obtained by these various methods has allowed their validity to be tested and precise conditions of use to be given. In the first part are presented the principles used and their ranges of validity. In the second part the experimental results are given, together with some indications on their comparison with theoretical estimations. (author) [French] Nous exposons et discutons diverses methodes utilisees, lors de l'etude physique du reacteur G1, pour determiner les variations du facteur de multiplication effectif consecutives a un changement donne dans la geometrie du milieu multiplicateur. La comparaison des resultats obtenus par diverses methodes nous a permis de tester leur validite et d'en preciser les conditions d'emploi. Dans une premiere partie, nous exposons les principes utilises et leurs domaines de validite. Dans une seconde partie nous donnons les resultats experimentaux obtenus avec quelques indications sur leur comparaison avec les estimations theoriques. (auteur)

  19. Energy industries in the Centre-Val de Loire region - June 2015

    International Nuclear Information System (INIS)

    Mialot, Marie-Madeleine; Ducroq, Caroline

    2015-07-01

    After an overview of the energy sector in the world (consumption growth, share of the different energies, main consuming countries, evolution of the energy mix, perspectives) and in France (energy consumption, energy production, jobs, trade balance, research policy and organisation), this publication proposes an overview of energy industries in the Centre-Val de Loire region. It provides some data such as regional consumption, share in the national energy production, jobs and employment structure. The next part proposes a sector-based approach by evoking a strong expertise in the oil and gas industry, by describing a rich industrial tissue about electro-nuclear energy (various activities, specialised urban areas, job creations in nuclear plants, education and training, research lead by private consultants), and by outlining that the territory is suitable for the development of renewable energies (solar, wind, biomass, and geothermal energies, energy storage, R and D, education)

  20. Three C-terminal residues from the sulphonylurea receptor contribute to the functional coupling between the KATP channel subunits SUR2A and Kir6.2

    Science.gov (United States)

    Dupuis, Julien P; Revilloud, Jean; Moreau, Christophe J; Vivaudou, Michel

    2008-01-01

    Cardiac ATP-sensitive potassium (KATP) channels are metabolic sensors formed by the association of the inward rectifier potassium channel Kir6.2 and the sulphonylurea receptor SUR2A. SUR2A adjusts channel gating as a function of intracellular ATP and ADP and is the target of pharmaceutical openers and blockers which, respectively, up- and down-regulate Kir6.2. In an effort to understand how effector binding to SUR2A translates into Kir6.2 gating modulation, we examined the role of a 65-residue SUR2A fragment linking transmembrane domain TMD2 and nucleotide-binding domain NBD2 that has been shown to interact with Kir6.2. This fragment of SUR2A was replaced by the equivalent residues of its close homologue, the multidrug resistance protein MRP1. The chimeric construct was expressed in Xenopus oocytes and characterized using the patch-clamp technique. We found that activation by MgADP and synthetic openers was greatly attenuated although apparent affinities were unchanged. Further chimeragenetic and mutagenetic studies showed that mutation of three residues, E1305, I1310 and L1313 (rat numbering), was sufficient to confer this defective phenotype. The same mutations had no effects on channel block by the sulphonylurea glibenclamide or by ATP, suggesting a role for these residues in activatory – but not inhibitory – transduction processes. These results indicate that, within the KATP channel complex, the proximal C-terminal of SUR2A is a critical link between ligand binding to SUR2A and Kir6.2 up-regulation. PMID:18450778

  1. Revision of by-laws about effluents of EdF's nuclear power plants

    International Nuclear Information System (INIS)

    2002-01-01

    In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, 14 C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

  2. Revision of by-laws about effluents of EdF's nuclear power plants; Revision des arretes de rejets des centrales nucleaires d'EDF

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, {sup 14}C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

  3. Caesium-137 in sandy sediments of the River Loire (FR): Assessment of an alluvial island evolving over the last 50 years

    Energy Technology Data Exchange (ETDEWEB)

    Detriche, Sebastien; Rodrigues, Stephane; Macaire, Jean-Jacques; Breheret, Jean-Gabriel; Bakyono, Jean-Paul [Universite Francois-Rabelais de Tours, CNRS/INSU UMR 6113 ISTO, Universite d' Orleans Faculte des Sciences et Techniques, Laboratoire de Geologie des Environnements Aquatiques Continentaux, Parc de Grandmont, 37200 Tours (France); Bonte, Philippe [UMR CNRS-CEA 1572, Laboratoire des Sciences du Climat et de l' Environnement - LSCE, CNRS, Domaine du CNRS, Bat. 12, 91198 Gif-sur-Yvette (France); Juge, Philippe [CETU-Elmis ingenieries, Antenne Universitaire en Val de Vienne, 11 quai Danton, 37500 Chinon (France)

    2010-07-01

    Recent sedimentological and morphological evolution of an island in the River Loire (FR) was investigated using the {sup 137}Cs method. This study describes the morphological adjustment of the island in the last 50 years, which corresponds to the increased bed incision of this sandy, multiple-channel environment because of, among other things, the increase in sediment extraction up to 1995. The results show that some {sup 137}Cs can be retained by sandy particles, potentially in clay minerals forming weathering features included in detrital sand grains. From a morphological perspective, significant lateral erosion can be observed in the upstream part of the island, while a weak lateral accretion occurs in its downstream section. Data about {sup 137}Cs and aerial photographs show that the morphology of the island margins has undergone significant changes leading to a lateral migration, while the centre of the island has remained relatively stable or is slowly eroding. The migration of the island depends on: (1) the withdrawal of inherited pre-incision morphological units, such as levees, or the development of new units, such as a channel shelf; (2) water and sediment supply from surrounding channels during flood events; (3) preferential sediment trapping (20 mm year{sup -1}) from the presence of riparian vegetation on the bank of the secondary channel that is subject to narrowing. The sedimentological and morphological response of the island in the context of incision of the Loire river bed is expressed mainly by lateral migration and secondarily by a low vertical adjustment. (authors)

  4. Caesium-137 in sandy sediments of the River Loire (FR): Assessment of an alluvial island evolving over the last 50 years

    International Nuclear Information System (INIS)

    Detriche, Sebastien; Rodrigues, Stephane; Macaire, Jean-Jacques; Breheret, Jean-Gabriel; Bakyono, Jean-Paul; Bonte, Philippe; Juge, Philippe

    2010-01-01

    Recent sedimentological and morphological evolution of an island in the River Loire (FR) was investigated using the 137 Cs method. This study describes the morphological adjustment of the island in the last 50 years, which corresponds to the increased bed incision of this sandy, multiple-channel environment because of, among other things, the increase in sediment extraction up to 1995. The results show that some 137 Cs can be retained by sandy particles, potentially in clay minerals forming weathering features included in detrital sand grains. From a morphological perspective, significant lateral erosion can be observed in the upstream part of the island, while a weak lateral accretion occurs in its downstream section. Data about 137 Cs and aerial photographs show that the morphology of the island margins has undergone significant changes leading to a lateral migration, while the centre of the island has remained relatively stable or is slowly eroding. The migration of the island depends on: (1) the withdrawal of inherited pre-incision morphological units, such as levees, or the development of new units, such as a channel shelf; (2) water and sediment supply from surrounding channels during flood events; (3) preferential sediment trapping (20 mm year -1 ) from the presence of riparian vegetation on the bank of the secondary channel that is subject to narrowing. The sedimentological and morphological response of the island in the context of incision of the Loire river bed is expressed mainly by lateral migration and secondarily by a low vertical adjustment. (authors)

  5. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

  6. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  7. The regional ground-based wind energy scheme of Pays-de-la-Loire: project, Assessment of the consultation on the regional wind energy project, final version, Prefect decree bearing approval of the regional ground-based wind energy scheme of Pays-de-la-Loire

    International Nuclear Information System (INIS)

    2012-08-01

    This document first presents the regional wind energy scheme (SRE) as a framework for ground-based wind energy development, and as the wind energy component of the regional climate air energy scheme (SRCAE), briefly presents the elaboration approach, and indicates the legal scope of this scheme. The next part outlines the high rate development of wind energy in the Pays-de-la-Loire region. The third part reports the identification, analysis and assessment of areas of interest for the development of wind energy. Finally, the objective of this development by 2020 is estimated

  8. Loire and Gironde turbid plumes: Characterization and influence on thermohaline properties

    Science.gov (United States)

    Costoya, X.; Fernández-Nóvoa, D.; deCastro, M.; Gómez-Gesteira, M.

    2017-12-01

    Knowledge and predictability of turbid river plumes is of great importance because they modulate the properties of the seawater adjacent to river mouths. The Loire and Gironde Rivers form the most important plumes in the Bay of Biscay, as they provide > 75% of total runoff. The development of the turbid plume under the influence of its main drivers was analyzed using Moderate Resolution Imaging Spectroradiometer satellite data from the period 2003-2015. River discharge was found to be the main driver, followed by wind, which also had an important effect in modulating the turbid plume during periods of high river discharge. Seaward and upwelling favorable winds enhanced the dispersion of plumes on seawater, whereas landward and downwelling favorable winds limited mixing with the adjacent ocean water. The maximum extension of the turbid plume was reached under landward winds. In addition, the spatio-temporal evolution of the East Atlantic pattern and the North Atlantic Oscillation was observed to affect the dynamics of plumes: positive values of both indices favored a greater extension of the plume. Thermohaline properties differed inside and outside the area affected by both rivers. In particular, these rivers maintain winter stratification inside the turbid plume, which results in a different warming ratio when compared with the adjacent ocean.

  9. PARR-2: reactor description and experiments

    International Nuclear Information System (INIS)

    Wyne, M.F.; Meghji, J.H.

    1990-12-01

    PARR-2 is a miniature neutron source reactor (MNSR) research reactor has been designed at the rate of 27 kW. Reactor assembly comprises of peaking characteristics with a self limiting flux. In this report reactor description with its assembly and instrumentation control system has been explained. The reactor engineering and physics experiments which can be performed on this reactor are explained in this report. PARR-2 is fueled with HEU fuel pins which are about 90% enriched in U-235. Specific requirements for the safety of the reactor, its building and the personnel, normal instrumentation as required in an industrial environment is sufficient. (A.B.)

  10. Fast flux measurements by means of threshold detectors on the reactor 'Melusine'; Mesures de flux rapides a l'aide de detecteurs a seuil sur le reacteur 'Melusine'

    Energy Technology Data Exchange (ETDEWEB)

    Leger, P; Sautiez, B [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    Using existing data on the (n,p) and (n,{alpha}) threshold reactions we have carried out fast flux measurements on the swimming pool type reactor 'Melusine'. Four common elements: P, S, Mg, Al were chosen because from the point of view of fast spectrum analysis they represent a fairly good energy range from 2.4 MeV to 8 MeV. The fission flux value found in the central element at a power of 1 MW is 1.4 x 10{sup 13} n/cm{sup 2}/s {+-} 0.14. (author) [French] A l'aide des donnees actuelles sur les reactions a seuil (n,p) et (n,{alpha}) nous avons realise des mesures de flux rapide dans le reacteur du type piscine 'Melusine'. Quatre corps courants: P, S, Mg, Al, ont ete choisis parce qu'ils constituent au point de vue de l'analyse du spectre rapide un assez bon etalement en energie de 2,4 MeV A 8 MeV. La valeur du flux de fission trouve dans l'element central a une puissance de 1 MW est de 1,4.10{sup 13} n/cm{sup 2}/s {+-} 0,14. (auteur)

  11. Reactor BR2: Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. A safety audit was conduced by the IAEA, the conclusions of which demonstrated the excellent performance of the plant in terms of operational safety. In 1999, the CALLISTO facility was extensively used for various programmes involving LWR pressure vessel materials, IASCC of LWR structural materials, fusion reactor materials and martensic steels for use in ADS systems. In 1999, BR2's commercial programmes were further developed

  12. Material test reactor fuel research at the BR2 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dyck, Steven Van; Koonen, Edgar; Berghe, Sven van den [Institute for Nuclear Materials Science, SCK-CEN, Boeretang, Mol (Belgium)

    2012-03-15

    The construction of new, high performance material test reactor or the conversion of such reactors' core from high enriched uranium (HEU) to low enriched uranium (LEU) based fuel requires several fuel qualification steps. For the conversion of high performance reactors, high density dispersion or monolithic fuel types are being developed. The Uranium-Molybdenum fuel system has been selected as reference system for the qualification of LEU fuels. For reactors with lower performance characteristics, or as medium enriched fuel for high performance reactors, uranium silicide dispersion fuel is applied. However, on the longer term, the U-Mo based fuel types may offer a more efficient fuel alternative and-or an easier back-end solution with respect to the silicide based fuels. At the BR2 reactor of the Belgian nuclear research center, SCK-CEN in Mol, several types of fuel testing opportunities are present to contribute to such qualification process. A generic validation test for a selected fuel system is the irradiation of flat plates with representative dimensions for a fuel element. By flexible positioning and core loading, bounding irradiation conditions for fuel elements can be performed in a standard device in the BR2. For fuel element designs with curved plates, the element fabrication method compatibility of the fuel type can be addressed by incorporating a set of prototype fuel plates in a mixed driver fuel element of the BR2 reactor. These generic types of tests are performed directly in the primary coolant flow conditions of the BR2 reactor. The experiment control and interpretation is supported by detailed neutronic and thermal-hydraulic modeling of the experiments. Finally, the BR2 reactor offers the flexibility for irradiation of full size prototype fuel elements, as 200mm diameter irradiation channels are available. These channels allow the accommodation of various types of prototype fuel elements, eventually using a dedicated cooling loop to provide the

  13. EBR-2 [Experimental Breeder Reactor-2], IFR [Integral Fast Reactor] prototype testing programs

    International Nuclear Information System (INIS)

    Lehto, W.K.; Sackett, J.I.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.

    1990-01-01

    The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development. (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

  14. Koostöös Eesti Instituudiga korraldas...

    Index Scriptorium Estoniae

    2004-01-01

    Katariina Gild korraldas Prantsusmaal kaks näitust: 4.-16. XI Tours'i eeslinnas Saint-Cyr-sur-Loire'i Charles X paviljonis ning 19.-30. XI Loches'i linnas. Näituse kujundasid Kaire Tali ja Krista Laos, eksponeeritud olid Kai Koppeli, Viivi-Ann Keerdo, Ülle Rajasalu, Virve Kermi, Kaire Tali, Pille Kivihalli, Jane Rannametsa, Anni Kreemi, Ene Parsi, Liivia Leshkini, Ülle Kõutsi ja Krista Laose tööd.

  15. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2001-01-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given

  16. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2001-04-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given.

  17. Blowing loop in the EL-4 reactor: CO{sub 2} flow control analogue study; Boucle de soufflage de la centrale EL-4 - regulation du debit CO{sub 2} - etude analogique

    Energy Technology Data Exchange (ETDEWEB)

    Chazal, G; Merle, J P; Guillemard, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Leroy, C; Robin, L; Jacquin, J C; Cornudet, A [Societe INDATOM, France (France)

    1966-07-01

    This report describes one study which contributed to the construction of the Monts d'Arree nuclear power station: EL-4. The reactor is cooled by a CO{sub 2} current provided by 3 turbo-blower groups. The priming vapour for the turbines is taken at the exit of the main CO{sub 2} - H{sub 2}O exchangers. The operation of EL 4 is based on a high degree of centralization of the controls which attributes an important role to the general regulation circuits. This general regulation includes in particular an internal blowing loop which controls the CO{sub 2} flow. The study of the control of this CO{sub 2} flow is made up of 3 parts: - analogue representation of the reactors cooling circuit and of the turbo blower unit. - first test campaign using the analogue computer describing the natural behaviour of the system in the absence of control. theoretical determination of the regulation factors; definition of the regulation using an analogue computer and second test campaign for recording the performances of the blowing loop. The 4. part of the report deals with the analogue study: analogue equations - development. (authors) [French] Ce rapport prend place parmi les etudes de realisation de la Centrale des Monts d'Arree EL-4. Le reacteur est refroidi par une circulation de CO{sub 2} assuree par 3 groupes turbosoufflantes. La vapeur d'entrainement des turbines est prelevee a la sortie des echangeurs principaux CO{sub 2} - H{sub 2}O. L'exploitation de EL-4 repose sur une centralisation poussee des moyens de controle-commande qui attribue un role essentiel aux circuits de regulation generale. Cette regulation generale comporte en particulier une boucle interne de soufflage qui realise un asservissement du debit de CO{sub 2}. L'etude de cette regulation du debit CO{sub 2} comprend 3 parties: - representation analogique du circuit de refroidissement du reacteur et de l'ensemble turbine-soufflante. - premiere campagne d'essais sur calculateur analogique decrivant le comportement

  18. Safety features of TR-2 reactor

    International Nuclear Information System (INIS)

    Tuerker, T.

    2001-01-01

    TR-2 is a swimming pool type research reactor with 5 MW thermal power and uses standard MTR plate type fuel elements. Each standard fuel element consist of 23 fuel plates with a meat + cladding thickness of 0.127 cm, coolant channel clearance is 0.21 cm. Originally TR-2 is designed for %93 enriched U-Al. Alloy fuel meat.This work is based on the preparation of the Final Safety Analyses Report (FSAR) of the TR-2 reactor. The main aspect is to investigate the behaviour of TR-2 reactor under the accident and abnormal operating conditions, which cowers the accident spectrum unique for the TR-2 reactor. This presentation covers some selected transient analyses which are important for the safety aspects of the TR-2 reactor like reactivity induced startup accidents, pump coast down (Loss of Flow Accident, LOFA) and other accidents which are charecteristic to the TR-2

  19. Étude des enduits et peintures murales du prieuré Saint-Martin de Mesvres (Saône-et-Loire

    Directory of Open Access Journals (Sweden)

    Agathe Foullon

    2011-08-01

    Full Text Available L’ancien prieuré Saint-Martin de Mesvres (Saône-et-Loire occupe une place intéressante dans le réseau religieux bourguignon au Moyen Âge : ses liens avec Autun, Flavigny, mais également Cluny, sont autant d’axes de recherches pour les études historiques et archéologiques en cours . L’étude des enduits et peintures murales du prieuré a débuté en 2009 par une analyse archéologique, menée dans le cadre d’un master 1 de l’université de Paris 4 Panthéon-Sorbonne . À la suite des premières observa...

  20. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2002-01-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system

  1. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2002-04-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system.

  2. The CO{sub 2} cooling gas for the reactors G2/G3 (leaking, analysis, activity); Le CO{sub 2} de refroidissement des reacteurs G2/G3 (fuites, analyse, activite)

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    The main objective of this study is to publicise the data obtained during five years operation of the reactor G2 and G3 at Marcoule as far as the cooling gas is concerned, from storage of reserves up to its slow escape into the atmosphere, and including all the stages of its practical use, its chemical examination, its nuclear behaviour and its possible physicochemical transformation. This work can not only yield information about the operations carried out at Marcoule but can also provide useful suggestions for improving the sealing and for decreasing the activity of the pressurized gas circuits in reactors similar to G2/G3. (authors) [French] Le but principal de cette etude est de diffuser les connaissances acquises au cours de cinq annees d'exploitation des reacteurs G2 et G3 de Marcoule en ce qui concerne le gaz de refroidissement, depuis son stockage d'appoint jusqu'a son echappement lent dans l'atmosphere, en passant par tous les stades de son utilisation pratique, de son etude chimique, de son comportement nucleaire, eventuellement de ses transformations physico-chimiques. Cette etude peut, non seulement renseigner sur les operations effectuees couramment a Marcoule, mais egalement donner des suggestions interessantes pour l'amelioration de l'etancheite et la diminution de l'activite des circuits de gaz en pression dans des reacteurs analogues a G2/G3. (auteurs)

  3. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    Moons, F.

    2007-01-01

    The irradiations in the BR2 reactor are in collaboration with or at the request of third parties such as the European Commission, the IAEA, research centres and utilities, reactor vendors or fuel manufacturers. The reactor also contributes significantly to the production of radioisotopes for medical and industrial applications, to neutron silicon doping for the semiconductor industry and to scientific irradiations for universities. Along the ongoing programmes on fuel and materials development, several new irradiation devices are in use or in design. Amongst others a loop providing enhanced cooling for novel materials testing reactor fuel, a device for high temperature gas cooled fuel as well as a rig for the irradiation of metallurgical samples in a Pb-Bi environment. A full scale 3-D heterogeneous model of BR2 is available. The model describes the real hyperbolic arrangement of the reactor and includes the detailed 3-D space dependent distribution of the isotopic fuel depletion in the fuel elements. The model is validated on the reactivity measurements of several tens of BR2 operation cycles. The accurate calculations of the axial and radial distributions of the poisoning of the beryllium matrix by 3 He, 6 Li and 3T are verified on the measured reactivity losses used to predict the reactivity behavior for the coming decades. The model calculates the main functionals in reactor physics like: conventional thermal and equivalent fission neutron fluxes, number of displacements per atom, fission rate, thermal power characteristics as heat flux and linear power density, neutron/gamma heating, determination of the fission energy deposited in fuel plates/rods, neutron multiplication factor and fuel burn-up. For each reactor irradiation project, a detailed geometry model of the experimental device and of its neighborhood is developed. Neutron fluxes are predicted within approximately 10 percent in comparison with the dosimetry measurements. Fission rate, heat flux and

  4. The research reactors their contribution to the reactors physics; Les reacteurs de recherche leur apport sur la physique des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Barral, J C [Electricite de France (EDF), 75 - Paris (France); Zaetta, A [CEA/Cadarache, Direction des Reacteurs Nucleaires, DRN, 13 - Saint-Paul-lez-Durance (France); Johner, J [CEA/Cadarache, Dept. de Recherches sur la Fusion Controlee (DRFC), 13 - Saint Paul lez Durance (France); Mathoniere, G [CEA/Saclay, DEN, 91 - Gif sur Yvette (France); and others

    2000-07-01

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  5. Analyse de l'effet de la suréducation sur l'efficacité technique des ...

    African Journals Online (AJOL)

    de tire-au-flanc, et l'état de santé (Vroom 1964 ; Sheppard & Herrick 1972 ; ... impact négatif significatif de la suréducation sur la satisfaction au travail ; son ..... présence syndicale sur la performance financière de 250 entreprises américaines.

  6. La cooperación Sur-Sur agrícola argentina con África Subsahariana: una historia que comienza

    OpenAIRE

    Morasso, Carla

    2015-01-01

    [es] En la última década Argentina ha sido un actor dinámico de la cooperación Sur-Sur. Sus acciones se han dirigido principalmente hacia América Latina, pero también se han promovido los vínculos con Asia y África. El artículo analiza particularmente la cooperación Sur-Sur entre Argentina y países de África Subsahariana en materia de desarrollo agrícola en el período 2003-2013, donde se destacan los roles del Fondo Argentino de Cooperación Sur-Sur y Triangula...

  7. CARACTERIZACIÓN DEL CONSUMO DE HORTALIZAS EN LAS FAMILIAS DEL SUR-SUR DE COSTA RICA

    Directory of Open Access Journals (Sweden)

    Alexis Villalobos-Monge

    2013-01-01

    Full Text Available El objetivo de este trabajo fue determinar los diferentes aspectos cuantitativos y cualitativos que explican la cultura de consumo actual de hortalizas en las familias residentes en la zona sur-sur de Costa Rica. Este trabajo expone resultados relacionados a la caracterización realizada en el 2011 en familias residentes en la denominada zona sur-sur de Costa Rica sobre la cultura de consumo de productos hortícolas. Se aplicaron cuestionarios a una muestra estratificada de familias; lo que permitió establecer la valoración de los precios de mercado, por parte de las familias, para consumir estos alimentos, donde se determinó un valor máximo de US$1,74 millones por semana. Los principales rubros de consumo de acuerdo al valor pagado fueron el tomate, la papa, el plátano, la cebolla y el brócoli, para citar los cinco principales. También fue posible establecer valoraciones cualitativas sobre el consumo de estos productos; por ejemplo se determinó que para el 71,2% de las familias, la frescura representa la característica de mayor valor, además, el principal sitio donde los núcleos familiares realizan las compras de estos alimentos corresponde a supermercados (38,4% de los casos.

  8. Application of MCNPX 2.7.D for reactor core management at the research reactor BR2

    International Nuclear Information System (INIS)

    Kalcheva, Silva; Koonen, Edgar

    2011-01-01

    The paper discusses application of the Monte Carlo burn up code MCNPX 2.7.D for whole core criticality and depletion analysis of the Material Testing Research Reactor BR2 at SCK-CEN in Mol, Belgium. Two different approaches in the use of MCNPX 2.7.D are presented. The first methodology couples the evolution of fuel depletion, evaluated by MCNPX 2.7.D in an infinite lattice with a steady-state 3-D power distribution in the full core model. The second method represents fully automatic whole core depletion and criticality calculations in the detailed 3-D heterogeneous geometry model of the BR2 reactor. The accuracy of the method and computational time as function of the number of used unique burn up materials in the model are being studied. The depletion capabilities of MCNPX 2.7.D are compared vs. the developed at the BR2 reactor department MCNPX & ORIGEN-S combined method. Testing of MCNPX 2.7.D on the criticality measurements at the BR2 reactor is presented. (author)

  9. The functioning of the reactors G2-G3 at Marcoule and E.D.F. 1; Experience de fonctionnement des reacteurs G2-G3 de Marcoule et enseignements des essais de demarrage du reacteur E.D.F. 1 de Chinon

    Energy Technology Data Exchange (ETDEWEB)

    Boussard, R; Conte, F [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Stolz, J M [Electricite de France (EDF), 75 - Paris (France)

    1964-07-01

    After resuming briefly the characteristics of the installations G2-G3 at Marcoule and EDF 1 at Chinon, the authors review the main aspects of the tests, the starting and the exploitation of these reactors. Among the various points examined, particular emphasis is given to the devices of original nature such as tubular fuel elements, flattening of the neutron flux by stuffing, behaviour of the reactor tanks and the cooling circuits, the blowers, unloading devices, regulation and functioning of the informations. This analysis deals equally with the performances obtained and the difficulties and the various incidents experienced during the initial starting period. Among the more interesting results, the progressive increase in the power of the Marcoule reactors is mentioned, obtained through a better knowledge of the parameters covering the functioning of the reactors such as the distribution of the flux and the temperatures etc... acquired during the course of the exploitation of the reactor. The conclusion reached by the authors is that the experience gained on these installations has shown: - that during an initial period, adjustments became necessary, all of which turned out to be possible, - that an analysis of their functioning has permitted the progressive movement towards a truly industrial exploitation. (authors) [French] Les auteurs, apres un bref rappel des caracteristiques des installations G2 - G3 de MARCOULE et E.D.F. 1 de CHINON, passent en revue les principaux aspects des essais, de la mise en service et de l'exploitation de ces centrales. Parmi les divers points examines, une attention speciale est accordee aux dispositifs presentant un caractere original tels que elements combustibles tubulaires, aplatissement du flux neutronique par gavage, comportement des caissons des reacteurs et des circuits de refroidissement, soufflantes, appareils de dechargement, regulation et fonctionnement des informations. L'analyse presentee porte tant sur les

  10. Le réseau d'échanges des savoirs de belleville e ménilmontant: uma discussão sobre associativismo e reciprocidade no mundo contemporâneo

    Directory of Open Access Journals (Sweden)

    Laura Graziela Gomes

    2001-12-01

    Full Text Available O presente artigo tem como objetivo tecer algumas reflexões sobre os modos de apropriação locais de uma forma associativa francesa específica - le réseau d' échanges des savoirs - de Belleville e Ménilmontant, dois quartiers populares, sediados no leste parisiense. A partir de minha experiência como participante do reseau, observações e conversas com os demais participantes, conclui que, basicamente, tratam-se de dois modos: o primeiro, relativo à produção de localidade, da condição de pertença dos moradores do quartier; o segundo, relativo à produção de capital social, traduzido em confiança e, por sua vez, formas de cooperação. O importante a ser ressaltado é que esses dois modos de apropriação não são exclusivos, ambos convivem, fundem- se e se interpenetram.

  11. Unión del magreb, un caso de regionalismo Sur-Sur

    Directory of Open Access Journals (Sweden)

    SofianE Bouhdiba

    2009-01-01

    Full Text Available Se exploran brevemente las fuerzas y limitaciones de la Unión del Magreb (UMA como una experiencia de regionalismo Sur-Sur, en el marco de mayor extensión. Se plantea la necesidad de que la UMA redireccione sus intereses, estrategias y alianzas hacia el sur, puesto que se ha vuelto un instrumento de intercambios comerciales con la Unión Europea y un eje estratégico de lucha contra el terrorismo para Estados Unidos. Además se invita a la misma UMA a que considere los alcances de instituciones de integración en América Latina y Asia a fin de fortalecerse como bloque.

  12. Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

    International Nuclear Information System (INIS)

    Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

    2014-01-01

    Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as 99 Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as 99 Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO 2 SO 4 ) with 994.2 g of 235 U (enrichment at 20%) providing an excess reactivity at operating temperature (40 o C) of 3.8 mk for a molality determined as 1.46 mol kg -1 for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 o C. Peak temperature and power were determined as 83 o C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the temperature and void coefficients are

  13. Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Canadian Forces (Canada)

    2014-07-01

    Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as {sup 99}Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as {sup 99}Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO{sub 2}SO{sub 4}) with 994.2 g of {sup 235}U (enrichment at 20%) providing an excess reactivity at operating temperature (40 {sup o}C) of 3.8 mk for a molality determined as 1.46 mol kg{sup -1} for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 {sup o}C. Peak temperature and power were determined as 83 {sup o}C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the

  14. Core monitoring at the WNP-2 reactor

    International Nuclear Information System (INIS)

    Skeen, D.R.; Torres, R.H.; Burke, W.J.; Jenkins, I.; Jones, S.W.

    1992-01-01

    The WNP-2 reactor is a 3,323-MW(thermal) boiling water reactor (BWR) that is operated by the Washington Public Power Supply System. The WNP-2 reactor began commercial operation in 1984 and is currently in its eighth cycle. The core monitoring system used for the first cycle of operation was supplied by the reactor vendor. Cycles 2 through 6 were monitored with the POWERPLEX Core Monitoring Software System (CMSS) using the XTGBWR simulation code. In 1991, the supply system upgraded the core monitoring system by installing the POWERPLEX 2 CMSS prior to the seventh cycle of operation for WNP-2. The POWERPLEX 2 CMSS was developed by Siemens Power Corporation (SPC) and is based on SPC's advanced state-of-the-art reactor simulator code MICROBURN-B. The improvements in the POWERPLEX 2 system are possible as a result of advances in minicomputer hardware

  15. Effets de l'audit clinique basé sur des critères sur de la qualité de la ...

    African Journals Online (AJOL)

    Effets de l'audit clinique basé sur des critères sur de la qualité de la prise en charge de la prééclampsie sévère dans le Département de Gynécologie Obstétrique du Centre Hospitalier Universitaire Yalgado Ouédraogo, Ouagadougou (Burkina Faso). Sibraogo Kiemtoré, Adama Dembélé, Adama Ouattara, Hyacinthe1,2 ...

  16. TA-2 Water Boiler Reactor Decommissioning Project

    International Nuclear Information System (INIS)

    Durbin, M.E.; Montoya, G.M.

    1991-06-01

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m 3 of low-level solid radioactive waste and 35 m 3 of mixed waste. 15 refs., 25 figs., 3 tabs

  17. Fast wave current drive in reactor scale tokamaks

    International Nuclear Information System (INIS)

    Moreau, D.

    1992-01-01

    The IAEA Technical Committee Meeting on Fast Wave Current Drive in Reactor Scale Tokamaks, hosted by the Commissariat a l'Energie Atomique (CEA), Departement de Recherches sur la Fusion Controlee (Centres d'Etudes de Cadarache, under the Euratom-CEA Association for fusion) aimed at discussing the physics and the efficiency of non-inductive current drive by fast waves. Relevance to reactor size tokamaks and comparison between theory and experiment were emphasized. The following topics are described in the summary report: (i) theory and modelling of radiofrequency current drive (theory, full wave modelling, ray tracing and Fokker-Planck calculations, helicity injection and ponderomotive effects, and alternative radio-frequency current drive effects), (ii) present experiments, (iii) reactor applications (reactor scenarios including fast wave current drive; and fast wave current drive antennas); (iv) discussion and summary. 32 refs

  18. EBR-2 [Experimental Breeder Reactor-2] test programs

    International Nuclear Information System (INIS)

    Sackett, J.I.; Lehto, W.K.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.; Hill, D.J.

    1990-01-01

    The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development, (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development, advanced control system development, plant diagnostics development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

  19. Dynamics of metallic contaminants at a basin scale--Spatial and temporal reconstruction from four sediment cores (Loire fluvial system, France).

    Science.gov (United States)

    Dhivert, E; Grosbois, C; Courtin-Nomade, A; Bourrain, X; Desmet, M

    2016-01-15

    From the 19th century, the Loire basin (France) presents potentially pollutant activities such as mining and heavy industries. This paper shows spatio-temporal distribution of trace elements in sediments at a basin-scale, based on a comparison of archived temporal signals recorded in four sedimentary cores. Anthropogenic sources contributing to sediment contamination are also characterized, using geochemical signatures recorded in river bank sediments of the most industrialized tributaries. This study highlights upstream-downstream differences concerning recorded contamination phases in terms of spatial influence and temporality of archiving processes. Such differences were related to (i) various spatial influences of contamination sources and (ii) polluted sediments dispersion controlled by transport capacity of metal-carrier phases and hydrosedimentary dynamics. Copyright © 2015 Elsevier B.V. All rights reserved.

  20. BR2 Reactor: Irradiation of fuels

    International Nuclear Information System (INIS)

    Verwimp, A.

    2005-01-01

    Safe, reliable and economical operation of reactor fuels, both UO 2 and MOX types, requires in-pile testing and qualification up to high target burn-up levels. In-pile testing of advanced fuels for improved performance is also mandatory. The objectives of research performed at SCK-CEN are to perform Neutron irradiation of LWR (Light Water Reactor) fuels in the BR2 reactor under relevant operating and monitoring conditions, as specified by the experimenter's requirements and to improve the on-line measurements on the fuel rods themselves

  1. Más allá de los mitos: análisis de la Cooperación Sur-Sur y Norte-Sur en el Ecuador. Sector Educación, período 2003- 2008

    OpenAIRE

    Escobar Sánchez, Wladimir Alexander

    2012-01-01

    La presente tesis de maestría analiza a la cooperación Norte-Sur y Sur-Sur como los dos principales modelos de funcionamiento de la cooperación hoy en día, a través de dos programas de ayuda internacional en el sector educación, en el período 2003-2008. El uno referente a la cooperación Norte-Sur, y el otro a la cooperación Sur-Sur. El propósito que presenta este trabajo académico es explicar a la cooperación internacional al desarrollo tomando en consideración a la teoría real...

  2. Étude sur l'entrepreneuriat dalit : Regard sur 25 % de la population ...

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

    Étude sur l'entrepreneuriat dalit : Regard sur 25 % de la population indienne. Cette étude, pilotée par Udit Raj, député du parlement indien, aide à mieux comprendre les contraintes que rencontrent les entrepreneurs dalits. Elle permettra de sonder 12 000 entrepreneurs dalits dans 14 états et de recueillir des données ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  5. Focus - Le développement de la méthanisation dans l’Ouest de la France

    Directory of Open Access Journals (Sweden)

    LE GUEN, Gaëlle ; DAMIANO, Armelle

    2013-10-01

    Full Text Available Les régions Pays de la Loire et Bretagne sont les premières régions d’élevage en France, avec une forte présence des industries agro-alimentaires. Face à ce constat, ces deux régions ont un fort potentiel de développement de la méthanisation. Les schémas régionaux climat air énergie (SRCAE se sont penchés sur cette question. Des études sur les filières de méthanisation ont été réalisées dans ce cadre, et les principales données issues de ces études sont présentées ici.

  6. Ageing management of the BR2 research reactor

    International Nuclear Information System (INIS)

    Verpoortem, J. R.; Van Dyck, S.

    2014-01-01

    At the Belgian nuclear research centre (SCK.CEN) several test reactors are operated. Among these, Belgian Reactor 2 (BR2) is the largest Material Test Reactor (MTR). This water-cooled, beryllium moderated reactor with a maximum thermal power of 100 MW became operational in 1962. Except for two major refurbishment campaigns of one year each, this reactor has been operated continuously over the past 50 years, with a frequency of 5-12 cycles per year. At present, BR2 is used for different research activities, the production of medical isotopes, the production of n-doped silicon and various training and education activities. (Author)

  7. Regional strategy of energy transition. The regional strategy for energy transition in Pays-de-la-Loire for 2014-2020

    International Nuclear Information System (INIS)

    Auxiette, Jacques; Clergeau, Christophe; Bouchaud, Emmanuelle

    2014-04-01

    As the Pays-de-la-Loire region has been committed for three years in the preparation for energy transition, this publication first recalls the main objectives to be reached by 2050 regarding energy consumption, electric power consumption, oil consumption by the transport sector, and greenhouse gas emissions. It outlines the need for a national strategy on the long term for energy transition, and presents the adopted approach for the elaboration of such a regional strategy, based on several experiments. The main axes of this strategy are then presented: to better and less consume energy (through thermal renovation, sustainable mobility, energy efficiency, energy saving behaviours), to make energy transition the engine of territory development (through a support to sectors, the development of regional energy production, and optimisation of consumptions and productions), and to elaborate tools for cooperative action

  8. Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

    Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

  9. Shutdown channels and fitted interlocks in atomic reactors; Chaines de securite et verrouillages installes sur les piles atomiques

    Energy Technology Data Exchange (ETDEWEB)

    Furet, J; Landauer, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    This catalogue consists of tables (one per reactor) giving the following information: number and type of detectors, range of the shutdown channels, nature of the associated electronics, thresholds setting off the alarms, fitted interlocks. These cards have been drawn up with a view to an examination of the reactors safety by the 'Reactor Safety Sub-Commission', they take into account the latest decisions. The reactors involved in this review are: Azur, Cabri, Castor-Pollux, Cesar-Marius-2, Edf-2, EL3, EL4, Eole, G1, G2-G3, Harmonie, Isis, Masurca, Melusine, Minerve, Osiris, Pegase, Peggy, PAT, Rapsodie, SENA, Siloe, Siloette, Triton-Nereide, and Ulysse. (authors) [French] Ce catalogue est compose d'un ensemble de tableaux (a raison de un tableau par pile) donnant les renseignements suivants: nombre et nature des detecteurs, dynamique des chaines, nature de l'electronique associee, seuils provoquant des actions de securite, verrouillages installes. Ces fiches ont ete etablies en vue de l'examen de la securite des piles par la 'Sous-Commission de Surete des Piles', et tiennent compte des decisions de celle-ci. Les reacteurs concernes sont: Azur, Cabri, Cator-Pollux, Cesar-Marius-2, Edf-2, EL3, EL4, Eole, G1, G2-G3, Harmonie, Isis, Masurca, Melusine, Minerve, Osiris, Pegase, Peggy, PAT, Rapsodie, SENA, Siloe, Siloette, Triton-Nereide, et Ulysse. (auteurs)

  10. Étude du Partenariat de recherche sur l'influenza aviaire en Asie sur ...

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

    Étude du Partenariat de recherche sur l'influenza aviaire en Asie sur l'efficacité des mesures de lutte. L'influenza aviaire hautement pathogène (H5N1) est une grave maladie qui touche la volaille et contamine les êtres humains dans une faible proportion. L'Organisation mondiale de la santé croit que le virus pourrait subir ...

  11. Action de Paenibacillus polymyxa SGK2 sur quelques champignons de la fusariose du blé dur (Triticum durum en Algérie

    Directory of Open Access Journals (Sweden)

    Lamia Lounaci

    2014-05-01

    Full Text Available Les tests ont porté sur l’action de P. polymyxa SGK2 à l’égard de F. graminearum, F. culmorum, F. verticillioides et M. nivale agents de la fusariose du blé dur en Algérie. La technique de confrontation directe en boîtes de Petri met en évidence une action inhibitrice caractérisée par un ralentissement de la croissance mycélienne. Après 7 jours d’incubation, un arrêt à distance des colonies du pathogène est observé. Nous étions également attachés à rechercher le (ou les moyen utilisé par P. polymyxa SGK2 pour inhiber la croissance des mycètes tests. Cette capacité naturelle agit par la synthèse d'une (ou des substance constitutive inhibitrice de la croissance des quatre champignons sur le milieu King B, d'une (ou des substance inductible inhibitrice de la croissance du F. culmorum et F. graminearum sur le même milieu, et d'une (ou des substance volatile inhibitrice de la croissance des quatre mycètes sur les milieux King B et PDA.

  12. BR2 reactor neutron beams

    International Nuclear Information System (INIS)

    Neve de Mevergnies, M.

    1977-01-01

    The use of reactor neutron beams is becoming increasingly more widespread for the study of some properties of condensed matter. It is mainly due to the unique properties of the ''thermal'' neutrons as regards wavelength, energy, magnetic moment and overall favorable ratio of scattering to absorption cross-sections. Besides these fundamental reasons, the impetus for using neutrons is also due to the existence of powerful research reactors (such as BR2) built mainly for nuclear engineering programs, but where a number of intense neutron beams are available at marginal cost. A brief introduction to the production of suitable neutron beams from a reactor is given. (author)

  13. Innovative Approach to Validation of Ultraviolet (UV) Reactors for Disinfection in Drinking Water Systems

    Science.gov (United States)

    Slide presentation at Conference: ASCE 7th Civil Engineering Conference in the Asian Region. USEPA in partnership with the Cadmus Group, Carollo Engineers, and other State & Industry collaborators, are evaluating new approaches for validating UV reactors to meet groundwater & sur...

  14. Fission product release from SLOWPOKE-2 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Harnden-Gillis, A M.C. [Queen` s Univ., Kingston, ON (Canada). Dept. of Physics

    1994-12-31

    Increasing radiation fields at several SLOWPOKE-2 reactors fuelled with highly enriched uranium aluminum alloy fuel have begun to interfere with the daily operation of these reactors. To investigate this phenomenon, samples of reactor container water and gas from the headspace were obtained at four SLOWPOKE-2 reactor facilities and examined by gamma ray spectroscopy methods. These radiation fields are due to the circulation of fission products within the reactor container vessel. The most likely source of the fission product release is an area of uranium-bearing material exposed to the coolant at the end weld line which originated at the time of fuel fabrication. The results of this study are compared with observations from an underwater visual examination of one core and the metallographic examination of archived fuel elements. 19 refs., 4 tabs., 8 figs.

  15. [Respiratory allergies among bakers and pastry cooks: epidemiologic survey done in 1991 by the occupational physicians of the Loire-Atlantique].

    Science.gov (United States)

    Anton, M; Bataille, A; Mollat, F; Bobe, M; Bonneau, C; Caramaniam, M N; Géraut, C; Dupas, D

    1995-01-01

    The aim was to study the prevalence of respiratory allergy (rhinitis and asthma) in a population of bakers and pastrycooks. In 1991, 485 bakers and pastry cooks were examined by 27 work-physicians of Loire-Atlantic. The investigation was composed of a standardised questionnaire (signs of respiratory function, atopic history, smoking of tobacco ...), a clinical examination, and tests of respiratory function. An allergy assessment was made of all subjects with symptoms. 14.4% of subjects had rhinitis and 6.4% asthma. Development of these pathologies was clearly job-related for 2/3 of those with rhinitis and more than half of the asthmatics (55%). Occupational rhinitis and asthma were significantly more frequent in bakers than in pastrycooks and were linked to atopic history. Occupational asthma was associated with length of exposure to flour and with occupational rhinitis. In conclusion, these findings are comparable with or a little less than those that have been reported in occupational literature. They under-estimate the importance of the problem because of the occupational selection effect that is associated with these pathologies. Rhinitis and asthma are 1.5 to 3 time more common in bakers than in pastrycooks.

  16. Sur la plurifonctionnalité du discours direct

    OpenAIRE

    Cigada Sara

    2012-01-01

    La comparaison entre les résultats de nombreux travaux sur le dialogue dans le texte littéraire, sur l’attestation linguistique de la subjectivité, sur la fonction argumentative des émotions dans le discours et sur les effets de polyphonie, suggère que la structure sémiotique et linguistique du discours direct (DD) se trouve au croisement stratégique de plusieurs axes de la construction discursive. Nous étudions donc l’insertion du DD dans le discours (cf. Rosier 2008: Le discours rapporté en...

  17. Annual public information report about the Belleville-sur-Loire nuclear facilities - 2015. This report is written in compliance with articles L. 125-15 and L125-16 of the French environment code

    International Nuclear Information System (INIS)

    2016-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2015, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  18. Pressurized water reactor simulator. Workshop material. 2. ed

    International Nuclear Information System (INIS)

    2005-01-01

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development. And the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21, 2nd edition, 'WWER-1000 Reactor Simulator' (2005). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23, 2nd edition, 'Boiling Water Reactor Simulator' (2005). This report consists of course material for workshops using a pressurized water reactor simulator

  19. A calculation method of available soil water content : application to viticultural terroirs mapping of the Loire valley

    Directory of Open Access Journals (Sweden)

    Etienne Goulet

    2004-12-01

    Full Text Available Vine water supply is one of the most important elements in the determination of grape composition and wine quality. Water supply conditions are in relation with available soil water content, therefore this one has to be determined when vineyard terroir mapping is undertaken. The available soil water content depends on soil factors like water content at field capacity, water content at the permanent wilting point, apparent density and rooting depth. The aim of this study is to seek the relationship between these factors and a simple soil characteristic such as texture which could be easily measurable in routine cartography. Study area is located in the Loire valley, in two different geological regions. First results indicate that it is possible to determine available soil water content from clay percentage, then from soil texture. These results also show that available soil water content algorithms differ with geological properties. This calculation can be used at each auger boring and results can be spatialised within a Geographical Information System that allows the production of available water content maps.

  20. Sur un deplacement de valeurs: traire et tirer

    Directory of Open Access Journals (Sweden)

    André Burger

    1972-12-01

    Full Text Available L'étymologie de firer est inconnue. Celie que le regretté W. von Wart burg a ern pouvoir avancer est inacceptable: firer serait sorti de marty rier par la grâce d'une fausse coupure mar tirier. Il est plus qu'improbable que cette «étymologie populaire» eût pu se produire si la langue ne possédait pas au préalable un verbe tirier. Au surplus aucun fait n'appuie cette hypothèse. Le FEW, t. VI, 1, p. 396, donne bien pour firer le sens de «torturer sur un treteam>, au XIIIe siècle, et p. 403, «démembrer en faisant tirer les quatre membles par des chevaux» et «torturer (qn en l'étendant sur un tréteau” au XIVe siècle; ces sens sont évidemment trop tardifs pour permettre des conclusions sur l'origine de firer, d'autant plus qu'ils s'expliquent sans peine par la valeur normale du mot, attesté dès la Chanson de Roland, sans aucun rapport avec martirie, mot savant de clerc, qui, dans le même texte s'applique deux fois sur quatre exemples aux Sarrasins, vv. 501 et 1467, où il ne signifie pas «martyre» mais <sur son étymologie et non sur les textes, que tirer aurait à l'origine »einen starken affektiven unterton« (FEW XIII, 2, p. 185. L'étude des exemples de la Chanson de Roland, confrontés avec ceux de traire, nons amènera à une conclusion toute différente.

  1. Advances in Reactor Physics, Mathematics and Computation. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    These proceedings of the international topical meeting on advances in reactor physics, mathematics and computation, Volume 2, are divided into 7 sessions bearing on: - session 7: Deterministic transport methods 1 (7 conferences), - session 8: Interpretation and analysis of reactor instrumentation (6 conferences), - session 9: High speed computing applied to reactor operations (5 conferences), - session 10: Diffusion theory and kinetics (7 conferences), - session 11: Fast reactor design, validation and operating experience (8 conferences), - session 12: Deterministic transport methods 2 (7 conferences), - session 13: Application of expert systems to physical aspects of reactor design and operation.

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

    Energy Technology Data Exchange (ETDEWEB)

    Jacquet, P.

    2011-05-23

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

  3. Effets des electrons secondaires sur l'ADN

    Science.gov (United States)

    Boudaiffa, Badia

    Les interactions des electrons de basse energie (EBE) representent un element important en sciences des radiations, particulierement, les sequences se produisant immediatement apres l'interaction de la radiation ionisante avec le milieu biologique. Il est bien connu que lorsque ces radiations deposent leur energie dans la cellule, elles produisent un grand nombre d'electrons secondaires (4 x 104/MeV), qui sont crees le long de la trace avec des energies cinetiques initiales bien inferieures a 20 eV. Cependant, il n'y a jamais eu de mesures directes demontrant l'interaction de ces electrons de tres basse energie avec l'ADN, du principalement aux difficultes experimentales imposees par la complexite du milieu biologique. Dans notre laboratoire, les dernieres annees ont ete consacrees a l'etude des phenomenes fondamentaux induits par impact des EBE sur differentes molecules simples (e.g., N2, CO, O2, H2O, NO, C2H 4, C6H6, C2H12) et quelques molecules complexes dans leur phase solide. D'autres travaux effectues recemment sur des bases de l'ADN et des oligonucleotides ont montre que les EBE produisent des bris moleculaires sur les biomolecules. Ces travaux nous ont permis d'elaborer des techniques pour mettre en evidence et comprendre les interactions fondamentales des EBE avec des molecules d'interet biologique, afin d'atteindre notre objectif majeur d'etudier l'effet direct de ces particules sur la molecule d'ADN. Les techniques de sciences des surfaces developpees et utilisees dans les etudes precitees peuvent etre etendues et combinees avec des methodes classiques de biologie pour etudier les dommages de l'ADN induits par l'impact des EBE. Nos experiences ont montre l'efficacite des electrons de 3--20 eV a induire des coupures simple et double brins dans l'ADN. Pour des energies inferieures a 15 eV, ces coupures sont induites par la localisation temporaire d'un electron sur une unite moleculaire de l'ADN, ce qui engendre la formation d'un ion negatif transitoire

  4. Présentations sur le Théme 2: Les instruments régionaux de ...

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

    4 nov. 2010 ... Retrouvez en bas de cette page en format PDF les présentations effectuées lors de la session 2 du mercredi 9 décembre sur le thème: Les instruments régionaux de financement et la lutte contre la pauvreté. Notes de cadrage : 1 - Intégration des services financiers dans les stratégies de la lutte contre la ...

  5. Neutron transport. Physics and calculation of nuclear reactors with applications to pressurized water reactors and fast neutron reactors. 2 ed.

    International Nuclear Information System (INIS)

    Bussac, J.; Reuss, P.

    1985-01-01

    This book presents the main physical bases of neutron theory and nuclear reactor calculation. 1) Interactions of neutrons with matter and basic principles of neutron transport; 2) Neutron transport in homogeneous medium and the neutron field: kinetic behaviour, slowing-down, resonance absorption, diffusion equation, processing methods; 3) Theory of a reactor constituted with homogeneous zones: critical condition, kinetics, separation of variables, calculation and neutron balance of the fundamental mode, one-group and multigroup theories; 4) Study of heterogeneous cell lattices: fast fission factor, resonance absorption, thermal output factor, diffusion coefficient, computer codes; 5) Operation and control of reactors: perturbation theory, reactivity, fuel properties evolution, poisoning by fission products, calculation of a reactor and fuel management; 6) Study of some types of reactors: PWR and fast breeder reactors, the main reactor types of the present French program [fr

  6. Mapping regional soil water erosion risk in the Brittany-Loire basin for water management agency

    Science.gov (United States)

    Degan, Francesca; Cerdan, Olivier; Salvador-Blanes, Sébastien; Gautier, Jean-Noël

    2014-05-01

    Soil water erosion is one of the main degradation processes that affect soils through the removal of soil particles from the surface. The impacts for environment and agricultural areas are diverse, such as water pollution, crop yield depression, organic matter loss and reduction in water storage capacity. There is therefore a strong need to produce maps at the regional scale to help environmental policy makers and soil and water management bodies to mitigate the effect of water and soil pollution. Our approach aims to model and map soil erosion risk at regional scale (155 000 km²) and high spatial resolution (50 m) in the Brittany - Loire basin. The factors responsible for soil erosion are different according to the spatial and time scales considered. The regional scale entails challenges about homogeneous data sets availability, spatial resolution of results, various erosion processes and agricultural practices. We chose to improve the MESALES model (Le Bissonnais et al., 2002) to map soil erosion risk, because it was developed specifically for water erosion in agricultural fields in temperate areas. The MESALES model consists in a decision tree which gives for each combination of factors the corresponding class of soil erosion risk. Four factors that determine soil erosion risk are considered: soils, land cover, climate and topography. The first main improvement of the model consists in using newly available datasets that are more accurate than the initial ones. The datasets used cover all the study area homogeneously. Soil dataset has a 1/1 000 000 scale and attributes such as texture, soil type, rock fragment and parent material are used. The climate dataset has a spatial resolution of 8 km and a temporal resolution of mm/day for 12 years. Elevation dataset has a spatial resolution of 50 m. Three different land cover datasets are used where the finest spatial resolution is 50 m over three years. Using these datasets, four erosion factors are characterized and

  7. 14 Oxydation du phenol sur un catalyseur à base de Fer supporté ...

    African Journals Online (AJOL)

    AKA BOKO

    Oxydation du phenol sur un catalyseur à base de Fer supporté sur une argile marocaine. Noura LAHBABI1*, Zakia RAIS2, M. HAJJAJI 3 et S. KACIM3. 1 Laboratoire d'ingénierie des matériaux organométalliques et moléculaire. Faculté des. Sciences Dhar El Mehrez, Fès, Maroc. 2 Laboratoire d'analyses physico-chimiques ...

  8. TPDWR2: thermal power determination for Westinghouse reactors, Version 2. User's guide

    International Nuclear Information System (INIS)

    Kaczynski, G.M.; Woodruff, R.W.

    1985-12-01

    TPDWR2 is a computer program which was developed to determine the amount of thermal power generated by any Westinghouse nuclear power plant. From system conditions, TPDWR2 calculates enthalpies of water and steam and the power transferred to or from various components in the reactor coolant system and to or from the chemical and volume control system. From these results and assuming that the reactor core is operating at constant power and is at thermal equilibrium, TPDWR2 calculates the thermal power generated by the reactor core. TPDWR2 runs on the IBM PC and XT computers when IBM Personal Computer DOS, Version 2.00 or 2.10, and IBM Personal Computer Basic, Version D2.00 or D2.10, are stored on the same diskette with TPDWR2

  9. Once-through CANDU reactor models for the ORIGEN2 computer code

    International Nuclear Information System (INIS)

    Croff, A.G.; Bjerke, M.A.

    1980-11-01

    Reactor physics calculations have led to the development of two CANDU reactor models for the ORIGEN2 computer code. The model CANDUs are based on (1) the existing once-through fuel cycle with feed comprised of natural uranium and (2) a projected slightly enriched (1.2 wt % 235 U) fuel cycle. The reactor models are based on cross sections taken directly from the reactor physics codes. Descriptions of the reactor models, as well as values for the ORIGEN2 flux parameters THERM, RES, and FAST, are given

  10. Agir sur la langue pour agir sur le monde : Micropolitiques linguistiques autogérées du genre dans les brochures libertaires

    OpenAIRE

    Abbou, Julie

    2015-01-01

    La dimension agissante de la langue sur le monde entraîne avec elle, comme un appel d'air, l'action sur la langue elle-même, et l'action sur la langue n'est jamais loin de se faire action politique. Les politiques linguistiques de féminisation en sont un exemple, où l'action politique se concentre sur la catégorisation du genre. Dans de nombreux cas, la politique linguistique se fait planification linguistique, cherchant de nouvelles normes. Dans de nombreux cas, mais pas toujours. Il existe ...

  11. Radiation protection at the RA Reactor in 1988, Part -2, RA reactor annual report

    International Nuclear Information System (INIS)

    Ninkovic, M.; Ajdacic, N.; Zaric, M.; Vukovic, Z.

    1988-01-01

    Radiation protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor and radiation protection; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Decontamination and relevant actions, collecting and treatment of fluid effluents; and and solid radioactive wastes [sr

  12. Irradiation effects on Zr-2.5Nb in power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Song, C., E-mail: Carol.Song@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2016-06-15

    Zirconium alloys are widely used as structural materials in nuclear applications because of their attractive properties such as a low absorption cross-section for thermal neutrons, excellent corrosion resistance in water, and good mechanical properties at reactor operating temperatures. Zr-2.5Nb is one of the most commonly used zirconium alloys and has been used for pressure tube materials in CANDU (Canada Deuterium Uranium) and RBMK (Reaktor Bolshoy Moshchnosti Kanalnyy, 'High Power Channel-type Reactor') reactors for over 40 years. In a recent report from the Electric Power Research Institute, Zr-2.5Nb was identified as one of the candidate materials for use in normal structural applications in light-water reactors owing to its increased resistance to irradiation-induced degradation as compared with currently used materials. Historically, the largest program of in-reactor tests on zirconium alloys was performed by Atomic Energy of Canada Limited. Over many years of in-reactor testing and CANDU operating experience with Zr- 2.5Nb, extensive research has been conducted on the irradiation effects on its microstructures, mechanical properties, deformation behaviours, fracture toughness, delayed hydride cracking, and corrosion. Most of the results on Zr-2.5Nb obtained from CANDU experience could be used to predict the material performance under light water reactors. This paper reviews the irradiation effects on Zr-2.5Nb in power reactors (including heavy-water and light-water reactors) and summarizes the current state of knowledge. (author)

  13. The action of the project coordinator with respect to reactor safety

    International Nuclear Information System (INIS)

    Leclercq, Jacques

    1981-01-01

    Before describing the various actions of the project coordinator (EDF) entrusted with the building of nuclear power stations, with respect to reactor safety in France, the definition of reactor safety and the various participants are mentioned first. These participants are: the Government Departments and the Experts involved (the Department of Nuclear Safety of the 'Institut de Protection et de Surete Nucleaire' forming the first technical support) and the applicant, namely the EDF. The reactor safety actions of the project coordinator are defined as from the following components: 1 - The targets laid down with respect to safety, the final objective being the protection of workers and the public against the potential dangers of the installations, principally against radiation. 2 - The safety methodology at the design stage of the power station: 'barrier' method, defence method in depth at three levels, lines of assurance method, and probabilistic method. 3 - Safety actions at the construction stage within the context of an assurance of quality programe. 4 - Safety at the trials, commissioning and operating stage, with the backing of the 'Groupe Operationnel de Demarrage (G.O.D.)' and the 'Commission d'Essais sur Site (C.E.S.)'. An initial balance sheet of the reactor safety actions for the PWR units built by the EDF is presented [fr

  14. Ecology of Legionella within water cooling circuits of nuclear power plants along the French Loire River

    International Nuclear Information System (INIS)

    Jakubek, Delphine

    2012-01-01

    The cooling circuits of nuclear power plants, by their mode of operating, can select thermophilic microorganisms including the pathogenic organism Legionella pneumophila. To control the development of this genus, a disinfection treatment of water cooling systems with monochloramine can be used. To participate in the management of health and environmental risks associated with the physico-chemical and microbiological modification of water collected from the river, EDF is committed to a process of increasing knowledge about the ecology of Legionella in cooling circuits and its links with its environment (physical, chemical and microbiological) supporting or not their proliferation. Thus, diversity and dynamics of culturable Legionella pneumophila were determined in the four nuclear power plants along the Loire for a year and their links with physico-chemical and microbiological parameters were studied. This study revealed a high diversity of Legionella pneumophila subpopulations and their dynamic seems to be related to the evolution of a small number of subpopulations. Legionella subpopulations seem to maintain strain-specific relationships with biotic parameters and present different sensitivities to physico-chemical variations. The design of cooling circuits could impact the Legionella community. The use of monochloramine severely disrupts the ecosystem but does not select biocide tolerant subpopulations. (author)

  15. IGORR 2: Proceedings of the 2. meeting of the International Group On Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-07-01

    The International group on Research Reactors was formed to facilitate the sharing of knowledge and experience among those institutions and individuals who are actively working to design, build, and promote new research reactors or to make significant upgrades to existing facilities. Sessions during this second meeting were devoted to research reactor reports (GRENOBLE reactor, FRM-II, HIFAR, PIK, reactors at JAERI, MAPLE, ANS, NIST, MURR, TRIGA, BR-2, SIRIUS 2); other neutron sources; and two workshops were dealing with research and development results and needs and reports on progress in needed of R and D areas identified at IGORR 1.

  16. IGORR 2: Proceedings of the 2. meeting of the International Group On Research Reactors

    International Nuclear Information System (INIS)

    1992-01-01

    The International group on Research Reactors was formed to facilitate the sharing of knowledge and experience among those institutions and individuals who are actively working to design, build, and promote new research reactors or to make significant upgrades to existing facilities. Sessions during this second meeting were devoted to research reactor reports (GRENOBLE reactor, FRM-II, HIFAR, PIK, reactors at JAERI, MAPLE, ANS, NIST, MURR, TRIGA, BR-2, SIRIUS 2); other neutron sources; and two workshops were dealing with research and development results and needs and reports on progress in needed of R and D areas identified at IGORR 1

  17. Architectures fromagères en pays d’Auge

    Directory of Open Access Journals (Sweden)

    Yannick Lecherbonnier

    2012-02-01

    Full Text Available Camemberts, livarots et pont-l’évêque participent encore largement à l'identification du pays d'Auge. Entre Saint-Pierre-sur-Dives et Livarot, de nombreux hâloirs, ou pièces d’affinage, témoignent de l’importance d’une production fermière aujourd’hui révolue et souvent peu documentée. Une simple lecture architecturale de ces édifices permet cependant de déterminer quels fromages y ont été affinés. Elle remet aussi en cause les principes couramment admis concernant leur aménagement, en particulier la disposition de leurs ouvertures, et montre que les prescriptions techniques émises au XIXe siècle et relayées par les sociétés savantes, sont restées lettre morte.Camemberts, livarots and pont-l’évêque are still largely part of the characterizing components of the pays d’Auge. Between Saint-Pierre-sur-Dives and Livarot, many hâloirs or cheese maturing rooms attest the importance of that bygone and often poorly documented agricultural production. A mere architectural examination of these buildings allows us nevertheless to determine which kind of cheese had been matured in which building. It gives us also a whole new perspective on the commonly received principles about the arrangement of the buildings, especially the setting of their apertures, and points the fact that the technical prescriptions from the 19th century that have been spread through the scientific societies have had no follow-up.

  18. The reactor Cabri; La pile cabri

    Energy Technology Data Exchange (ETDEWEB)

    Ailloud, J; Millot, J P [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    circumstances... - experimental investigations on power excursions linked with precise initial conditions: the aim of this work is to define the basis for theoretical research, and the limits beyond which the risks of explosion cease to be negligible. The research work will be done so as to enable checking with outside reactor experiments and to continue them in the explosion field. - studies of the behaviour of the reactor control-instrumentation. - experimental investigations related with transient operation with initial short life (study of boiling, temperature measurements, vacuum pressure and fraction...) with the aim of defining the hypotheses of a theory on swimming-pool reactor kinetics related to heat transfer phenomena, - investigations of the behaviour of fuels in reactors (these experiments are planned to be carried out in loops) Preliminary experimental results. CABRI went critical on the 21 December 1963. The first transient experiments are expected for March 1964. (authors) [French] II devenait necessaire de construire en France une pile qui permette d'etudier les conditions de fonctionnement des installations futures, de choisir, tester et mettre au point les dispositifs de securite a adopter. On a choisi une pile a eau, type de pile qui correspond aux constructions les plus nouvelles du CEA en matiere de piles laboratoire ou d'universite; il importe en effet de pouvoir evaluer les risques presentes et d'etudier les possibilites d'augmentation de puissance constamment demandees par les utilisateurs: il est particulierement interessant d'eclaircir les phenomenes d'oscillation de puissance et les risques de calefaction (burn out). Les programmes de travaux sur CABRI seront harmonises avec les travaux effectues sur les Spert americains de meme type; lors de sa construction des contacts fructueux ont ete etablis avec les specialistes americains qui ont defini les premiers de ces reacteurs. La communication donne une description sommaire de la pile et decrit le

  19. Kunstiakadeemia arhitektuuritudengid Pariisis / Artur Staškevitš, Laura Linsi, Roland Reemaa ... [jt.] ; üles kirjutanud Margit Mutso

    Index Scriptorium Estoniae

    2011-01-01

    Eesti Kunstialadeemia arhitektuuri eriala tudengite muljeid Pariisist ja osalemisest Pariisi Belleville'i arhitektuurikõrgkoolis (Ecole Nationale Supérieure d'Architecture Paris-Belleville) toimunud töötoas. Tuli kavandada üliõpilaselamu elitaarsesse Marais' piirkonda, leida üliõpilaselamise mudel

  20. Eesti arhitektuur Eesti kultuurifestivalil Pariisis / Margit Mutso

    Index Scriptorium Estoniae

    Mutso, Margit, 1966-

    2011-01-01

    25. ja 26. novembril Pariisi Belleville'i arhitektuurikõrgkoolis (Ecole Nationale Supérieure d'Architecture Paris-Belleville) toimunud seminaridest teemadel "Ehitada kaitsealusesse piirkonda", "Tööstussadamate muutumine", "Noored arhitektid. Võistlus kui meetod". Avati Eesti eramajade näitus "50 maja"

  1. Characterization of the Three Mile Island Unit-2 reactor building atmosphere prior to the reactor building purge

    International Nuclear Information System (INIS)

    Hartwell, J.K.; Mandler, J.W.; Duce, S.W.; Motes, B.G.

    1981-05-01

    The Three Mile Island Unit-2 reactor building atmosphere was sampled prior to the reactor building purge. Samples of the containment atmosphere were obtained using specialized sampling equipment installed through penetration R-626 at the 358-foot (109-meter) level of the TMI-2 reactor building. The samples were subsequently analyzed for radionuclide concentration and for gaseous molecular components (O 2 , N 2 , etc.) by two independent laboratories at the Idaho National Engineering Laboratory (INEL). The sampling procedures, analysis methods, and results are summarized

  2. Radiation protection at the RA Reactor in 1998, RA reactor annual report, Part -2

    International Nuclear Information System (INIS)

    Ninkovic, M.; Pavlovic, R.; Mandic, M.; Pavlovic, S.; Grsic, Z.

    1998-01-01

    Radiation protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Collecting and treatment of fluid effluents; and (4) radioactive wastes, decontamination and actions. Each of the category is described as a separate annex of this report [sr

  3. Present Status of Nitrogen Fixation by Reactor Radiation; Etat Actuel des Recherches sur l'oxydation directe de l'azote sous irradiation dans des reacteurs; Sovremennoe sostoyani opytov po okisleniyu azota izlucheniem iz reaktorov; Estado actual de las investigaciones sobre fijacion del nitrogeno por irradiacion en reactores

    Energy Technology Data Exchange (ETDEWEB)

    Harteck, P; Dondes, S [Rensselaer Polytechnic Institute, Troy, NY (United States)

    1960-07-15

    Investigations in nitrogen fixation by reactor radiation which have been carried out at Rensselear and Brookhaven National Laboratory for a number of years, have used the fission recoil energy directly as ionizing radiation by means of the dispersion of U{sup 235} in glass fibers about five microns in diameter. The effects of temperature, pressure and nitrogen-oxygen ratio on the G-value for nitrogen fixation have been determined and reported in the literature. A brief summary of this work is given. The above work has been done in static systems; more recent work has involved both static and flow systems. In static systems, major emphasis has been placed on the effect of radiation intensity especially at the kinetic radiation equilibrium. It has been found that the production of N0{sub 2} and N{sub 2}0 in 4:1 and 2:1 nitrogen-oxygen mixtures proceeds to the point of total oxygen consumption. A flow (cycling) system is now operating in a loop in the Brookhaven reactor. Data are presented on the effects of temperature, pressure, mixture ratio and radiation intensity which may be applied to the design of a future chemonuclear reactor. The present system is operating at 10 atmospheres and 150{sup o}C. The temperature is a function of the fission energy released in the glass fibers and the heat resistance of the loop. Another loop to operate at 50 - 75 atmospheres and 600{sup o}C is under construction. These loops make possible the evaluation of the characteristics of a continuous system, including the behaviour of the fission products released in the gas stream. The complicated kinetics of nitrogen oxidation are outlined in three stages: initial reactions in the systems, reactions after some fixed nitrogen has been produced, and finally the kinetics at radiation equilibrium. The conditions for the formation of N{sub 2}0{sub 3}, N{sub 2}0{sub 4} and O{sub 3} are considered, together with their effects and the overall process. (author) [French] Des recherches sur l

  4. Quelques noddees sur l’ecologie de la vedetation des dunes et sur la fonction de l’enraciment dans l’edification de dunes a la Cote Mediterraneenne de la France. I

    NARCIS (Netherlands)

    Boterenbrood, A.J.; Donsellaar-Ten Bokkel Huinink, van W.A.E.; Donselaar, van J.

    1956-01-01

    Dans la végétation des dunes du Languedoc J. BRAUN-BLANQUET (1952) distingue trois associations, à savoir; 1) l’Agropyretum mediterraneum parmi et sur les premières dunes basses; 2) l’Ammophiletum arundinaceae sur les dunes plus hautes; et 3) le Crucianelletum maritimae dans les dépressions et en

  5. Active species in a large volume N2-O2 post-discharge reactor

    International Nuclear Information System (INIS)

    Kutasi, K; Pintassilgo, C D; Loureiro, J; Coelho, P J

    2007-01-01

    A large volume post-discharge reactor placed downstream from a flowing N 2 -O 2 microwave discharge is modelled using a three-dimensional hydrodynamic model. The density distributions of the most populated active species present in the reactor-O( 3 P), O 2 (a 1 Δ g ), O 2 (b 1 Σ g + ), NO(X 2 Π), NO(A 2 Σ + ), NO(B 2 Π), NO 2 (X), O 3 , O 2 (X 3 Σ g - ) and N( 4 S)-are calculated and the main source and loss processes for each species are identified for two discharge conditions: (i) p = 2 Torr, f = 2450 MHz, and (ii) p = 8 Torr, f = 915 MHz; in the case of a N 2 -2%O 2 mixture composition and gas flow rate of 2 x 10 3 sccm. The modification of the species relative densities by changing the oxygen percentage in the initial gas mixture composition, in the 0.2%-5% range, are presented. The possible tuning of the species concentrations in the reactor by changing the size of the connecting afterglow tube between the active discharge and the large post-discharge reactor is investigated as well

  6. G 2 reactor project; Projet de pile a double fin: G 2

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The CEA actually constructs the G-2 reactor core working with natural uranium, which will use graphite as moderator, and gas under pressure as cooling fluid. This report presents the specificity of the new reactor: - the different elements of the reactor core, - the control and the security of the reactor, - the renewal of the fuel, - the biologic surrounding wall, - and the cooling circuit. (M.B.) [French] le Commissariat a l'Energie Atomique construit actuellement la pile G-2 a Uranium naturel, qui utilisera le graphite comme moderateur, et le gaz sous pression comme fluide de refroidissement. Ce rapport presente les specificite du nouveau reacteur: - les differents elements de la pile, - le controle et la securite du reacteur, - le renouvellement du combustible, - l'enceinte biologique, - et le circuit de refroidissement. (M.B.)

  7. Reactor handbook. 2. rev. ed.

    International Nuclear Information System (INIS)

    Lederer, B.J.; Wildberg, D.W.

    1992-01-01

    On the basis of the guidelines on expert knowledge, the book discusses the subjects of atomic physics, heat transfer, nuclear power plants, reactor materials, radiation protection, reactor safety, reactor instrumentation, and reactor operation, with special regard to nuclear power plants with LWR-type reactors. The book is intended for shift personnel, especially gang bosses, reactor operators, and control station operators: for this reason a practical and rather popular style has been chosen. However, the book will also be a manual for other operating personnel, personnel of producer companies, expert organisations, authorities, and students. It can be used as a textbook for staff training, a manual for the practice, and as accompanying book for teaching at nuclear engineering schools. (orig.) With 173 figs [de

  8. Annual report on JEN-1 and JEN-2 Reactors; Informe periodico de Reactores JEN-1 y JEN-2 correpondiente al ano 1972

    Energy Technology Data Exchange (ETDEWEB)

    Montes Ponce de Leon, J.

    1974-07-01

    In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

  9. The first metallurgical tests on plutonium; Premiers essais metallurgiques sur le plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Grison, E; Abramson, R; Anselin, F; Monti, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    Metallic plutonium was first prepared in France in January 1956, as soon as we had access to quantities of the order of several grams of plutonium, which had been extracted from the rods of the pile EL2 at Saclay. Since up to the present this reactor, of thermal power 2 000 kW, has been our only source of plutonium, we have so far only worked on experimental quantities sufficient for the basic tests but not for tests on a scale of possible applications. It is this work, carried out during this phase of preliminary research, which is described below. With the starting up of the plutonium extraction plant at Marcoule, where the reactor G1 has been operating at power for more than a year, we shall go on next to a another order of magnitude which will allow the manufacture and experimentation of prototype fuel elements. (author) [French] La premiere elaboration de plutonium metallique en France fut faite en janvier 1956, des que nous pumes disposer de quantites de plutonium de l'ordre de quelques grammes, qui avaient ete retires des barreaux de la pile EL2 de Saclay. Ce reacteur, d'une puissance thermique de 2 000 kW, ayant ete jusqu'a present notre seule source de plutonium, nous n'avons encore travaille que sur des quantites experimentales suffisantes pour les essais de base, mais non pour des essais a l'echelle d'applications possibles. Ce sont les travaux effectues pendant cette phase de recherches preliminaires qui seront evoques ci-dessous. Avec la mise eu route de l'usine d'extraction de plutonium de Marcoule, ou le reacteur G1 fonctionne en puissance depuis plus d'un an, nous allons passer prochainement a un autre ordre de grandeur, qui nous permettra la fabrication et l'experimentation d'elements combustibles prototypes. (auteur)

  10. Optimized Control Rods of the BR2 Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kalcheva, Silva; Koonen, E.

    2007-09-15

    At the present time the BR-2 reactor uses control elements with cadmium as neutron absorbing part. The lower section of the control element is a beryllium assembly cooled by light water. Due to the burn up of the lower end of the cadmium section during the reactor operation, the presently used rods for reactivity control of the BR-2 reactor have to be replaced by new ones. Considered are various types Control Rods with full active part of the following materials: cadmium (Cd), hafnium (Hf), europium oxide (Eu2O3) and gadolinium (Gd2O3). Options to decrease the burn up of the control rod material in the hot spot, such as use of stainless steel in the lower active part of the Control Rod are discussed. Comparison with the characteristics of the presently used Control Rods types is performed. The changing of the characteristics of different types Control Rods and the perturbation effects on the reactor neutronics during the BR-2 fuel cycle are investigated. The burn up of the Control Rod absorbing material, total and differential control rods worth, macroscopic and effective microscopic absorption cross sections, fuel and reactivity evolution are evaluated during approximately 30 operating cycles.

  11. Optimized Control Rods of the BR2 Reactor

    International Nuclear Information System (INIS)

    Kalcheva, Silva; Koonen, E.

    2007-01-01

    At the present time the BR-2 reactor uses control elements with cadmium as neutron absorbing part. The lower section of the control element is a beryllium assembly cooled by light water. Due to the burn up of the lower end of the cadmium section during the reactor operation, the presently used rods for reactivity control of the BR-2 reactor have to be replaced by new ones. Considered are various types Control Rods with full active part of the following materials: cadmium (Cd), hafnium (Hf), europium oxide (Eu2O3) and gadolinium (Gd2O3). Options to decrease the burn up of the control rod material in the hot spot, such as use of stainless steel in the lower active part of the Control Rod are discussed. Comparison with the characteristics of the presently used Control Rods types is performed. The changing of the characteristics of different types Control Rods and the perturbation effects on the reactor neutronics during the BR-2 fuel cycle are investigated. The burn up of the Control Rod absorbing material, total and differential control rods worth, macroscopic and effective microscopic absorption cross sections, fuel and reactivity evolution are evaluated during approximately 30 operating cycles.

  12. El (los Sur buscando al Sur. Una construcción entre estereotipos y realidad.

    Directory of Open Access Journals (Sweden)

    Mabel Franzone

    2010-11-01

    Full Text Available Todas las lecturas que podamos hacer del Sur, de sus propias representaciones, de aquellas vehiculizadas por el Norte, de sus creaciones, de sus reacciones, de su búsqueda constante de identidad, son lecturas de múltiples situaciones, que llaman a cruces insoslayables entre pueblos, entre distintas etnias, entre disciplinas, entre sentimientos que van desde el rechazo hasta la atracción casi magnética entre los dos hemisferios. Nuestra intención primera era la de reunir de manera aproximativa las problemáticas actuales de los Sur, ligadas a lo imaginario.

  13. Upgrading of the research reactors FRG-1 and FRG-2

    International Nuclear Information System (INIS)

    Krull, W.

    1981-01-01

    In 1972 for the research reactor FRG-2 we applied for a license to increase the power from 15 MW to 21 MW. During this procedure a public laying out of the safety report and an upgrading procedure for both research reactors - FRG-1 (5 MW) and FRG-2 - were required by the licensing authorities. After discussing the legal background for licensing procedures in the Federal Republic of Germany the upgrading for both research reactors is described. The present status and future licensing aspects for changes of our research reactors are discussed, too. (orig.) [de

  14. A Nitrogen-16 Power Channel in the Melusine Cooling Circuit; Chaine de puissance azote 16 sur le circuit de refrigeration de melusine

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    A power channel, which is to be used on Melusine, the 2 MW pool-type reactor built at Grenoble Nuclear Center, is described. It will be used for measuring of {sup 16}N activity of water after passage through the reactor core. The experimental system as well as the measuring instruments are described. Solutions to problems likely to arise are given. The experimental results show that this power measurement is free from neutron flux local deformations, from control rods position, and from experiments. The power indicated is to {+-}2% the same as the thermodynamic power. Since May 1962, this power channel is used as a reference for the operation of the reactor. It is also provided for on the Siloe 10 MW reactor. (author) [French] L'objet de ce rapport est la description d'une nouvelle chaine de puissance pour la pile piscine 'Melusine' de 2 MW du Centre d'etudes Nucleaires de Grenoble. Il s'agit de la mesure de l'activite en azote 16 de l'eau apres son passage dans le coeur du reacteur. Le dispositif experimental ainsi que les appareils de mesure y sont decrits. Les reponses aux differents problemes poses sont donnees. Les resultats experimentaux montrent que cette mesure de puissance est independante des deformations locales de flux de neutrons, de la position des barres de controle et des manipulations. La puissance indiquee par cette chaine est a 2 % pres identique a la puissance thermodynamique. Depuis mai 1962, elle est utilisee comme reference pour le pilotage de la pile. Elle est aussi prevue sur la pile 'Siloe' de 10 MW. (auteur)

  15. Power Reactor Design at Zero Power; Etudes de Reacteurs de Puissance, au Moyen de Machines de Puissance Zero; Konstruktsiya ehnergeticheskogo reaktora nulevoj moshchnosti; Diseno de Reactores Generadores con Ayuda de Reactores de Potencia Nula

    Energy Technology Data Exchange (ETDEWEB)

    Redman, W. C.; Plumlee, K. E.; Baird, Q. L. [Argonne National Laboratory, Argonne, IL (United States)

    1964-02-15

    reliance placed in the past on exponential and critical systems for fulfilling Argonne's responsibilities in reactor development. An indication of their future role is provided by a brief summary of the current and planned programmes for the existing members of, and anticipated additions to, Argonne's family of operating zero-power reactors. (author) [French] Avec le reacteur de puissance zero du Laboratoire national d'Argonne, on a procede a des etudes de reacteurs tres divers; reacteurs de recherche, generatrices nucleaires, reacteurs pour la propulsion, pour la production de radioisotopes et reacteurs experimentaux; les ensembles associes - exponentiels et critiques non empoisonnes - ont fourni les donnees debase. Afin de rendre compte d'experiences recentes et de montrer quelle masse de renseignements sur la physique des reacteurs on peut obtenir avec des systemes a bas flux, les auteurs exposent les programmes experimentaux ci-apres: 1. Etude des proprietes des elements combustibles en oxydes d'uranium et de thorium, immerges dans l'eau lourde, en s'attachant particulierement aux donnees necessaires pour l'etude d'un deuxieme coeur pour le reacteur experimental a eau bouillante du Laboratoire d'Argonne; 2. Maquette d'un reacteur de recherche a haut flux, qui permettra de verifier les calculs faits au cours de l'etude, de determiner la geometrie optimale et d'estimer l'effet du taux de combustion; 3. Determination des repartitions energetiques et de l'effet de l'immersion des cartouches sur la reactivite pour un reacteur experimental a ebullition et a surchauffe combinees; 4. Etude d'un coeur de reacteur surgenerateur plutonigene a neutrons rapides, alimente en U{sup 235} et refroidi au sodium qui constituerait la charge initiale du Deuxieme reacteur surgenerateur experimental d'Argonne; 5. Etude des caracteristiques d'un reacteur a deux regions, l'une thermique et l'autre rapide, en interaction. Dans l'expose de ces programmes, les auteurs expliquent pourquoi on a

  16. Purification by molecular sieve of helium used as inert cover gas in nuclear reactors; Epuration de l'helium de couverture des reacteurs nucleaires par adsorption sur tamis moleculaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    A method carried out at fairly low temperatures (between -50 and -80 deg. C) has been studied for the purification of the helium used as cover gas for heavy water in reactors. The use of the 5A molecular sieve has been adopted because of its superiority over other adsorbents in this temperature range. The particular problems connected with adsorption under dynamic conditions have been dealt with separately. The nitrogen adsorption isotherms have been plotted and the heat of adsorption calculated. (authors) [French] Une methode d'epuration, a temperature moderement basse (comprise entre -50 et -80 deg. C) de l'helium servant de couverture inerte a l'eau lourde des reacteurs a ete etudiee. L'emploi au tamis moleculaire 5A a ete retenu pour la superiorite de celui-ci sur d'autres adsorbants dans ce domaine de temperatures. Les problemes particuliers a l'adsorption en regime dynamique ont ete separement traites. Les isothermes d'adsorption d'azote ont ete tracees et la chaleur d'adsorp. tion calculee. (auteurs)

  17. Annual report on JEN-1 and JEN-2 Reactors

    International Nuclear Information System (INIS)

    Montes Ponce de Leon, J.

    1974-01-01

    In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

  18. System Design of a Supercritical CO_2 cooled Micro Modular Reactor

    International Nuclear Information System (INIS)

    Kim, Seong Gu; Cho, Seongkuk; Yu, Hwanyeal; Kim, Yonghee; Jeong, Yong Hoon; Lee, Jeong Ik

    2014-01-01

    Small modular reactor (SMR) systems that have advantages of little initial capital cost and small restriction on construction site are being developed by many research organizations around the world. Existing SMR concepts have the same objective: to achieve compact size and a long life core. Most of small modular reactors have much smaller size than the large nuclear power plant. However, existing SMR concepts are not fully modularized. This paper suggests a complete modular reactor with an innovative concept for reactor cooling by using a supercritical carbon dioxide. The authors propose the supercritical CO_2 Brayton cycle (S-CO_2 cycle) as a power conversion system to achieve small volume of power conversion unit (PCU) and to contain the reactor core and PCU in one vessel. A conceptual design of the proposed small modular reactor was developed, which is named as KAIST Micro Modular Reactor (MMR). The supercritical CO_2 Brayton cycle for the S-CO_2 cooled reactor core was optimized and the size of turbomachinery and heat exchanger were estimated preliminary. The nuclear fuel composed with UN was proposed and the core lifetime was obtained from a burnup versus reactivity calculation. Furthermore, a system layout with fully passive safety systems for both normal operation and emergency operation was proposed. (author)

  19. Reactor Physics Development for Advanced Gas-Cooled Reactors; Recherches en Physique des Reacteurs, pour des Reacteurs Perfectionnes Refroidis par un Gaz; Razrabotka metodov v oblasti reaktornoj fiziki dlya usovershenstvovannogo reaktora s gazovym okhlazhdeniem; Progresos de la Fisica de los Reactores de Tipo Avanzado Refrigerados por Gas

    Energy Technology Data Exchange (ETDEWEB)

    Moore, J. [United Kingdom Atomic Energy Authority (United Kingdom)

    1964-04-15

    effects in APEX, HERO and AGR and for determining fine structure data and power distribution in the complex fuel assemblies are of particular interest. Current and future theoretical work is concentrated primarily on development of an alternative method to hetrecontrol and FTD2 for dealing with reactor cores after considerable burn-up of the fuel. The experimental programme on HERO is designed to test these methods with complex cores including plutonium bearing fuel. Additional information on the effect of plutonium will be derived from operation of AGR and physics measurements on fuel after irradiation. (author) [French] Le memoire relate les recherches experimentales et theoriques auxquelles on a procede lois de l'etude, de la realisation et de la mise en service du reacteur perfectionne refroidi par un gaz (AGR) de Windscale et, d'une facon generale, pour la mise au point d'un filiere de ce type en vue de la production d'energie electrique industrielle. Il decrit l'important volume de travail qui a ete necessaire en vue d'elaborer les methodes theoriques voulues pour calculer: a) la repartition du flux et l'equilibre de la reactivite dans un coeur complexe; b) la repartition de la puissance dans des geometries de combustible complexes-, c) les effets de l'irradiation sur le cycle du combustible et la repartition de la puissance. A titre d'introduction, le memoire resume la documentation experimentale et les methodes theoriques qui sont le resultat des recherches sur la filiere a uranium gaine de magnox et decrit la documentation experimentale obtenue par le programme commun des industries britanniques (BICEP); toutes ces donnees ont servi de point de depart pour l'elaboration de methodes theoriques applicables a l'AGR. On s'est servi de l'ensemble critique APEX et du reacteur HERO de puissance zero avec des configurations de reseau regulieres et diverses combinaisons de perturbateurs (notamment des barres de commande) pour calculer les parametres de reseau de l'AGR et

  20. The SLOWPOKE-2 reactor with low enrichment uranium oxide fuel

    International Nuclear Information System (INIS)

    Townes, B.M.; Hilborn, J.W.

    1985-06-01

    A SLOWPOKE-2 reactor core contains less than 1 kg of highly enriched uranium (HEU) and the proliferation risk is very low. However, to overcome proliferation concerns a new low enrichment uranium (LEU) fuelled reactor core has been designed. This core contains approximately 180 fuel elements based on the Zircaloy-4 clad UOsub(2) CANDU fuel element, but with a smaller outside diameter. The physics characteristics of this new reactor core ensure the inherent safety of the reactor under all conceivable conditions and thus the basic SLOWPOKE safety philosophy which permits unattended operation is not affected

  1. Sexualidad, migraciones y fronteras en contextos de integración sur-sur

    Directory of Open Access Journals (Sweden)

    Martha Cecilia Ruiz

    Full Text Available Resumen Este artículo se pregunta sobre los procesos de diferenciación, jerarquización e inclusión/exclusión de poblaciones migrantes en contextos migratorios sur-sur, y sobre el rol que juega la sexualidad en estos procesos. Partiendo de un estudio etnográfico sobre las migrantes peruanas y colombianas en el sector del comercio sexual de Ecuador, se analiza la manera en que la sexualidad se convierte en un sitio privilegiado para re-imaginar las diferencias y jerarquías nacionales en un mundo globalizado e integrado regionalmente, y se explica cómo los regímenes de control sobre las migraciones y la sexualidad femenina se articulan entre sí para restablecer el orden idealizado de la nación.

  2. The reactor Cabri; La pile cabri

    Energy Technology Data Exchange (ETDEWEB)

    Ailloud, J.; Millot, J.P. [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    exceptional circumstances... - experimental investigations on power excursions linked with precise initial conditions: the aim of this work is to define the basis for theoretical research, and the limits beyond which the risks of explosion cease to be negligible. The research work will be done so as to enable checking with outside reactor experiments and to continue them in the explosion field. - studies of the behaviour of the reactor control-instrumentation. - experimental investigations related with transient operation with initial short life (study of boiling, temperature measurements, vacuum pressure and fraction...) with the aim of defining the hypotheses of a theory on swimming-pool reactor kinetics related to heat transfer phenomena, - investigations of the behaviour of fuels in reactors (these experiments are planned to be carried out in loops) Preliminary experimental results. CABRI went critical on the 21 December 1963. The first transient experiments are expected for March 1964. (authors) [French] II devenait necessaire de construire en France une pile qui permette d'etudier les conditions de fonctionnement des installations futures, de choisir, tester et mettre au point les dispositifs de securite a adopter. On a choisi une pile a eau, type de pile qui correspond aux constructions les plus nouvelles du CEA en matiere de piles laboratoire ou d'universite; il importe en effet de pouvoir evaluer les risques presentes et d'etudier les possibilites d'augmentation de puissance constamment demandees par les utilisateurs: il est particulierement interessant d'eclaircir les phenomenes d'oscillation de puissance et les risques de calefaction (burn out). Les programmes de travaux sur CABRI seront harmonises avec les travaux effectues sur les Spert americains de meme type; lors de sa construction des contacts fructueux ont ete etablis avec les specialistes americains qui ont defini les premiers de ces reacteurs. La communication donne une

  3. Operation of the SLOWPOKE-2 reactor in Jamaica

    Energy Technology Data Exchange (ETDEWEB)

    Grant, C.N.; Lalor, G.C.; Vuchkov, M.K. [University of the West Indies, Kingston (Jamaica)

    2001-07-01

    Over the past sixteen years lCENS has operated a SLOWPOKE 2 nuclear reactor almost exclusively for the purpose of neutron activation analysis. During this period we have adopted a strategy of minimum irradiation times while optimizing our output in an effort to increase the lifetime of the reactor core and to maintaining fuel integrity. An inter-comparison study with results obtained with a much larger reactor at IPEN has validated this approach. The parameters routinely monitored at ICENS are also discussed and the method used to predict the next shim adjustment. (author)

  4. Irradiation techniques at BR2 reactor

    International Nuclear Information System (INIS)

    Hebel, W.

    1978-01-01

    Since 1963 the material testing reactor BR2 at Mol is operated for the realisation of numerous research programs and experiments on the behavior of materials under nuclear radiation and in particular under intensive neutron exposure. During this period special irradiation techniques and experimental devices were developed according to the desiderata of the different experiments and to the irradiation possibilities offered at BR2. The design and the operating characteristics of quite a number of those irradiation rigs of proven reliability may be used or can be made available for new irradiation experiments. A brief description is given of some typical irradiation devices designed and constructed by CEN/SCK, Technology and Energy Dpt. They are compiled according to their main use for the different research and development programs realized at BR2. Their eventual application however for different objectives could be possible. A final chapter summarizes the principal irradiation conditions offered by BR2 reactor. (author)

  5. Comparative study of the ionic exchange of Ca{sup ++}, Sr{sup ++}, and Ba{sup ++} cations on resins and inorganic exchangers; Etude comparative de l'echange ionique des cations Ca{sup ++}, Sr{sup ++} et Ba{sup ++} sur resine et sur echangeurs mineraux

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-03-01

    With a view to applying the results to certain problems related to chemical separations in activation analysis, a study has been made, of the possibilities of separating the alkaline-earth elements Ca, Sr and Ba on organic resins and inorganic exchangers using the radioactive indicator method. The partition coefficients of the cations Ca{sup 2+}, Sr{sup 2+} and Ba{sup 2+} have been measured on Dowex 50 W (NH{sub 4}{sup +}) x 8 resin in the presence of EDTA - NTA - EGTA and DCTA as complexing agents, and on zirconium phosphate, tungstate and molybdate in the presence of HCl and NH{sub 4}Cl. Methods have been developed for separating mixtures of alkaline-earth elements using DCTA-NH{sub 4}{sup +} followed by elution on Dowex 50 W (NH{sub 4}{sup +}) x 8 resin columns and on zirconium phosphate. Amongst the complexing agents used on the ion-exchange resins the most promising appears to be DCTA which leads to partition coefficients Ca, Sr and Ba which are very different. The results of measurements of partition coefficients on zirconium phosphate (NH{sub 4}{sup +} form) using DCTA-NH{sub 4}{sup +} show the interesting possibilities of separations on columns. The separation of the alkaline-earth elements on zirconium phosphate seems to be less quantitative than on Dowex 50 resin; it is however much faster in the former case and this can be useful for treating short half-life radioisotopes in activation analysis. (author) [French] En vue de l'application a certains problemes de separations chimiques en analyse par activation, on a etudie les possibilites de separation des elements alcalino-terreux Ca-Sr et Ba sur resine organique et sur echangeurs mineraux par la methode des indicateurs radioactifs. Les coefficients de partage des cations Ca{sup +2}, Sr{sup +2} et Ba{sup +2} sur resine Dowex 50 W (NH{sub 4}{sup +}) x 8 en milieux complexants EDTA - NTA - EGTA et DCTA et sur phosphate, tungstate et molybdate de zirconium en milieu HCl et NH{sub 4}Cl ont ete mesures. Des

  6. Effet de la composition de différents substrats culturaux sur ...

    African Journals Online (AJOL)

    SARAH

    31 janv. 2014 ... Effet de la substrats culturaux sur paramètres de croissance ... des graines, mais ce substrat a donné des performances acceptables sur la croissance longitudinale des ..... élevés en conteneurs sur différents types de.

  7. Recherches sur les courants ésotériques occidentaux modernes

    OpenAIRE

    Faivre, Antoine

    2009-01-01

    Conférences de la première heure Elles ont porté principalement sur deux ouvrages récents relevant de la spécialité. Le premier, de Helmut Zander (Anthroposophie in Deutschland. Theosophische Weltanschauung und gesellschaftliche Praxis 1884‑1945, 2 vol., Vandenhoeck & Ruprecht, Göttingen 2007), fort documenté, nous a donné l’occasion de faire le point sur l’état actuel de la recherche en matière d’Anthroposophie steinerienne et de Société Théosophique. Mais nous avons commenté surtout un sous...

  8. Neonatal diabetes and congenital hyperinsulinism caused by mutations in ABCC8/SUR1 are associated with altered and opposite affinities for ATP and ADP

    Directory of Open Access Journals (Sweden)

    Joseph eBryan

    2015-04-01

    Full Text Available ATP-sensitive K+ (KATP channels composed of potassium inward-rectifier type 6.2 and sulfonylurea receptor type 1 subunits (Kir6.2/SUR14 are expressed in various cells in the brain and endocrine pancreas where they couple metabolic status to membrane potential. In β-cells, increases in cytosolic [ATP/ADP]c inhibit KATP channel activity, leading to membrane depolarization and exocytosis of insulin granules. Mutations in ABCC8 (SUR1 or KCNJ11 (Kir6.2 can result in gain or loss of channel activity and cause neonatal diabetes (ND or congenital hyperinsulinism (CHI, respectively. SUR1 is reported to be a Mg2+-dependent ATPase. A prevailing model posits that ATP hydrolysis at SUR1 is required to stimulate openings of the pore. However, recent work shows nucleotide binding, without hydrolysis, is sufficient to switch SUR1 to stimulatory conformations. The actions of nucleotides, ATP and ADP, on ND (SUR1E1506D and CHI (SUR1E1506K mutants, without Kir6.2, were compared to assess both models. Both substitutions significantly impair hydrolysis in SUR1 homologues. SUR1E1506D has greater affinity for MgATP than wildtype; SUR1E1506K has reduced affinity. Without Mg2+, SUR1E1506K has a greater affinity for ATP4- consistent with electrostatic attraction between ATP4-, unshielded by Mg2+, and the basic lysine. Further analysis of ND and CHI ABCC8 mutants in the second transmembrane and nucleotide binding domains (TMD2 & NBD2, found a relation between their affinities for ATP (± Mg2+ and their clinical phenotype. Increased affinity for ATP is associated with ND; decreased affinity with CHI. In contrast, MgADP showed a weaker relationship. Diazoxide, known to reduce insulin release in some CHI cases, potentiates switching of CHI mutants from non-stimulatory to stimulatory states consistent with diazoxide stabilizing a nucleotide-bound conformation. The results emphasize the greater importance of nucleotide binding vs hydrolysis in the regulation of KATP channels

  9. TMI-2 reactor vessel head removal

    International Nuclear Information System (INIS)

    Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

    1985-09-01

    This report describes the safe removal and storage of the Three Mile Island Unit 2 (TMI-2) reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training, the head was safely removed and stored; and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

  10. La grange seigneuriale de « l’hébergement » de Flux à Lailly-en-Val (Loiret au XIVe siècle

    Directory of Open Access Journals (Sweden)

    Daniel Bontemps

    2012-04-01

    Full Text Available La grange seigneuriale de Flux à Lailly-en-Val (Loiret est construite sur le lit majeur de la Loire en zone primitivement inondable. Transformée par les siècles, elle n’en conserve pas moins son pourtour d’origine et une charpente à fermes et pannes sur poteaux dont les bois ont été coupés vers 1320 (dendrochronologie. Grâce à des aveux du XIVe siècle, postérieurs d’un tiers de siècle à sa construction, on constate qu’elle occupait une situation à part dans « l’hébergement » de Flux. Son implantation près de Beaugency permettait de transporter la part des récoltes qui y étaient entreposées en peu de temps pour y être vendue.The seigniorial barn of Flux at Lailly-en-Val (Loiret was built on the main bed of the river Loire which, at the time, was liable to inundation. The building has been modified over the centuries but nonetheless conserves its original footprint and its original wooden trusses and purlins. These are supported by posts the timber of which, according to dendrochronological analysis, was cut in about 1320. In archival consents dating from the 14th century, a third of a century after the construction, it is possible to see how the barn occupied a peripheral situation in the ‘hébergement’, the lodging of Flux. Its location near Beaugency allowed for parts of the harvest to be rapidly stored in the barn prior to sale.

  11. TMI-2 reactor vessel plenum final lift

    International Nuclear Information System (INIS)

    Wilson, D.C.

    1986-01-01

    Removal of the plenum assembly from the TMI-2 reactor vessel was necessary to gain access to the core region for defueling. The plenum was lifted from the reactor vessel by the polar crane using three specially designed pendant assemblies. It was then transferred in air to the flooded deep end of the refueling canal and lowered onto a storage stand where it will remain throughout the defueling effort. The lift and transfer were successfully accomplished on May 15, 1985 in just under three hours by a lift team located in a shielded area within the reactor building. The success of the program is attributed to extensive mockup and training activities plus thorough preparations to address potential problems. 54 refs

  12. Refurbishment programme for the BR2-reactor

    Energy Technology Data Exchange (ETDEWEB)

    Koonen, E [Centre d' Etude de l' Energie Nucleaire, Studiecentrum voor Kernenergie, BR2 Department, Boeretang, Mol (Belgium)

    1992-07-01

    BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

  13. Refurbishment programme for the BR2-reactor

    International Nuclear Information System (INIS)

    Koonen, E.

    1992-01-01

    BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

  14. Heavy water moderated gas-cooled reactors; Filiere eau lourde - gaz

    Energy Technology Data Exchange (ETDEWEB)

    Bailly du Bois, B; Bernard, J L; Naudet, R; Roche, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    France has based its main effort for the production of nuclear energy on natural Uranium Graphite-moderated gas-cooled reactors, and has a long term programme for fast reactors, but this country is also engaged in the development of heavy water moderated gas-cooled reactors which appear to present the best middle term prospects. The economy of these reactors, as in the case of Graphite, arises from the use of natural or very slightly enriched Uranium; heavy water can take the best advantages of this fuel cycle and moreover offers considerable development potential because of better reactor performances. A prototype plant EL 4 (70 MW) is under construction and is described in detail in another paper. The present one deals with the programme devoted to the development of this reactor type in France. Reasons for selecting this reactor type are given in the first part: advantages and difficulties are underlined. After reviewing the main technological problems and the Research and Development carried out, results already obtained and points still to be confirmed are reported. The construction of EL 4 is an important step of this programme: it will be a significant demonstration of reactor performances and will afford many experimentation opportunities. Now the design of large power reactors is to be considered. Extension and improvements of the mechanical structures used for EL 4 are under study, as well as alternative concepts. The paper gives some data for a large reactor in the present state of technology, as a result from optimization studies. Technical improvements, especially in the field of materials could lead to even more interesting performances. Some prospects are mentioned for the long run. Investment costs and fuel cycles are discussed in the last part. (authors) [French] La France, qui a base son effort principal pour la production d'energie nucleaire sur la filiere des reacteurs a uranium naturel et graphite refroidis par gaz, et qui a un programme a plus

  15. Modalities of exploitation of the AP2 fuel fabrication plant at the FBFC facility of Romans-sur-Isere (INB98)

    International Nuclear Information System (INIS)

    2001-01-01

    This decision from the French authority of nuclear safety (ASN) aims at establishing a normal framework to the effluents management and waste storage activities that are carried out inside the 'south storage shed' of the AP2 fuel fabrication plant of the FBFC facility of Romans-sur-Isere (France). (J.S.)

  16. SUR. Breve informe de la Expedición Yelcho al Polo Sur (1909-1910

    Directory of Open Access Journals (Sweden)

    Ursula K. Le Guin

    2013-12-01

    Full Text Available Ursula K. Le Guin Escritora norteamericana, famosa por sus obras de ciencia fi cción y fantasía, en las cuales el tema de género ocupa una posición central. Ganadora de los premios Hugo y Nébula que la catapultaron a la fama. “SUR. A summary report of the Yelcho expedition to the Antarctic, 1909-1910”. Apáreció publicado por primera vez en la revista New Yorker, el 1° de febrero de 1982. La palabra SUR aparece en español en el original. (http://www.newyorker.com/ar Traducción de Susana E. Matallana Peláez

  17. SurR9C84A protects and recovers human cardiomyocytes from hypoxia induced apoptosis

    Energy Technology Data Exchange (ETDEWEB)

    Ashok, Ajay [Nanomedicine-Laboratory of Immunology and Molecular Biomedical Research (NLIMBR), School of Medicine (SoM), Faculty of Health, Centre for Molecular and Medical Research - C-MMR, Deakin University, Waurn Ponds, Victoria 3216 (Australia); Department of Pathology, Case Western Reserve University, 2103 Cornell Rd. WRB 5128, Cleveland, OH 44106-7288 (United States); Kanwar, Jagat Rakesh [Nanomedicine-Laboratory of Immunology and Molecular Biomedical Research (NLIMBR), School of Medicine (SoM), Faculty of Health, Centre for Molecular and Medical Research - C-MMR, Deakin University, Waurn Ponds, Victoria 3216 (Australia); Krishnan, Uma Maheswari [Centre for Nanotechnology & Advanced Biomaterials (CeNTAB), School of Chemical & Biotechnology (SCBT), SASTRA University, Thanjavur 613401 (India); Kanwar, Rupinder Kaur, E-mail: rupinder.kanwar@deakin.edu.au [Nanomedicine-Laboratory of Immunology and Molecular Biomedical Research (NLIMBR), School of Medicine (SoM), Faculty of Health, Centre for Molecular and Medical Research - C-MMR, Deakin University, Waurn Ponds, Victoria 3216 (Australia)

    2017-01-01

    Survivin, as an anti-apoptotic protein and a cell cycle regulator, is recently gaining importance for its regenerative potential in salvaging injured hypoxic cells of vital organs such as heart. Different strategies are being employed to upregulate survivin expression in dying hypoxic cardiomyocytes. We investigated the cardioprotective potential of a cell permeable survivin mutant protein SurR9C84A, for the management of hypoxia mediated cardiomyocyte apoptosis, in a novel and clinically relevant model employing primary human cardiomyocytes (HCM). The aim of this research work was to study the efficacy and mechanism of SurR9C84A facilitated cardioprotection and regeneration in hypoxic HCM. To mimic hypoxic microenvironment in vitro, well characterized HCM were treated with 100 µm (48 h) cobalt chloride to induce hypoxia. Hypoxia induced (HI) HCM were further treated with SurR9C84A (1 µg/mL) in order to analyse its cardioprotective efficacy. Confocal microscopy showed rapid internalization of SurR9C84A and scanning electron microscopy revealed the reinstatement of cytoskeleton projections in HI HCM. SurR9C84A treatment increased cell viability, reduced cell death via, apoptosis (Annexin-V assay), and downregulated free cardiac troponin T and MMP-9 expression. SurR9C84A also upregulated the expression of proliferation markers (PCNA and Ki-67) and downregulated mitochondrial depolarization and ROS levels thereby, impeding cell death. Human Apoptosis Array further revealed that SurR9C84A downregulated expression of pro-apoptotic markers and augmented expression of HSPs and HTRA2/Omi. SurR9C84A treatment led to enhanced levels of survivin, VEGF, PI3K and pAkt. SurR9C84A proved non-toxic to normoxic HCM, as validated through unaltered cell proliferation and other marker levels. Its pre-treatment exhibited lesser susceptibility to hypoxia/damage. SurR9C84A holds a promising clinical potential for human cardiomyocyte survival and proliferation following hypoxic injury

  18. Sur terre comme sur mer: organisations spatiales en mer du Nord et mer de Norvège

    Directory of Open Access Journals (Sweden)

    Maryvonne LE BERRE

    1998-09-01

    Full Text Available L'article montre, au moyen de représentations cartographiques et graphiques, les structures spatiales développées en mer pour l'exploitation des hydrocarbures. Malgré les différences de milieu, l'appropriation et l'occupation territoriales du domaine maritime s'effectuent selon les mêmes principes que sur le continent, à ceci près que ce qui s'étale en surface sur le continent se développe à la verticale en mer.

  19. Refurbishing the BR2 materials testing reactor

    International Nuclear Information System (INIS)

    Baugnet, J.M.; Dekeyser, J.; Gubel, P.

    1995-01-01

    SCK/CEN is refurbishing its BR2 reactor to allow its further operation during the next 15 years; in doing so, it chooses to keep BR2 available for future scientific and technological irradiation programs within an international context. (author) 2 figs

  20. TIC & TER. Stratégie numérique et qualité de service à la SNCF

    OpenAIRE

    Emangard, Pierre-Henry

    2015-01-01

    Le développement des techniques d’information et de communication a conduit la SNCF à développer une stratégie commerciale numérique vis-à-vis de tous ses segments de clientèle. S’appuyant sur le cas du secteur Sud Loire Océan, l’article montre que le développement des services d’information à la clientèle en temps réel a paradoxalement servi d’alibi pour laisser la qualité du service ferroviaire régional TER se dégrader, ce qui a eu pour conséquence une baisse sensible du trafic. Cet exemple...

  1. Hausse des taxes sur le tabac et politiques de lutte antitabac au ...

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

    Par ailleurs, les études existantes sur les effets des taxes sur le tabac sont fondées sur l'" élasticité de la demande en fonction du prix ", une mesure qui indique l'évolution de la demande globale de cigarettes en réaction à une modification des prix, mais qui ne tient pas compte des effets d'une augmentation des taxes sur ...

  2. Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    International Nuclear Information System (INIS)

    1966-01-01

    This Volume 2 of the Proceedings of 2. Yugoslav symposium on reactor physics includes eight papers dealing with the following topics: method for measuring high anti reactivities of a reactor system; integration method for thermal reaction rate calculation; Determination of initial core configuration for BHWR-200 MWe; safety shutdowns and failures of the RA reactor equipment; determining the reactivity of absorption rods; measurements of thermal and fast neutron fluxes at the TRIGA reactor and other measurements during operation of the TRIGA reactor; mathematical modelling of the reactor safety; review of problems and methods for radiation risk assessment in the environment of a nuclear power plant

  3. SIRIUS 2: A versatile medium power research reactor

    International Nuclear Information System (INIS)

    Rousselle, P.

    1992-01-01

    Most of the Research Reactors in the world have been critical in the Sixties and operated for twenty to thirty years. Some of them have been completely shut down, modified, or simply refurbished; the total number of RR in operation has decreased but there is still an important need for medium power research reactors in order: - to sustain a power program with fuel and material testing for NPP or fusion reactors; - to produce radioisotopes for industrial or medical purposes, doped silicon, NAA or neutron radiography; - to investigate further the condensed matter, with cold neutrons routed through neutron guides to improved equipment; - to develop new technologies and applications such as medical alphatherapy. Hence, taking advantage of nearly hundred reactor x years operation and backed up by the CEA experience, TECHNICATOME assisted by FRAMATOME has designed a new versatile multipurpose Research Reactor (20-30 Mw) SIRIUS 2 taking into account: - more stringent safety rules; - the lifetime; - the flexibility enabling a wide range of experiments and, - the future dismantling of the facility according to the ALARA criteria

  4. Effets de six composts sur les réponses physiologiques ...

    African Journals Online (AJOL)

    Les effets de ces six composts sur le potentiel hydrique, la fuite d'électrolyte, la teneur en amidon des feuilles et sur quelques paramètres agronomiques ont été évalués sur les plantes stressées en comparaison avec les plantes témoins. Les résultats indiquent des valeurs du potentiel hydrique foliaire très faibles et une ...

  5. Regional prospective and strategy for energy. A comparison of scenarios for the Pays-de-la-Loire, Nord-Pas-de-Calais, and Provence-Cote-d'Azur regions

    International Nuclear Information System (INIS)

    Fink, Meike

    2014-01-01

    A report proposes an overview of prospective studies in France. It discusses the criteria which distinguish various prospective scenarios, comments the emergence of a shared and common vocabulary for prospective studies, proposes a historical overview of prospective studies on energy in France, and a qualitative comparison of ten prospective regional studies in France. In a second part, it reports a data-based and qualitative analysis of scenarios for three regions (Pays de la Loire, Nord Pas de Calais, and Provence-Alps-Cote d'Azur): methodology, context of elaboration of prospective studies and comparison of scenarios in the three regions, data for years of reference, used variables, compliance with national commitments, application to different sectors (industry, agriculture, building, transports), analysis of energy supply. A first version of this report is provided

  6. OTUS - Reactor inventory management system based on ORIGEN2

    Energy Technology Data Exchange (ETDEWEB)

    Poellaenen, R; Toivonen, H; Lahtinen, J; Ilander, T

    1995-10-01

    ORIGEN2 is a computer code that calculates nuclide composition and other characteristics of nuclear fuel. The use of ORIGEN2 requires good knowledge in reactor physics. However, once the input has been defined for a particular reactor type, the calculations can be easily repeated for any burnup and decay time. This procedure produces large output files that are difficult to handle manually. A new computer code, known as OTUS, was designed to facilitate the postprocessing of the data. OTUS makes use of the inventory files precalculated with ORIGEN2 in a way that enables their versatile treatment for different safety analysis purposes. A data base is created containing a comprehensive set of ORIGEN2 calculations as a function of fuel burnup and decay time. OTUS is a reactor inventory management system for a microcomputer with Windows interface. Four major data operations are available: (1) Build data modifies ORIGEN2 output data into a suitable format, (2) View data enables flexible presentation of the data as such, (3) Different calculations, such as nuclide ratios and hot particle characteristics, can be performed for severe accident analyses, consequence analyses and research purposes, (4) Summary files contain both burnup dependent and decay time dependent inventory information related to the nuclide and the reactor specified. These files can be used for safeguards, radiation monitoring and safety assessment. (orig.) (22 refs., 29 figs.).

  7. Conférence sur l'efficacité

    CERN Document Server

    Jullien, François

    2005-01-01

    Philosophe et sinologue, François Jullien présente ici une conférence qu'il a prononcée auprès de chefs d'entreprise et dans le milieu du management. D'un côté, la conception européenne de l'efficacité est liée à la modélisation comme à la finalité et revendique l'action jusqu'à l'héroïsme ; de l'autre, la pensée chinoise de l'efficience, indirecte et discrète, s'appuie sur le potentiel de situation et induit des " transformations silencieuses ", sans éclat ni même événement. Par-delà cet écart, il s'agira d'interroger la nature de l'effectivité ; ou comment l'intervention humaine réussit à se brancher sur la propension des choses et s'y laisse intégrer. Ce propos se garde donc de séparer tant soit peu l'art d'opérer sur des situations et l'exercice de la philosophie ; en résultent des effets de lecture portant sur l'histoire du XXe siècle ainsi que la géopolitique - et géoéthique - à venir.

  8. The 2nd reactor core of the NS Otto Hahn

    International Nuclear Information System (INIS)

    Manthey, H.J.; Kracht, H.

    1979-01-01

    Details of the design of the 2nd reactor core are given, followed by a brief report summarising the operating experience gained with this 2nd core, as well as by an evaluation of measured data and statements concerning the usefulness of the knowledge gained for the development of future reactor cores. Quite a number of these data have been used to improve the concept and thus the specifications for the fuel elements of the 3rd core of the reactor of the NS Otto Hahn. (orig./HP) [de

  9. EL-2 reactor: Thermal neutron flux distribution

    International Nuclear Information System (INIS)

    Rousseau, A.; Genthon, J.P.

    1958-01-01

    The flux distribution of thermal neutrons in EL-2 reactor is studied. The reactor core and lattices are described as well as the experimental reactor facilities, in particular, the experimental channels and special facilities. The measurement shows that the thermal neutron flux increases in the central channel when enriched uranium is used in place of natural uranium. However the thermal neutron flux is not perturbed in the other reactor channels by the fuel modification. The macroscopic flux distribution is measured according the radial positioning of fuel rods. The longitudinal neutron flux distribution in a fuel rod is also measured and shows no difference between enriched and natural uranium fuel rods. In addition, measurements of the flux distribution have been effectuated for rods containing other material as steel or aluminium. The neutron flux distribution is also studied in all the experimental channels as well as in the thermal column. The determination of the distribution of the thermal neutron flux in all experimental facilities, the thermal column and the fuel channels has been made with a heavy water level of 1825 mm and is given for an operating power of 1000 kW. (M.P.)

  10. Physics design of advanced steady-state tokamak reactor A-SSTR2

    International Nuclear Information System (INIS)

    Nishio, Satoshi; Ushigusa, Kenkichi

    2000-10-01

    Based on design studies on the fusion power reactor such as the DEMO reactor SSTR, the compact power reactor A-SSTR and the DREAM reactor with a high environmental safety and high availability, a new concept of compact and economic fusion power reactor (A-SSTR2) with high safety and high availability is proposed. Employing high temperature superconductor, the toroidal filed coils supplies the maximum field of 23T on conductor which corresponds to 11T at the magnetic axis. A-SSTR2 (R p =6.2m, a p =1.5m, I p =12MA) has a fusion power of 4GW with β N =4. For an easy maintenance and for an enough support against a strong electromagnetic force on coils, a poloidal coils system has no center solenoid coils and consists of 6 coils located on top and bottom of the machine. Physics studies on the plasma equilibrium, controllability of the configuration, the plasma initiation and non-inductive current ramp-up, fusion power controllability and the diverter have shown the validity of the A-SSTR2 concept. (author)

  11. FORE-2, Thermohydraulics and Space-Independent Reactor Kinetics for Transients

    International Nuclear Information System (INIS)

    Fox, J.N.; Lawler, B.E.; Butz, H.R.; Heames, T.J.

    1984-01-01

    1 - Description of problem or function: FORE2 is a coupled thermal hydraulics-point kinetics digital computer code designed to calculate significant reactor parameters under steady-state conditions, or as functions of time during transients. The transients may result from a programmed reactivity insertion or a power change. Variable inlet coolant flow rate and temperature are considered. The code calculates the reactor power, the individual reactivity feedbacks, and the temperature of coolant, cladding, fuel, structure, and additional material for up to seven axial positions in three channel types which represent radial zones of the reactor. The heat of fusion, accompanying fuel melting, the liquid metal voiding reactivity, and the spatial and the time variation of the fuel cladding gap coefficient due to changes in gap size are considered. 2 - Method of solution: FORE2 input consists of property data, geometry, power and flow distribution factors, external time varying functions, experimental coefficients, and termination data. The differential equations for fluid flow, heat transfer, and point neutronics are solved by explicit finite-difference procedures. 3 - Restrictions on the complexity of the problem: Reactor excursions which can be calculated are restricted to those transients in which the reactor is not substantially destroyed. As a general rule, changes in reactor geometry and composition during an excursion are limited to those cases in which the reactivity effects of the changes may be considered as small perturbations of the initial system. Thus, accidents involving large-scale disassembly and bulk meltdown of a core are not covered by FORE2. FORE2 is valid only while the core retains its initial geometry

  12. Use of cadmium in solution in the EL 4 reactor moderator irreversible fixing of cadmium on the metallic surfaces; Utilisation du cadmium en solution dans le moderateur du reacteur EL 4 - fixation irreversible du cadmium sur les surfaces metalliques

    Energy Technology Data Exchange (ETDEWEB)

    Croix, O; Paoli, O; Lecomte, J; Dolle, L; Gallic, Y [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    In the framework of research into the poisoning of the EL-4 reactor by cadmium sulphate, measurements have been made by two different methods of the residual amounts of cadmium liable to be fixed irreversibly on the surfaces in contact with the heavy water. A marked influence of the pH has been noticed. The mechanism of the irreversible fixing is compatible with the hypothesis of an ion-exchange in the surface oxide layer. In a sufficiently wide range of pH the cadmium thus fixed causes very little residual poisoning. The stability of the cadmium sulphate solutions is however rather low in the conditions of poisoning. (authors) [French] Dans le cadre des etudes sur l'empoisonnement du reacteur EL-4 par le sulfate de cadmium, les quantites residuelles de cadmium susceptibles de se fixer irreversiblement sur les parois que mouillerait l'eau lourde, ont ete mesurees experimentalement par deux methodes differentes. On observe une influence nette du pH. Le mecanisme de la fixation irreversible est compatible avec l'hypothese d'un echange d'ions dans la pellicule d'oxyde superficielle. Dans des limites suffisamment larges de pH, la cadmium ainsi fixe n'occasionne pas d'empoisonnement residuel important. La stabilite des solutions de sulfate de cadmium dans les conditions de l'empoisonnement est cependant mediocre. (auteurs)

  13. Taxes sur les cigarettes en Tanzanie | IDRC - International ...

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

    Taxes sur les cigarettes en Tanzanie. De 2002 à 2007, le tabagisme a connu une hausse de 20 % en Tanzanie, une augmentation qui devrait atteindre 46 % en 2016 si la tendance se maintient. On s'attend à ce que cette hausse du tabagisme ait d'importantes répercussions sur la santé publique et le développement ...

  14. Keeping research reactors relevant: A pro-active approach for SLOWPOKE-2

    International Nuclear Information System (INIS)

    Cosby, L.R.; Bennett, L.G.I.; Nielsen, K.; Weir, R.

    2010-01-01

    The SLOWPOKE is a small, inherently safe, pool-type research reactor that was engineered and marketed by Atomic Energy of Canada Limited (AECL) in the 1970s and 80s. The original reactor, SLOWPOKE-1, was moved from Chalk River to the University of Toronto in 1970 and was operated until upgraded to the SLOWPOKE-2 reactor in 1973. In all, eight reactors in the two versions were produced and five are still in operation today, three having been decommissioned. All of the remaining reactors are designated as SLOWPOKE-2 reactors. These research reactors are prone to two major issues: aging components and lack of relevance to a younger audience. In order to combat these problems, one SLOWPOKE -2 facility has embraced a strategy that involves modernizing their reactor in order to keep the reactor up to date and relevant. In 2001, this facility replaced its aging analogue reactor control system with a digital control system. The system was successfully commissioned and has provided a renewed platform for student learning and research. The digital control system provides a better interface and allows flexibility in data storage and retrieval that was never possible with the analogue control system. This facility has started work on another upgrade to the digital control and instrumentation system that will be installed in 2010. The upgrade includes new computer hardware, updated software and a web-based simulation and training system that will allow licensed operators, students and researchers to use an online simulation tool for training, education and research. The tool consists of: 1) A dynamic simulation for reactor kinetics (e.g., core flux, power, core temperatures, etc). This tool is useful for operator training and student education; 2) Dynamic mapping of the reactor and pool container gamma and neutron fluxes as well as the vertical neutron beam tube flux. This research planning tool is used for various researchers who wish to do irradiations (e.g., neutron

  15. Calculations of reactor-accident consequences, Version 2. CRAC2: computer code user's guide

    International Nuclear Information System (INIS)

    Ritchie, L.T.; Johnson, J.D.; Blond, R.M.

    1983-02-01

    The CRAC2 computer code is a revision of the Calculation of Reactor Accident Consequences computer code, CRAC, developed for the Reactor Safety Study. The CRAC2 computer code incorporates significant modeling improvements in the areas of weather sequence sampling and emergency response, and refinements to the plume rise, atmospheric dispersion, and wet deposition models. New output capabilities have also been added. This guide is to facilitate the informed and intelligent use of CRAC2. It includes descriptions of the input data, the output results, the file structures, control information, and five sample problems

  16. Thermal reactor benchmark tests on JENDL-2

    International Nuclear Information System (INIS)

    Takano, Hideki; Tsuchihashi, Keichiro; Yamane, Tsuyoshi; Akino, Fujiyoshi; Ishiguro, Yukio; Ido, Masaru.

    1983-11-01

    A group constant library for the thermal reactor standard nuclear design code system SRAC was produced by using the evaluated nuclear data JENDL-2. Furthermore, the group constants for 235 U were calculated also from ENDF/B-V. Thermal reactor benchmark calculations were performed using the produced group constant library. The selected benchmark cores are two water-moderated lattices (TRX-1 and 2), two heavy water-moderated cores (DCA and ETA-1), two graphite-moderated cores (SHE-8 and 13) and eight critical experiments for critical safety. The effective multiplication factors and lattice cell parameters were calculated and compared with the experimental values. The results are summarized as follows. (1) Effective multiplication factors: The results by JENDL-2 are considerably improved in comparison with ones by ENDF/B-IV. The best agreement is obtained by using JENDL-2 and ENDF/B-V (only 235 U) data. (2) Lattice cell parameters: For the rho 28 (the ratio of epithermal to thermal 238 U captures) and C* (the ratio of 238 U captures to 235 U fissions), the values calculated by JENDL-2 are in good agreement with the experimental values. The rho 28 (the ratio of 238 U to 235 U fissions) are overestimated as found also for the fast reactor benchmarks. The rho 02 (the ratio of epithermal to thermal 232 Th captures) calculated by JENDL-2 or ENDF/B-IV are considerably underestimated. The functions of the SRAC system have been continued to be extended according to the needs of its users. A brief description will be given, in Appendix B, to the extended parts of the SRAC system together with the input specification. (author)

  17. Cu-Zn-Pb multi isotopic characterization of a small watershed (Loire river basin, France)

    Science.gov (United States)

    Desaulty, A. M.; Millot, R.; Perret, S.; Bourrain, X.

    2015-12-01

    Combating metal pollution in surface water is a major environmental, public health and economic issue. Knowledge of the behavior of metals, such as copper (Cu), zinc (Zn) and lead (Pb) in sediments and dissolved load, is a key factor to improve the management of rivers. Recent advances in mass spectrometry related to the development of MC-ICPMS allow to analyze the isotopic composition of these elements, and previous studies show the effectiveness of isotopic analyses to determine the anthropogenic sources of pollution in environment. The goal of this study is to use the Cu-Zn-Pb multi-isotopic signature to track the pollutions in surface water, and to understand the complex processes causing the metals mobilization and transport in environment. More particularly we investigate the mechanisms of distribution between the dissolved load and particulate load, known to play an important role in the transport of metals through river systems. As case study, we chose a small watershed, poorly urbanized in the Loire river basin. Its spring is in a pristine area, while it is only impacted some kilometers further by the releases rich in metals coming from a hospital water treatment plant. First a sampling of these liquid effluents as well as dissolved load and sediment from upstream to downstream was realized and their concentrations and isotopic data were determined. Then to simulate a lot of potential natural and anthropogenic modifications of environmental conditions, we made sequential extraction protocol using various reagents on the sediments. Isotopic analyzes were performed also on the various extracting solutions. Isotopic ratios were measured using a Neptune MC-ICPMS at the BRGM, after a protocol of purification for Zn and Cu. The results showed that, these isotopic systematics reveal important informations about the mechanists of mobilization and transport of metals through river systems. However experiments performed under laboratory conditions will be necessary

  18. WWER-1000 reactor simulator. Material for training courses and workshops. 2. ed

    International Nuclear Information System (INIS)

    2005-01-01

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No.12, Reactor Simulator Development (2001). Course material for workshops using a pressurized water reactor (PWR) simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication, Training Course Series No. 22, 2nd edition, Pressurized Water Reactor Simulator (2005) and Training Course Series No.23, 2nd edition, Boiling Water Reactor Simulator (2005). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation

  19. ASAMPSA2 best-practices guidelines for L2 PSA development and applications. Volume 3 - Extension to Gen IV reactors

    International Nuclear Information System (INIS)

    Bassi, C.; Bonneville, H.; Brinkman, H.; Burgazzi, L.; Polidoro, F.; Vincon, L.; Jouve, S.

    2010-01-01

    The main objective assigned to the Work Package 4 (WP4) of the 'ASAMPSA2' project (EC 7. FPRD) consist in the verification of the potential compliance of L2PSA guidelines based on PWR/BWR reactors (which are specific tasks of WP2 and WP3) with Generation IV representative concepts. Therefore, in order to exhibit potential discrepancies between LWRs and new reactor types, the following work was based on the up-to-date designs of: - The European Fast Reactor (EFR) which will be considered as prototypical of a pool-type Sodium-cooled Fast Reactor (SFR); - The ELSY design for the Lead-cooled Fast Reactor (LFR) technology; - The ANTARES project which could be representative of a Very-High Temperature Reactor (VHTR); - The CEA 2400 MWth Gas-cooled Fast Reactor (GFR). (authors)

  20. Current status of restoration work for obstacle and upper core structure in reactor vessel of experimental fast reactor 'Joyo'. 2-2

    International Nuclear Information System (INIS)

    Okuda, Eiji; Ito, Hiromichi; Yoshihara, Shizuya

    2014-01-01

    An accident occurred in experimental fast reactor 'Joyo' in 2007 which is obstruction of fuel change equipment caused by contacting rotating plug and MARICO-2. In addition, we confirmed two happenings in the reactor vessel that (1) Deformation of MARICO-2 subassembly on the in vessel storage rack together with a transfer pot, (2) Deformation of the Upper core structure of 'Joyo' caused by contacting MARICO-2 subassembly and the UCS. We do the restoration work for restoring it. This time, we describe current status of Replacement work of the UCS. (author)

  1. Le Projet d’Ole Lando sur les Contrats

    DEFF Research Database (Denmark)

    Holle, Marie-Louise

    2017-01-01

    En 2016 le projet de recherche le plus important jusqu’à présent sur le droit nordique des contrats a pris fin et un livre, de presque 400 pages, en a marqué l’aboutissement. Le résultat du projet est un « restatement » tel qu’il existe aux États-Unis. Le Restatement porte sur les règles et les...

  2. A pulsed fast reactor; Un reacteur pulse a neutrons rapides; Impul'snyj reaktor na bystrykh nejtronakh; Reactor rapido pulsado

    Energy Technology Data Exchange (ETDEWEB)

    Blokhin, G. E.; Blokhintsev, D. I.; Blyumkina, Yu. A.; Bondarenko, I. I.; Deryagin, B. N.; Zajmovskij, A. S.; Zinov' ev, V. P.; Kazachkovskij, O. D.; Krasnoyarov, N. V.; Lejpunskij, A. I.; Malykh, V. A.; Nazarov, P. M.; Nikolaev, S. K.; Stavisskij, Yu. Ya.; Ukraintsev, F. I.; Frank, I. M.; Shapiro, F. Ji.; Yazvitskij, Yu. S. [Akademiya Nauk, Moscow, SSSR (Russian Federation)

    1962-03-15

    A pulsed fast reactor (IBR) has been operating at rated capacity since December 1960 in the Joint Institute for Nuclear Research. This reactor is used as a pulsed neutron source for physical experiments carried out by the time-of-flight method. It is used for total cross-section and intermediate neutron capture cross- section measurements, for studying the interaction between slow neutrons and solids and liquids, and for measuring neutron spectra produced in various media. The paper describes the basic structural features of the reactor and the results of the experiments for which it has been used. The reactor's operating system is based on recurrent pulses. Power pulses are produced when the mobile part of the reactor core moves swiftly through the stationary part of the core. The mobile part of the core is fastened to a rotating disc and travels at a speed of 230 m/s. The frequency of power pulses can be altered by means of an auxiliary mobile zone which has a range of 2.3-88 pulses per second. The mean power of the reactor is 1 kW, and the half-width of the power pulse in 36 {mu}s. The reactor is provided with a control and safety system which ensures automatic maintenance of mean power and swift shutdown in the event of any operational irregularity. It is fitted with a system of evacuated-neutron-flight tubes used in time-of-flight experiments. The main tube is 1000 m in length. In the start-up process and during physical experiments carried out on the reactor, the influence on reactivity of displacing the controls and the mobile parts of the core was studied ; the length of the pulse was measured under various operating conditions, and power pulse amplitude fluctuations were studied. Further measurements were made to establish the lifetime of prompt neutrons, the effective fraction of delayed neutrons, and coefficients of reactivity. (author) [French] L'Institut unifie de recherches nucleaires dispose d'un reacteur puise a neutrons rapides (IBR), qui

  3. Determination of {sup 90}Sr, {sup 63}Ni and {sup 55}Fe activities by liquid scintillation counting in the environmental samples close to French nuclear power plants located on Loire and Garonne rivers

    Energy Technology Data Exchange (ETDEWEB)

    Rousseau, G.; Mokili, M.B.; Le Roy, C.; Deniau, I. [SUBATECH, IN2P3 (France); Gontier, G.; Boyer, C. [EDF-DPI-DIN-CIDEN (France); Hemidy, P.Y. [EDF-DPN-UNIE-GPRE-IEV (France); Chardon, P. [CNRS/IN2P3 (France)

    2014-07-01

    The protection of the aquatic and terrestrial environment from a wide range of radioactive contaminants released by nuclear industry requires continuous monitoring of radionuclides released into the environment. Specific measurement methods depending of the radionuclide are used to determinate this contribution. A lot of radionuclide can easily be measured at low level by gamma spectrometry, like {sup 137}Cs, {sup 60}Co..., but others like {sup 90}Sr, {sup 63}Ni or {sup 55}Fe require prior specific radiochemical separations. Activity of {sup 90}Sr values in environmental samples are available but only few measurements of {sup 63}Ni and {sup 55}Fe activities have been carried out in samples collected in the environment close to French nuclear power plants located on the Loire and Garonne rivers despite they represent 12% to 24% for {sup 63}Ni activity and <1% for {sup 55}Fe + other minor radionuclides of total activity of their liquid effluent discharges. {sup 90}Sr is not rejected by the liquid effluent discharges of Nuclear Power Plants and can be found in the environmental samples because of thermonuclear test and subsequently after the Chernobyl nuclear power plant accident. Considering the French Nuclear Power Plant located on Loire and Garonne rivers, the determination of {sup 90}Sr, {sup 63}Ni and {sup 55}Fe levels in the environmental samples around French nuclear power plants is carried out to detect the traces of these radionuclides originating from nuclear technology activities. The environment around five French nuclear Power Plants was investigated for 4 years between 2009 and 2014. The radionuclide activities determined by liquid scintillation counting after chemical steps were performed on a large set of various matrix samples likely to be encountered in environmental monitoring as soils, sediments, terrestrial and aquatic bio-indicators. It was found that the mean activity concentration of the most frequently detected was for the radionuclide {sup 90

  4. Multiple 3d Approaches for the Architectural Study of the Medieval Abbey of Cormery in the Loire Valley

    Science.gov (United States)

    Pouyet, T.

    2017-02-01

    This paper will focus on the technical approaches used for a PhD thesis regarding architecture and spatial organization of benedict abbeys in Touraine in the Middle Ages, in particular the abbey of Cormery in the heart of the Loire Valley. Monastic space is approached in a diachronic way, from the early Middle Ages to the modern times using multi-sources data: architectural study, written sources, ancient maps, various iconographic documents… Many scales are used in the analysis, from the establishment of the abbeys in a territory to the scale of a building like the tower-entrance of the church of Cormery. These methodological axes have been developed in the research unit CITERES for many years and the 3D technology is now used to go further along in that field. The recording in 3D of the buildings of the abbey of Cormery allows us to work at the scale of the monastery and to produce useful data such as sections or orthoimages of the ground and the walls faces which are afterwards drawn and analysed. The study of these documents, crossed with the other historical sources, allowed us to emphasize the presence of walls older than what we thought and to discover construction elements that had not been recognized earlier and which enhance the debate about the construction date St Paul tower and associated the monastic church.

  5. Neutron detection in an atomic reactor core using semi-conductors; Detection des neutrons par semi-conducteur dans un coeur de reacteur atomique

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    In this paper, the first part describes the principle of nuclear particle detection by means of semiconductor diodes and the general application of these. The second part describes fabrication of the device used to estimate thermic neutron fluxes in core of a swimming pool type reactor. The useful volume (2.9 mm thickness) is in the light water moderator, between combustible elements plates. The results, principally obtained in the core of Siloette reactor at the 'Centre d'Etudes Nucleaires de Grenoble' at low power, are mentioned in the third part. Flux maps have been set and comparison between converter's products: Bore 10, Lithium 6, Uranium 235 is made. (author) [French] Dans ce rapport, une premiere partie porte sur la description du principe de detection des particules nucleaires par diodes a semi-conducteur et sur l'application generale de celles-ci. Une deuxieme partie s'attache a decrire la fabrication du materiel utilise pour evaluer les flux de neutrons thermiques dans un coeur de reacteur type pile piscine. L'espace de mesure (2,9 mm d'epaisseur) se situe entre les plaques des elements combustibles, dans le moderateur eau legere. Les resultats, obtenus principalement dans le coeur du reacteur Siloette du Centre d'Etudes Nucleaires de Grenoble aux basses puissances de fonctionnement, sont rapportes dans la troisieme partie. Des cartes de flux ont ete dressees et une comparaison est faite entre les produits 'convertisseurs' suivants: Bore 10, Lithium 6, Uranium 235. (auteur)

  6. Detection of radioactive gases in the CO{sub 2} cooling the reactors G 2 - G 3; Detection des gaz radioactifs dans le CO{sub 2} de refroidissement des piles G2 - G3

    Energy Technology Data Exchange (ETDEWEB)

    Pouthier, J; Rossi, J [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1968-07-01

    The carbon dioxide cooling the reactors G2 - G3 contains activation gases and fission gases. It is of interest to know their concentration, for example to be able to deduce rapidly the norms which would have to be applied in the case of an incident in the circuit. Gas-phase chromatography is applied daily for carrying out analyses. The chromatogram has separate peaks due to tritium, argon 41, krypton 85 and the 133 and 135 isotopes of xenon. By integrating each peak it is possible to calculate the specific activity of each product. The construction of an apparatus for carrying out continuous measurements is under consideration. (authors) [French] Le gaz carbonique, refroidissant les reacteurs G2 - G3, contient des gaz d'activation et des gaz de fission. Il est interessant de connaitre leur teneur par exemple pour etre en mesure de deduire rapidement les normes qu'il y aurait lieu d'appliquer en cas d'incidents sur le circuit. La methode de chromatographie en phase gazeuse est employee quotidiennement pour faire des analyses. Le chromatogramme se presente sous forme de pics distincts dus au tritium, a l'argon 41, au krypton 85 et aux isotopes 133 et 135 du xenon. L'integration de chaque pic permet de calculer l'activite specifique de chaque compose. Il est envisage de construire un appareil pour des mesures en continu. (auteurs)

  7. Sterilization of E. coli bacterium in a flowing N2-O2 post-discharge reactor

    International Nuclear Information System (INIS)

    Villeger, S; Cousty, S; Ricard, A; Sixou, M

    2003-01-01

    Effective destruction of Escherichia coli (E. coli) bacteria has been obtained in a flowing N 2 -O 2 microwave post-discharge reactor. The sterilizing agents are the O atoms and the UV emissions of NOβ which are produced by N and O atoms recombination in the reactor. In the following plasma conditions: pressure 5 Torr, flow rate 1 L n min -1 , microwave power of 100 W in a quartz tube of 5 mm, an O atom density of 2.5x10 15 cm -3 is measured by NO titration in the post-discharge reactor with UV emission in a N 2 -(5%)O 2 gas mixture. Full destruction of 10 13 cfu ml -1 E. coli is observed after a treatment time of 25 min. (rapid communication)

  8. Safe dismantling of the SVAFO research reactors R2 and R2-0 in Sweden

    International Nuclear Information System (INIS)

    ARNOLD, Hans-Uwe; BROY, Yvonne; Dirk Schneider

    2017-01-01

    The R2 and R2-0 reactors were part of the Swedish government's research program on nuclear power from the early 1960's. Both reactors were shut down in 2005 following a decision by former operator Studsvik Nuclear AB. The decommissioning of the R2 and R2-0 reactors is divided into three phases. The first phase - awarded to AREVA - involved dismantling of the reactors and associated systems in the reactor pool, treatment of the disassembled components as well as draining, cleaning and emptying the pool. In the second phase, the pool structure itself will be dismantled, while removal of remaining reactor systems, treatment and disposal of materials and clean-up will be carried out in the third stage. The entire work is planned to be completed before the end of this decade. The paper describes the several steps of phase 1 - starting with the team building, followed by the dismantling operations and covers challenges encountered and lessons learned as well. The reactors consist of 5.400 kg aluminum, 6.000 kg stainless steel restraint structures as well as, connection elements of the mostly flanged components (1.000 kg). The most demanding - from a radiological point of view - was the R2-0 reactor that was limited to ∼ 1 m"3 construction volumes but with an extremely heterogeneous activation profile. Based on the calculated radiological entrance data and later sampling, nuclide vectors for both reactors depending on the real placement of the single component and on the material (aluminum and stainless steel) were created. Finally, for the highest activated component from R2 reactor, 85 Sv/h were measured. The dismantling principles - adopted on a safety point of view - were the following: The always protected base area of the ponds served as a flexible buffer area for waste components and packaging. Specific protections were also installed on the walls to protect them from mechanical stress which may occur during dismantling work. A specific work platform was

  9. IMPLICATION DE CERTAINES MUTATIONS DANS LES GENES BRCA1 ET BRCA2 SUR LA PRÉDISPOSITION AU CANCER DU SEIN ET AU CANCER OVARIEN

    Directory of Open Access Journals (Sweden)

    Lucian Negura

    2007-08-01

    Full Text Available Le cancer du sein, ainsi que celui ovarien, est une maladie fréquente chez les femmes, ayant un traitement assez difficile et, malheureusement, de sérieuses répercutions sur le physique ; c’est pourquoi il s’avère essentiel que la maladie soit dépistée dès les phases précoces. La prédisposition génétique est responsable de 5% des cancers et de 25% des cas apparus avant l’age de 30 ans [Breast Cancer Linkage Consortium, 1997]. Nous présentons ici l’implication des gènes suppresseurs des tumeurs BRCA1 et BRCA2 sur cette prédisposition.

  10. Research on anhydrous hydrazine synthesis; Recherche sur la synthese de l'hydrazine anhydre

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-03-15

    The first part of this work concerns the radiolysis of pure liquid ammonia. The fundamental importance of the dose rate and of the dose on the yield of radiolytic products has been demonstrated. By using a capture solute at concentrations of between 10{sup -3} and 1.2 mole s/litre, it has been possible to determine the yields of radicals and of molecules in the irradiated pure ammonia. During later work, it was possible to determine, by systematically varying the physico-chemical parameters, the most favorable conditions for carrying out the radiosynthesis; the maximum radiochemical yield of the hydrazine obtained has a value: G (N{sub 2}H{sub 4}) = 2.2/100 eV. An analysis of the molecular yields in the presence of deuterated solutes makes it possible to explain partially the role of the capture species. A project is also described for an installation producing hydrazine continuously; it is followed by an economic study of the process. From this work it appears that the yields of hydrazine obtained justify an industrial application, especially if strong radiation sources are available, for example nuclear reactors. (author) [French] La premiere partie de l'etude a porte sur la radiolyse de l'ammoniac liquide pur. Le role fondamental du debit de dose et de la dose sur les rendements des produits de radiolyse a ete mise en evidence. L'emploi de solute capteur dont les concentrations sont comprises entre 10{sup -3} et 1,2 mole/litre, a permis de determiner la valeur des rendements radicalaires et moleculaires dans l'ammoniac pur irradie. Au cours d'une etape ulterieure, une variation systematique des parametres physico-chimiques a permis de determiner les conditions les plus favorables a la radiosynthese le rendement radiochimique maximum de l'hydrazine obtenu a pour valeur: G(N{sub 2}H{sub 4}) 2,2/100 eV. L'analyse des rendements moleculaires en presence de solutes deuteres nous permet de rendre compte partiellement du role des capteurs. Un projet d'une installation

  11. Radio elements transfer from water to atmosphere through degassing processes in the Loire estuary: the Flore project

    International Nuclear Information System (INIS)

    Fontugne, M.; Hatte, C.; Paterne, M.; Maro, D.; Germain, P.; Hebert, D.; Rozet, M.; Voiseux, C.; Solier, L.; Tenailleau, L.; Abril, G.

    2004-01-01

    The behaviour of the toxic substances in the environment covers various fields of investigations like contamination by the radioelements, heavy metals and organic compounds. The knowledge of the biogeochemical cycles of the radioelements basically their temporal and spatial distributions is essential to a better understanding of their biological effects. Estuarine environments present a major interest since they constitute accumulation areas of wastes and rejections of the majority of the anthropogenic activities. These transition zones between fresh waters and ocean, characterised by the change of the physico- chemical properties (pH, salinity, turbidity) allows a redistribution of the radioelements by their speciation or phase change thus modifying their bio-availability. The Loire River estuary receives the rejections of radioelements being able to come from various sources like the nuclear thermal power stations (fourteen engines with discharges of carbon-14, tritium), the hospital complexes (rejections of iodine 131). The aims of FLORE program is to study the distribution of these radioelements and processes of phase transfer in this estuary especially in the mud plug area where the biochemical activity is intense. If most of the processes of transfer are now well established, fluxes of radioelements between water and the atmosphere are not quantified. Two oceanographic cruises carried out in February and September 2003 on board N/O 'Cotes de La Manche' allow to present distribution Iodine 131 within the estuary and the first estimation of radiocarbon and tritium fluxes from the river water to the atmosphere. (author)

  12. Droits, justice et réseaux sociaux sur Internet (Amérique latine ...

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

    ... sur la question de la protection des renseignements personnels sur Internet, ... Derechos y justicia y el movimiento social en internet (5 de agosto de 2009 ... Programme de recherche sur le virus Zika Canada-Amérique latine et Caraïbes.

  13. Influence of fluvial environments on sediment archiving processes and temporal pollutant dynamics (Upper Loire River, France).

    Science.gov (United States)

    Dhivert, E; Grosbois, C; Rodrigues, S; Desmet, M

    2015-02-01

    Floodplains are often cored to build long-term pollutant trends at the basin scale. To highlight the influences of depositional environments on archiving processes, aggradation rates, archived trace element signals and vertical redistribution processes, two floodplain cores were sampled near in two different environments of the Upper Loire River (France): (i) a river bank ridge and (ii) a paleochannel connected by its downstream end. The base of the river bank core is composed of sandy sediments from the end of the Little Ice Age (late 18th century). This composition corresponds to a proximal floodplain aggradation (sediments that settled in the distal floodplain. In this distal floodplain environment, the aggradation rate depends on the topography and connection degree to the river channel. The temporal dynamics of anthropogenic trace element enrichments recorded in the distal floodplain are initially synchronous and present similar levels. Although the river bank core shows general temporal trends, the paleochannel core has a better resolution for short-time variations of trace element signals. After local water depth regulation began in the early 1930s, differences of connection degree were enhanced between the two cores. Therefore, large trace element signal divergences are recorded across the floodplain. The paleochannel core shows important temporal variations of enrichment levels from the 1930s to the coring date. However, the river bank core has no significant temporal variations of trace element enrichments and lower contamination levels because of a lower deposition of contaminated sediments and a pedogenetic trace elements redistribution. Copyright © 2014 Elsevier B.V. All rights reserved.

  14. Benchmark calculations for VENUS-2 MOX -fueled reactor dosimetry

    International Nuclear Information System (INIS)

    Kim, Jong Kung; Kim, Hong Chul; Shin, Chang Ho; Han, Chi Young; Na, Byung Chan

    2004-01-01

    As a part of a Nuclear Energy Agency (NEA) Project, it was pursued the benchmark for dosimetry calculation of the VENUS-2 MOX-fueled reactor. In this benchmark, the goal is to test the current state-of-the-art computational methods of calculating neutron flux to reactor components against the measured data of the VENUS-2 MOX-fuelled critical experiments. The measured data to be used for this benchmark are the equivalent fission fluxes which are the reaction rates divided by the U 235 fission spectrum averaged cross-section of the corresponding dosimeter. The present benchmark is, therefore, defined to calculate reaction rates and corresponding equivalent fission fluxes measured on the core-mid plane at specific positions outside the core of the VENUS-2 MOX-fuelled reactor. This is a follow-up exercise to the previously completed UO 2 -fuelled VENUS-1 two-dimensional and VENUS-3 three-dimensional exercises. The use of MOX fuel in LWRs presents different neutron characteristics and this is the main interest of the current benchmark compared to the previous ones

  15. PCU arrangement of a supercritical CO{sub 2} cooled micro modular reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seong Gu; Baik, Seungjoon; Cho, Seong Kuk; Oh, Bong Seong; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    As part of the SMR(Small Modular Reactor)s development effort, the authors propose a concept of supercritical CO{sub 2} (S-CO{sub 2}) cooled fast reactor combined with the S-CO{sub 2} Brayton cycle. The reactor concept is named as KAIST Micro Modular Reactor (MMR). The S-CO{sub 2} Brayton cycle has many strong points when it is used for SMR's power conversion unit. It occupies small footprints due to the compact cycle components and simple layout. Thus, a concept of one module containing the S-CO{sub 2} cooled fast reactor and power conversion system is possible. This module can be shipped via ground transportation (by trailer) or marine transportation. In this study, the authors propose a new conceptual layout for the S-CO{sub 2} cooled direct cycle while considering various issues for arranging cycle components. The new design has an improved cycle efficiency (from 31% to 34%) than the earlier version of MMR by reducing pressure drops in the heat exchangers. As a more efficient option, a recompression recuperated cycle was also designed. It improves 5% of thermal efficiency while 18tons of mass can be added in comparison to the simple recuperated cycle. Even if we adopt recompression cycle as a PCU, the weight of module (152tons) is less than the ground transportable limit (260tons)

  16. TMI-2 reactor vessel head removal

    International Nuclear Information System (INIS)

    Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

    1984-12-01

    This report describes the safe removal and storage of the Three Mile Island Unit 2 reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training the head was safely removed and stored and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

  17. Low-level radioactive waste management in EDF nuclear power plants (FRANCE)

    International Nuclear Information System (INIS)

    Boussard, C.

    1991-01-01

    This paper shows some recent examples of Low-level radioactive waste management in EDF nuclear power plants: - Radioactive liquid wastes proceeding from steam generators leaching (NOGENT SUR SEINE-1 REACTOR) - Thermal insulation proceeding from heat exchanger and blower (CHINON-2 REACTOR) - Old iron from reactor dismantling (CHINON-3 REACTOR, MARCOULE G1 REACTOR, MARCOULE G2-G3 REACTORS) - fresh air filter and fire detector - CHINON-2 REACTOR breaker chambers

  18. Neutronic study using oxide and nitride fuels for the Super Phenix 2 reactor

    International Nuclear Information System (INIS)

    Batista, J.L.; Renke, C.A.C.

    1991-11-01

    This report presents a neutronic analysis and a description of the Super Phenix 2 reactor, taken as reference. We present the methodology and results for cell and global reactor calculations for oxide (U O 2 - Pu O 2 ) and nitride (U N - Pu N) fuels. To conclude we compare the performance of oxide and nitride fuels for the reference reactor. (author)

  19. Shadow corrosion evaluation in the Studsvik R2 reactor

    International Nuclear Information System (INIS)

    Sanders, Ch.; Lysell, G.

    2000-01-01

    Post-irradiation examination has shown that increased corrosion occurs when zirconium alloys are in contact with or in proximity to other metallic objects. The observations indicate an influence of irradiation from the adjacent component as the enhanced corrosion occurs as a 'shadow' of the metallic object on the zirconium surface. This phenomenon could ultimately limit the lifetime of certain zirconium alloy components in the reactor. The Studsvik R2 materials test reactor has an In-Core Autoclave (INCA) test facility especially designed for water chemistry and materials research. The INCA facility has been evaluated and found suitable for shadow corrosion studies. The R2 reactor core containing the INCA facility was modeled with the Monte Carlo N-Particle (MCNP) code in order to evaluate the electron deposition in various materials and to develop a hypothesis of the shadow corrosion mechanism. (authors)

  20. Seismic behaviour of gas cooled reactor components

    International Nuclear Information System (INIS)

    1990-08-01

    On invitation of the French Government the Specialists' Meeting on the Seismic Behaviour of Gas-Cooled Reactor Components was held at Gif-sur-Yvette, 14-16 November 1989. This was the second Specialists' Meeting on the general subject of gas-cooled reactor seismic design. There were 27 participants from France, the Federal Republic of Germany, Israel, Japan, Spain, Switzerland, the United Kingdom, the Soviet Union, the United States, the CEC and IAEA took the opportunity to present and discuss a total of 16 papers reflecting the state of the art of gained experiences in the field of their seismic qualification approach, seismic analysis methods and of the capabilities of various facilities used to qualify components and verify analytical methods. Since the first meeting, the sophistication and expanded capabilities of both the seismic analytical methods and the test facilities are apparent. The two main methods for seismic analysis, the impedance method and the finite element method, have been computer-programmed in several countries with the capability of each of the codes dependent on the computer capability. The correlations between calculation and tests are dependent on input assumptions such as boundary conditions, soil parameters and various interactions between the soil, the buildings and the contained equipment. The ability to adjust these parameters and match experimental results with calculations was displayed in several of the papers. The expanded capability of some of the new test facilities was graphically displayed by the description of the SAMSON vibration test facility at Juelich, FRG, capable of dynamically testing specimens weighing up to 25 tonnes, and the TAMARIS facility at the CEA laboratories in Gif-sur-Yvette where the largest table is capable of testing specimens weighing up to 100 tonnes. The proceedings of this meeting contain all 16 presented papers. A separate abstract was prepared for each of these papers. Refs, figs and tabs

  1. 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

  2. Benchmark tests of JENDL-3.2 for thermal and fast reactors

    International Nuclear Information System (INIS)

    Takano, Hideki

    1995-01-01

    Benchmark calculations for a variety of thermal and fast reactors have been performed by using the newly evaluated JENDL-3 Version-2 (JENDL-3.2) file. In the thermal reactor calculations for the uranium and plutonium fueled cores of TRX and TCA, the k eff and lattice parameters were well predicted. The fast reactor calculations for ZPPR-9 and FCA assemblies showed that the k eff , reactivity worth of Doppler, sodium void and control rod, and reaction rate distribution were in a very good agreement with the experiments. (author)

  3. Radionuclide distribution in TMI-2 reactor building basement liquids and solids

    International Nuclear Information System (INIS)

    Horan, J.T.; McIsaac, C.V.; Keefer, D.G.

    1984-01-01

    As a result of the TMI-2 accident, approximately 2.46 x 10 6 L of contaminated water were released to the Reactor Building basement. The principal fission product release pathway from the damaged core was through the reactor coolant system (RCS) to the pressurizer, through the pressure-operated relief valve (PORV) on the pressurizer to the Reactor Coolant Drain Tank (RCDT), and then through the RCDT rupture disk to the Reactor Building basement. Since August 1979, a number of efforts have been made to determine the location, quantity, and composition of fission products released to the Reactor Building basement. These efforts have included sampling of the basement water and solids, the basement sump pump recirculation line, the RCDT, and visual surveys using a closed circuit television (CCTV) system. The analysis of basement samples has provided data on the physical and radioisotopic characteristics of the liquids and solids. This paper describes the sample collection techniques and discusses radiochemical analyses results

  4. An experimental investigation of fission product release in SLOWPOKE-2 reactors

    International Nuclear Information System (INIS)

    Harnden, A.M.C.

    1995-09-01

    Increasing radiation fields due to a release of fission products in the reactor container of several SLOWPOKE-2 reactors fuelled with a highly-enriched uranium (HEU) alloy core have been observed. It is believed that these increases are associated with the fuel fabrication where a small amount of uranium-bearing material is exposed to the coolant at the end-welds of the fuel element. To investigate this phenomenon samples of reactor water and gas from the headspace above the water have been obtained and examined by gamma spectrometry methods for reactors of various burnups at the University of Toronto, Ecole Polytechnique and Kanata Isotope Production Facility. An underwater visual examination of the fuel core at Ecole Polytechnique has also provided information on the condition of the core. This report (Volume 1) summarizes the equipment, analysis techniques and results of tests conducted at the various reactor sites. The data report is published as Volume 2. (author). 30 refs., 9 tabs., 20 figs

  5. The Oak Ridge Research Reactor: safety analysis: Volume 2, supplement 2

    International Nuclear Information System (INIS)

    Hurt, S.S.

    1986-11-01

    The Oak Ridge Research Reactor Safety Analysis was last updated via ORNL-4169, Vol. 2, Supplement 1, in May of 1978. Since that date, several changes have been effected through the change-memo system described below. While these changes have involved the cooling system, the electrical system, and the reactor instrumentation and controls, they have not, for the most part, presented new or unreviewed safety questions. However, some of the changes have been based on questions or recommendations stemming from safety reviews or from reactor events at other sites. This paper discusses those changes which were judged to be safety related and which include revisions to the syphon-break system and changes related to seismic considerations which were very recently completed. The maximum hypothetical accident postulated in the original safety analysis requires dynamic containment and filtered flow for compliance with 10CFR100 limits at the site boundary

  6. Heat transfer tests conducted on full-scale model, to investigate cooling conditions of EL.3 experimental reactor; Essais de transmission de chaleur sur maquette pour l'etude du refroidissement de la pile EL 3

    Energy Technology Data Exchange (ETDEWEB)

    Raievski, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Butzbach, M; Domenjoud, M [Alsthom, 75 - Paris (France); Bousquet, M [Chantiers de l' Atlantique (France); Braudeau, M; Milliat, M [Electricite de France (EDF), 75 - Paris (France)

    1958-07-01

    For such high heat flux density as is released in the channels of EL3 reactor (2.10{sup 6} kcal/m{sup 2}h on the hottest point) cooling conditions have proved to be satisfactory, that is free from nucleate boiling. The arrangements provided for these tests and the technique used for measurements (of temperature particularly) are specified. Two fields have been investigated: in the former (forced convection without nucleate boiling) a good agreement is found with Colburn's formula. The influence of the ratio L/D is pointed out. The latter field is of forced convection with beginning of nucleate boiling; there the observed raise of the transfer coefficient has been shown occurring with some delay. (author)Fren. [French] A la valeur elevee prevue pour la densite de flux de chaleur (2.10{sup 6} kcal/m{sup 2}h au point le plus chaud) il est verifie que le refroidissement de la pile s'effectue normalement (sans ebullition de paroi). Les essais sont menes sur la maquette grandeur nature d'un canal d'EL3. Les dispositions relatives a la conduite des essais et a la technique des mesures (de temperature en particulier) sont precisees. Deux domaines sont etudies; pour t{sub p} < T{sub sat} (convection forcee sans ebullition de paroi) on constate un bon accord avec la formule de Colburn, avec toutefois l'influence du rapport L/D. Pour t{sub p} < T{sub sat} (debut d'ebullition) l'augmentation prevue du coefficient de transmission presente un certain retard. (auteur)

  7. Loss of coolant analysis for the tower shielding reactor 2

    International Nuclear Information System (INIS)

    Radcliff, T.D.; Williams, P.T.

    1990-06-01

    The operational limits of the Tower Shielding Reactor-2 (TSR-2) have been revised to account for placing the reactor in a beam shield, which reduces convection cooling during a loss-of-coolant accident (LOCA). A detailed heat transfer analysis was performed to set operating time limits which preclude fuel damage during a LOCA. Since a LOCA is survivable, the pressure boundary need not be safety related, minimizing seismic and inspection requirements. Measurements of reactor component emittance for this analysis revealed that aluminum oxidized in water may have emittance much higher than accepted values, allowing higher operating limits than were originally expected. These limits could be increased further with analytical or hardware improvements. 5 refs., 7 figs

  8. Dalhousie SLOWPOKE-2 reactor: A nuclear analytical chemistry facility

    International Nuclear Information System (INIS)

    Chatt, A.; Holzbecher, J.

    1990-01-01

    SLOWPOKE is an acronym for Safe Low POwer Kritical Experiment. The SOWPOKE-2 is a compact, inherently safe, swimming-pool-type reactor designed by the Atomic Energy of Canada Limited for neutron activation analysis (NAA) and isotope production. The Dalhousie University SLOWPOKE-2 reactor (DUSR) has been operating since 1976; a large beryllium reflector was added in 1986 to extend its lifetime by another 8 to 10 yr. The DUSR is generally operated at half-power with a maximum thermal flux of 1.1 x 10 12 n/cm 2 ·s in the inner pneumatic sites and that of 5.4 x 10 11 n/cm 2 ·s in the outer sites. Despite this comparatively low flux, SLOWPOKE-2 reactors have many beneficial features that are continuously being exploited at the DUSR facility for developing nuclear analytical methods for fundamental as well as applied studies. Although NAA is a well-established analytical technique, much of the activation analysis being performed in most facilities has been limited to methods using fairly long-lived nuclides. The approach at the DUSR facility has been to utilize the highly homogeneous, stable, and reproducible neutron flux to develop NAA methods based on short-lived nuclides. SLOWPOKE reactors have a fairly high epithermal neutron flux, which is being advantageously used for determining several trace elements in complex matrices. Radiochemical NAA (RNAA) methods using coprecipitation, distillation, and ion-exchange separations have been used for the determination of very low levels of several elements in biological materials

  9. [Identification of alloantibodies and their associations: balance sheet of a year at the Auvergne-Loire French Blood Establishment].

    Science.gov (United States)

    Duboeuf, S; Flourié, F; Courbil, R; Benamara, A; Rigal, E; Cognasse, F; Garraud, O

    2012-12-01

    Some alloantibodies and their combinations can lead to delays or even an impasse in a transfusion, owing to the necessity of finding compatible red blood cell concentrates. The aim of this study was to determine the specificities of the most common alloantibodies, as well as the most common combinations of alloantibodies. A retrospective study analysed erythrocyte alloantibodies identified in 2008 in the immunohematology laboratories at the Auvergne-Loire French Blood Establishment. The following data were studied: frequency, specificities of the alloantibodies, date of discovery, and patient age and sex. One thousand eight hundred and fifteen alloantibodies were identified in 1575 patients (median age: 63.5years, female/male ratio: 3.03). The most common alloantibodies were directed against the following antigens: RH3/E (18.7%), KEL1/K (17.3%), RH1/D (16.4%), MNS1/M (9.4%), FY1/Fya (6.9%), RH2/C (6.1%), KEL3/Kpa (4.7%), JK1/Jka (4.3%) and RH4/c (4.1%). In 13.1% of patients, at least two alloantibodies were identified. The pairs most frequently combined were anti-RH1/RH2, anti-RH3/RH4 and anti-RH3/KEL1. Specific associations of paired alloantibodies were identified. The main combinations provide indications on the choice of red cell concentrates in the inventory for a given patient. The data collected in our study show that when an antibody is identified, it is recommended for subsequent transfusion episodes to respect the phenotype RH 1-5 (D, C, E, c, e) and KEL1 (K) of the patient, and if possible antigens JK1 (Jka) and FY1 (Fya), and to a lesser extent MNS3 (S). Detailed knowledge of the immunological mechanisms leading to the formation of these alloantibodies and their combinations would allow better prevention of erythrocyte alloimmunization. Copyright © 2012 Elsevier Masson SAS. All rights reserved.

  10. Recherche en partenariat sur la transition nutritionnelle et les ...

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

    l'évolution du risque a suivi et a débouché sur une stratégie de prévention ... de recherche ont pu avoir un impact sur les politiques et pro- .... Deux études étaient donc entreprises ..... à la même thématique et de recruter par eux-mêmes les.

  11. Renforcement de l'influence de la recherche sur l'élaboration des ...

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

    Réflexions

    influent sur les politiques, mais de façons différentes. Le lien entre recherche et influence sur les politiques n'est ... Renforcement de l'influence de la recherche sur l'élaboration des politiques d'adaptation. PA. NOS. /G .... ceux de la CMAE ont dit avoir besoin de soutien technique. Il était malheureusement difficile pour le ...

  12. FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative

    International Nuclear Information System (INIS)

    Greene, S.R.; Spellman, D.J.; Bevard, B.B.

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative

  13. FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative

    Energy Technology Data Exchange (ETDEWEB)

    Greene, S.R.; Spellman, D.J.; Bevard, B.B. [and others

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative.

  14. Dynamic simulation of the 2 MWt slowpoke heating reactor

    International Nuclear Information System (INIS)

    Tseng, C.M.; Lepp, R.M.

    1982-04-01

    A 2 MWt SLOWPOKE reactor, intended for commercial space heating, is being developed at the Chalk River Nuclear Laboratories. A small-signal dynamic simulation of this reactor, without closed-loop control, was developed. Basic equations were used to describe the physical phenomena in each kf the eight reactor subsystems. These equations were then linearized about the normal operation conditions and rearranged in a dimensionless form for implementation. The overall simulation is non-linear. Slow transient responses (minutes to days) of the simulation to both reactivity and temperature perturbations were measured at full power. In all cases the system reached a new steady state in times varying from 12 h to 250 h. These results illustrate the benefits of the inherent negative reactivity feedback of this reactor concept. The addition of closed-loop control using core outlet temperature as the controlled variable to move a beryllium reflector is also examined

  15. Distribution of energy of impulses of the modernized IBR-2 REACTOR

    International Nuclear Information System (INIS)

    Tayibov, L.A; Mehtiyeva, R.N.; )

    2011-01-01

    Full text: For the modernized IBR-2 reactor there are two main reasons causing fluctuations of energy of impulses [1,3] on low power of stochastic fluctuations, on the nominal - giving rise to fluctuations of external reactance. The fluctuations of pulse energy is quite significant (20%). They affect the dynamics of the reactor, the process of regulation, starting, as well as the work of the experimental apparatus, etc. It is clear that research of fluctuation of energy of impulses has special value for the IBR-2 type reactor. Sufficient information about the statistical properties of the reactor noise gives the density distribution of the energy pulse power. We used the usual procedure of statistical analysis of time series. Calculated pulse energy of density and the parameters of this distribution.

  16. Components of SurA required for outer membrane biogenesis in uropathogenic Escherichia coli.

    Directory of Open Access Journals (Sweden)

    Kristin M Watts

    2008-10-01

    Full Text Available SurA is a periplasmic peptidyl-prolyl isomerase (PPIase and chaperone of Escherichia coli and other Gram-negative bacteria. In contrast to other PPIases, SurA appears to have a distinct role in chaperoning newly synthesized porins destined for insertion into the outer membrane. Previous studies have indicated that the chaperone activity of SurA rests in its "core module" (the N- plus C-terminal domains, based on in vivo envelope phenotypes and in vitro binding and protection of non-native substrates.In this study, we determined the components of SurA required for chaperone activity using in vivo phenotypes relevant to disease causation by uropathogenic E. coli (UPEC, namely membrane resistance to permeation by antimicrobials and maturation of the type 1 pilus usher FimD. FimD is a SurA-dependent, integral outer membrane protein through which heteropolymeric type 1 pili, which confer bladder epithelial binding and invasion capacity upon uropathogenic E. coli, are assembled and extruded. Consistent with prior results, the in vivo chaperone activity of SurA in UPEC rested primarily in the core module. However, the PPIase domains I and II were not expendable for wild-type resistance to novobiocin in broth culture. Steady-state levels of FimD were substantially restored in the UPEC surA mutant complemented with the SurA N- plus C-terminal domains. The addition of PPIase domain I augmented FimD maturation into the outer membrane, consistent with a model in which domain I enhances stability of and/or substrate binding by the core module.Our results confirm the core module of E. coli SurA as a potential target for novel anti-infective development.

  17. La gentrification et ses pionniers : le rôle des artistes off en question

    Directory of Open Access Journals (Sweden)

    Elsa Vivant

    2008-09-01

    Full Text Available Cet article propose d’évaluer le rôle des artistes, et plus particulièrement des squats d’artistes, dans la gentrification. La littérature anglo-saxonne insiste en effet beaucoup sur le rôle déterminant de l’arrivée d’artistes plus ou moins marginaux (ceux de la scène dite off dans le déclenchement de la gentrification d’un quartier. Ces artistes sont considérés non seulement comme des initiateurs de la revalorisation symbolique des quartiers qu’ils investissent, mais aussi comme des ferments d’un changement d’ambiance qui permettrait l’arrivée de gentrifieurs plus aisés. Cet article met à l’épreuve ce schéma explicatif à partir de l’étude du cas de Belleville à Paris. Il mobilise pour ce faire deux enquêtes, l’une sur le rapport à leur quartier des habitants de deux rues particulièrement gentrifiées, l’autre sur le marché immobilier. Il apparaît que les artistes sont plus des témoins ou des indicateurs de la gentrification que des déclencheurs ou des catalyseurs. Ils sont partie prenante d’un mouvement de revalorisation de la centralité et de ses ressources (notamment culturelle qui les dépassent. Ce mouvement les dépasse d’autant plus que l’éthique « artiste » s’est largement diffusée dans toutes les couches de la société.This article aims at reassessing the role of artists, and more specifically the role of squatters in the gentrification process. The Anglo-American literature argues that artists influx, especially the underground ones (that we call off, is the key element to trigger the gentrification process in a neighbourhood. These artists are considered as pioneers of the symbolic revalorisation process and as the agent of atmosphere change that brings wealthier gentrifiers to settle down. This article reassesses this scheme, based on the case of Belleville neighbourhood in Paris. It relies on two pieces of researches.  The first one analyses the inhabitants

  18. Equipment for thermal neutron flux measurements in reactor R2

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, E; Nilsson, T; Claeson, S

    1960-04-15

    For most of the thermal neutron flux measurements in reactor R2 cobalt wires will be used. The loading and removal of these wires from the reactor core will be performed by means of a long aluminium tube and electromagnets. After irradiation the wires will be scanned in a semi-automatic device.

  19. A conceptual design of LIB fusion reactor: UTLIF(2)

    International Nuclear Information System (INIS)

    Madarame, Haruki; Kondo, Shunsuke; Iwata, Shuichi; Oka, Yoshiaki; Miya, Kenzo.

    1984-01-01

    UTLIF(2) is a conceptual design study on a light ion beam driven fusion reactor based on a concept of rod-bundle blanket. Survivability and maintainability of the first wall and the blanket are regarded as of major importance in the design. The blanket rod is composed of a thick tube which has enough stiffness, a thin wrapping wall which receives high heat flux, and liquid lithium which breeds tritium and removes generated heat. The rod can be pulled out from the outside of the reactor vessel, hence the replacement is very easy. Nuclear and thermal analysis have been made and the performance of the reactor has been shown to be satisfactory. (author)

  20. The BR2 materials testing reactor. Past, ongoing and under-study upgradings

    Energy Technology Data Exchange (ETDEWEB)

    Baugnet, J M; Roedt, Ch de; Gubel, P; Koonen, E [Centre d' Etude de I' Energie Nucleaire, Studiecentrum voor Kernenergie, C.E.N./S.C.K., Mol (Belgium)

    1990-05-01

    The BR2 reactor (Mol, Belgium) is a high-flux materials testing reactor. The fuel is 93% {sup 235}U enriched uranium. The nominal power ranges from 60 to 100 MW. The main features of the design are the following: 1) maximum neutron flux, thermal: 1.2 x 10{sup 15} n/cm{sup 2} s; fast (E > 0.1 MeV) : 8.4 x 10{sup 14} n /cm{sup 2} s; 2) great flexibility of utilization: the core configuration and operation mode can be adapted to the experimental loading; 3) neutron spectrum tailoring; 4) availability of five 200 mm diameter channels besides the standard channels (84 mm diameter); 5) access to the top and bottom covers of the reactor authorizing the irradiation of loops. The reactor is used to study the behaviour of fuel elements and structural materials intended for future nuclear power stations of several types (fission and fusion). Irradiations are carried out in connection with performance tests up to very high burn-up or neutron fluence as well as for safety experiments, power cycling experiments, and generally speaking, tests under off-normal conditions. Irradiations for nuclear transmutation (production of high specific activity radio-isotopes and transplutonium elements), neutron-radiography, use of beam tubes for physics studies, and gamma irradiations are also carried out. The BR2 is used in support of Belgian programs, at the request of utilities, industry and universities and in the framework of international agreements. The paper reviews the past and ongoing upgrading and enhancement of reactor capabilities as well as those under study or consideration, namely with regard to: reactor equipment, fuel elements, irradiation facilities, reactor operation conditions and long-term strategy. (author)

  1. TiO2 Solar Photocatalytic Reactor Systems: Selection of Reactor Design for Scale-up and Commercialization—Analytical Review

    Directory of Open Access Journals (Sweden)

    Yasmine Abdel-Maksoud

    2016-09-01

    Full Text Available For the last four decades, viability of photocatalytic degradation of organic compounds in water streams has been demonstrated. Different configurations for solar TiO2 photocatalytic reactors have been used, however pilot and demonstration plants are still countable. Degradation efficiency reported as a function of treatment time does not answer the question: which of these reactor configurations is the most suitable for photocatalytic process and optimum for scale-up and commercialization? Degradation efficiency expressed as a function of the reactor throughput and ease of catalyst removal from treated effluent are used for comparing performance of different reactor configurations to select the optimum for scale-up. Comparison included parabolic trough, flat plate, double skin sheet, shallow ponds, shallow tanks, thin-film fixed-bed, thin film cascade, step, compound parabolic concentrators, fountain, slurry bubble column, pebble bed and packed bed reactors. Degradation efficiency as a function of system throughput is a powerful indicator for comparing the performance of photocatalytic reactors of different types and geometries, at different development scales. Shallow ponds, shallow tanks and fountain reactors have the potential of meeting all the process requirements and a relatively high throughput are suitable for developing into continuous industrial-scale treatment units given that an efficient immobilized or supported photocatalyst is used.

  2. Espacio herido, tiempo acelerado, imaginario conmovido. Interrogantes sobre la postmodernidad del Sur.

    Directory of Open Access Journals (Sweden)

    Mabel Franzone

    2010-11-01

    Full Text Available Estableciendo una relación estrecha entre espacio, tiempo e imaginario, este escrito intenta tratar la gran separación Norte- Sur, acaecida con la hipermodernidad y sus consecuencias sobre la destrucción del espacio del Sur ; la cuestión de fondo encara las huellas que puede dejar en los cuerpos y en los imaginarios. Los límites impuestos se tratan en cuatro niveles : históricos, geográficos, económicos- sociales y de la representación. Para una crítica de la modernidad se han tomado parámetros de pensamiento que operan en una trama mediana, forma de pensar propia al Sur y que muestran la necesidad de una epistemología también propia al Sur, que refleje las cuestiones fundamentales y que tenga en cuenta la emancipación y la solidaridad como categorías para repensar el Sur.

  3. Estilos estructurales del Subandino Sur de Bolivia

    OpenAIRE

    Rocha, Emilio

    2013-01-01

    El Subandino Sur de Bolivia es una típica faja plegada y corrida de lámina delgada, con una notable regularidad en la geometría de las estructuras. Esta es una característica típica de las fajas plegadas en las que no se involucra el basamento en la deformación. Sin embargo, cuando se analiza en detalle la geometría y evolución de la deformación del Subandino Sur, se verifica que existen numerosas desviaciones de dicha regularidad. En el presente trabajo se estudiaron los diferentes procesos ...

  4. Planned Scientific programs around the Triga Mark 2 Reactor

    International Nuclear Information System (INIS)

    Majah, M Ibn.

    2007-01-01

    Full text: Nuclear techniques have been introduced to Morocco since the sixties. After the energy crisis of 1973, Morocco decides to create the National Center for Energy Sciences and Nuclear Techniques (CNESTEN) under the supervision of the Ministry of high Education and Research, with a research commercial and support vocation. CNESTEN is in charge of promoting nuclear application, to act as technical support for the authorities and to prepare the technological basis for nuclear power option. In 1998, CNESTEN started the construction of Nuclear Research Centre. The on going activities cover many sectors : earth and environmental sciences, high energy physics, safety and security, waste management. In 2001, CNESTEN started the construction of a 2MW TRiga Mark 2 Reactor, with the possibility to increase the power to 3 MW. The construction was achieved in January 2007. The operation of the reactor is expected for April 2007. The program of the utilization of the reactor was established with th contribution of the university and with the assistance of IAEA. Some of the experimental set-up installed around the reactor have been designed. CNESTEN has developed cooperation with Nuclear research centres from other countries and is receiving visitors and trainees mainly through the IAEA [fr

  5. Research on anhydrous hydrazine synthesis; Recherche sur la synthese de l'hydrazine anhydre

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-03-15

    The first part of this work concerns the radiolysis of pure liquid ammonia. The fundamental importance of the dose rate and of the dose on the yield of radiolytic products has been demonstrated. By using a capture solute at concentrations of between 10{sup -3} and 1.2 mole s/litre, it has been possible to determine the yields of radicals and of molecules in the irradiated pure ammonia. During later work, it was possible to determine, by systematically varying the physico-chemical parameters, the most favorable conditions for carrying out the radiosynthesis; the maximum radiochemical yield of the hydrazine obtained has a value: G (N{sub 2}H{sub 4}) = 2.2/100 eV. An analysis of the molecular yields in the presence of deuterated solutes makes it possible to explain partially the role of the capture species. A project is also described for an installation producing hydrazine continuously; it is followed by an economic study of the process. From this work it appears that the yields of hydrazine obtained justify an industrial application, especially if strong radiation sources are available, for example nuclear reactors. (author) [French] La premiere partie de l'etude a porte sur la radiolyse de l'ammoniac liquide pur. Le role fondamental du debit de dose et de la dose sur les rendements des produits de radiolyse a ete mise en evidence. L'emploi de solute capteur dont les concentrations sont comprises entre 10{sup -3} et 1,2 mole/litre, a permis de determiner la valeur des rendements radicalaires et moleculaires dans l'ammoniac pur irradie. Au cours d'une etape ulterieure, une variation systematique des parametres physico-chimiques a permis de determiner les conditions les plus favorables a la radiosynthese le rendement radiochimique maximum de l'hydrazine obtenu a pour valeur: G(N{sub 2}H{sub 4}) 2,2/100 eV. L'analyse des rendements moleculaires en presence de solutes deuteres nous permet de rendre compte partiellement du role des

  6. Rapport annuel au Parlement Loi sur la protection des ...

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

    3) l'innovation, la politique et la science, 4) la recherche pour l'équité en santé et ... Le Centre n'a reçu aucune plainte au sujet de l'administration de la Loi sur la ... Art. 18(2). VI. Extentions/. Prorogations des délais. 30 days or under /. 30 jours ...

  7. Le lancement canadien du Rapport sur les politiques alimentaires ...

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

    1 mai 2018 ... Cet événement sera filmé, puis accessible en ligne sur la chaîne YouTube du CRDI. Le Rapport sur les politiques alimentaires mondiales 2018 passe en revue les principaux faits nouveaux et événements en matière de politiques alimentaires survenus au cours de l'année. D'éminents chercheurs ...

  8. Analyse technico–économique des Aliments densifies sur les ...

    African Journals Online (AJOL)

    Une étude portant sur l'influence des aliments densifiés sur la performance de croissance des boucs roux de Maradi a été conduite entre juillet 2016 à septembre 2016. Quarante deux (42) boucs ont été répartis au hasard en six lots de sept individus. Chaque lot correspond à un aliment ou traitement préparé à partir des.

  9. New K-Ar ages of altered rocks from Paramillos Sur and Norte: Interpretation of the results; Nuevas edades K-Ar de las rocas alteradas de Paramillos Sur y Norte: Interpretacion de los resultados

    Energy Technology Data Exchange (ETDEWEB)

    Koukharsky, Magdalena; Brodtkorb, Alejo [Buenos Aires Univ. (Argentina). Facultad de Ciencias Exactas y Naturales; Munizaga, Francisco [Chile Univ., Santiago (Chile). Dept. de Geologia

    1998-07-01

    The whole-rock K-Ar dates from porphyry copper prospects of Paramillos Sur (phyllic and potasic alteration zones) and Paramillos Norte (propilitic zone) are reported. Radiometric data yielded 17,8 {+-} 0,9 Ma, 15,8 {+-} 1,0 Ma and 15,2 {+-} 0,5 Ma in Paramillos Sur, and 17,3 {+-} 0,7 Ma in Paramillos Norte, which can be added to an previously reported age of 16,4 {+-} 0,3 Ma. These data are in agreement with isotopic ages from non altered or non mineralized magmatic rocks of the region. When the isotopic ages and petrographic characteristics of the dated rocks are considered, two alteration-mineralization events are suggested for Paramillos Sur prospect. However this possibility needs to be confirmed by means of future studies, in view of the reduced interval between these events when compared with the analytical errors. (author)

  10. Concilier plaisir et nutrition. Travaux des groupes de travail PNNS sur les lipides et sur le goût

    OpenAIRE

    Souliac , L.; Bizet, G.; Remy, S.

    2010-01-01

    Les ministères chargés de l'alimentation et de la santé ont incité les opérateurs à mettre sur le marché des aliments moins riches en lipides, par la signature avec l'État de chartes d'engagement sur la composition nutritionnelle. L'observatoire de la qualité de l'alimentation suit l'évolution de ces efforts. Les lipides ont un rôle technologique et sensoriel important qu'il convient de prendre en considération. Il est aujourd'hui possible d'améliorer le profil nutritionnel des aliments, tout...

  11. Données préliminaires sur le paludisme humain en zones rurale et ...

    African Journals Online (AJOL)

    SARAH

    31 juil. 2017 ... axée sur le diagnostic précoce et la prise en charge rapide des ... recherche investigue sur les connaissances, attitudes et ... paludisme et (vi) sur la source de traitement du paludisme. ... technique ELISA (Burkot et al., 1984).

  12. Power noise spectrum classification in the problem of the IBR-2 reactor

    International Nuclear Information System (INIS)

    Bargel, M.; Kitowski, J.; Pepelyshev, Yu.N.

    1988-01-01

    The classification spectrum results of random fluctuations in the IBR-2 energy pulse are presented. The work is performed for the application of the obtained results to the reactor diagnostics and the study of its noise uncontrolled states. For classification of the spectra the method of pattern recognition based upon the ISODATA heuristic algorithm is used. It is shown that a set of noise uncontrolled reactor states, registered during the reactor operation period at power of 0.4-2 MVt with the first variant of moving reflector (1983-1986) is formed into 4(5) most typical states. Each of the states corresponds to the general conditions of the reactor core cooling and provides the normal work of the moving reflector. However, these states differ in coolant flow, power level and peculiarities of the moving reflector rotation regime. One type of anomal power noise, connected with some disorder in the moving reflctor work, is isolated. This work also presents the possibility of control over the state of moving reflectors according to the change in the amplitude of power oscillations at some frequences. The reactor noise classification results can be used as the data bank for the IBR-2 reactor diagnostic system

  13. Characterization of surface antigen protein 1 (SurA1) from Acinetobacter baumannii and its role in virulence and fitness.

    Science.gov (United States)

    Liu, Dong; Liu, Zeng-Shan; Hu, Pan; Cai, Ling; Fu, Bao-Quan; Li, Yan-Song; Lu, Shi-Ying; Liu, Nan-Nan; Ma, Xiao-Long; Chi, Dan; Chang, Jiang; Shui, Yi-Ming; Li, Zhao-Hui; Ahmad, Waqas; Zhou, Yu; Ren, Hong-Lin

    2016-04-15

    Acinetobacter baumannii is a Gram-negative bacillus that causes nosocomial infections, such as bacteremia, pneumonia, and meningitis and urinary tract and wound infections. In the present study, the surface antigen protein 1 (SurA1) gene of A. baumannii strain CCGGD201101 was identified, cloned and expressed, and then its roles in fitness and virulence were investigated. Virulence was observed in the human lung cancer cell lines A549 and HEp-2 at one week after treatment with recombinant SurA1. One isogenic SurA1 knock-out strain, GR0015, which was derived from the A. baumannii strain CCGGD201101 isolated from diseased chicks in a previous study, highlighted the effect of SurA1 on fitness and growth. Its growth rate in LB broth and killing activity in human sera were significantly decreased compared with strain CCGGD201101. In the Galleria mellonella insect model, the isogenic SurA1 knock-out strain exhibited a lower survival rate and decreased dissemination. These results suggest that SurA1 plays an important role in the fitness and virulence of A. baumannii. Copyright © 2016 Elsevier B.V. All rights reserved.

  14. Enquêtes sur les soucoupes volantes

    OpenAIRE

    Lagrange, Pierre

    2007-01-01

    La dispute autour du mot « preuve » se réduit à une question : Qu'est-ce qui constitue une preuve ? Faut-il qu'un ovni atterrisse à l'entrée du Pentagone, près des bureaux des chefs d'État-Major ? Ou bien est-ce une preuve quand une station de radar au sol détecte un ovni, envoie un jet l'intercepter, que le pilote du jet le voit et le suit sur son radar pour finir par le voir disparaître à une vitesse phénoménale ? Ou est-ce une preuve quand un pilote tire sur un ovni et maintient son histoi...

  15. Research reactor FR2 - 20 years chemical and radiochemical measurements

    International Nuclear Information System (INIS)

    Feuerstein, H.; Graebner, H.; Oschinski, J.; Hoffmann, W.; Beyer, J.

    1986-09-01

    The FR2 has been a D 2 O cooled and moderated research reactor with a thermal output of 44 MW. It was in operation from 1961 to 1981. Because of the operating conditions of the reactor, only a small number of routine measurements were performed. For these however special techniques had to be developed. During the 20 years of operation a number of special events occured or have been observed, sometimes with very amazing results, e.g. the 'aceton effect'. This report describes the chemical and radiochemical conditions of the reactor systems, as well as the results of the surveilance work. Not described are measurements for the many experiments. The last chapter gives in a short form a description of the most unusual events and observations. (orig.) [de

  16. Venting krypton-85 from the Three Mile Island Unit 2 reactor building

    International Nuclear Information System (INIS)

    Burton, H.M.

    1981-01-01

    To permit the less restricted access to the reactor building necessary to maintain instrumentation and equipment, and to proceed towad the total decontamination of the facility, General Public Utilities, operators of the facility referred to hereafter as GPU, asked the United States Nuclear Regulatory Commission, or NRC, for permission to remove the 85 Kr from the reactor building by venting it to the environment. GPU supported their request with the Safety Analysis and Environmental Assessment Report on the proposed reactor building venting plan. On June 12, 1980, after seven months of licensing deliberations and numerous public hearings, the NRC granted GPU's request. The actual venting took place between June 28 and July 11, 1980. This report presents an overview of the detailed effort involved in the TMI-2 reactor building venting program. The findings reported here are condensed from a published report entitled TMI-2 Reactor Building Purge--Kr-85 Venting

  17. Research on economics and CO2 emission of magnetic and inertial fusion reactors

    International Nuclear Information System (INIS)

    Mori, Kenjiro; Yamazaki, Kozo; Oishi, Tetsutarou; Arimoto, Hideki; Shoji, Tatsuo

    2011-01-01

    An economical and environment-friendly fusion reactor system is needed for the realization of attractive power plants. Comparative system studies have been done for magnetic fusion energy (MFE) reactors, and been extended to include inertial fusion energy (IFE) reactors by Physics Engineering Cost (PEC) system code. In this study, we have evaluated both tokamak reactor (TR) and IFE reactor (IR). We clarify new scaling formulas for cost of electricity (COE) and CO 2 emission rate with respect to key design parameters. By the scaling formulas, it is clarified that the plant availability and operation year dependences are especially dominant for COE. On the other hand, the parameter dependences of CO 2 emission rate is rather weak than that of COE. This is because CO 2 emission percentage from manufacturing the fusion island is lower than COE percentage from that. Furthermore, the parameters dependences for IR are rather weak than those for TR. Because the CO 2 emission rate from manufacturing the laser system to be exchanged is very large in comparison with CO 2 emission rate from TR blanket exchanges. (author)

  18. Experimental methods of reactor physics; Methodes experimentales de physique des reacteurs a neutrons thermiques

    Energy Technology Data Exchange (ETDEWEB)

    Breton, D; Lafore, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    This paper is a synthesis of various experimental methods in use with the reactors of the Commissariat a l'Energie Atomique. The main techniques used are mentioned and the difficulties encountered and the accuracy obtained are particularly dwelt upon. The application of these various methods to reactors in order to obtain specific results is also indicated. This paper consists of five parts. I - General methods. Macroscopic and microscopic flux distribution (anisotropy effect), power distribution, etc... II - Kinetic measurements a) pulsed neutron technique: apparatus and accuracy; application to {lambda}t and to anti reactivity measurements; application to graphite, light water and beryllium oxide. b) oscillation techniques: equipment and accuracy; application to the measurements of effective cross sections and resonance integrals. c) fluctuations: apparatus and technique of measurement. III - Poison methods. Description of methods for introducing and extracting the poison, difficulties encountered with light and heavy water, measurement of temperature coefficients and anti-reactivity. IV - Spectra measurements. Choice and development of foils, problems of measurement, application to spectral measurements for thermalization studies, application to dosimetry. V - Experimental shielding measurements. The technique and apparatus recently developed in this field are presented. (authors) [French] Cette communication fait une synthese des differentes methodes experimentales mises en oeuvre sur les reacteurs du CEA. Elle presente les principales techniques utilisees et insiste plus particulierement sur les difficultes rencontrees et la precision obtenue; elle indique egalement l'application de ces differentes methodes sur les reacteurs, en vue de l'obtention des resultats determines. Elle comporte cinq parties: I - METHODES GENERALES: Distribution de flux macroscopique et microscopique (effet d'anisotropie), distribution de puissance, etc... II - MESURES CINETIQUES: a

  19. Development of a TiO2-coated optical fiber reactor for water decontamination

    International Nuclear Information System (INIS)

    Danion, A.

    2004-09-01

    The objective of this study was to built and to study a photo-reactor composed by TiO 2 -coated optical fibers for water decontamination. The physico-chemical characteristics and the optical properties of the TiO 2 coating were first studied. Then, the influences of different parameters as the coating thickness, the coating length and the coating volume were investigated both on the light transmission in the TiO 2 - coated fiber and on the photo-catalytic activity of the fiber for a model compound (malic acid). The photo-catalytic degradation of malic acid was optimized using the experimental design methodology allowing to build a multi-fiber reactor comprising 57 optical fibers. The photo-degradation of malic acid was conducted in the multi-fiber reactor and it was demonstrated that the multi-fiber reactor was more efficient than the single-fiber reactor at the same fibers density. Finally, the multi-fiber reactor was applied to the photo-degradation of a fungicide, called fenamidone, and a degradation pathway was proposed. (author)

  20. Physical events that occur in the reactor core during load changes; Les effets physiques sur le coeur mis en jeu lors des variations de puissance

    Energy Technology Data Exchange (ETDEWEB)

    Paulin, Ph. [Electricite de France (EDF/DPN/UNIE/GECC), 93 - Saint-Denis (France); Golfier, H. [CEA Saclay (DEN-DANS/DM2S/SERMA/LPEC), 91 - Gif-sur-Yvette (France)

    2007-05-15

    The reactor core control aims at mastering 2 important parameters that are relevant for reactor availability and safety. First, the reactivity that sets the power output and secondly, the power map in order to handle hot spots. In PWR-type reactors, physical events such as moderator or fuel temperature changes, xenon concentration, that are important for both parameters, evolve during load changes but also during power plateaus and are dependent on burn-up. In this article temperature effect and xenon poisoning are analysed and their impact are assessed along an irradiation campaign through a core neutronic simulation and data from instrumentation. Xenon oscillations are particularly well illustrated. The counter-reactions of the means used for reactor controlling: soluble boron and control rods, are also analysed. (A.C.)

  1. Hausse des taxes sur le tabac dans trois pays d'Amérique centrale ...

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

    Les chercheurs mèneront des études sur la demande de produits du tabac dans le ... sur les techniques modernes de contrôle de la chaîne d'approvisionnement, ... IWRA/CRDI sur les changements climatiques et la gestion adaptive de l'eau.

  2. TMI-2 reactor-vessel head removal and damaged-core-removal planning

    International Nuclear Information System (INIS)

    Logan, J.A.; Hultman, C.W.; Lewis, T.J.

    1982-01-01

    A major milestone in the cleanup and recovery effort at TMI-2 will be the removal of the reactor vessel closure head, planum, and damaged core fuel material. The data collected during these operations will provide the nuclear power industry with valuable information on the effects of high-temperature-dissociated coolant on fuel cladding, fuel materials, fuel support structural materials, neutron absorber material, and other materials used in reactor structural support components and drive mechanisms. In addition, examination of these materials will also be used to determine accident time-temperature histories in various regions of the core. Procedures for removing the reactor vessel head and reactor core are presented

  3. Une nouvelle ouverture sur le monde pour les femmes | CRDI ...

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

    'appellent ailleurs dans le dédale d'étals et d'allées serrés. En plus de son travail sur le marché, Jertrudes est également secrétaire de l'association des femmes qui vendent sur ce marché. Le groupe est un endroit où elles ...

  4. Economic Effect on the Plutonium Cycle of Employing {sup 235}U in Fast Reactor Start-Up; Incidence Economique du Demarrage des Reacteurs Rapides a l'Aide d'Uranium-235 sur le Cycle du Plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Van Dievoet, J.; Egleme, M.; Hermans, L. [BELGONUCLEAIRE, Bruxelles (Belgium)

    1967-09-15

    Preliminary results are presented of a study carried out under an agreement concluded between Euratom and the Belgian Government to evaluate the advantages of loading fast reactors with {sup 235}U. There are several ways of starting up a fast reactor with {sup 235}U: (1) the reactor can be operated entirely with enriched uranium, the plutonium produced being used to start up and operate other reactors; in this case the uranium is recycled within the reactor and more enriched uranium is added; (2) the plutonium produced can be partly recycled within the reactor together with the uranium; in this case the reactor is transformed gradually into a plutonium reactor. These two procedures can be combined and applied simultaneously in different enrichment zones of the same reactor, enriched uranium being added, for example, to the internal zone and plutonium recycled in the external zone. The method of reprocessing the fuel is also a complicating factor, depending on whether the core and the axial breeding blankets are reprocessed together or separately. Similarly, where a reactor has several enrichment zones, these can likewise be reprocessed either together or separately. The calculations are performed with the help of a code that uses the equivalence coefficients defined by Baker and Ross for the part relating to the characteristics of successive reactors, and the discounted fuel cycle cost method for the economic part. In the first stage of this work a rough analysis was made. The reloading of each zone was assumed to be carried out in a single operation, and the time spent by the fuel elements out of pile was ignored. In a later stage, progressive reloading by batches will be considered, with allowance for fabrication and reprocessing times, etc. The most interesting results relate to variations in fuel composition (plutonium content, isotopic composition) from one cycle to another, variations in the fuel cycle characteristics (doubling time, loading and unloading

  5. Influence de l'irrigation sur le rendement et sur la qualité des raisins

    Directory of Open Access Journals (Sweden)

    J. Cerny

    1968-12-01

     Le travail présenté résume les résultats de l'expérience avec l'irrigation supplémentaire de la vigne dans le domaine sec du Sud de la Moravie ainsi que son influence sur le rendement et la qualité des raisins.

  6. Proceedings of the 1992 topical meeting on advances in reactor physics. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    This document, Volume 2, presents proceedings of the 1992 Topical Meeting on Advances in Reactor Physics on March 8--11, 1992 at Charleston, SC. Session topics were as follows: Transport Theory; Fast Reactors; Plant Analyzers; Integral Experiments/Measurements & Analysis; Core Computational Systems; Reactor Physics; Monte Carlo; Safety Aspects of Heavy Water Reactors; and Space-Time Core Kinetics. The individual reports have been cataloged separately. (FI)

  7. Fissile fuel production and usage of thermal reactor waste fueled with UO2 by means of hybrid reactor system

    International Nuclear Information System (INIS)

    Ipek, O.

    1997-01-01

    The use of Fast Breeder Reactors to produce fissile fuel from nuclear waste and the operation of these reactors with a new neutron source are becoming today' topic. In the thermonuclear reactors, it is possible to use 2.45-14.1 MeV - neutrons which can be obtained by D-T, D-D Semicatalyzed (D-D) and other fusion reactions. To be able to do these, Hybrid Reactor System, which still has experimental and theoretical studies, have to be taken into consideration.In this study, neutronic analysis of hybrid blanket with grafit reflector, is performed. D-T driven fusion reaction is surrounded by UO 2 fuel layer and the production of ''2''3''9Pu fissile fuel from waste ''2''3''8U is analyzed. It is also compared to the other possible fusion reactions. The results show that 815.8 kg/year ''2''3''8Pu with D-T reaction and 1431.6 kg/year ''2''3''8Pu with semicatalyzed (D-D) reaction can be produced for 1000 MW fusion power. This means production of 2.8/ year and 4.94/ year LWR respectively. In addition, 1000 MW fusion flower is is multiplicated to 3415 MW and 4274 MW for D-T and semicatalyzed (D-D) reactions respectively. The system works subcritical and these values are 0.4115 and 0.312 in order. The calculations, ANISN-ORNL code, S 16 -P 3 approach and DLC36 data library are used

  8. Caractérisation intégrée du vignoble alsacien : aspects méthodologiques et application à l'étude des composantes naturelles des principaux terroirs

    Directory of Open Access Journals (Sweden)

    Éric Lebon

    1993-12-01

    Full Text Available Parmi les méthodes utilisées en vue de la définition des potentialités viticoles, l'approche intégrée des terroirs fondée sur la notion de séquence écogéopédologique développée en Moyenne Vallée de la Loire par l'INRA d'Angers s'est révélée particulièrement performante. Son application à la caractérisation du vignoble d'Alsace, fondamentalement différent sur le plan de sa structure géologique, nécessite un certain nombre d'aménagements méthodologiques liés à une variabilité paysagère marquée. Ainsi, une typologie des paysages s'appuyant sur des paramètres tels que l'ouverture du paysage, la répartition et l'orientation des masques est proposée. Elle vient compléter les descripteurs stationnels classiques (altitude, pente et exposition. Le concept de séquence écogéopédologique reste pertinent dans ce contexte moyennant l'adjonction du paramètre exposition, dans le cas des terroirs sur versants. Dans cette optique, les caractéristiques des composantes naturelles des grands types de terroirs alsaciens sont présentées à partir de l'étude de cas concrets.

  9. Journal Afrika Statistika ISSN 0852-0305 Sur les estimateurs du ...

    African Journals Online (AJOL)

    Sur les estimateurs du maximum de vraisemblance dans les mod`eles multiplicatifs de Poisson et binomiale négative. 298. [1], Berk [2], Bickel et Doksum [3], ..... montrons l'implication (A2) ⇒(A1). Soit ˆµ l'EMV du mod`ele, alors toutes ses composantes sont strictement positives, et, d'apr`es le lemme 3, il vérifie l'équation.

  10. A theoretical analysis of methanol synthesis from CO2 and H2 in a ceramic membrane reactor

    NARCIS (Netherlands)

    Gallucci, F.; Basile, A.

    2007-01-01

    In this theoretical work the CO2 conversion into methanol in both a traditional reactor (TR) and a membrane reactor (MR) is considered. The purpose of this study was to investigate the possibility of increasing CO2 conversion into methanol with respect to a TR. A zeolite MR, able to combine

  11. El bioclima humano en urbes del sur de México para condiciones de duplicación de CO2 atmosférico

    Directory of Open Access Journals (Sweden)

    Adalberto Tejeda Martínez

    2012-02-01

    Full Text Available . A partir del concepto de temperatura efectiva (TE, se presenta un escenario de las condiciones de bioclima humano de ocho ciudades importantes del sur de México, obtenido de predicciones regionales de modelos de circulación general para el caso de una duplicación en la concentración atmosférica global de CO2. Los resultados se ilustran con gráficas de las condiciones de confort actuales y futuras para el sur del país. Se encontró que, pese a los procesos de aclimatación, se intensificarán las sensaciones cálidas debido al efecto invernadero. Combinando lo anterior con proyecciones conservadoras del incremento de la población para la segunda mitad del siglo XXI, se estima que las ciudades de clima cálido quintuplicarán las necesidades de enfriamiento para obtener el confort de sus habitantes.

  12. 118 Variabilité climatique et son incidence sur les ressources en ...

    African Journals Online (AJOL)

    MARTINE

    particulièrement fortes et touchent de nombreux secteurs d'activité. Le changement ... économique était basé sur l'agriculture est très sensible au contexte climatique [8,9]. ..... rupture. 3-2-6 Calcul du coefficient de tarissement : loi de Maillet.

  13. Cronos 2: a neutronic simulation software for reactor core calculations

    International Nuclear Information System (INIS)

    Lautard, J.J.; Magnaud, C.; Moreau, F.; Baudron, A.M.

    1999-01-01

    The CRONOS2 software is that part of the SAPHYR code system dedicated to neutronic core calculations. CRONOS2 is a powerful tool for reactor design, fuel management and safety studies. Its modular structure and great flexibility make CRONOS2 an unique simulation tool for research and development for a wide variety of reactor systems. CRONOS2 is a versatile tool that covers a large range of applications from very fast calculations used in training simulators to time and memory consuming reference calculations needed to understand complex physical phenomena. CRONOS2 has a procedure library named CPROC that allows the user to create its own application environment fitted to a specific industrial use. (authors)

  14. Chaire de recherche trilatérale Canada – Afrique du Sud sur les ...

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

    Le présent projet met l'accent sur les interactions entre l'humain et la faune, notamment sur les pauvres des zones rurales en pays tropical et sur l'effet des changements climatiques que ces derniers subiront. Puisant dans la recherche menée à la station de biologie expérimentale de l'Université Makere, près du parc ...

  15. Study and Construction of the Metal Vessels for the Reactors of the EDF1 and EDF2 Sectors at Chinon; Etude et construction des caissons metalliques des reacteurs des tranches EDF1 et EDF2 de la centrale de Chinon; Izuchenie i konstruktsiya metallicheskikh korpusov reaktorov pervoj i vtoroj chasti programm ehlektrostantsij; Estudio y construccion de los recipientes metalicos de los reactores EDF1 y EDF2 de la central de Chinon

    Energy Technology Data Exchange (ETDEWEB)

    Lamiral, G.; Millot, R.; Passerieux, P. [Electricite de France, Clamart, Seine (France)

    1963-10-15

    The first two natural uranium-graphite-C0{sub 2} reactors at the Chinon station have metal vessels of thick manganese-molybdenum steel plate. The studies carried out on these vessels raised certain problems, particularly in connection with the design and dimensions of the port reinforcements. The reinforcements for the control-rod channels and fuel ports were studied on mock-ups and the results obtained were checked on the completed reactors during hydraulic tests. The type of construction initially used for the EDF1 vessel was relatively simple. The plates to be welded were locally preheated, and the vessel was not supposed to undergo more than one stress-relief heat treatment after completion of all the welding. Serious cracks developed, however, and it became necessary to alter the whole method of construction. In particular, the welding was now done after overall preheating and the vessel was subjected to multiple stress-relief treatments. This made it possible to fabricate the vessels for EDF1 and EDF2, but at the same time imposed certain limitations which considerably complicated work on the site. (author) [French] Les reacteurs a uranium naturel, graphite et gaz carbonique des deux premieres tranches de la Centrale de Chinon comportent des caissons metalliques realises a partir de toles de fortes epaisseurs, en acier au manganese-molybdene. Les etudes de ces paissons ont pose certains problemes, notamment en ce qui concerne les renforts d'ouvertures. Les renforts des passages des barres de controle et des orifices de chargement ont ete etudies sur maquette et les resultats obtenus ont ete controles sur les ouvrages termines lors des epreuves hydrauliques. Le mode de construction initialement utilise pour le caisson de la tranche EDF1 etait relativement simple; les toles a souder etaient prechauffees localement et le caisson ne devait subir qu'un seul traitement thermique de detente, apres execution de toutes les soudures. Une fissuration importante en cours

  16. Set of rules SOR 2 reactor site criteria

    International Nuclear Information System (INIS)

    1976-06-01

    The purpose of this set of rules is to describe criteria which guide the Director in his evaluation of the suitability of proposed sites for stationary power and testing reactors subject to SOR 2. (B.G.)

  17. Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

    International Nuclear Information System (INIS)

    Liu Guisheng

    1995-01-01

    How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testings of CENDL-2 and ENDF/B-6. (4 tabs., 2 figs.)

  18. Rapport annuel au Parlement Loi sur la protection des ...

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

    Larocque, Samia

    1 juil. 1983 ... TBS/SCT 350-63 (Rév. 2011/03). 31/03/2014. 01/04/2013. Période visée par le rapport : Reçues pendant la période visée par le rapport. Total. En suspens à la fin de la période de rapport précédente. Rapport statistique sur la Loi sur la protection des renseignements personnels. Nom de l'institution :.

  19. Reconnaissance aveugle de codages OSTBC basée sur les propriétés matricielles des statistiques d'ordre 2.

    OpenAIRE

    Choqueuse , Vincent ,; Collin , Ludovic; Yao , Koffi Clément; Burel , Gilles

    2007-01-01

    International audience; La reconnaissance aveugle des paramètres d'une communication est une thématique importante dans le contexte des récepteurs auto-configurants et de la guerre électronique. Actuellement, peu de recherches se focalisent sur la reconnaissance aveugle du codage spatio-temporel utilisé dans les communications sans fils multi-émetteurs. Pour caractériser ces codages, nous proposons une nouvelle fonction de contraste basée sur des propriétés matricielles remarquables de statis...

  20. Study of isotopic exchange reactors (1961); Etude des reacteurs d'echange isotopique (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Grandcollot, P; Dirian, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    A study is made of the general case of the theory of first-order isotopic chemical exchange between a gaseous and a liquid phase in a reactor, starting from fundamental reaction kinetics data, and without making any limiting hypothesis concerning the value of the separation factor. The cases of counter-current reactors and of co-current reactors are considered successively. The general deuterium conservation equation requires the definition of the quotient of the reactor; the performances of this reactor are characterised by its overall efficiency. The idea of the ratio is introduced because it represents a convenient intermediary in the calculations. The search for an additive value for reactors in series leads logically to the defining of an exchange capacity, and a total efficiency, or number of theoretical reactors. This method of expressing the performances of a reactor is more general than the efficiency due to Murphee which only has a physical significance in the particular case of homogeneous liquid reactors. The relationships between these various quantities are established, and the representation due to Mc Cabe and Thiele is generalized. The reactor performances are linked to the first - order reaction kinetics by the transfer number. The relationships are given for a certain number of concrete cases. Finally the application of these calculations is given, together with the approximations necessary in the case where, because of the presence of several components in each phase, the exchange reaction no longer obeys a single kinetic law. (authors) [French] On examine dans le cas general la theorie d'un reacteur quelconque pour l'echange chimique isotopique du premier ordre entre une phase gazeuse et une phase liquide, a partir des donnees fondamentales sur la cinetique de la reaction, sans faire aucune hypothese limitative sur le cas des reacteurs a contre ourant, puis celui des reacteurs a co-courant. L'equation generale de conservation du deuterium

  1. Colza et abeilles : exposé de la problématique et mise en place d’un dispositif de vigilance sur les ruchers en région Centre

    Directory of Open Access Journals (Sweden)

    Robert Céline

    2011-05-01

    Full Text Available The apiarian and agricultural sectors got together to set up an apiary survey in Eure-et-Loir, in 2010, during oilseed rape flowering. The aim of this observatory was to highlight what can occur during oilseed rape flowering regarding bee population evolution and agricultural practices. The year 2010 was marked by important larvae and brood mortalities which induced a national investigation. Among the 4 surveyed apiaries, 2 were also concerned by these mortalities but this could not be explained by the observations and the analysis that were carried out. However, this survey enabled us to identify apiarian and agricultural practices around the apiaries and to combine expert testimonies of apiarian and agricultural professionals.

  2. Groundwater Monitoring Plan for the Reactor Technology Complex Operable Unit 2-13

    International Nuclear Information System (INIS)

    Richard P. Wells

    2007-01-01

    This Groundwater Monitoring Plan describes the objectives, activities, and assessments that will be performed to support the on-going groundwater monitoring requirements at the Reactor Technology Complex, formerly the Test Reactor Area (TRA). The requirements for groundwater monitoring were stipulated in the Final Record of Decision for Test Reactor Area, Operable Unit 2-13, signed in December 1997. The monitoring requirements were modified by the First Five-Year Review Report for the Test Reactor Area, Operable Unit 2-13, at the Idaho National Engineering and Environmental Laboratory to focus on those contaminants of concern that warrant continued surveillance, including chromium, tritium, strontium-90, and cobalt-60. Based upon recommendations provided in the Annual Groundwater Monitoring Status Report for 2006, the groundwater monitoring frequency was reduced to annually from twice a year

  3. Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

    International Nuclear Information System (INIS)

    Liu Guisheng

    1995-11-01

    How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testing of CENDL-2 and ENDF/B-6. (author). 8 refs, 2 figs, 4 tabs

  4. Des pratiques culturales influent sur les attaques de deux ravageurs ...

    African Journals Online (AJOL)

    La culture de tomate est attaquée par plusieurs ravageurs dont Helicoverpa armigera et Tuta absoluta. Dans le but d'évaluer l'effet des pratiques culturales de la tomate sur ces principaux ravageurs dans les Niayes (Sénégal), un échantillonnage de 98 parcelles est effectué, sur quatre cycles de culture en saison sèche, de ...

  5. An experimental investigation of fission product release in SLOWPOKE-2 reactors - Data report

    International Nuclear Information System (INIS)

    Harnden, A.M.C.

    1995-09-01

    The results of an investigation into the release of fission products from SLOWPOKE-2 reactors fuelled with a highly-enriched uranium alloy core are detailed in Volume 1. This data report (Volume 2) contains plots of the activity concentrations of the fission products observed in the reactor container at the University of Toronto, Ecole Polytechnique and the Kanata Isotope Production Facility. Release rates from the reactor container water to the gas headspace are also included. (author)

  6. The safety and efficacy of hemostasis with Clo-Sur P.A.D. after transcatheter arterial chemoembolization

    International Nuclear Information System (INIS)

    Jung, Seung Chai; Jae, Hwan Jun; Kim, Sang Youn; Lee, Whal; Chung, Jin Wook; Park, Jae Hyung

    2007-01-01

    We wanted to evaluate the safety and efficacy of a new hemostatic device, Clo-Sur P.A.D., at an arterial access site after performing femoral arterial catheterization to achieve transcatheter arterial chemoembolization (TACE). From August 2002 to March 2005, 113 patients who underwent TACE and agreed on using the Clo-Sur P.A.D. were enrolled in this study. We evaluated the mean time interval from compression to the first movement and also to the first walk. We also evaluated such complications as rebleeding, pseudoaneurysm, vascular occlusion, hematoma, infection and pain. For 92 patients who had previous experiences with manual compression, we evaluated their preference of hemostatic method by asking them. Successful hemostasis was achieved with the Clo-Sur P.A.D. in 105 subjects (92%). The mean time interval from compression to the first movement was 201 minutes, and that to the first walk was 267 minutes. There was no statistical difference between the complicated and the uncomplicated groups for the mean time, prothrombin time, Child-Pugh class and platelet count (ρ > 0.05). Rebleeding occurred in 3 patients (2.7%) and mild hematoma around puncture site was noted in 5 patients (5.4%). Eighty-seven patients (95%) preferred Clo-Sur P.A.D. to the manual compression method. The Clo-Sur P.A.D. is a safe and effective hemostatic device and it provides early ambulation after TACE

  7. Les mesures de gel et de confiscation en vertu de la Loi sur les embargos

    OpenAIRE

    Schnyder, Nicolas

    2009-01-01

    Etude du mécanisme d'adoption des mesures de gel et de confiscation en vertu de la Loi sur les embargos et leurs conséquences tant sur la personne principalement touchée par ces mesures que sur les tiers.

  8. Commission des Nations Unies sur les produits indispensables aux ...

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

    Étude des soins de santé primaires dispensés dans les pays du cône Sud. Les pays membres du Réseau de recherche sur les systèmes et services de santé dans les pays du cône Sud (Red de Investigación en Sistemas y Servicios de Salud en el Cono Sur) ont des systèmes de... Voir davantageÉtude des soins de santé ...

  9. Savoir lire les centres historiques comme clé pour construire la ville de demain

    Directory of Open Access Journals (Sweden)

    Alexis Sierra

    2010-05-01

    Full Text Available Yves Dauge est sénateur d’Indre et Loire (membre de la commission de la culture, de l'éducation et de la communication, membre du groupe d'études sur le patrimoine architectural. Inspecteur général de l’équipement, ancien maire de Chinon, il a été délégué interministériel à la ville et au développement social urbain de 1988 à 1991. Il a conduit la délégation française au Vème Forum Urbain Mondial à Rio. Il anime avec les services du Ministère des Affaires Etrangères et Européennes, le nouvea...

  10. Safety assessments relating to the use of new fuels in research reactors: application to the case of FRM 2 reactor fuel

    International Nuclear Information System (INIS)

    Abou Yehia, H.; Bars, G.; Tran Dai

    2001-01-01

    After giving a brief reminder of the procedure applied in France for the licensing of the use of a new fuel type or design in a research reactor, we outline the main safety aspects associated with such a modification. Finally, by way of an example, we focus on the safety assessment relating to the IRIS irradiation device used in SILOE reactor, in particular for the qualification of the fuel dedicated to FRM II reactor of the Technical University of Munich. This qualification was carried out on a U 3 Si 2 fuel plate enriched to about 90 % in weight of 235 U and containing 1.5 g of uranium per cm 3 . The evaluation performed by the IPSN for GRS did not call into question the choice of U 3 Si 2 fuel plates for the FRM-II reactor. (authors)

  11. Thermal neutron flux distribution in ET-RR-2 reactor thermal column

    Directory of Open Access Journals (Sweden)

    Imam Mahmoud M.

    2002-01-01

    Full Text Available The thermal column in the ET-RR-2 reactor is intended to promote a thermal neutron field of high intensity and purity to be used for following tasks: (a to provide a thermal neutron flux in the neutron transmutation silicon doping, (b to provide a thermal flux in the neutron activation analysis position, and (c to provide a thermal neutron flux of high intensity to the head of one of the beam tubes leading to the room specified for boron thermal neutron capture therapy. It was, therefore, necessary to determine the thermal neutron flux at above mentioned positions. In the present work, the neutron flux in the ET-RR-2 reactor system was calculated by applying the three dimensional diffusion depletion code TRITON. According to these calculations, the reactor system is composed of the core, surrounding external irradiation grid, beryllium block, thermal column and the water reflector in the reactor tank next to the tank wall. As a result of these calculations, the thermal neutron fluxes within the thermal column and at irradiation positions within the thermal column were obtained. Apart from this, the burn up results for the start up core calculated according to the TRITION code were compared with those given by the reactor designer.

  12. Apollo-L2, an advanced fuel tokamak reactor utilizing direct conversion

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Blanchard, J.P.; El-Guebaly, L.A.; Khater, H.Y.; Santarius, J.F.; Sawan, M.E.; Sviatoslavsky, I.N.; Wittenberg, L.J.; Witt, R.J.

    1989-01-01

    A scoping study of a tokamak reactor fueled by a D- 3 He plasma is presented. The Apollo D- 3 He tokamak capitalizes on recent advances in high field magnets (20 T) and utilizes rectennas to convert the synchrotron radiation directly to electricity. The low neutron wall loading (0.1 MW/m 2 ) permits a first wall lasting the life of the plant and enables the reactor to be classified as inherently safe. The cost of electricity is less than that from a similar power level DT reactor. 10 refs., 1 fig., 4 tabs

  13. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    Kouts, H.

    1986-01-01

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

  14. Rapid data acquisition from the safety system of the FRJ-2 reactor

    International Nuclear Information System (INIS)

    Inhoven, H.

    1980-06-01

    The central department for research reactors (ZFR) of the Juelich Nuclear Research Centre (KFA) is operating the reactors FRJ-1 (MERLIN) and FRJ-2 (DIDO) since 1962. In 1976, a Siemens 330 computer has been put into operation especially for the processing of data from the DIDO reactor, followed by another computer of the same type for the purpose of processing data from the ZFR department in general. The present report is a result of the work investigating 'Data acquisition and data processing in the FRJ-2' and primarily discusses the complex of 'fast analog and binary signals'. The activities in this field of work have been and still are mainly concerned with general problems encountered in adapting a currently 14-year-old reactor system to a digital computer, namely problems such as data decoupling in the safety system of the reactor, data acquisition using the CAMAC system, data transfer via an 'extended branch', data acquisition software as core-resident programs, temporary storage as common data, interpreting software as peripheral - storage - resident programs. (orig./WB) [de

  15. Estimasi Model Seemingly Unrelated Regression (SUR dengan Metode Generalized Least Square (GLS

    Directory of Open Access Journals (Sweden)

    Ade Widyaningsih

    2015-04-01

    Full Text Available Regression analysis is a statistical tool that is used to determine the relationship between two or more quantitative variables so that one variable can be predicted from the other variables. A method that can used to obtain a good estimation in the regression analysis is ordinary least squares method. The least squares method is used to estimate the parameters of one or more regression but relationships among the errors in the response of other estimators are not allowed. One way to overcome this problem is Seemingly Unrelated Regression model (SUR in which parameters are estimated using Generalized Least Square (GLS. In this study, the author applies SUR model using GLS method on world gasoline demand data. The author obtains that SUR using GLS is better than OLS because SUR produce smaller errors than the OLS.

  16. Estimasi Model Seemingly Unrelated Regression (SUR dengan Metode Generalized Least Square (GLS

    Directory of Open Access Journals (Sweden)

    Ade Widyaningsih

    2014-06-01

    Full Text Available Regression analysis is a statistical tool that is used to determine the relationship between two or more quantitative variables so that one variable can be predicted from the other variables. A method that can used to obtain a good estimation in the regression analysis is ordinary least squares method. The least squares method is used to estimate the parameters of one or more regression but relationships among the errors in the response of other estimators are not allowed. One way to overcome this problem is Seemingly Unrelated Regression model (SUR in which parameters are estimated using Generalized Least Square (GLS. In this study, the author applies SUR model using GLS method on world gasoline demand data. The author obtains that SUR using GLS is better than OLS because SUR produce smaller errors than the OLS.

  17. Effet du compost à base de Calotropis procera (Aiton) W.T. Aiton sur ...

    African Journals Online (AJOL)

    Objectifs: Une étude à base de compost de Calotropis procera a été menée afin de mesurer l'effet sur la production de l'arachide sur de sols pauvres. Méthodologie et résultats: L'essai a été conduit sur le site de Doyaba au niveau des zones marginales du Tchad avec la variété fleur 11 d'arachide (Arachis hypogaea L.) ...

  18. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  19. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  20. Estimation of power feedback parameters of pulse reactor IBR-2M on transients

    International Nuclear Information System (INIS)

    Pepyolyshev, Yu.N.; Popov, A.K.

    2013-01-01

    Parameters of the IBR-2M reactor power feedback (PFB) on a model of the reactor dynamics by mathematical treatment of two registered transients are estimated. Frequency characteristics and the pulse transient characteristics corresponding to these PFB parameters are calculated. PFB parameters received thus can be considered as their express tentative estimation as real measurements in this case occupy no more than 30 minutes. Total PFB is negative at 1 and 2 MW. At the received estimations of PFB parameters in a self-regulation mode it is possible to consider the stability margins of the IBR-2M reactor satisfactory

  1. Gestion des agroecosystemes sur le mont agou en zone forestiere ...

    African Journals Online (AJOL)

    Dans le but d'une meilleure mise en valeur de l'espace, plusieurs espèces végétales sont cultivées en association essentiellement avec Persea americana. L'approche méthodologique est basée sur des inventaires floristiques et écologiques sur 45 placettes de 25 m x 25 m dans les agrosystèmes. Une diversité de 85 ...

  2. Taxes sur les cigarettes en Tanzanie | CRDI - Centre de recherches ...

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

    On s'attend à ce que cette hausse du tabagisme ait d'importantes répercussions sur la santé publique et le développement économique. Il ressort de l'expérience d'autres régions que le moyen le plus efficace de renverser une telle tendance consiste à augmenter les taxes sur les cigarettes. Toutefois, les responsables des ...

  3. Independent CO2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Task 2.50.05

    International Nuclear Information System (INIS)

    Stojic, M.; Pavicevic, M.

    1964-01-01

    This report contains the following volumes V and VI of the Project 'Independent CO 2 loop for cooling the samples irradiated in RA reactor vertical experimental channels': Design project of the dosimetry control system in the independent CO 2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels, and Safety report for the Independent CO 2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels [sr

  4. PSA Level 2 activities for RBMK reactors

    International Nuclear Information System (INIS)

    Gubler, R.

    1998-01-01

    Probabilistic safety analyses (PSAs) of the boiling water graphite moderated pressure tube reactors (RBMKs) have been developed only recently and they are limited to Level 1. Activities at the IAEA were first motivated because of the difficulties to characterize core damage for RBMK reactors. Core damage probability is used in documents of the IAEA as a convenient single valued measure, for example for probabilistic safety criteria. The limited number of PSAs that have been completed for the RBMK reactors have shown that several special features of these channel type reactors necessitate revisiting of the characterization of core damage for these reactors. Furthermore, it has become increasingly evident that detailed deterministic analysis of DBAs and beyond design basis accidents reveal considerable insights into RBMK response to various accident conditions. These analyses can also help in better characterizing the outstanding phenomenological uncertainties, improved EOPs and AM strategies, including potential risk-beneficial accident negative backfits. The deterministic efforts should be focused first on elucidating accident progression processes and phenomena, and second on finding, qualifying and implementing procedures to minimize the risk of severe accident states The IAEA PSA procedures were mainly developed in New of vessel type LWRs, and would therefore require extensions to make them directly applicable. to channel type reactors. (author) (author)

  5. Studsvik's R2 reactor - Review of activities

    Energy Technology Data Exchange (ETDEWEB)

    Grounes, Mikael; Tomani, Hans; Graeslund, Christian; Rundquist, Hans; Skoeld, Kurt [Studsvik Nuclear AB, Nykoeping (Sweden)

    1993-07-01

    A general description of the R2 reactor, its associated facilities and its history is given. The facilities and range of work are described for the following types of activities: fuel testing, materials testing, neutron transmutation doping of silicon, activation analysis, radioisotope production and basic research including thermal neutron scattering, nuclear chemistry and neutron capture radiography. (author)

  6. Decommissioning of reactor facilities (2). Required technology

    International Nuclear Information System (INIS)

    Yanagihara, Satoshi

    2014-01-01

    Decommissioning of reactor facilities was planned to perform progressive dismantling, decontamination and radioactive waste disposal with combination of required technology in a safe and economic way. This article outlined required technology for decommissioning as follows: (1) evaluation of kinds and amounts of residual radioactivity of reactor facilities with calculation and measurement, (2) decontamination technology of metal components and concrete structures so as to reduce worker's exposure and production of radioactive wastes during dismantling, (3) dismantling technology of metal components and concrete structures such as plasma arc cutting, band saw cutting and controlled demolition with mostly remote control operation, (3) radioactive waste disposal for volume reduction and reuse, and (4) project management of decommissioning for safe and rational work to secure reduction of worker's exposure and prevent the spreading of contamination. (T. Tanaka)

  7. Topographic effect on Radio-Magnetotelluric and Slingram signals: application to a levee along the Loire river, France.

    Science.gov (United States)

    Duval, Rodolphe; Fauchard, Cyrille; Antoine, Raphael

    2014-05-01

    We study the influence of the topography of a levee on the electric and magnetic signals obtained with the Radio-Magnetotelluric method (RMT) and the Slingram method, respectively. For the RMT method, field measurements have been modelled with a finite element commercial software (AC/DC and Radio-Frequency modules of Comsol Multiphysics). A levee situated in Orléans (France) along the Loire river has been considered in order to design a model taking into account the skin depth and the incident wavelength. The effect of the incident electromagnetic field direction has been assessed with two different incident wave directions: BBC 5 from Salford (UK) and France-Inter from Allouis (France). The simulations highlight the tri-dimensional effects of the topography in the apparent resistivity, observed on the crest of the levee, depending on the incident field direction and topography. For the Slingram method, the magnetic field has been simulated using the AC/DC module of Comsol. The ratio of the primary magnetic field on the secondary one, received in a loop is determined above a straight levee. The study aims to show the various responses obtained in function of both vertical and horizontal coil configurations. We show that the signal also depends on the topography and the right configuration of the coils alignment with respect to the levee stretch direction. In this study, a buried gas pipe is also characterized by the two methods. Numerical modelling of 3D electromagnetic effects on geophysical signals helps to interpret the field measurements and offers to the stakeholder an optimized methodology for geophysical surveys on levees.

  8. Reproduction of the PSBR reactor with Exterminator-2; Reproduccion del reactor PSBR con exterminador-2

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1983-08-15

    To reproduce the reactor PSBR reported in (1), with the available version of the Exterminator-II in the ININ, they took the dimensions, composition specifications, effective sections of the different compositions (excepting those of the central thimble and of the moderator), the K{sub eff} and the factors of power (FP) for the different burners. Based on the comparison of the K{sub eff} and of the FP obtained with those reported the precision it is determined before in the reproduction of the reactor mentioned. (Author)

  9. Integral physics data for fast-reactor design; Donnees de physique integrale intervenant dans les etudes de reacteur a neutrons rapides; Integral'nye fizicheskie dannye dlya raschetov reaktorov na bystrykh nejtronakh; Datos fisicos integrales para el diseno de reactores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Loewenstein, W B; Meneghetti, D [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    systems. (author) [French] La compilation recente du chapitre sur la physique des reacteurs a neutrons rapides dans la preparation de la deuxieme edition de 'Reactor Physics Constants' a entraine une recapitulation des resultats disponibles des mesures experimentales globales. Le choix des donnees integrales connues relatives a la physique des reacteurs a neutrons rapides a faire figurer dans cette compilation a ete fait en fonction de deux criteres : a) informations recueillies a partir de reacteurs relativement simples et qui se pretent a des analyses theoriques simples, et b) informations recueillies a partir de reacteurs complexes, representant des prototypes ou des maquettes, et qui offrent un interet general pour les reacteurs de puissance a neutrons rapides. Le premier critere a pour objet de donner une enumeration des informations concernant les systemes les plus couramment utilises pour verifier les parametres des sections efficaces et les methodes de calcul. Le deuxieme critere est fonde sur la representation des informations courantes concernant les reacteurs a surgeneration, a neutrons rapides, existant. Ces informations sont trop compliquees pour qu'il soit possible de proceder a leur egard a des analyses theoriques simples. Elles prouvent la complexite du reacteur reel, par rapport a l'experience critique plus schematique et plus facile a analyser. Les donnees integrales intervenant dans les calculs de reacteurs sont les resultats des mesures faites, sur des types de reacteurs critiques ou non, des diverses grandeurs de la physique des reacteurs qui presentent un interet pratique et/ou theorique. Elles caracterisent le type de reacteur et aident a sa comprehension. Les mesures portent sur la masse critique, le facteur forme du coeur, les pourcentages de detection, les spectres des neutrons, les experiences de substitution de materiaux, le gain reflecteur, le temps de vie des neutrons, l'{alpha} de Rossi et sur d'autres grandeurs similaires. Les auteurs

  10. Production of Sn-117m in the BR2 high-flux reactor.

    Science.gov (United States)

    Ponsard, B; Srivastava, S C; Mausner, L F; Russ Knapp, F F; Garland, M A; Mirzadeh, S

    2009-01-01

    The BR2 reactor is a 100MW(th) high-flux 'materials testing reactor', which produces a wide range of radioisotopes for various applications in nuclear medicine and industry. Tin-117m ((117m)Sn), a promising radionuclide for therapeutic applications, and its production have been validated in the BR2 reactor. In contrast to therapeutic beta emitters, (117m)Sn decays via isomeric transition with the emission of monoenergetic conversion electrons which are effective for metastatic bone pain palliation and radiosynovectomy with lesser damage to the bone marrow and the healthy tissues. Furthermore, the emitted gamma photons are ideal for imaging and dosimetry.

  11. Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

    International Nuclear Information System (INIS)

    Greneche, D.

    2014-01-01

    This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

  12. Proceedings of 2. Yugoslav symposium on reactor physics, Part 1, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    International Nuclear Information System (INIS)

    1966-01-01

    This Volume 1 of the Proceedings of 2. Yugoslav symposium on reactor physics includes nine papers dealing with the following topics: reactor kinetics, reactor noise, neutron detection, methods for calculating neutron flux spatial and time dependence in the reactor cores of both heavy and light water moderated experimental reactors, calculation of reactor lattice parameters, reactor instrumentation, reactor monitoring systems; measuring methods of reactor parameters; reactor experimental facilities

  13. Comparative study between fluidized bed and fixed bed reactors in methane reforming with CO2 and O2 to produce syngas

    International Nuclear Information System (INIS)

    Jing Qiangshan; Lou Hui; Mo Liuye; Zheng Xiaoming

    2006-01-01

    Reforming of methane with carbon dioxide and oxygen was investigated over Ni/MgO-SiO 2 catalysts using fixed bed and fluidized bed reactors. The conversions of CH 4 and CO 2 in a fluidized bed reactor were close to thermodynamic equilibrium. The activity and stability of the catalyst in the fixed bed reactor were lower than that in the fluidized bed reactor due to carbon deposition and nickel sintering. TGA and TEM techniques were used to characterize the spent catalysts. The results showed that a lot of whisker carbon was found on the catalyst in the rear of the fixed bed reactor, and no deposited carbon was observed on the catalysts in the fluidized bed reactor after reaction. It is suggested that this phenomenon is related to a permanent circulation of catalyst particles between the oxygen rich and oxygen free zones. That is, fluidization of the catalysts in the fluidized bed reactor favors inhibiting deposited carbon and thermal uniformity in the reactor

  14. 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)

  15. Benchmark testing of Canadol-2.1 for heavy water reactor

    International Nuclear Information System (INIS)

    Liu Ping

    1999-01-01

    The new version evaluated nuclear data library of ENDF-B 6.5 has been released recently. In order to compare the quality of evaluated nuclear data CENDL-2.1 with ENDF-B 6.5, it is necessary to do benchmarks testing for them. In this work, CENDL-2.1 and ENDF-B 6.5 were used to generated the WIMS-69 group library respectively, and benchmarks testing was done for the heavy water reactor, using WIMS5A code. It is obvious that data files of CENDL-2.1 is better than that of old WIMS library for the heavy water reactors calculations, and is in good agreement with those of ENDF-B 6.5

  16. 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

  17. Oxygen suppression in boiling water reactors. Phase 2. Annual report 1981, December 2, 1980-December 31, 1981

    International Nuclear Information System (INIS)

    Burley, E.L.

    1982-07-01

    A hydrogen addition test will be performed in the Dresden-2 reactor of Commonwealth Edison Company during 1982. Up to 2 ppM hydrogen will be added to and dissolved in the reactor feedwater to reverse the radiolysis reaction in the reactor core and suppress oxgen concentration in the primary coolant. At low oxygen levels the propensity of stressed and sensitized 304 stainless steel toward intergranular stress corrosion cracking is greatly reduced. The test will answer outstanding questions and uncertainties in the areas of water chemistry, equipment design and materials performance. Nine special sample facilities will be prepared in the primary coolant, main stream, feedwater/condensate, and offgas systems. Instrumentation will be available to measure hydrogen, oxygen, conductivity, pH, soluble and insoluble corrosion products, and electrochemical potentials. In addition, an autoclave in which confirming constant extension rate tests can be conducted in reactor water will be provided

  18. Characterization of fuel distributions in the Three-Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McNeece, J.P.; Kaiser, B.J.; McElroy, W.N.

    1984-04-01

    The resolution of technical issues generated by the accident at Three-Mile Island Unit 2 (TMI-2) will inevitably be of long range benefit. Determination of the fuel debris dispersal in the TMI-2 reactor system represents a major technical issue. In reactor recovery operations, such as for the safe handling and final disposal of TMI-2 waste, quantitative fuel assessments are being conducted throughout the reactor core and primary coolant system

  19. Influence du système de logement sur quelques performances ...

    African Journals Online (AJOL)

    Les effets de deux systèmes de logement (batterie de cages et sol sur litière) sur les performances zootechniques et économiques des poules pondeuses ont été évalués en zone tropicale humide, au sud du Benin. Un total de 180 poules pondeuses (Isa Brown) de 26 semaines d'âge était réparti en deux groupes de 108 et ...

  20. Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

    International Nuclear Information System (INIS)

    Bissani, M; O'Kelly, D S

    2006-01-01

    A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to provide color-enhanced gemstones but is

  1. Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; O' Kelly, D S

    2006-05-08

    A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to

  2. analysis and implementation of reactor protection system circuits - case study Egypt's 2 nd research reactor-

    International Nuclear Information System (INIS)

    Elnokity, O.E.M.

    2006-01-01

    this work presents a way to design and implement the trip unit of a reactor protection system (RPS) using a field programmable gate arrays (FPGA). instead of the traditional embedded microprocessor based interface design method, a proposed tailor made FPGA based circuit is built to substitute the trip unit (TU), which is used in Egypt's 2 nd research reactor ETRR-2. the existing embedded system is built around the STD32 field computer bus which is used in industrial and process control applications. it is modular, rugged, reliable, and easy-to-use and is able to support a large mix of I/O cards and to easily change its configuration in the future. therefore, the same bus is still used in the proposed design. the state machine of this bus is designed based around its timing diagrams and implemented in VHDL to interface the designed TU circuit

  3. 152 Etude de cas sur l'impact des amendements organiques vis-à ...

    African Journals Online (AJOL)

    john mukalay

    Etude de cas sur l'impact des amendements organiques vis-à-vis de la salinité en culture de bananier. Michel Mazinga KWEY1, Séverin Kalala BANZE2 et John Banza MUKALAY2*. 1Laboratoire des cultures in vitro, Département de phytotechnie, Faculté des sciences agronomiques,. Université de Lubumbashi, BP 1825, ...

  4. Environmental, social, and corporate report 2012 - Cezus Paimboeuf (Areva)

    International Nuclear Information System (INIS)

    2013-01-01

    CEZUS, a subsidiary of AREVA, is the global leader in the market for zirconium, the metal used, among other things, for fuel cladding in the heart of nuclear reactors. CEZUS's operations are distributed over six sites. The site in Paimboeuf, in the Loire-Atlantique department, fabricates zirconium-alloy cladding tubes and guide tubes. This document shows details of the CEZUS Paimboeuf facility and its 2012 initiatives on: consumption and waste management, risk management, environmental and safety management, social and corporate responsibilities

  5. Simulation of power excursions - Osiris reactor; Simulation des excursions de puissance - pile Osiris

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    Following the experimental work accomplished in the U.S.A. on Borax 1 and SPERT 1 and the accident of SL 1, the 'Commissariat a l'Energie Atomique' started a research program about the safety of its own swimming Pool reactors, with regard to power excursions. The first research work led to the design of programmed explosive charges, adapted to the simulation of a power excursion. This report describes the application of these methods to the investigation of Osiris safety. (author) [French] A la suite des essais effectues aux U.S.A. sur BORAX 1 et SPERT 1 et de l'accident survenu a SL 1, le Commissariat a l'Energie Atomique a lance un programme d'etudes sur la surete de ses reacteurs piscines vis-a-vis des excursions de puissance. Les premieres etudes ont abouti A la mise au point de charges programmees capables de simuler une excursion de puissance. On trouvera dans le present rapport l'application de ces methodes a l'etude de la surete d'OSIRIS. (auteur)

  6. General outline of the operation and utilization of the BR2 reactor

    International Nuclear Information System (INIS)

    Baugnet, J.M.; Leonard, F.; Gandolfo, J.M.; Lenders, H.

    1978-01-01

    The BR2 reactor is a high-flux material testing reactor of the thermal heterogeneous type. The fuel is 93% 235 U enriched uranium in the form of plates clad in aluminium. The moderator consists of beryllium and light water, the water being pressurized (12.5kg/cm 2 )and acting also as coolant. The pressure vessel is of aluminium, and is placed in a pool of demineralized water. One should stress the following main features of the design: the experimental channels are skew, the tube bundle presenting the form of a hyperboloid of revolution (see figure 1)-this gives easy access at the top and bottom reactor covers allowing complex instrumented devices, while maintaining a very high neutron flux at the core; great flexibilty of utilization, due to the fact that it is possible to adapt the core configuration to the experimental loading as the fissile charge can be centred on different experimental channels; although BR2 is a thermal reactor, it is possible to achieve neutron spectra very similar to those obtained in a fast reactor, either by the use of absorbing screens or by the use of fissile material within the experimental device; five 200mm diameter channels are available for loading large experimental irradiation devices, as in-pile sodium, gas or water loops. (author)

  7. Benchmark testing of CENDL-2 for U-fuel thermal reactors

    International Nuclear Information System (INIS)

    Zhang Baocheng; Liu Guisheng; Liu Ping

    1995-01-01

    Based on CENDL-2, NJOY-WIMS code system was used to generate 69-group constants, and do benchmark testing for TRX-1,2; BAPL-UO-2-1,2,3; ZEEP-1,2,3. All the results proved that CENDL-2 is reliable for thermal reactor calculations. (3 tabs.)

  8. Un paysage de l’industrie : canaux et usines en Val de Germigny (Cher

    Directory of Open Access Journals (Sweden)

    Patrick Léon

    2012-04-01

    Full Text Available Le canal de Berry et le canal latéral à la Loire, qui se rejoignent au port de Marseille-lès-Aubigny, ont été ouverts à la fin des années 1830. Ils constituent un maillon essentiel du réseau de canaux dans la France centrale. Le canal de Berry, voulu par les sidérurgistes berrichons pour approvisionner les forges en charbon, a rapidement joué un rôle déterminant dans l’implantation de nouvelles usines entre le milieu du XIXe siècle et les années 1920, surtout les tuileries-briqueteries et celles produisant de la chaux hydraulique et du ciment naturel. Pour les mêmes raisons, ces dernières ont aussi choisi les bords du canal latéral à la Loire qui a été initialement conçu pour pallier les insuffisances de la navigation sur le fleuve. Les canaux seront d’abord considérés comme des ouvrages hydrauliques, architecturaux et techniques mais on verra aussi le trafic et le fret qui les animent. Ils sont enfin les serviteurs des grandes usines qui en dépendent étroitement pour leur approvisionnement et l’écoulement de leur production. Par conséquent, un paysage particulier s’est constitué, caractérisé par le lien organique entre canal et usines selon une géographie linéaire : formes de la proximité de l’établissement industriel par rapport à la voie d’eau artificielle, embranchements particuliers (canaux, voies ferrées et ponts, ports.The Berry canal and the lateral canal running alongside the Loire, which meet up at the port of Marseille-lès-Aubigny, were cut at the end of the 1830s. They are an essential part of the network of canals in central France. The Berry canal, originally created for the iron and steel producers of the Berry region in order to facilitate coal supplies to their ironworks, became a vital influence in the implantation of new factories, from the middle of the nineteenth century up to the 1920s. Of particular importance were the brick and tile works, and other factories producing

  9. Reconfiguración de la Cooperación Sur-Sur en la región latinoamericana y la participación internacional de los actores subnacionales

    Directory of Open Access Journals (Sweden)

    Mariana Calvento

    2015-01-01

    Full Text Available El presente trabajo describe y analiza las actua-les características de la Cooperación Sur-Sur en América Latina, especialmente el papel de los actores subnacionales en dicha dinámica. A su vez, analiza las modalidades que adquiere esta cooperación en el contexto político regio-nal de la última década, donde se evidencia un importante avance de la integración de los países latinoamericanos. Finalmente, estudila relación existente entre los principios de la Cooperación Sur-Sur con la participación in-ternacional de los actores subnacionales a partir de la relevancia que adquieren algunas de es-tas formas de cooperación, como es el caso de la Red mercociudades, el Foro Consultivo de Municipios, Estados Federados, Provincias y Departamentos del mercosur (fccr mer-cosur y la Federación Latinoamericana de Ciudades, Municipios y Asociaciones de Go-biernos Locales (flacma, que nuclean a estos actores y promueven mecanismos institucionales que favorecen la participación de las ciudades a través de diferentes instrumentos de intercambio y cooperación.

  10. 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)

  11. Shadow corrosion testing in the INCA facility in the Studsvik R2 reactor

    International Nuclear Information System (INIS)

    Nystrand, A.C.; Lassing, A.

    1999-01-01

    Shadow corrosion is a phenomenon which occurs when zirconium alloys are in contact with or in proximity to other metallic objects in a boiling water reactor environment (BWR, RBMK, SGHWR etc.). An enhanced corrosion occurs on the zirconium alloy with the appearance of a 'shadow' of the metallic object. The magnitude of the shadow corrosion can be significant, and is potentially limiting for the lifetime of certain zirconium alloy components in BWRs and other reactors with a similar water chemistry. In order to evaluate the suitability of the In-Core Autoclave (INCA) in the Studsvik R2 materials testing reactor as an experimental facility for studying shadow corrosion, a demonstration test has been performed. A number of test specimens consisting of Zircaloy-2 tubing in contact with Inconel were exposed in an oxidising water chemistry. Some of the specimens were placed within the reactor core and some above the core. The conclusion of this experiment after post irradiation examination is that it is possible to use the INCA facility in the Studsvik R2 reactor to develop a significant level of shadow corrosion after only 800 hours of irradiation. (author)

  12. Rapport. Sur le droit à l’appréciation critique et sur les restrictions légitimes de l’importunité de l'homosexualité

    Directory of Open Access Journals (Sweden)

    Mikhaïl N. Kouznetsov

    2011-10-01

    Full Text Available Dans le présent Rapport on entend par la notion “homosexualité” sa plus large et spécifique signification en tant que “l’ideologie de l'homosexualisme”. SOMMAIRE: Introduction - 1. Argumentation du droit à l’évaluation critique de l'homosexualité et de ses aspects sociaux - 2. Caractère agressif de l'idéologie de l'homosexualisme - 3. Atteinte cruelle et inhumaine de lésions corporelles portée à l’individu, les dommages à sa santé dans la pratique de l'homosexualité ”masculine” - 4. Sur la manipulation par les chiffres - 5.  Mythe sur la discriminations massives des homosexuels - 6. Violation des Droits de l’Homme et insulte à la dignité humaine pendant les ”gay parades” - 7. Normes de la législation étrangère, émanant de la reconnaissance par l'État des méfaits sociaux de l'homosexualité - 8. Positions juridiques de la Cour Européenne des Droits de l'Homme ayant le point d’impact sur l’élaboration des solutions à propos des questions à discuter - 9. Contradiction à ”l’Ordre public” de la Fédération de Russie des exigences d'établir des régimes juridiques privilégiés pour les homosexuels et leurs groupements et de poursuivre pour toute critique de l'homosexualité – 10. Conclusions.

  13. The 5th surveillance testing for Kori unit 2 reactor vessel materials

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Kee Ok; Kim, Byoung Chul; Lee, Sam Lai; Choi, Kwon Jae; Gong, Un Sik; Chang, Jong Hwa; Joo, Yong Sun; Ahn, Sang Bok; Hong, Joon Hwa [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2001-03-01

    Surveillance testing for reactor vessel materials is performed in order to evaluate the irradiation embrittlement due to neutrons during operation and set the condition of safe operation of nuclear reactor. The 5th surveillance testing was performed completely by Korea Atomic Energy Research Institute at Taejeon after the capsule was transported from Kori site including its removal from reactor. Fast neutron fluences for capsules were calculated and various testing including mechanical and chemistry analysis were performed in order to evaluate the integrity of Kori unit 2 reactor vessel during the operation until life time. The evaluation results are as follows; Fast neutron fluences for capsules V, R, P, T and N are 2.837E+18, 1.105E+19, 2.110E+19, 3.705E+19 and 4.831E+19n/cm{sup 2}, respectively. The bias factor, the ratio of measurement/calculation, was 0.918 for the 1st through 5th testing and the calculational uncertainty, 11.6% satisfied the requirement of USNRC Reg.Guide DG-1053, 20%. The best estimated neutron fluence for reactor vessel inside surface was 1.898E+19n/cm{sup 2} based on the end of 15th fuel cycle and it was predicted that the fluences of vessel inside surface at 32, 40, 48 and 56EFPY would reach 4.203E+19, 5.232E+19, 6.262E+19 and 7.291E+19n/cm{sup 2} based on the current calculation. The result through this analysis for Kori unit 2 showed that there would be no problem for the pressurized thermal shock(PTS) during the operation until design life. 49 refs., 35 figs., 48 tabs. (Author)

  14. Digital, remote control system for a 2-MW research reactor

    International Nuclear Information System (INIS)

    Battle, R.E.; Corbett, G.K.

    1988-01-01

    A fault-tolerant programmable logic controller (PLC) and operator workstations have been programmed to replace the hard-wired relay control system in the 2-MW Bulk Shielding Reactor (BSR) at Oak Ridge National Laboratory. In addition to the PLC and remote and local operator workstations, auxiliary systems for remote operation include a video system, an intercom system, and a fiber optic communication system. The remote control station, located at the High Flux Isotope Reactor 2.5 km from the BSR, has the capability of rector startup and power control. The system was designed with reliability and fail-safe features as important considerations. 4 refs., 3 figs

  15. Controverses sur les sucres [Controversies about sugars

    Directory of Open Access Journals (Sweden)

    Malika BOUCHENAK

    2016-12-01

    Full Text Available La surconsommation de sucres ajoutés et leurs effets putatifs sur diverses pathologies cardiométaboliques continuent de susciter des controverses. Dans les années 1950, le taux élevé de maladies cardiovasculaires (MCV, chez les hommes Américains a conduit à des études sur le rôle des facteurs alimentaires, tels que le cholestérol, les phytostérols, l'excès de calories, les acides aminés, les graisses, les glucides, les vitamines et les minéraux, à influencer le risque de MCV. Dans les années 60, deux éminents physiologistes, plaidant pour des hypothèses causales divergentes de MCV, John Yudkin a identifié les sucres ajoutés comme agent primaire, tandis que Ancel Keys identifiait les graisses totales, les graisses saturées et le cholestérol alimentaire. Cependant, dans les années 80, peu de scientifiques croyaient que les sucres ajoutés jouaient un rôle important dans la maladie coronarienne, et les premiers conseils nutritionnels de 1980 (1980 Dietary Guidelines for americans étaient axés sur la réduction des graisses totales, des graisses saturées et du cholestérol alimentaire pour la prévention des MCV.

  16. New competition in the world market of nuclear reactors; La nouvelle concurrence sur le marche mondial des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Finon, D. [Centre National de la Recherche Scientifique (CNRS), CIRED (EHESS et CNRS), 75 - Paris (France)

    2005-06-01

    As nuclear orders are picking up a little, there are strengths competing against one another in the world industry of reactors, an industry that has been deeply affected for twenty years, by the smallness of the market and the reorganization of the electromechanical industry. Competition remains particularly difficult, even though, in terms of exports, national markets in industrialized countries such as the American market and European market are now open to foreign newcomers. One of the reasons of the difficulty is the increased commercial competition based on advanced reactor techniques untested due to strong faith in technology leading to forget the learning difficulties of older reactor types. On a narrow market, demanding and with very specific political interference, the reasoning is not like on an ordinary capital equipment market. Each builder tries to sell by relying on the assets it has in addition to the offered price and related services: industrial reputation and experience that play confusedly when untested advanced reactors are competing with one another, credit terms offered by the State and the government's influence on the market of emerging economies, the backing o the State's financial insurance in the event of risks taken in the sale of turnkey untested reactors. In the competition of the five manufacturers in the export market, American builders do not seem to have the best place, though even the leading position of Framatome ANP shows some limits. (author)

  17. A nodal Grean's function method of reactor core fuel management code, NGCFM2D

    International Nuclear Information System (INIS)

    Li Dongsheng; Yao Dong.

    1987-01-01

    This paper presents the mathematical model and program structure of the nodal Green's function method of reactor core fuel management code, NGCFM2D. Computing results of some reactor cores by NGCFM2D are analysed and compared with other codes

  18. RHTF 2, a 1200 MWe high temperature reactor

    International Nuclear Information System (INIS)

    Brisbois, Jacques

    1978-01-01

    After having adapted to French conditions the 1160 MWe G.A.C. reactor, Commissariat a l'Energie Atomique and French Industry have decided to design an High Temperature Reactor 1200 MWe based on the G.A.C. technology and taking into account the point of view of Electricite de France and the experience of C.E.A. and industry on the gas cooled reactor technology. The main objective of this work is to produce a reactor design having a low technical risk, good operability, with an emphasis on the safety aspects easing the licensing problems

  19. Turkey's regulatory plans for high enriched to low enriched conversion of TR-2 reactor core

    International Nuclear Information System (INIS)

    Guelol Oezdere, Oya

    2003-01-01

    Turkey is a developing country and has three nuclear facilities two of which are research reactors and one pilot fuel production plant. One of the two research reactors is TR-2 which is located in Cekmece site in Istanbul. TR-2 Reactor's core is composed of both high enriched and low enriched fuel and from high enriched to low enriched core conversion project will take place in year 2005. This paper presents the plans for drafting regulations on the safety analysis report updates for high enriched to low enriched core conversion of TR-2 reactor, the present regulatory structure of Turkey and licensing activities of nuclear facilities. (author)

  20. Techno-economic assessment of membrane assisted fluidized bed reactors for pure H_2 production with CO_2 capture

    International Nuclear Information System (INIS)

    Spallina, V.; Pandolfo, D.; Battistella, A.; Romano, M.C.; Van Sint Annaland, M.; Gallucci, F.

    2016-01-01

    Highlights: • Membrane reactors improve the overall efficiency of H_2 production up to 20%. • Respect to conventional reforming, the H_2 yield increases from 12% to 20%. • The COH is reduced of at least 220% using membrane reactors. • FBMR capture 72% of CO_2 with a specific cost of 8 eur/tonn_C_O_2_. • MA-CLR can reach 90% of CO_2 avoided with same cost of FTR. - Abstract: This paper addresses the techno-economic assessment of two membrane-based technologies for H_2 production from natural gas, fully integrated with CO_2 capture. In the first configuration, a fluidized bed membrane reactor (FBMR) is integrated in the H_2 plant: the natural gas reacts with steam in the catalytic bed and H_2 is simultaneously separated using Pd-based membranes, and the heat of reaction is provided to the system by feeding air as reactive sweep gas in part of the membranes and by burning part of the permeated H_2 (in order to avoid CO_2 emissions for heat supply). In the second system, named membrane assisted chemical looping reforming (MA-CLR), natural gas is converted in the fuel rector by reaction with steam and an oxygen carrier (chemical looping reforming), and the produced H_2 permeates through the membranes. The oxygen carrier is re-oxidized in a separate air reactor with air, which also provides the heat required for the endothermic reactions in the fuel reactor. The plants are optimized by varying the operating conditions of the reactors such as temperature, pressures (both at feed and permeate side), steam-to-carbon ratio and the heat recovery configuration. The plant design is carried out using Aspen Simulation, while the novel reactor concepts have been designed and their performance have been studied with a dedicated phenomenological model in Matlab. Both configurations have been designed and compared with reference technologies for H_2 production based on conventional fired tubular reforming (FTR) with and without CO_2 capture. The results of the analysis show

  1. Reactor building integrity testing: A novel approach at Gentilly 2 - principles and methodology

    International Nuclear Information System (INIS)

    Collins, N.; Lafreniere, P.

    1991-01-01

    In 1987, Hydro-Quebec embarked on an ambitious development program to provide the Gentilly 2 nuclear power station with an effective, yet practical reactor building Integrity Test. The Gentilly 2 Integrity Test employs an innovative approach based on the reference volume concept. It is identified as the Temperature Compensation Method (TCM) System. This configuration has been demonstrated at both high and low test pressure and has achieved extraordinary precision in the leak rate measurement. The Gentilly 2 design allows the Integrity Test to be performed at a nominal 3 kPa(g) test pressure during an (11) hour period with the reactor at full power. The reactor building Pressure Test by comparison, is typically performed at high pressure 124 kPa(g)) in a 7 day window during an annual outage. The Integrity Test was developed with the goal of demonstrating containment availability. Specifically it was purported to detect a leak or hole in the 'bottled-up' reactor building greater in magnitude than an equivalent pipe of 25 mm diameter. However it is considered feasible that the high precision of the Gentilly 2 TCM System Integrity Test and a stable reactor building leak characteristic will constitute sufficient grounds for the reduction of the Pressure Test frequency. It is noted that only the TCM System has, to this date, allowed a relevant determination of the reactor building leak rate at a nominal test pressure of 3 kPa(g). Classical method tests at low pressure have lead to inconclusive results due to the high lack of precision

  2. La estrategia de liderazgo regional de la India a través de la cooperación sur-sur (2003-2012)

    OpenAIRE

    Jaime Garzón, Carlos Felipe

    2014-01-01

    La presente investigación tiene como objetivo analizar en qué medida la estrategia de liderazgo regional de la India ha sido impulsada a través de los programas y proyectos de cooperación sur-sur ofrecidos por este país en el periodo de 2003-2012. De igual forma se pretende indagar sobre el papel histórico que ha jugado la India en el establecimiento y posterior evolución de esta nueva forma de cooperación que ha sido vista por la mayoría de los académicos como un complemento de la cooperació...

  3. Enjeux de territoires sur une frontière méconnue

    Directory of Open Access Journals (Sweden)

    Françoise Grenand

    2012-11-01

    Full Text Available « J’ai travaillé dans le temps sur le chantier d’un pont sur le Zambèze. Je me suis toujours demandé pourquoi ils avaient décidé de faire un pont à cet endroit : c’est la même chose sur les deux rives… ». Humphrey Bogart, in African Queen, de John Huston, 1951.Il y a encore quatre décennies, la Guyane ignorait superbement qu’elle eût un voisin nommé Brésil. Une frontière en commun ? Et même la plus longue frontière terrestre de la France ? Les deux seules librairies du département ne proposai...

  4. Maximum credible accident analysis for TR-2 reactor conceptual design

    International Nuclear Information System (INIS)

    Manopulo, E.

    1981-01-01

    A new reactor, TR-2, of 5 MW, designed in cooperation with CEN/GRENOBLE is under construction in the open pool of TR-1 reactor of 1 MW set up by AMF atomics at the Cekmece Nuclear Research and Training Center. In this report the fission product inventory and doses released after the maximum credible accident have been studied. The diffusion of the gaseous fission products to the environment and the potential radiation risks to the population have been evaluated

  5. UO{sub 2} and PuO{sub 2} utilization in high temperature engineering test reactor with helium coolant

    Energy Technology Data Exchange (ETDEWEB)

    Waris, Abdul, E-mail: awaris@fi.itb.ac.id; Novitrian,; Pramuditya, Syeilendra; Su’ud, Zaki [Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia); Aji, Indarta K. [Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia)

    2016-03-11

    High temperature engineering test reactor (HTTR) is one of high temperature gas cooled reactor (HTGR) types which has been developed by Japanese Atomic Energy Research Institute (JAERI). The HTTR is a graphite moderator, helium gas coolant, 30 MW thermal output and 950 °C outlet coolant temperature for high temperature test operation. Original HTTR uses UO{sub 2} fuel. In this study, we have evaluated the use of UO{sub 2} and PuO{sub 2} in form of mixed oxide (MOX) fuel in HTTR. The reactor cell calculation was performed by using SRAC 2002 code, with nuclear data library was derived from JENDL3.2. The result shows that HTTR can obtain its criticality condition if the enrichment of {sup 235}U in loaded fuel is 18.0% or above.

  6. SurF: an innovative framework in biosecurity and animal health surveillance evaluation.

    Science.gov (United States)

    Muellner, Petra; Watts, Jonathan; Bingham, Paul; Bullians, Mark; Gould, Brendan; Pande, Anjali; Riding, Tim; Stevens, Paul; Vink, Daan; Stärk, Katharina Dc

    2018-05-16

    Surveillance for biosecurity hazards is being conducted by the New Zealand Competent Authority, the Ministry for Primary Industries (MPI) to support New Zealand's biosecurity system. Surveillance evaluation should be an integral part of the surveillance life cycle, as it provides a means to identify and correct problems and to sustain and enhance the existing strengths of a surveillance system. The surveillance evaluation Framework (SurF) presented here was developed to provide a generic framework within which the MPI biosecurity surveillance portfolio, and all of its components, can be consistently assessed. SurF is an innovative, cross-sectoral effort that aims to provide a common umbrella for surveillance evaluation in the animal, plant, environment and aquatic sectors. It supports the conduct of the following four distinct components of an evaluation project: (i) motivation for the evaluation, (ii) scope of the evaluation, (iii) evaluation design and implementation and (iv) reporting and communication of evaluation outputs. Case studies, prepared by MPI subject matter experts, are included in the framework to guide users in their assessment. Three case studies were used in the development of SurF in order to assure practical utility and to confirm usability of SurF across all included sectors. It is anticipated that the structured approach and information provided by SurF will not only be of benefit to MPI but also to other New Zealand stakeholders. Although SurF was developed for internal use by MPI, it could be applied to any surveillance system in New Zealand or elsewhere. © 2018 2018 The Authors. Transboundary and Emerging Diseases Published by Blackwell Verlag GmbH.

  7. Los rubios. Recherche sur les différents états de la mémoire et sur la reconstruction d’une identité

    Directory of Open Access Journals (Sweden)

    Marta Mariasole Raimondi

    2010-11-01

    Full Text Available Los rubios, Argentina, 2003. Réalisation : Albertina Carri. Interprètes : Analìa Couceyro, Albertina Carri. Durée : 89 min. Noir & blanc et couleurs. Langue espagnole. Introduction Mélange de souvenirs, d’anecdotes, de fragments et d’imagination. Los rubios [trad. Les Blonds] ne se présente pas comme un film de dénonciation ou comme un documentaire historique sur les detenidos-desparecidos. Dans ce film, Albertina Carri propose plutôt sa vision personnelle sur la disparition de ses parents. L...

  8. Sur la plurifonctionnalité du discours direct

    Directory of Open Access Journals (Sweden)

    Cigada Sara

    2012-07-01

    Full Text Available La comparaison entre les résultats de nombreux travaux sur le dialogue dans le texte littéraire, sur l’attestation linguistique de la subjectivité, sur la fonction argumentative des émotions dans le discours et sur les effets de polyphonie, suggère que la structure sémiotique et linguistique du discours direct (DD se trouve au croisement stratégique de plusieurs axes de la construction discursive. Nous étudions donc l’insertion du DD dans le discours (cf. Rosier 2008: Le discours rapporté en français; Kerbrat 2005: Le Discours en interaction et Id. 2008: Le Dialogue comme objet d’analyse linguistique; Maingueneau 2010: Manuel de linguistique pour le texte littéraire en tant que phénomène de rupture sémiotique (Genette 1972: Figures III et Id. 1983: Nouveau discours du récit, dans ses fonctions discursives plurielles, tantôt émotives (Tannen 1989: Talking Voices; Plantin-Traverso-Vosghanian 2008: Parcours des émotions en interaction, tantôt argumentatives (Doury 2001: La Fonction argumentative des échanges rapportés; Stati 1990: Le transphrastique. Du point de vue méthodologique, nous nous proposons de revisiter empiriquement, par l'étude de corpus, les traits linguistiques structuraux qui caractérisent l’insertion du DD dans un récit à l'écrit, en les comparant systématiquement aux traits de l’insertion du DD dans un récit à l'oral. Une analyse parallèle est possible en ce qui concerne les fonctions discursives, que le DD typiquement déroule dans les récits. Les fonctions du DD décrites à partir de l'étude des corpus sont plurielles: on reconnaît des fonctions fortement argumentatives d'autres plus typiquement narratives, tandis que d'autres encore amalgament les deux fonctions. Le « contrat de littéralité », qui selon Genette ne porterait jamais que sur la teneur du discours, doit donc être fortement nuancé selon les contextes, tandis que l'effet de sens le plus directement lié à la

  9. The Chernobyl reactor accident. Pt. 1 and 2

    International Nuclear Information System (INIS)

    1986-06-01

    The report first summarizes the available information on the various incidents of the whole accident scenario, and combines the information to present a first general outline and a basis for appraisal. The most significant incidents reported, namely power excursion, core meltdown, and fire, are discussed with a view to the reactor design and safety of reactors installed in the FRG. The main differences and advantages of German reactor designs are shown, as e.g.: Power excursions are mastered by inherent physical conditions; far better redundancy of engineered safety systems; enclosure of the complete reactor cooling system in a pressure-retaining steel containment; reactor buildings being made of reinforced concrete. The second part of the report deals with the radiological effects to be expected for our country. Data are given on the varying radiological exposure of the different regions. The fate and uptake of radioactivity in the human body are discussed. The conclusion drawn from the data presented is that the individual exposure due to the reactor accident will remain within the variations and limits of natural radioactivity and effects. (orig./HP) [de

  10. Load-deflection characteristics of small-bore insulated-pipe clamps

    International Nuclear Information System (INIS)

    Severud, L.K.; Clark, G.L.

    1981-12-01

    The special insulated clamps used on both FFTF and CRBR piping utilize a Belleville spring arrangement to compensate for pipe thermal expansion. Analysis indicates that this produces a non-linear, directionally sensitive clamp spring rate. Since these spring rates influence the seismic response of a supported piping system, it was deemed necessary to evaluate them further by test. This has been accomplished for the FFTF clamps. A more standard insulated pipe clamp, which does not incorporate Belleville springs to accommodate thermal expansion, was also tested. This type clamp is simple in design, and economically attractive. It may have wide application prospects for use in LMFBR small bore auxiliary piping operating at temperatures below 427 0 C. Load deflection tests were conducted on 2.54 CM and 7.62 CM diameter samples of these commercial clamps

  11. Burst slug detection system in french power reactors (1961); La detection des ruptures de gaines dans les reacteurs de puissance francais (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    Gas samples are taken from the channels of the reactor and the short lived fission products are electrostatically collected to be analysed by a phosphor and photomultiplier system. The electrostatic collection and rotating electrode detector is described and its main uses exposed. Experience has shown the interest of measuring the evolution of fission products activities and not their absolute value only. In this way, data processing equipment have been designed and adapted to the detection apparatus. The system developed and realized for the G-l - G-2 - G-3 - EDF-1 - EDF-2 reactors are compared. (authors) [French] Un prelevement de gaz est effectue dans les canaux du reacteur et les produits de fission a vie courte sont collectes electrostatiquement pour etre analyses par un ensemble scintillateur-photomultiplicateur. Le detecteur a collection electrostatique et electrode tournante est decrit et ses applications principales sont exposees. L'experience a montre l'interet de mesurer l'evolution des activites en produits de fission et non seulement leur valeur absolue. D'ou le developpement d'ensembles de traitement des informations associes aux chaines de detection. Comparaison des realisations sur les reacteurs G-l - G-2 - G-3 - EDF-1 et EDF-2. (auteurs)

  12. New K-Ar ages of altered rocks from Paramillos Sur and Norte: Interpretation of the results

    International Nuclear Information System (INIS)

    Koukharsky, Magdalena; Brodtkorb, Alejo; Munizaga, Francisco

    1998-01-01

    The whole-rock K-Ar dates from porphyry copper prospects of Paramillos Sur (phyllic and potasic alteration zones) and Paramillos Norte (propilitic zone) are reported. Radiometric data yielded 17,8 ± 0,9 Ma, 15,8 ± 1,0 Ma and 15,2 ± 0,5 Ma in Paramillos Sur, and 17,3 ± 0,7 Ma in Paramillos Norte, which can be added to an previously reported age of 16,4 ± 0,3 Ma. These data are in agreement with isotopic ages from non altered or non mineralized magmatic rocks of the region. When the isotopic ages and petrographic characteristics of the dated rocks are considered, two alteration-mineralization events are suggested for Paramillos Sur prospect. However this possibility needs to be confirmed by means of future studies, in view of the reduced interval between these events when compared with the analytical errors. (author)

  13. Synthesis of the IRSN report related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor. Referral of the Permanent Group of Experts for nuclear reactors (GPR), examination of probabilistic level-2 safety studies (EPS 2) and severe accidents (AG) of the Flamanville reactor nr 3. Opinion related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor (FA3). Electronuclear reactors - EDF - Flamanville 3 EPR reactor. Severe accidents and probabilistic level 2 studies

    International Nuclear Information System (INIS)

    2015-01-01

    This document gathers several documents. The first one recalls the main arrangements implemented on the FA3 EPR reactor regarding accidents with core fusion, reports the analysis made by the IRSN about the sizing of these arrangements to reach a controlled status of the installation after a severe accident, regarding the probabilistic level-2 safety assessment, regarding the radiological impact of a severe accident on the population and on the environment, regarding those aimed at facing a total and long duration loss of electric power sources and cold sources, and about the situation of the reactor with respect to WENRA positions on severe accidents for new reactors. The second document is a letter sent by the ASN to the Permanent Group of Experts for nuclear reactors (GPR) to address probabilistic level-2 safety studies (EPS2) and severe accidents for the Flamanville 3 reactor. The third one reports the opinion of the GPR on these both issues and proposes a set of recommendations. The next document is a letter sent by the ASN to the Flamanville 3 project manager at EDF which recalls the related objectives, the ASN opinion on the implemented arrangements for severe accidents (de-pressurization of the primary circuit, management of hydrogen-related risks, corium recovery and cooling outside the vessel, limitation of vapour explosion risks outside the vessel, heat evacuation system, containment enclosure, management of the risk of a return to criticality), to face a total and long duration loss of electricity sources and cold sources, and other aspects addressed in the IRSN analysis. Requests and remarks formulated by the ASN are provided in an appendix to this last document

  14. GSTAR-SUR Modeling With Calendar Variations And Intervention To Forecast Outflow Of Currencies In Java Indonesia

    Science.gov (United States)

    Akbar, M. S.; Setiawan; Suhartono; Ruchjana, B. N.; Riyadi, M. A. A.

    2018-03-01

    Ordinary Least Squares (OLS) is general method to estimates Generalized Space Time Autoregressive (GSTAR) parameters. But in some cases, the residuals of GSTAR are correlated between location. If OLS is applied to this case, then the estimators are inefficient. Generalized Least Squares (GLS) is a method used in Seemingly Unrelated Regression (SUR) model. This method estimated parameters of some models with residuals between equations are correlated. Simulation study shows that GSTAR with GLS method for estimating parameters (GSTAR-SUR) is more efficient than GSTAR-OLS method. The purpose of this research is to apply GSTAR-SUR with calendar variation and intervention as exogenous variable (GSTARX-SUR) for forecast outflow of currency in Java, Indonesia. As a result, GSTARX-SUR provides better performance than GSTARX-OLS.

  15. Irradiated graphite studies prior to decommissioning of G1, G2 and G3 reactors

    International Nuclear Information System (INIS)

    Bonal, J.P.; Vistoli, J.Ph.; Combes, C.

    2005-01-01

    G1 (46 MW th ), G2 (250 MW th ) and G3 (250 MW th ) are the first French plutonium production reactors owned by CEA (Commissariat a l'Energie Atomique). They started to be operated in 1956 (G1), 1959 (G2) and 1960 (G3); their final shutdown occurred in 1968, 1980 and 1984 respectively. Each reactor used about 1200 tons of graphite as moderator, moreover in G2 and G3, a 95 tons graphite wall is used to shield the rear side concrete from neutron irradiation. G1 is an air cooled reactor operated at a graphite temperature ranging from 30 C to 230 C; G2 and G3 are CO 2 cooled reactors and during operation the graphite temperature is higher (140 C to 400 C). These reactors are now partly decommissioned, but the graphite stacks are still inside the reactors. The graphite core radioactivity has decreased enough so that a full decommissioning stage may be considered. Conceming this decommissioning, the studies reported here are: (i) stored energy in graphite, (ii) graphite radioactivity measurements, (iii) leaching of radionuclide ( 14 C, 36 Cl, 63 Ni, 60 Co, 3 H) from graphite, (iv) chlorine diffusion through graphite. (authors)

  16. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  17. A Conceptual Study on a Supercritical CO_2-cooled Micro Modular Reactor

    International Nuclear Information System (INIS)

    Yu, Hwanyeal; Hartanto, Donny; Kim, Yonghee

    2014-01-01

    A Micro Modular Reactor (MMR) using Supercritical-CO_2 (S-CO_2) as coolant has been investigated from the neutronics perspective. The MMR is designed to be transportable so it can reach the remote areas. The thermal power of the reactor is 36.2 M Wth. The size of the active core is limited to 1.2 m length and 93.16 cm width. The size of whole core is 2.8 m length and 166.9 cm width. The reactor lifetime design target is 20 years. To maximize the fuel volume fraction in the core, high density uranium nitride UN"1"5 was used. The PbO/MgO reflector was also utilized to improve the neutron economy. The S-CO_2 is chosen as the coolant because it offers a higher thermal efficiency. In this study, neutronics calculations and depletion using McCARD Monte Carlo code has been done to determine the lifetime and behavior of the core. Several important safety parameters such as Control Rod worth, Doppler reactivity coefficients and coolant void reactivity coefficient have also been analyzed. (author)

  18. Comparison of the N Reactor and Ignalina Unit No. 2 Level 1 Probabilistic Safety Assessments

    International Nuclear Information System (INIS)

    Coles, G.A.; McKay, S.L.

    1995-06-01

    A multilateral team recently completed a full-scope Level 1 Probabilistic Safety Assessment (PSA) on the Ignalina Unit No. 2 reactor plant in Lithuania. This allows comparison of results to those of the PSA for the U.S. Department of Energy's (DOE) N Reactor. The N Reactor, although unique as a Western design, has similarities to Eastern European and Soviet graphite block reactors

  19. Dans le labyrinthe de verre. La négociation sur l'effet de serre

    OpenAIRE

    Hourcade , Jean Charles

    2002-01-01

    National audience; En parcourant les étapes principales de la « négociation climat », on fait apparaître le jeu de miroirs qui se déroule entre Europe et États-Unis, dans un contexte historique caractérisé par les débats sur la mondialisation, la volonté de leadership de l'Union européenne sur ce thème, la montée aux États-Unis d'inquiétudes sur le maintien de leur suprématie.On montre aussi pourquoi ce jeu, après avoir masqué des possibilités réelles de compromis, a débouché en 2000 sur l'éc...

  20. CHAP-2 heat-transfer analysis of the Fort St. Vrain reactor core

    International Nuclear Information System (INIS)

    Kotas, J.F.; Stroh, K.R.

    1983-01-01

    The Los Alamos National Laboratory is developing the Composite High-Temperature Gas-Cooled Reactor Analysis Program (CHAP) to provide advanced best-estimate predictions of postulated accidents in gas-cooled reactor plants. The CHAP-2 reactor-core model uses the finite-element method to initialize a two-dimensional temperature map of the Fort St. Vrain (FSV) core and its top and bottom reflectors. The code generates a finite-element mesh, initializes noding and boundary conditions, and solves the nonlinear Laplace heat equation using temperature-dependent thermal conductivities, variable coolant-channel-convection heat-transfer coefficients, and specified internal fuel and moderator heat-generation rates. This paper discusses this method and analyzes an FSV reactor-core accident that simulates a control-rod withdrawal at full power

  1. Sur les lherzolites et ophites des Pyrénées

    NARCIS (Netherlands)

    Zwart, H.J.

    1953-01-01

    Depuis longtemps on trouve dans la littérature sur la géologie des Pyrénées des discussions sur les lherzolites et les ophites, concernant leur origine, leur âge et leur mode de formation. En général ces discussions ont rendu difficile l'éclaircissement de ce problème et un résumé de toute la

  2. L'incidence des pesticides sur les producteurs de pommes de terre ...

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

    27 janv. 2011 ... De 1990 à 1993, lui et Charles Crissman du Centre international de la pomme de terre (CIP) en Équateur ont participé à une étude appelée Tradeoffs qui portait sur les effets des pesticides sur la santé, l'environnement et la productivité. Tous deux sont chargés de la direction des recherches du projet ...

  3. Turismo en Segovia sur. Análisis y propuestas de mejora

    OpenAIRE

    Herranz Marcos, María

    2015-01-01

    Este trabajo hace un análisis sobre el turismo rural y sostenible. El cual se basa en el territorio de Segovia sur. Segovia sur tiene un gran potencial turístico, que en algunas zonas es menos conocido. Por ello la creación de una serie de propuestas (senderismo, cicloturismo) que de forma sostenible potencien el desarrollo del turismo en esa zona. Grado en Turismo

  4. Development of Zr-2.5Nb pressure tubes for Advanced CANDU Reactor

    International Nuclear Information System (INIS)

    Bickel, G.A.; Griffiths, M.; Douchant, A.; Douglas, S.; Woo, O.T.; Buyers, A.

    2010-01-01

    In an Advanced CANDU Reactor (ACR), pressure tubes of cold-worked Zr-2.5Nb materials will be used in the reactor core to contain the fuel bundles and the light water coolant. They will be subjected to higher temperature, pressure and flux than that in a CANDU reactor. In order to ensure that these tubes will perform acceptably over their 30-year design life in such an environment, a manufacturing process has been developed to produce 6.5 mm thick ACR pressure tubes with optimized chemical composition, improved mechanical properties and in-reactor behaviour. The test and examination results show that, when compared with current in-service pressure tubes, the mechanical properties of ACR pressure tubes are significantly improved. Based on previous experience with CANDU reactor pressure tubes an assessment of the grain structure and texture indicates that the in-reactor creep deformation will be improved also. Analysis of the distribution of texture parameters from a trial batch of 26 tubes shows that the variability is reduced relative to tubes fabricated in the past. This reduction in variability together with a shift to a coarser grain structure will result in a reduction in diametral creep design limits and thus a longer economic life for the fuel channels of the advanced CANDU reactor. (author)

  5. Etude des répercussions de la pollution industrielle sur la riziculture ...

    African Journals Online (AJOL)

    Les industries spécialisées dans le textile déversent leurs eaux usées dans le ... sur les sols, les compositions chimiques des plants de riz et sur la production. ... The effluents quality varies on day, the pH from 3.9 to 10.6 and the electrical ...

  6. Preliminary Design of S-CO2 Brayton Cycle for KAIST Micro Modular Reactor

    International Nuclear Information System (INIS)

    Kim, Seong Gu; Kim, Min Gil; Bae, Seong Jun; Lee, Jeong Ik

    2013-01-01

    This paper suggests a complete modular reactor with an innovative concept of reactor cooling by using a supercritical carbon dioxide directly. Authors propose the supercritical CO 2 Brayton cycle (S-CO 2 cycle) as a power conversion system to achieve small volume of power conversion unit (PCU) and to contain the core and PCU in one vessel for the full modularization. This study suggests a conceptual design of small modular reactor including PCU which is named as KAIST Micro Modular Reactor (MMR). As a part of ongoing research of conceptual design of KAIST MMR, preliminary design of power generation cycle was performed in this study. Since the targets of MMR are full modularization of a reactor system with S-CO 2 coolant, authors selected a simple recuperated S-CO 2 Brayton cycle as a power conversion system for KAIST MMR. The size of components of the S-CO 2 cycle is much smaller than existing helium Brayton cycle and steam Rankine cycle, and whole power conversion system can be contained with core and safety system in one containment vessel. From the investigation of the power conversion cycle, recompressing recuperated cycle showed higher efficiency than the simple recuperated cycle. However the volume of heat exchanger for recompressing cycle is too large so more space will be occupied by heat exchanger in the recompressing cycle than the simple recuperated cycle. Thus, authors consider that the simple recuperated cycle is more suitable for MMR. More research for the KAIST MMR will be followed in the future and detailed information of reactor core and safety system will be developed down the road. More refined cycle layout and design of turbomachinery and heat exchanger will be performed in the future study

  7. Severe accident analysis for level 2 PSA of SMART reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jin Yong; Lee, Jeong Hun; Kim, Jong Uk; Yoo, Tae Geun; Chung, Soon Il; Kim, Min Gi [FNC Technology Co., Seoul (Korea, Republic of)

    2010-12-15

    The objectives of this study are to produce data for level 2 PSA and evaluation results of severe accident by analyzing severe accident sequence of transient events, producing fault tree of containment systems and evaluating direct containment heating of the SMART. In this project, severe accident analysis results were produced for general transient, loss of feedwater, station blackout, and steam line break events, and based on the results, design safety of SMART was verified. Also, direct containment heating phenomenon of the SMART was evaluated using TCE methodology. For level 2 PSA, fault tree of the containment isolation system, reactor cavity flooding system, plant chilled water system, and reactor containment building HVAC system was produced and analyzed

  8. Recent advances in the utilization and the irradiation technology of the refurbished BR2 reactor

    International Nuclear Information System (INIS)

    Dekeyser, J.; Benoit, P.; Decloedt, C.; Pouleur, Y.; Verwimp, A.; Weber, M.; Vankeerberghen, M.; Ponsard, B.

    1999-01-01

    Operation and utilization of the materials testing reactor BR2 at the Belgian Nuclear Research Centre (SCK·CEN) has since its start in 1963 always followed closely the needs and developments of nuclear technology. In particular, a multitude of irradiation experiments have been carried out for most types of nuclear power reactors, existing or under design. Since the early 1990s and increased focus was directed towards more specific irradiation testing needs for light water reactor fuels and materials, although other areas of utilization continued as well (e.g. fusion reactor materials, safety research, ...), including also the growing activities of radioisotope production and silicon doping. An important milestone was the decision in 1994 to implement a comprehensive refurbishment programme for the BR2 reactor and plant installations. The scope of this programme comprised very substantial studies and hardware interventions, which have been completed in early 1997 within planning and budget. Directly connected to this strategic decision for reactor refurbishment was the reinforcement of our efforts to requalify and upgrade the existing irradiation facilities and to develop advanced devices in BR2 to support emerging programs in the following fields: - LWR pressure vessel steel, - LWR irradiation assisted stress corrosion cracking (IASCC), - reliability and safety of high-burnup LWR fuel, - fusion reactor materials and blanket components, - fast neutron reactor fuels and actinide burning, - extension and diversification of radioisotope production. The paper highlights these advances in the areas of BR2 utilisation and the ongoing development activities for the required new generation of irradiations devices. (author)

  9. An improved thermal-hydraulic modeling of the Jules Horowitz Reactor using the CATHARE2 system code

    Energy Technology Data Exchange (ETDEWEB)

    Pegonen, R., E-mail: pegonen@kth.se [KTH Royal Institute of Technology, Roslagstullsbacken 21, SE-10691 Stockholm (Sweden); Bourdon, S.; Gonnier, C. [CEA, DEN, DER, SRJH, CEA Cadarache, 13108 Saint-Paul-lez-Durance Cedex (France); Anglart, H. [KTH Royal Institute of Technology, Roslagstullsbacken 21, SE-10691 Stockholm (Sweden)

    2017-01-15

    Highlights: • An improved thermal-hydraulic modeling of the JHR reactor is described. • Thermal-hydraulics of the JHR is analyzed during loss of flow accident. • The heat exchanger approach gives more realistic and less conservative results. - Abstract: The newest European high performance material testing reactor, the Jules Horowitz Reactor, will support current and future nuclear reactor designs. The reactor is under construction at the CEA Cadarache research center in southern France and is expected to achieve first criticality at the end of this decade. This paper presents an improved thermal-hydraulic modeling of the reactor using solely CATHARE2 system code. Up to now, the CATHARE2 code was simulating the full reactor with a simplified approach for the core and the boundary conditions were transferred into the three-dimensional FLICA4 core simulation. A new more realistic methodology is utilized to analyze the thermal-hydraulic simulation of the reactor during a loss of flow accident.

  10. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  11. Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966; 2. Jugoslovenski simpozijum iz reaktorske fizike, Deo 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1966-07-01

    This Volume 2 of the Proceedings of 2. Yugoslav symposium on reactor physics includes eight papers dealing with the following topics: method for measuring high anti reactivities of a reactor system; integration method for thermal reaction rate calculation; Determination of initial core configuration for BHWR-200 MWe; safety shutdowns and failures of the RA reactor equipment; determining the reactivity of absorption rods; measurements of thermal and fast neutron fluxes at the TRIGA reactor and other measurements during operation of the TRIGA reactor; mathematical modelling of the reactor safety; review of problems and methods for radiation risk assessment in the environment of a nuclear power plant.

  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

    notamment l'introduction de taux de reactivite normaux et anormaux, les consequences des effets supposes de reactivite, a partir du comportement physique de l'alliage combustible et de la structure du reacteur, ainsi que par extrapolation des experiences faites sur TREAT au systeme EBR-II. Il examine le probleme de la fusion du coeur de EBR-II. (author) [Spanish] La memoria informa sobre los calculos del comportamiento estatico, dinamico y a largo plazo de la reactividad del reactor reproductor experimental EBR-II, asi como sobre los resultados y analisis de los experimentos criticos en seco del EBR-II y de los experimentos simulados en el reactor de potencia cero ZPR-III. Insiste particularmente en los problemas de fisica del reactor que, en la elaboracion del proyecto, siguen a la eleccion del modelo, pero preceden a la construccion y puesta en marcha del reactor. Presenta diversos analisis del reactor desde el punto de vista de la seguridad y formula consideraciones sobre la evaluacion de los riesgos y su influencia sobre el diseno del reactor. El trabajo explica tambien la manera de emplear los datos obtenidos en los experimentos arriba citados. Estos experimentos, su analisis y sus predicciones teoricas constituyen la base para determinar el comportamiento fisico del reactor. La memoria estudia detalladamente las limitaciones inherentes a la aplicacion de los datos experimentales al funcionamiento del reactor de potencia. Ello incluye datos precisos sobre as dimensiones del cuerpo, el enriquecimiento de la aleacion combustible, o de ambos factores; el establecimiento de una reactividad adecuada para el reactor funcionando o detenido, la determinacion de la variacion de los coeficientes de reactividad en funcion de la temperatura de funcionamiento y de la potencia generadora y detalles de la distribucion de la potencia y del flujo en diversos puntos de la estructura del reactor. La memoria expone tambien el problema general que supone transferir a la verdadera geometria

  13. Cooperación Sur-Sur para el fortalecimiento de los laboratorios de control de medicamentos de la Comunidad del Caribe (CARICOM

    Directory of Open Access Journals (Sweden)

    José María Parisi

    Full Text Available RESUMEN Objetivo Describir los beneficios obtenidos a través de la cooperación Sur-Sur y Triangular, como una potencial herramienta para el fortalecimiento en el control de la calidad de los medicamentos en los Laboratorios Oficiales de Control de Medicamentos (LOCM de la Región de las Américas. Métodos Estudio descriptivo del proyecto para el fortalecimiento en el control de la calidad de los medicamentos en los LOCM de la Comunidad del Caribe (CARICOM. Resultados La capacitación fue desarrollada por profesionales de la Administración Nacional de Medicamentos, Alimentos y Tecnología Médica (ANMAT de Argentina, a profesionales de Guyana, Jamaica, Surinam y Trinidad y Tobago. El proyecto contó con financiamiento del Fondo Argentino de Cooperación Sur-Sur y Triangular (FO.AR y coordinación de la Organización Panamericana de la Salud (OPS. Se revisaron los documentos de Buenas Prácticas de Laboratorio (BPL de la Organización Mundial de la Salud (OMS y de la Red Panamericana para la Armonización de la Reglamentación Farmacéutica (Red-PARF y se fortaleció el área de controles físicos químicos, principalmente en relación a medicamentos para el tratamiento de la tuberculosis, la malaria y el VIH/sida, todos de importancia estratégica para esos países. Conclusión Este tipo de colaboraciones permiten transferir experiencia, optimizar los recursos, armonizar procedimientos y regulaciones y reforzar capacidades en término de recursos humanos, y constituyen una herramienta valiosa en la reducción de las asimetrías que pudieron establecerse en diferentes áreas entre diferentes países de nuestra región.

  14. L'Avenir de la Vie sur la Terre

    CERN Document Server

    CERN. Geneva

    2007-01-01

    Notre planète va mal : réchauffement climatique, épuisement des ressources naturelles, pollutions des sols et de l'eau provoquées par les industries civiles et guerrières, disparité des richesses, malnutrition des hommes, taux d'extinction effarant des espèces vivantes, etc. La situation est-elle vraiment dramatique ? Que penser des thèses qui contestent ce pessimisme ? À partir des données scientifiques les plus crédibles - et de leurs incertitudes -, Hubert Reeves dresse un bilan précis des menaces qui pèsent sur la planète. Son diagnostic est alarmant : si la vie sur Terre est robuste, c'est l'avenir de l'espèce humaine qui est en cause. Le sort de l'aventure humaine, entamée il y a des millions d'années, va-t-il se jouer en l'espace de quelques décennies ? Notre avenir est entre nos mains. Il faut réagir, et vite, avant qu'il ne soit trop tard. Auteur de nombreux ouvrages sur l'odyssée cosmique tel Patience dans l'azur ou Poussières d'étoiles, Hubert Reeves est astrophysicien et dire...

  15. La Convention de Rio sur la diversité biologique

    OpenAIRE

    Maljean-Dubois , Sandrine

    2016-01-01

    International audience; Du 3 au 14 juin 1992, en écho à la première grande conférence onusienne sur l'environnement et le développement, celle de Stockholm organisée en 1972, se tenait à Rio de Janeiro la Conférence des Nations Unies sur l'environnement et le développement (CNUED), dite aussi Sommet de la Terre. Cette conférence marquait une étape dans la perception des enjeux environnementaux et suscitait de vifs espoirs. Un programme d'action pour le XXI ème siècle, Action 21, dont le chapi...

  16. Liquid metal fast breeder reactor steam generator survey of the consequences of large scale sodium water reaction

    International Nuclear Information System (INIS)

    Vambenepe, G.

    1978-01-01

    The ''Retona'' three-dimensional hydrodynamic computing code is being developed by Electricity de France to survey the consequences, on the very plant, of a large scale sodium water reaction in liquid metal steam generators. In this communication, the heat-exchanger geometry is schematized and the problem solving process briefly described under assumed simplifying hypotheses. The application of the results to the Creusot-Loire steam generator selected for Super-Phenix are given as an example. (author)

  17. Where are the radioactive wastes in France? Brochure no 2; Ou sont les dechets radioactifs en France? Brochure no 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 2 concerns the Bretagne (Brittany), Pays de la Loire, Haute-Normandie, Basse-Normandie and Centre regions. (J.S.)

  18. Problems of nuclear reactor safety. Vol. 2

    International Nuclear Information System (INIS)

    Goncharov, L.A.

    1995-01-01

    Theses of proceedings of the 9 Topical Meeting on problems of nuclear power plant safety are presented. Reports include results of neutron-physical experiments carried out for reactor safety justification. Concepts of advanced reactors with improved safety are considered. Results of researches on fuel cycles are given too

  19. Bâle 3 : Quels impacts sur le financement des pays émergents ?

    OpenAIRE

    Figuet, Jean-Marc; Humblot, Thomas; Lahet, Delphine

    2013-01-01

    La persistance de crises bancaires démontre l'incapacité des établissements de crédit à s'autoréguler. De ce fait, le Comité de Bâle étend largement le périmètre de la nouvelle règlementation prudentielle. Sur la base de la littérature sur les déterminants des flux de capitaux transfrontières et d'un GMM système, cet article analyse l'impact potentiel de l'accord Bâle 3 sur les flux de capitaux bancaires provenant des banques de 16 pays industrialisés à destination d'un panel de 30 pays émerg...

  20. The Effect Of Beryllium Interaction With Fast Neutrons On the Reactivity Of ETRR-2 Research Reactor

    International Nuclear Information System (INIS)

    Aziz, M.; El Messiry, A.M.

    2000-01-01

    The effect of beryllium interactions with fast neutrons is studied for Etrr 2 research reactors. Isotope build up inside beryllium blocks is calculated under different irradiation times. a new model for the Etrr 2 research reactor is designed using MCNP code to calculate the reactivity and flux change of the reactor due to beryllium poison

  1. Economics and utilization of thorium in nuclear reactors. Technical annexes 1 and 2

    International Nuclear Information System (INIS)

    1978-05-01

    An assessment of the impact of utilizing the 233 U/thorium fuel cycle in the U.S. nuclear economy is strongly dependent upon several decisions involving nuclear energy policy. These decisions include: (1) to recycle or not recycle fissile material; (2) if fissile material is recycled, to recycle plutonium, 233 U, or both; and (3) to deploy or not to deploy advanced reactor designs such as Fast Breeder Reactors (FBR's), High Temperature Gas Reactors (HTGR's), and Canadian Deuterium Uranium Reactors (CANDU's). This report examines the role of thorium in the context of the above policy decisions while focusing special attention on economics and resource utilization

  2. Effets du travail du sol sur le comportement chimique et biologique ...

    African Journals Online (AJOL)

    SARAH

    31 juil. 2017 ... RESUME. Objectif : L'objectif de cette étude est de comparer les effets de six techniques culturales de mise en place du blé tendre sur certaines propriétés chimiques et biologiques du sol et les conséquences sur le rendement grain et ses composantes dans la région «non chernozem» en 7ème années ...

  3. Development of UO2/PuO2 dispersed in uranium matrix CERMET fuel system for fast reactors

    International Nuclear Information System (INIS)

    Sinha, V.P.; Hegde, P.V.; Prasad, G.J.; Pal, S.; Mishra, G.P.

    2012-01-01

    CERMET fuel with either PuO 2 or enriched UO 2 dispersed in uranium metal matrix has a strong potential of becoming a fuel for the liquid metal cooled fast breeder reactors (LMR’s). In fact it may act as a bridge between the advantages and disadvantages associated with the two extremes of fuel systems (i.e. ceramic fuel and metallic fuel) for fast reactors. At Bhabha Atomic Research Centre (BARC), R and D efforts are on to develop this CERMET fuel by powder metallurgy route. This paper describes the development of flow sheet for preparation of UO 2 dispersed in uranium metal matrix pellets for three different compositions i.e. U–20 wt%UO 2 , U–25 wt%UO 2 and U–30 wt%UO 2 . It was found that the sintered pellets were having excellent integrity and their linear mass was higher than that of carbide fuel pellets used in Fast Breeder Test Reactor programme (FBTR) in India. The pellets were characterized by X-ray diffraction (XRD) technique for phase analysis and lattice parameter determination. The optical microstructures were developed and reported for all the three different U–UO 2 compositions.

  4. Development of UO2/PuO2 dispersed in uranium matrix CERMET fuel system for fast reactors

    Science.gov (United States)

    Sinha, V. P.; Hegde, P. V.; Prasad, G. J.; Pal, S.; Mishra, G. P.

    2012-08-01

    CERMET fuel with either PuO2 or enriched UO2 dispersed in uranium metal matrix has a strong potential of becoming a fuel for the liquid metal cooled fast breeder reactors (LMR's). In fact it may act as a bridge between the advantages and disadvantages associated with the two extremes of fuel systems (i.e. ceramic fuel and metallic fuel) for fast reactors. At Bhabha Atomic Research Centre (BARC), R & D efforts are on to develop this CERMET fuel by powder metallurgy route. This paper describes the development of flow sheet for preparation of UO2 dispersed in uranium metal matrix pellets for three different compositions i.e. U-20 wt%UO2, U-25 wt%UO2 and U-30 wt%UO2. It was found that the sintered pellets were having excellent integrity and their linear mass was higher than that of carbide fuel pellets used in Fast Breeder Test Reactor programme (FBTR) in India. The pellets were characterized by X-ray diffraction (XRD) technique for phase analysis and lattice parameter determination. The optical microstructures were developed and reported for all the three different U-UO2 compositions.

  5. Utilization of the SLOWPOKE-2 research reactor

    International Nuclear Information System (INIS)

    Lalor, G.C.

    2001-01-01

    SLOWPOKEs are typically low power research reactors that have a limited number of applications. However, a significant range of NAA can be performed with such reactors. This paper describes a SLOWPOKE-based NAA program that is performing a valuable series of studies in Jamaica, including geological mapping and pollution assessment. (author)

  6. Sur?Surva - the Forgotten God [In Bulgarian

    Directory of Open Access Journals (Sweden)

    G. Simeonova

    2014-12-01

    Full Text Available Тhis paper deals with the neglected god – Sur/Surva. The author considers in full detail this problem, finding an evidence for the statements proposed by a new perusal of Stefan Verkovich’s Veda Slovena.

  7. Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

  8. Perception du risque et vulnérabilité des milieux humides sur la côte ...

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

    Ils repéreront et évalueront les facteurs de stress associés aux changements climatiques pour ensuite analyser les facteurs qui influent sur la gestion des milieux humides et sur la perception des risques au sein des collectivités locales. Cette analyse débouchera sur l'élaboration de lignes directrices pour encourager les ...

  9. Measurements at the RA Reactor related to the VISA-2 project - Part 1, Start-up of the RA reactor and measurement of new RA reactor core parameters

    International Nuclear Information System (INIS)

    Markovic, H.

    1962-07-01

    The objective of the measurements was determining the neutron flux in the RA reactor core. Since the number of fuel channels is increased from 56 to 68 within the VISA-2 project, it was necessary to attain criticality of the RA reactor and measure the neutron flux properties. The 'program of RA reactor start-up' has been prepared separately and it is included in this report. Measurements were divided in two phases. First phase was measuring of the neutron flux after the criticality was achieved but at zero power. During phase two measurements were repeated at several power levels, at equilibrium xenon poisoning. This report includes experimental data of flux distributions and absolute values of the thermal and fast neutron flux in the RA reactor experimental channels and values of cadmium ratio for determining the neutron epithermal flux. Data related to calibration of regulatory rods for cold un poisoned core are included [sr

  10. Sur le discours et l’histoire en foucault. Entretien avec Jacques Guilhaumou

    Directory of Open Access Journals (Sweden)

    Welisson Marques

    2013-08-01

    Full Text Available Dans cet entretien inédit, Jaques Guilhaumou parle sur la question du discours et de l´histoire dans la pensée de Michel Foucault en regardant telles questions à partir du belvédère de l’Analyse du Discours selon la perception française. Il commence en présentant un panorama de ses travaux plus actuels et souligne ensuite le rôle décisif de Foucault dans le établissement de une nouvelle relation entre le discours et l´histoire. Dans cette direction, il donne des détails sur quelques influences épistémologiques de la pensée foucaultienne qui viennent surtout de Nietzsche et Koselleck. Comme un grand étudiant de la pensée marxiste, Guilhaumou parle aussi sur le concept de l´ideologie et ses plusières métamorphoses conceptuelles dans autres champs jusqu´au moment de parler sur la question du pouvoir. Il parle quand même sur la problématique de l´analyse des images dans l´Analyse du Discours, une question favorable pour beaucoup des analystes du discours qui s´occupent avec le syncrétisme sémiotique des ses objets dans l´actualité. Enfin, il indique l´existence de une théorie du discours diluée dans la pensée du philosophe.

  11. Reactor limitation system improves the safety and availability of the Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Souza Mendes, J.E. de

    1987-01-01

    Beyond the classic Reactor Protection System and Reactor Control System, nuclear plant Angra 2 has a third system called Reactor Limitation System which combines the intelligence features of the control systems with the high reliability of the protection systems. In determined events, which are not controlled by the control system (e.g.: load rejection, failure of one main reactor coolant pump), the Reactor Limitation System actuates automatically in order to lead the plant to a safe operating condition and so it avoids the actuation of the Reactor Protection System and consequently the reactor trip. This increases safety and availability of the plant and reduces component stresses. After the safe operating condition is reached, the process guidance automatically returns to the control systems. (Author) [pt

  12. Pouvoir et sexualité. Le discours féministe sur la prostitution en France (1968-1986.

    Directory of Open Access Journals (Sweden)

    Damien Simonin

    2010-07-01

    Full Text Available Cette recherche porte sur les discours sur la prostitution dans la presse féministe, entre 1968 et 1986 en France. Durant cette période, le mouvement féministe est composé de courants conflictuels (courants réformistes et révolutionnaires, différentialistes et universalistes et il porte des discours hétérogènes (informations sur la prostitution, analyses théoriques et politiques, témoignages de prostituées. Pourtant, ces discours s'accordent sur la revendication d'une libération des rapport...

  13. Experiments on light water lattices with enriched uranium fuel; Analyse des donnees experimentales sur les reseaux a eau legere et uranium enrichi

    Energy Technology Data Exchange (ETDEWEB)

    Audinet, M [Societe des Forges et Ateliers du Creusot, 75 - Paris (France); Lamare, J de [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Panossian, J [Societe Alsacienne de Constructions Mecaniques (France)

    1958-07-01

    Experiments a light water lattices with slightly enriched uranium fuel, have been performed at Brookhaven and Bettis Plant Laboratories. The results are studied and compared with simple theories on reactor calculations. By taking into account shadow effects and non Maxwellian neutron spectrum, which are important in this kind of reactors, we have been able to explain the observed results fairly well. We can thus give a constituent set of formulas with which to calculate lattices similar to there we studied. (author) [French] Les resultats d'experiences effectuees aux Laboratoires de Brookbaven et de Bettis Plant, sur des reseaux heterogenes a eau legere et uranium metallique legerement enrichi, sont analyses et confrontes avec les theories simples du calcul de pile. En tenant compte des effets d'interaction et d'echauffement du spectre de neutrons qui sont importants dans ce type de reacteurs, on parvient a rendre compte convenablement des resultats observes. On a ainsi mis au point un formulaire permettant le calcul des reseaux quivpeuvent etre consideres comme assez semblables aux reseaux etudies. (auteur)

  14. CO_2 capture with solid sorbent: CFD model of an innovative reactor concept

    International Nuclear Information System (INIS)

    Barelli, L.; Bidini, G.; Gallorini, F.

    2016-01-01

    Highlights: • A new reactor solution based on rotating fixed beds was presented. • The preliminary design of the reactor was approached. • A CFD model of the reactor, including CO_2 capture kinetic, was developed. • The CFD model is validated with experimental results. • Sorbent exploitation increasing is possible thanks to the new reactor. - Abstract: In future decarbonization scenarios, CCS with particular reference to post-combustion technologies will be an important option also for energy intensive industries. Nevertheless, today CCS systems are rarely installed due to high energy and cost penalties of current technology based on chemical scrubbing with amine solvent. Therefore, innovative solutions based on new/optimized solvents, sorbents, membranes and new process designs, are R&D priorities. Regarding the CO_2 capture through solid sorbents, a new reactor solution based on rotating fixed beds is presented in this paper. In order to design the innovative system, a suitable CFD model was developed considering also the kinetic capture process. The model was validated with experimental results obtained by the authors in previous research activities, showing a potential reduction of energy penalties respect to current technologies. In the future, the model will be used to identify the control logic of the innovative reactor in order to verify improvements in terms of sorbent exploitation and reduction of system energy consumption.

  15. MULTI-LOOP CONTROL DESIGN IN MULTIVARIABLE (2X2 CONTINUOUS STIRRED TANK REACTOR

    Directory of Open Access Journals (Sweden)

    Abdul Wahid

    2015-06-01

    Full Text Available With this study, the design and tuning of multi-loop for multivariable (2x2 CSTR will be made in order to achieve optimum CSTR control performance. This study used Bequette model reactor and MATLAB software and is expected to be able to cope with disturbances in the reactor so that the reactor system is able to stabilize quickly despite the distractions. In this study, the design will be made using multi-loop approach, along with PI controller as the next step. Then, BLT and auto-tune tuning method will be used in PI controller and given disturbances to both of tuning method. The controller performances are then compared. Results of the study are then analyzed for discussions and conclusions. Results from this study have shown that in terms of disturbance rejection, BLT is better than auto-tune based on comparison between both of controller performances. For IAE for the case of temperature, BLT is 30% better than auto-tune, but it is almost the same for the case of concentration. For settling time for the case of concentration, BLT is 30% better than auto-tune, and for the case of temperature, BLT is 18% better than auto-tune. For rise time for the case of concentration and temperature, BLT is 30% better than auto-tune.

  16. Operating reactors licensing actions summary. Volume 5, No. 2

    International Nuclear Information System (INIS)

    1985-04-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management. This summary report is published primarily for internal NRC use in managing the Operating Reactors Licensing Actions Program

  17. Tests of Neutron Spectrum Calculations with the Help of Foil Measurements in a D{sub 2}O and in an H{sub 2}O-Moderated Reactor and in Reactor Shields of Concrete an Iron

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, R; Aalto, E

    1964-09-15

    Foil measurements covering the fast, epithermal and thermal neutron energy regions have been made in the centre of the Swedish D{sub 2}O-moderated reactor R1, in the pool reactor R2-0, and in different positions in reactor shields of iron, magnetite concrete and ordinary concrete. Neutron spectra have also been calculated for most of these positions, often with the help of a numerical integration of the Boltzmann equation. The measurements and the calculated spectra are presented.

  18. Microflow photochemistry: UVC-induced [2 + 2]-photoadditions to furanone in a microcapillary reactor

    Directory of Open Access Journals (Sweden)

    Sylvestre Bachollet

    2013-10-01

    Full Text Available [2 + 2]-Cycloadditions of cyclopentene and 2,3-dimethylbut-2-ene to furanone were investigated under continuous-flow conditions. Irradiations were conducted in a FEP-microcapillary module which was placed in a Rayonet chamber photoreactor equipped with low wattage UVC-lamps. Conversion rates and isolated yields were compared to analogue batch reactions in a quartz test tube. In all cases examined, the microcapillary reactor furnished faster conversions and improved product qualities.

  19. Altiplano Sur de Bolivia

    OpenAIRE

    Alvarez-Flores, Ricardo; Bommel, Pierre; Bourliaud, Jean; Chevarria Lazo, Marco; Cortes, Geneviève; Cruz, Pablo; Del Castillo, C.; Gasselin, Pierre; Joffre, Richard; Leger, Francois; Nina Laura, Juan Peter; Rambal, Serge; Rivière, Gilles; Tichit, Muriel; Tourrand, Jean-François

    2014-01-01

    Alimento de base de las poblaciones andinas desde hace milenios, la quinua se ha convertido hoy en un producto apreciado en el mercado internacional de alimentos dietéticos, orgánicos y equitativos. Este cambio lo iniciaron los mismos productores del Altiplano Sur de Bolivia hace aproximadamente unos 40 años. En medio de un desierto de altura, ellos lograron desarrollar una floreciente producción agrícola de exportación. Aunque cuentan con lucrativos nichos de mercado, los productores de quin...

  20. Marín E. y Romero M. (Eds., Cuando el Sur piensa el Sur. Los giros de la cooperación al desarrollo, Bogotá: Universidad Externado de Colombia, 364 pp.

    Directory of Open Access Journals (Sweden)

    Daniel Vargas

    2016-07-01

    Full Text Available El marco introductorio del libro indica que los Estados ubicados en África, Asia y América del Sur, comparten algunas características climáticas, geológicas, biotípicas, económicas e históricas como fuentes inagotables de diversidades identitarias. Es por esto que cobran sentido y adquieren eco las palabras de la líder Leonor Zalabata de la etnia Arhuaca de Colombia transcritas en el epígrafe de la presente reseña, quien al preguntársele por el futuro de los pueblos originarios respondió: “somos y seguiremos siendo”. Lo que significa que, al considerar que los pueblos indígenas y autóctonos son un actor común en los continentes del Sur, y afianzados en la defensa de su identidad, promueven el autodesarrollo, convirtiéndose así en un actor político relevante en los procesos de cooperación Sur-Sur.

  1. A simulation Model of the Reactor Hall Ventilation and air Conditioning Systems of ETRR-2

    International Nuclear Information System (INIS)

    Abd El-Rahman, M.F.

    2004-01-01

    Although the conceptual design for any system differs from one designer to another. each of them aims to achieve the function of the system required. the ventilation and air conditioning system of reactors hall is one of those systems that really differs but always dose its function for which it is designed. thus, ventilation and air conditioning in some reactor hall constitute only one system whereas in some other ones, they are separate systems. the Egypt Research Reactor-2 (ETRR-2)represents the second type. most studies conducted on ventilation and air conditioning simulation models either in traditional building or for research rectors show that those models were not designed similarly to the model of the hall of ETRR-2 in which ventilation and air conditioning constitute two separate systems.besides, those studies experimented on ventilation and air conditioning simulation models of reactor building predict the temperature and humidity inside these buildings at certain outside condition and it is difficult to predict when the outside conditions are changed . also those studies do not discuss the influences of reactor power changes. therefore, the present work deals with a computational study backed by infield experimental measurements of the performance of the ventilation and air conditioning systems of reactor hall during normal operation at different outside conditions as well as at different levels of reactor power

  2. Thermal design of heat-exchangeable reactors using a dry-sorbent CO2 capture multi-step process

    International Nuclear Information System (INIS)

    Moon, Hokyu; Yoo, Hoanju; Seo, Hwimin; Park, Yong-Ki; Cho, Hyung Hee

    2015-01-01

    The present study proposes a multi-stage CO 2 capture process that incorporates heat-exchangeable fluidized-bed reactors. For continuous multi-stage heat exchange, three dry regenerable sorbents: K 2 CO 3 , MgO, and CaO, were used to create a three-stage temperature-dependent reaction chain for CO 2 capture, corresponding to low (50–150 °C), middle (350–650 °C), and high (750–900 °C) temperature stages, respectively. Heat from carbonation in the high and middle temperature stages was used for regeneration for the middle and low temperature stages. The feasibility of this process is depending on the heat-transfer performance of the heat-exchangeable fluidized bed reactors as the focus of this study. The three-stage CO 2 capture process for a 60 Nm 3 /h CO 2 flow rate required a reactor area of 0.129 and 0.130 m 2 for heat exchange between the mid-temperature carbonation and low-temperature regeneration stages and between the high-temperature carbonation and mid-temperature regeneration stages, respectively. The reactor diameter was selected to provide dense fluidization conditions for each bed with respect to the desired flow rate. The flow characteristics and energy balance of the reactors were confirmed using computational fluid dynamics and thermodynamic analysis, respectively. - Highlights: • CO 2 capture process is proposed using a multi-stage process. • Reactor design is conducted considering heat exchangeable scheme. • Reactor surface is designed by heat transfer characteristics of fluidized bed

  3. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

    Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

  4. Effets du stress salin sur la germination des graines de Gossypium ...

    African Journals Online (AJOL)

    SARAH

    31 août 2014 ... herbeuses et vives tandis que 40 % des graines ont germé sur tanne arbustive en milieu réel. Conclusion et application: l'objectif général de cette étude menée en milieu contrôlé (application des doses de sel) et en milieu réel (tannes) était de montrer les effets du stress salin sur la germination des graines.

  5. Core design calculations of IRIS reactor using modified CORD-2 code package

    International Nuclear Information System (INIS)

    Pevec, D.; Grgic, D.; Jecmenica, R.; Petrovic, B.

    2002-01-01

    Core design calculations, with thermal-hydraulic feedback, for the first cycle of the IRIS reactor were performed using the modified CORD-2 code package. WIMSD-5B code is applied for cell and cluster calculations with two different 69-group data libraries (ENDF/BVI rev. 5 and JEF-2.2), while the nodal code GNOMER is used for diffusion calculations. The objective of the calculation was to address basic core design problems for innovative reactors with long fuel cycle. The results were compared to our results obtained with CORD-2 before the modification and to preliminary results obtained with CASMO code for a similar problem without thermal-hydraulic feedback.(author)

  6. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  7. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  8. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  9. Apprentissage en ligne et sur le tas au Mexique | CRDI - Centre de ...

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

    Laura Dávila est de retour sur les bancs de l'école. Installée à son bureau dans la classe virtuelle @Campus Mexico, cette fonctionnaire mexicaine se renseigne sur son propre gouvernement — ses ministères et son cadre juridique, les lois qui encadrent l'accès à l'information et la responsabilité de la fonction publique, ...

  10. Synthèse de la recherche sur les moyens de subsistance pouvant ...

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

    Synthèse de la recherche sur les moyens de subsistance pouvant remplacer la culture du tabac. Dans l'espoir de faire obstacle aux politiques visant à réduire la demande de produits du tabac, les compagnies de tabac font valoir que ces politiques auront des répercussions négatives sur l'emploi et l'économie des pays ...

  11. Incidence des prix et des taxes sur la consommation de produits du ...

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

    Incidence des prix et des taxes sur la consommation de produits du tabac en Argentine, en Bolivie et au Chili. Partout en Amérique du Sud, les adultes et les enfants font une grande consommation de tabac. Un nouveau projet de recherche se penchera sur les avantages et les limites des stratégies de fixation des prix et de ...

  12. La vérite sur ce qui nous motive

    CERN Document Server

    Pink, Daniel H

    2011-01-01

    Voici enfin la traduction française du best-seller international DRIVE ! Qu'est-ce qui nous motive vraiment ? Dans quels cas sommes-nous les plus performants et les plus enthousiastes ? La plupart d'entre nous sommes persuadés que les récompenses (salaire, primes...) sont notre meilleure motivation. La logique de la carotte et du bâton finalement... Et si nous faisions fausse route ? En s'appuyant sur quatre décennies d'études scientifiques et psychologiques sur la motivation humaine, Pink démontre que les entreprises dirigent très mal leurs équipes avec d'énormes conséquences sur notre vie (absence d'ambition, lassitude, morosité). Le secret de la performance (et de la satisfaction) dans les entreprises, l'enseignement ou dans notre vie personnelle , c'est le besoin profondément humain de diriger sa propre vie, d'apprendre, de créer de nouvelles choses et de s'améliorer. Dans ce livre, Pink examine les 3 éléments de la motivation, l'autonomie, la maîtrise et le besoin de donner un sens ...

  13. BR2 reactor: medical and industrial applications

    International Nuclear Information System (INIS)

    Ponsard, B.

    2005-01-01

    The radioisotopes are produced for various applications in the nuclear medicine (diagnostic, therapy, palliation of metastatic bone pain), industry (radiography of welds, ...), agriculture (radiotracers, ...) and basic research. Due to the availability of high neutron fluxes (thermal neutron flux up to 10 15 n/cm 2 .s), the BR2 reactor is considered as a major facility through its contribution for a continuous supply of products such 99 Mo ( 99 mTc), 131 I, 133 Xe, 192 Ir, 186 Re, 153 Sm, 90 Y, 32 P, 188 W ( 188 Re), 203 Hg, 82 Br, 41 Ar, 125 I, 177 Lu, 89 Sr, 60 Co, 169 Yb, 147 Nd, and others. Neutron Transmutation Doped (NTD) silicon is produced for the semiconductor industry in the SIDONIE (Silicon Doping by Neutron Irradiation Experiment) facility, which is designed to continuously rotate and traverse the silicon through the neutron flux. These combined movements produce exceptional dopant homogeneity in batches of silicon measuring 4 and 5-inches in diameter by up to 750 mm in length. The main objectives of work performed were to provide a reliable and qualitative supply of radioisotopes and NTD-silicon to the customers in accordance with a quality system that has been certified to the requirements of the EN ISO 9001: 2000. This new Quality System Certificate has been obtained in November 2003 for the Production of radioisotopes for medical and industrial applications and the Production of Neutron Transmutation Doped (NTD) Silicon in the BR2 reactor

  14. Possible future roles for fast breeder reactors Part 1 and 2

    International Nuclear Information System (INIS)

    1978-06-01

    Part 1. The Fast Breeder Reactor (in particular in its sodium cooled version) has been steadily developed in the Community. This report attempts to quantify the advantages of this system in terms of fossil energy and uranium savings in the medium/long term as well as to examine some long term economic implications. The methodology of comparing scenarios, not individual reactor systems is followed. These scenarios have been chosen taking into account a range of assumptions concerning Community energy demand growth, fossil energy and uranium availability and technological capabilities. Part 2. The fast breeder reactor (FBR), particularly its sodium-cooled form (LMFBR) has been under development in the Community for many years. Industrial enterprises dedicated to its commercialisation have been formed and long range plans for its industrial utilisation are being formulated. The value of breeder reactors from the point of view of minimising Community fuel requirements has been discussed in Part I of this report (1). In Part II the consequences of delaying their introduction, and the demands placed upon the recycle industry by the introduction of fast reactors of different characteristics, using the Community electricity demand scenarios developed for Part I, are discussed. In addition comments are provided upon the effect of FBR introduction on the size of plutonium stocks

  15. A regression approach for Zircaloy-2 in-reactor creep constitutive equations

    International Nuclear Information System (INIS)

    Yung Liu, Y.; Bement, A.L.

    1977-01-01

    In this paper the methodology of multiple regressions as applied to Zircaloy-2 in-reactor creep data analysis and construction of constitutive equation are illustrated. While the resulting constitutive equation can be used in creep analysis of in-reactor Zircaloy structural components, the methodology itself is entirely general and can be applied to any creep data analysis. The promising aspects of multiple regression creep data analysis are briefly outlined as follows: (1) When there are more than one variable involved, there is no need to make the assumption that each variable affects the response independently. No separate normalizations are required either and the estimation of parameters is obtained by solving many simultaneous equations. The number of simultaneous equations is equal to the number of data sets. (2) Regression statistics such as R 2 - and F-statistics provide measures of the significance of regression creep equation in correlating the overall data. The relative weights of each variable on the response can also be obtained. (3) Special regression techniques such as step-wise, ridge, and robust regressions and residual plots, etc., provide diagnostic tools for model selections. Multiple regression analysis performed on a set of carefully selected Zircaloy-2 in-reactor creep data leads to a model which provides excellent correlations for the data. (Auth.)

  16. Coolant radiolysis studies in the high temperature, fuelled U-2 loop in the NRU reactor

    International Nuclear Information System (INIS)

    Elliot, A.J.; Stuart, C.R.

    2008-06-01

    An understanding of the radiolysis-induced chemistry in the coolant water of nuclear reactors is an important key to the understanding of materials integrity issues in reactor coolant systems. Significant materials and chemistry issues have emerged in Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR) and CANDU reactors that have required a detailed understanding of the radiation chemistry of the coolant. For each reactor type, specific computer radiolysis models have been developed to gain insight into radiolysis processes and to make chemistry control adjustments to address the particular issue. In this respect, modelling the radiolysis chemistry has been successful enough to allow progress to be made. This report contains a description of the water radiolysis tests performed in the U-2 loop, NRU reactor in 1995, which measured the CHC under different physical conditions of the loop such as temperature, reactor power and steam quality. (author)

  17. Design and computational analysis of passive siphon breaker for 49-2 swimming pool reactor

    International Nuclear Information System (INIS)

    Yue Zhiting; Song Yunpeng; Liu Xingmin; Zou Yao; Wu Yuanyuan

    2014-01-01

    Based on safety considerations, a passive siphon breaker will be added to the primary cooling system of 49-2 Swimming Pool Reactor (SPR). With the breaker location determined, the capability of siphon breakers with diameters of 1.5 cm and 2.0 cm was calculated and analyzed respectively by RELAP5/MOD3.3 code. The results show that in the condition of large break loss of coolant accident these two sizes of siphon breakers are able to break the siphon phenomena, and maintain the pool water level above the reactor core when the reactor and the pump are shutdown. In the end, to be conservative, the siphon breaker with diameter of 2.0 cm is adopted. (authors)

  18. Efficient H2O2/CH3COOH oxidative desulfurization/denitrification of liquid fuels in sonochemical flow-reactors.

    Science.gov (United States)

    Calcio Gaudino, Emanuela; Carnaroglio, Diego; Boffa, Luisa; Cravotto, Giancarlo; Moreira, Elizabeth M; Nunes, Matheus A G; Dressler, Valderi L; Flores, Erico M M

    2014-01-01

    The oxidative desulfurization/denitrification of liquid fuels has been widely investigated as an alternative or complement to common catalytic hydrorefining. In this process, all oxidation reactions occur in the heterogeneous phase (the oil and the polar phase containing the oxidant) and therefore the optimization of mass and heat transfer is of crucial importance to enhancing the oxidation rate. This goal can be achieved by performing the reaction in suitable ultrasound (US) reactors. In fact, flow and loop US reactors stand out above classic batch US reactors thanks to their greater efficiency and flexibility as well as lower energy consumption. This paper describes an efficient sonochemical oxidation with H2O2/CH3COOH at flow rates ranging from 60 to 800 ml/min of both a model compound, dibenzotiophene (DBT), and of a mild hydro-treated diesel feedstock. Four different commercially available US loop reactors (single and multi-probe) were tested, two of which were developed in the authors' laboratory. Full DBT oxidation and efficient diesel feedstock desulfurization/denitrification were observed after the separation of the polar oxidized S/N-containing compounds (S≤5 ppmw, N≤1 ppmw). Our studies confirm that high-throughput US applications benefit greatly from flow-reactors. Copyright © 2013 Elsevier B.V. All rights reserved.

  19. Direct In Situ Quantification of HO2 from a Flow Reactor.

    Science.gov (United States)

    Brumfield, Brian; Sun, Wenting; Ju, Yiguang; Wysocki, Gerard

    2013-03-21

    The first direct in situ measurements of hydroperoxyl radical (HO2) at atmospheric pressure from the exit of a laminar flow reactor have been carried out using mid-infrared Faraday rotation spectroscopy. HO2 was generated by oxidation of dimethyl ether, a potential renewable biofuel with a simple molecular structure but rich low-temperature oxidation chemistry. On the basis of the results of nonlinear fitting of the experimental data to a theoretical spectroscopic model, the technique offers an estimated sensitivity of reactor exit temperature range of 398-673 K. Accurate in situ measurement of this species will aid in quantitative modeling of low-temperature and high-pressure combustion kinetics.

  20. Reactor science and technology: operation and control of reactors

    International Nuclear Information System (INIS)

    Qiu Junlong

    1994-01-01

    This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

  1. Status and perspective of development of cold moderators at the IBR-2 reactor

    International Nuclear Information System (INIS)

    Kulikov, S; Shabalin, E

    2012-01-01

    The modernized IBR-2M reactor will start its operation with three water grooved moderators in 2011. Afterwards, they will be exchanged by a new complex of moderators. The complex consists of three so-called kombi-moderators, each of them containing a pre-moderator, a cold moderator, grooved ambient water moderators and post-moderators. They are mounted onto three moveable trolleys that serve to deliver and install moderators near the reactor core. The project is divided in three stages. In 2012 the first stage of development of complex of moderators will be finished. The water grooved moderator will be replaced with the new kombi-moderator for beams nos. 7, 8, 10, 11. Main parameters of moderators for this direction will be studied then. The next stages will be done for beams nos. 2-3 and for beams nos. 1, 9, 4-6, consequently. Cold moderator chambers at the modernized IBR-2 reactor are filled with thousands of beads (∼3.5 - 4 mm in diameter) of moderating material. The cold helium gas flow delivers beads from the charging device to the moderator during the fulfillment process and cools down them during the reactor cycle. The mixture of aromatic hydrocarbons (mesithylen and m-xylen) has been chosen as moderating material. The explanation of the choice of material for novel cold neutron moderators, configuration of moderator complex for the modernized IBR-2 reactor and the main results of optimization of moderator complex for the third stage of moderator development are discussed in the article.

  2. Status and perspective of development of cold moderators at the IBR-2 reactor

    Science.gov (United States)

    Kulikov, S.; Shabalin, E.

    2012-03-01

    The modernized IBR-2M reactor will start its operation with three water grooved moderators in 2011. Afterwards, they will be exchanged by a new complex of moderators. The complex consists of three so-called kombi-moderators, each of them containing a pre-moderator, a cold moderator, grooved ambient water moderators and post-moderators. They are mounted onto three moveable trolleys that serve to deliver and install moderators near the reactor core. The project is divided in three stages. In 2012 the first stage of development of complex of moderators will be finished. The water grooved moderator will be replaced with the new kombi-moderator for beams #7, 8, 10, 11. Main parameters of moderators for this direction will be studied then. The next stages will be done for beams #2-3 and for beams #1, 9, 4-6, consequently. Cold moderator chambers at the modernized IBR-2 reactor are filled with thousands of beads (~3.5 - 4 mm in diameter) of moderating material. The cold helium gas flow delivers beads from the charging device to the moderator during the fulfillment process and cools down them during the reactor cycle. The mixture of aromatic hydrocarbons (mesithylen and m-xylen) has been chosen as moderating material. The explanation of the choice of material for novel cold neutron moderators, configuration of moderator complex for the modernized IBR-2 reactor and the main results of optimization of moderator complex for the third stage of moderator development are discussed in the article.

  3. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  4. Perspectives de développement de la production industrielle d'hydrogène par électrolyse alcaline avancée Development Outlook for Industrial Hydrogen Production by Advanced Alkaline Electrolysis

    Directory of Open Access Journals (Sweden)

    Derive C.

    2006-11-01

    Full Text Available Dans les conditions du développement du programme nucléaire français qui permettent une production d'électricité à un coût intéressant en heures creuses, la production d'hydrogène par électrolyse de l'eau peut être envisagée à moyen terme en compétition avec les autres procédés de fabrication d'hydrogène tels que le reformage de gaz naturel. Dans le cadre de leur coopération, Électricité de France (EDF et le Gaz de France (GDF conduisent, depuis 1976, un programme de recherches et développement sur la production d'hydrogène par électrolyse alcaline de l'eau ayant pour but, par comparaison avec des installations existantes, de réduire le coût d'investissement et de conserver un rendement identique. Les études préalables ont montré que ces objectifs pouvaient être atteints par une électrolyse avancée avec élévation de la densité de courant et de la température. Ces contraintes techniques ont conduit EDF et le GDF à lancer des études sur la tenue chimique et la résistance mécanique des matériaux, sur une sélection de composants de cellules adaptés et sur l'amélioration de la conception d'ensemble des installations. Les deux groupements industriels français - pilotés par Alsthom-Atlantique et Creusot-Loire - associés à ces travaux depuis 1979, ont fixé les conditions de fonctionnement suivantes : - électrolyte à base de potasse (40 % en masse; - température de 120 et 160°C; - pression de 30 et 70 bar. Dans un premier temps, les constructeurs ont réalisé une étude technico-économique sur la production massive d'hydrogène à partir d'usines de puissance d'environ 300 MWe, fourni les plans de détail d'une installation pilote de 2 MWe et entrepris la qualification de leurs choix technologiques sur des boucles-prototypes de 25-30 kWe. Afin de valider plus complètement les choix retenus et d'approfondir les problèmes d'extrapolation à des électrolyseurs de grande taille, les essais sur boucles

  5. Brine/CO2 Interfacial Properties and Effects on CO2 Storage in Deep Saline Aquifers Propriétés interfaciales saumure/CO2 et effets sur le stockage du CO2 dans des aquifères salins profonds

    Directory of Open Access Journals (Sweden)

    Chalbaud C.

    2010-05-01

    équent, les propriétés interfaciales entre le milieu poreux constituant le réservoir, le CO2, la saumure et/ou le gaz du réservoir jouent un rôle important sur l’efficacité de n’importe quelle opération de stockage de CO2. Dans le cas des aquifères salins profonds, il existe un manque de données certain en ce qui concerne les propriétés interfaciales saumure-CO2 en conditions de stockage. Plus spécifiquement, des données expérimentales de tension interfaciale saumure-CO2 et une meilleure compréhension du comportement de la mouillabilité en fonction des conditions thermodynamiques et ses effets sur l’écoulement dans le milieu poreux sont nécessaires. Dans cet article, nous présentons un jeu de données expérimentales complet de tensions interfaciales (IFT en conditions de pression, température et salinité représentatives de celles d’un site de stockage, et une corrélation semi-analytique pour modéliser les valeurs expérimentales dont certaines ont été récemment publiées [Chalbaud C., Robin M., Lombard J.-M., Egermann P., Bertin H. (2009 Interfacial Tension Measurements and Wettability Evaluation for Geological CO2 Storage, Adv. Water Resour. 32, 1, 1-109]. Cet article porte un intérêt particulier sur des tests effectués avec des échantillons de roches qui montrent un comportement mouillant du CO2 pour des roches carbonatées de mouillabilité intermédiaire (IW ou mouillables à l’huile (OW. Ces résultats sont cohérents avec les observations faites à l’échelle du pore en micromodèles. Ce comportement mouillant du CO2 a un effet négatif sur la capacité de stockage d’un site donné.

  6. Loss-of-Flow and Loss-of-Pressure Simulations of the BR2 Research Reactor with HEU and LEU Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Licht, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Bergeron, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Dionne, B. [Argonne National Lab. (ANL), Argonne, IL (United States); Sikik, E. [Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium); Van den Branden, G. [Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium); Koonen, E. [Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium)

    2016-01-01

    Belgian Reactor 2 (BR2) is a research and test reactor located in Mol, Belgium and is primarily used for radioisotope production and materials testing. The Materials Management and Minimization (M3) Reactor Conversion Program of the National Nuclear Security Administration (NNSA) is supporting the conversion of the BR2 reactor from Highly Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU) fuel. The reactor core of BR2 is located inside a pressure vessel that contains 79 channels in a hyperboloid configuration. The core configuration is highly variable as each channel can contain a fuel assembly, a control or regulating rod, an experimental device, or a beryllium or aluminum plug. Because of this variability, a representative core configuration, based on current reactor use, has been defined for the fuel conversion analyses. The code RELAP5/Mod 3.3 was used to perform the transient thermal-hydraulic safety analyses of the BR2 reactor to support reactor conversion. The input model has been modernized relative to that historically used at BR2 taking into account the best modeling practices developed by Argonne National Laboratory (ANL) and BR2 engineers.

  7. Plateforme régionale sur les ordinateurs personnels, déchets ...

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

    Institution. SUR Corporación de Estudios Sociales y Educación. Pays d' institution. Chili. Contenus connexes. Un numéro spécial de la revue met en lumière les conclusions d'une étude financée par le CRDI sur le travail rémunéré des femmes. Policy in Focus publie un numéro spécial présentant des données probantes ...

  8. Impacts de l'exploitation artisanale de l'or sur les ressources ...

    African Journals Online (AJOL)

    L'exploitation de l'or est devenue ces deux dernières années l'activité principale de la population de Kéméni, une localité située dans la Préfecture de Tchaoudjo (Région Centrale du Togo). La présente étude a identifié l'impact de cette activité sur les ressources naturelles. L'approche méthodologique s'est basée sur des ...

  9. The direct conversion of heat into electricity in reactors; Conversion directe de la chaleur en electricite dans les piles

    Energy Technology Data Exchange (ETDEWEB)

    Devin, B; Bliaux, J; Lesueur, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The direct conversion of heat into electricity by thermionic emission in an atomic reactor has been studied with the triple aim of its utilisation: as an energy source for a space device, at the head of a conventional conversion system in power installations, or finally in association with the thermoelectric conversion in very low power installations. The laboratory experiments were mainly orientated towards the electron extraction of metals and compounds and their behaviour at high temperatures. Converters furnishing up to 50 amps at 0. 4 volts with an efficiency close to 10 p. 100 have been constructed in the laboratory; the emitters were heated by electron bombardment and were composed of tungsten covered with an uranium carbide deposit or molybdenum covered with cesium. The main aspects of the coupling between the converter and the reactor have been covered from the point of view of electronics: the influence of the mismatching of the load on the temperature of the emitter and the influence of thermal flux density on the temperature of the emitter and the stability of the converter. Converters using uranium carbide as the electron emitter have been tested in reactors. Tests have been made under dynamic conditions in order to determine the dynamic characteristics. The load matching curves have been constructed and the overall performances of several cells coupled in such a way as to form a reactor rod have been deduced. This information is fundamental to the design of a control system for a thermionic conversion reactor. The problems associated with the reliability of thermionic converters connected in series in the same reactor rod have been examined theoretically. Finally, the absorption isotherms have been drawn at the ambient temperatures for krypton and xenon on activated carbon with the aim of investigating the escape of fission products in a converter. (author) [French] La conversion directe de chaleur en electricite par emission thermionique dans une

  10. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

  11. Gas-cooled reactor thermal-hydraulics using CAST3M and CRONOS2 codes

    International Nuclear Information System (INIS)

    Studer, E.; Coulon, N.; Stietel, A.; Damian, F.; Golfier, H.; Raepsaet, X.

    2003-01-01

    The CEA R and D program on advanced Gas Cooled Reactors (GCR) relies on different concepts: modular High Temperature Reactor (HTR), its evolution dedicated to hydrogen production (Very High Temperature Reactor) and Gas Cooled Fast Reactors (GCFR). Some key safety questions are related to decay heat removal during potential accident. This is strongly connected to passive natural convection (including gas injection of Helium, CO 2 , Nitrogen or Argon) or forced convection using active safety systems (gas blowers, heat exchangers). To support this effort, thermal-hydraulics computer codes will be necessary tools to design, enhance the performance and ensure a high safety level of the different reactors. Accurate and efficient modeling of heat transfer by conduction, convection or thermal radiation as well as energy storage are necessary requirements to obtain a high level of confidence in the thermal-hydraulic simulations. To achieve that goal a thorough validation process has to ve conducted. CEA's CAST3M code dedicated to GCR thermal-hydraulics has been validated against different test cases: academic interaction between natural convection and thermal radiation, small scale in-house THERCE experiments and large scale High Temperature Test Reactor benchmarks such as HTTR-VC benchmark. Coupling with neutronics is also an important modeling aspect for the determination of neutronic parameters such as neutronic coefficient (Doppler, moderator,...), critical position of control rods...CEA's CAST3M and CRONOS2 computer codes allow this coupling and a first example of coupled thermal-hydraulics/neutronics calculations has been performed. Comparison with experimental data will be the next step with High Temperature Test Reactor experimental results at nominal power

  12. Further study on parameterization of reactor NAA: Pt. 2

    International Nuclear Information System (INIS)

    Tian Weizhi; Zhang Shuxin

    1989-01-01

    In the last paper, Ik 0 method was proposed for fission interference corrections. Another important kind of interferences in reator NAA is due to threshold reaction induced by reactor fast neutrons. In view of the increasing importance of this kind of interferences, and difficulties encountered in using the relative comparison method, a parameterized method has been introduced. Typical channels in heavy water reflector and No.2 horizontal channel of Heavy Water Research Reactor in the Insitute of Atomic Energy have been shown to have fast neutron energy distributions (E>4 MeV) close to primary fission neutron spectrum, by using multi-threshold detectors. On this basis, Ti foil is used as an 'instant fast neutron flux monitor' in parameterized corrections for threshold reaction interferences in the long irradiations. Constant values of φ f /φ s = 0.70 ± 0.02% have been obtained for No.2 rabbit channel. This value can be directly used for threshold reaction inference correction in the short irradiations

  13. EL-2 reactor: Thermal neutron flux distribution; EL-2: Repartition du flux de neutrons thermiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The flux distribution of thermal neutrons in EL-2 reactor is studied. The reactor core and lattices are described as well as the experimental reactor facilities, in particular, the experimental channels and special facilities. The measurement shows that the thermal neutron flux increases in the central channel when enriched uranium is used in place of natural uranium. However the thermal neutron flux is not perturbed in the other reactor channels by the fuel modification. The macroscopic flux distribution is measured according the radial positioning of fuel rods. The longitudinal neutron flux distribution in a fuel rod is also measured and shows no difference between enriched and natural uranium fuel rods. In addition, measurements of the flux distribution have been effectuated for rods containing other material as steel or aluminium. The neutron flux distribution is also studied in all the experimental channels as well as in the thermal column. The determination of the distribution of the thermal neutron flux in all experimental facilities, the thermal column and the fuel channels has been made with a heavy water level of 1825 mm and is given for an operating power of 1000 kW. (M.P.)

  14. The analysis for inventory of experimental reactor high temperature gas reactor type

    International Nuclear Information System (INIS)

    Sri Kuntjoro; Pande Made Udiyani

    2016-01-01

    Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 Bq, 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term and it

  15. Integral Inherently Safe Light Water Reactor (I2S-LWR)

    International Nuclear Information System (INIS)

    Petrovic, Bojan; Memmott, Matthew; Boy, Guy; Charit, Indrajit; Manera, Annalisa; Downar, Thomas; Lee, John; Muldrow, Lycurgus; Upadhyaya, Belle; Hines, Wesley; Haghighat, Alierza

    2017-01-01

    This final report summarizes results of the multi-year effort performed during the period 2/2013- 12/2016 under the DOE NEUP IRP Project ''Integral Inherently Safe Light Water Reactors (I 2 S-LWR)''. The goal of the project was to develop a concept of a 1 GWe PWR with integral configuration and inherent safety features, at the same time accounting for lessons learned from the Fukushima accident, and keeping in mind the economic viability of the new concept. Essentially (see Figure 1-1) the project aimed to implement attractive safety features, typically found only in SMRs, to a larger power (1 GWe) reactor, to address the preference of some utilities in the US power market for unit power level on the order of 1 GWe.

  16. Continuous backfitting measures for the FRG-1 and FRG-2 research reactors

    International Nuclear Information System (INIS)

    Blom, K.H.; Falck, K.; Krull, W.

    1990-01-01

    The GKSS-Research Centre Geesthacht GmbH has been operating the research reactors FRG-1 and FRG-2 with power levels of 5 MW and 15 MW for 31 and 26 years respectively. Safe operation at full power levels over so many years with an average utilization between 180 d to 250 d per year is possible only with great efforts in modernization and upgrading of the research reactors. Emphasis has been placed on backfitting since around 1975. At that time within the Federal Republic of Germany many new guidelines, rules, ordinances, and standards in the field of (power) reactor safety were published. Much work has been done on the modernization of the FRG-1 and FRG-2 research reactors therefore within the last ten years. Work done within the last two years and presently underway includes: measures against water leakage through the concrete and along the beam tubes; repair of both cooling towers; modernization of the ventilation system; measures for fire protection; activities in water chemistry and water quality; installation of a double tubing for parts of the primary piping of the FRG-1; replacement of instrumentation, process control systems (operation and monitoring system) and alarm system; renewal of the emergency power supply; installation of internal lightning protection; installation of a cold neutron source; enrichment reduction for FRG-1. These efforts will continue to allow safe operation of our research reactors over their whole operational life

  17. Eric Clapton et Pete Postlethwaite sur la liste des honneurs de fin d'annee

    CERN Multimedia

    2003-01-01

    "Le guitariste Eric Clapton, l'acteur Pete Postlethwaite et l'un des peres de l'internet Tim Berners-Lee figurent, aux cotes du XV d'Angleterre, sur la liste de fin d'annee des principales personnalites distinguees par la reine Elizabeth II" (1/2 page).

  18. Effet sur la compétitivité des réglementations relatives à la gestion des effluents

    DEFF Research Database (Denmark)

    Andersen, Mikael Skou

    2004-01-01

    Grâce à un regard approfondi sur le secteur laitier dans les pays de l'OCDE, cette étude permet de mieux analyser l'impact des subventions à l'agriculture et des politiques de l'environnement sur l'environnement et sur la compétitivité internationale des produits laitiers. Ce chapitre étudie les ...

  19. The influence of xenon poisoning in high-flux reactors on the choice of control rod speeds (1961); Influence de l'empoisonnement xenon dans les piles a haut flux sur le choix de la vitesse des barres de controle (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    - The general laws are restated concerning the changes in xenon and iodine concentrations in thermal neutron reactors, assuming an uniform neutron flux distribution in the core. It is shown how the evolution in the xenon poisoning influences the selection of the control rod speed, at start-up. Certain simple methods of calculation are developed making it possible to resolve the problem of the choice of this speed in the case where the xenon poisoning is taken into account. (author) [French] - On rappelle les lois generales relatives aux evolutions de concentration xenon et iode dans les piles atomiques a neutrons thermiques lorsqu'on suppose une repartition uniforme du flux de neutrons dans le coeur. On montre comment l'evolution de l'empoisonnement xenon influe sur le choix de la vitesse des barres de controle en periode de demarrage. On developpe certaines methodes de calculs simples permettant de resoudre le probleme du choix de la vitesse des barres de controle, dans le cas ou l'on tient compte de l'empoisonnement xenon. (auteur)

  20. Bilan du programme autrichien de recherche sur les paysages

    Directory of Open Access Journals (Sweden)

    Karolina Begusch-Pfefferkorn

    2009-03-01

    Full Text Available Austrian Landscape Research, a programme of the Austrian Ministry of Science, has created scientific foundations for the sustainable development of Austrian landscapes and regions (plus bordering regions. Landscapes and regions were to be explored from different angles; implementing the research findings was to be part of the research work. The programme was designed to make room for science open to society, for unconventional ideas, methods, and courses of action. Programmatic targets and research principles supported this intent. The results of the programme met with national and international approval. The ALR knowledge balance is an attempt at presenting and assessing the achievements of this comprehensive contract research programme.Le programme du Ministère autrichien des Sciences, intitulé « Recherche sur le paysage autrichien », visait à construire les fondements scientifiques d’un développement durable des paysages et des régions de l’Autriche et des territoires limitrophes. Les paysages et les régions ont été étudiés selon différentes approches disciplinaires et la mise en pratique des résultats de cette étude était partie prenante du programme de recherche. La vocation de ce programme était de faire la place à une science ouverte sur la société, à des idées, méthodes et pratiques non conventionnelles. Les objectifs du programme et les principes de recherche vont dans le sens de ces exigences. Les résultats du programme ont été reconnus sur le plan national et international. Le bilan des connaissances du programme de recherche sur le paysage autrichien (KLF a pour but de présenter et d’évaluer les performances de ce vaste programme de recherche.

  1. TiO2-photocatalyzed As(III) oxidation in a fixed-bed, flow-through reactor.

    Science.gov (United States)

    Ferguson, Megan A; Hering, Janet G

    2006-07-01

    Compliance with the U.S. drinking water standard for arsenic (As) of 10 microg L(-1) is required in January 2006. This will necessitate implementation of treatment technologies for As removal by thousands of water suppliers. Although a variety of such technologies is available, most require preoxidation of As(III) to As(V) for efficient performance. Previous batch studies with illuminated TiO2 slurries have demonstrated that TiO2-photocatalyzed AS(III) oxidation occurs rapidly. This study examined reaction efficiency in a flow-through, fixed-bed reactor that provides a better model for treatment in practice. Glass beads were coated with mixed P25/sol gel TiO2 and employed in an upflow reactor irradiated from above. The reactor residence time, influent As(III) concentration, number of TiO2 coatings on the beads, solution matrix, and light source were varied to characterize this reaction and determine its feasibility for water treatment. Repeated usage of the same beads in multiple experiments or extended use was found to affect effluent As(V) concentrations but not the steady-state effluent As(III) concentration, which suggests that As(III) oxidation at the TiO2 surface undergoes dynamic sorption equilibration. Catalyst poisoning was not observed either from As(V) or from competitively adsorbing anions, although the higher steady-state effluent As(III) concentrations in synthetic groundwater compared to 5 mM NaNO3 indicated that competitive sorbates in the matrix partially hinder the reaction. A reactive transport model with rate constants proportional to incident light at each bead layer fit the experimental data well despite simplifying assumptions. TiO2-photocatalyzed oxidation of As(III) was also effective under natural sunlight. Limitations to the efficiency of As(III) oxidation in the fixed-bed reactor were attributable to constraints of the reactor geometry, which could be overcome by improved design. The fixed-bed TiO2 reactor offers an environmentally

  2. EFFET DU GETTERING SUR LA LONGUEUR DE DIFFUSION DES PLAQUETTES DE SILICIUM SEMICRISTALLIN "SOPLIN"

    Directory of Open Access Journals (Sweden)

    A MOUHOUB

    2003-06-01

    Full Text Available L’effet des diffusions du phosphore à haute température (T = 900°C sur la longueur de diffusion (Ln des plaquettes de silicium semicristallin SOPLIN (SOlidification by PLanar INterface est déterminé par la mesure de la réponse spectrale de la photopile réalisée sur le matériau traité. L’influence de ces recuits sur les paramètres photovoltaïques est enregistrée dans les caractéristiques courant - tension sous éclairement simulé et la réponse spectrale.

  3. Exxon nuclear neutronics design methods for pressurized water reactors. Supplement 2

    International Nuclear Information System (INIS)

    Skogen, F.B.; Stout, R.B.

    1977-01-01

    Modifications to the Exxon Nuclear PWR neutronic design calculational methods are presented as well as the results obtained when these improved methods are compared to reactor measurements. The basic PWR design tools remain unchanged; i.e., the XPOSE code is used for generating the basic nuclear parameters, the PDQ-7 code is used for calculating reactivity and x-y power distributions, and the XTG code is used for three-dimensional analysis. The recent start-up experiences at D. C. Cook Unit 1 and H. B. Robinson Unit 2 have provided a significant increase in the data base supporting the current ENC PWR neutronic methods. The verification comparisons contained in the supplement include reactor measurements from D. C. Cook Unit 1, Cycle 2; H. B. Robinson Unit 2, Cycles 4 and 5; Palisades Cycle 2, and R. E. Ginna, Cycle 7

  4. Characterization of fuel distribution in the Three Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McNeece, J.P.; Kaiser, B.J.; McElroy, W.N.

    1984-01-01

    Neutron and gamma-ray dosimetry are being used for nondestructive assessment of the fuel distribution throughout the Three Mile Island Unit 2 (TMI-2) reactor core region and primary cooling system. The fuel content of TMI-2 makeup and purification Demineralizer A has been quantified with Si(Li) continuous gamma-ray spectrometry and solid-state track recorder (SSTR) neutron dosimetry. For fuel distribution characterization in the core region, results from SSTR neutron dosimetry exposures in the TMI-2 reactor cavity are presented. These SSTR results are consistent with the presence of a significant amount of fuel debris, equivalent to several fuel assemblies or more, lying at the bottom of the reactor vessel. (Auth.)

  5. Estimation of power feedback parameters of the IBR-2M reactor by square wave reactivity

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Popov, A.K.; Sumkhuu, D.

    2016-01-01

    Parameters of the IBR-2M reactor power feedback (PFB) are estimated based on the analysis of power transients caused by deliberate square wave reactivity when the pulsed reactor operates in the self-regulation mode. The PFB of the IBR-2M is described by three linear first-order differential equations. Two components of the PFB are responsible for the negative feedback and one, for the positive. The overall feedback is negative, i.e., it has a stabilizing effect for the operation of the reactor. The slowest negative component of the PFB is probably caused by heating of the fuel. Periodically repeated in the process of exploitation, estimation of the PFB parameters is one of the methods to ensure safety operation of the reactor. [ru

  6. L'objectivation et la perfection des femmes dans la publicité. La perception des consommateurs vis-à-vis des femmes représentées dans des campagnes publicitaires et ses effets sur la marque et sur eux-mêmes.

    OpenAIRE

    Van Dessel, Sophie; Loir, Estelle

    2017-01-01

    Depuis son apparition, la publicité contribue consciemment ou inconsciemment au changement de perception du corps de la femme. Dans la société occidentale, utiliser le corps de la femme pour inciter à l’achat d’un produit est une pratique commune dans le marketing. Un ensemble d’effets en tous genres sont à observer sur la perception des consommateurs à propos du produit et sur la marque, sur leur perception vis-à-vis des mannequins et des femmes en général et finalement sur la perception qu’...

  7. Renforcement des capacités de recherche sur les TIC-D au Moyen ...

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

    La recherche sur les incidences et les impacts des technologies de l'information et de la communication (TIC) sur le développement social et humain est embryonnaire au Moyen-Orient et en Afrique du Nord (région MOAN). Ce projet vise à encourager les chercheurs de la région MOAN à entreprendre des recherches ...

  8. Proceedings of 2. Yugoslav symposium on reactor physics, Part 3, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    International Nuclear Information System (INIS)

    1966-01-01

    This Volume 3 of the Proceedings of 2. Yugoslav symposium on reactor physics includes three papers describing the following: model for spatial synthesis of automated control system of the GCR type reactor; model for analysis of hydrodynamic processes at the BHWR type reactors; mathematical model for safety analysis of heavy water power reactor

  9. L'urbanisation sur le plateau d'allada au sud-Benin, agent des ...

    African Journals Online (AJOL)

    La méthodologie adoptée pour mener à bien cette étude est basée d'une part, sur la revue documentaire et d'autre part, sur les enquêtes de terrain menées dans toutes les communes du département de l'Atlantique. La recherche documentaire a permis de cerner les contours de l'urbanisation et d'évaluer son ampleur ...

  10. Produire des données probantes sur l'agriculture sexospécifique ...

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

    Le secteur agricole joue un rôle clé dans le tissu social et l'économie de ... il est important de comprendre la façon dont la dynamique sexospécifique influe sur ... aux ressources et le contrôle de celles-ci; l'emploi du temps et la main-d'œuvre; ... IWRA/CRDI sur les changements climatiques et la gestion adaptive de l'eau.

  11. TOKMINA, Toroidal Magnetic Field Minimization for Tokamak Fusion Reactor. TOKMINA-2, Total Power for Tokamak Fusion Reactor

    International Nuclear Information System (INIS)

    Hatch, A.J.

    1975-01-01

    1 - Description of problem or function: TOKMINA finds the minimum magnetic field, Bm, required at the toroidal coil of a Tokamak type fusion reactor when the input is beta(ratio of plasma pressure to magnetic pressure), q(Kruskal-Shafranov plasma stability factor), and y(ratio of plasma radius to vacuum wall radius: rp/rw) and arrays of PT (total thermal power from both d-t and tritium breeding reactions), Pw (wall loading or power flux) and TB (thickness of blanket), following the method of Golovin, et al. TOKMINA2 finds the total power, PT, of such a fusion reactor, given a specified magnetic field, Bm, at the toroidal coil. 2 - Method of solution: TOKMINA: the aspect ratio(a) is minimized, giving a minimum value for Bm. TOKMINA2: a search is made for PT; the value of PT which minimizes Bm to the required value within 50 Gauss is chosen. 3 - Restrictions on the complexity of the problem: Input arrays presently are dimensioned at 20. This restriction can be overcome by changing a dimension card

  12. Ligand binding and conformational changes of SUR1 subunit in pancreatic ATP-sensitive potassium channels.

    Science.gov (United States)

    Wu, Jing-Xiang; Ding, Dian; Wang, Mengmeng; Kang, Yunlu; Zeng, Xin; Chen, Lei

    2018-06-01

    ATP-sensitive potassium channels (K ATP ) are energy sensors on the plasma membrane. By sensing the intracellular ADP/ATP ratio of β-cells, pancreatic K ATP channels control insulin release and regulate metabolism at the whole body level. They are implicated in many metabolic disorders and diseases and are therefore important drug targets. Here, we present three structures of pancreatic K ATP channels solved by cryo-electron microscopy (cryo-EM), at resolutions ranging from 4.1 to 4.5 Å. These structures depict the binding site of the antidiabetic drug glibenclamide, indicate how Kir6.2 (inward-rectifying potassium channel 6.2) N-terminus participates in the coupling between the peripheral SUR1 (sulfonylurea receptor 1) subunit and the central Kir6.2 channel, reveal the binding mode of activating nucleotides, and suggest the mechanism of how Mg-ADP binding on nucleotide binding domains (NBDs) drives a conformational change of the SUR1 subunit.

  13. System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2

    International Nuclear Information System (INIS)

    Ellis, R.J.

    2000-01-01

    The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors

  14. Patologia molecular do receptor de sulfoniluréia (SUR1)

    OpenAIRE

    Reis, André F.; Velho, Gilberto

    2000-01-01

    The sulfonylurea receptor is a subunit of the ATP-sensitive potassium channel, which is expressed in the pancreatic beta cell. The central role of this receptor in glucose-induced insulin secretion was confirmed by description that mutations in this gene might result in hyperinsulinemic hypoglycemia of infancy. The possible role of SUR1 gene variants in the genetic susceptibility for type 2 diabetes mellitus has been studied. In this review, we discuss the results concerning the genetic varia...

  15. INFLUENCE DE LA PROPOLIS SUR LA MITOSE DANS LE MERYSTEME DE SECALE CEREALE L.

    Directory of Open Access Journals (Sweden)

    Mioara Navrotescu

    2005-08-01

    Full Text Available Cette recherche présente l’influence de propolis sur la mitose dans le merysteme de Secale cereale L. (2n=14. On confirme l’utilisation de plus en plus large de ce produit apicole - propolis - au niveau de la thérapeutique.

  16. Report on the operation in 1973 of the FR 2 research reactor

    International Nuclear Information System (INIS)

    Moeller, I.; Steiger, W.

    1975-04-01

    Also in 1973, the heavy-water moderated research and testing reactor FR 2 was operated to schedule at 44 MW nominal power. Again, the availability of the plant was slightly improved. Experimental utilization through instrumented irradiation capsules strongly increased as compared to the previous year. Up to 16 capsule test rigs at a time were inserted in the reactor. As to the beam tube experiments, up to 13 experiments covering a total of 18 test rigs were conducted simultaneously at the 12 reasonably usable beam holes. At the beginning of the year all of the positions available were occupied by 5 loop experiments. Isotope production reached its highest value with a total of 2,372 irradiated capsules (1.3% more than the year before). Some remarkable figures characterized the year 1973: On August 16, 1973 ten years of full power operation at a nominal power of 12 and 44 MW, respectively, had been reached. On July 24, 1973 the 50,000th isotope irradiation was performed in the reactor and on December 26, 1973 a total energy release of 100,000 MWd was recorded. Moreover, the 125,000th visitor of the reactor was welcomed on December 6, 1973. (orig./UA) [de

  17. Influence de la densité de plantation et du mode d'entretien du sol sur l'alimentation minérale de la vigne

    Directory of Open Access Journals (Sweden)

    René Morlat

    1984-06-01

    In a field experiment started in 1971 at Montreuil-Bellay (Valley of Loire several planting densities with « Chenin » vine grafted on S04 rootstock, were compared with two soil management treatments (chemical weed control and permanent grass cover. Every year, mineral composition of leaves and musts is determined. The permanent grass cover increases Mg and P concentrations of leaves while the Zn concentration of leaves increases in the low density vines. A good positive correlation between the P percentage of leaves ant this of musts is obtained. The permanent grass cover decreases the N concentration of musts while the low density vines with chemical control increase this percentage.

  18. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to decontamination of the Three Mile Island Unit 2 (TMI-2) reactor building. The report covers activities for the period of June 1, 1979 through March 29, 1985. The data collected from activity reports, reactor containment entry records, and other sources were entered into a computerized data system which permits extraction/manipulation of specific information which can be used in planning for recovery from an accident similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during decontamination of the reactor building. Support activities conducted outside of radiation areas are excluded from the scope of this report. Computerized reports included in this document are: a chronological summary listing work performed relating to reactor building decontamination for the period specified; and summary reports for each major task during the period. Each task summary is listed in chronological order for zone entry and subtotaled for the number of personnel entries, exposures, and man-hours. Manually-assembled table summaries are included for: labor and exposures by department and labor and exposures by major activity

  19. Where are the radioactive wastes in France? Brochure no 2

    International Nuclear Information System (INIS)

    2004-01-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 2 concerns the Bretagne (Brittany), Pays de la Loire, Haute-Normandie, Basse-Normandie and Centre regions. (J.S.)

  20. Evaluation of the Three Mile Island Unit 2 reactor building decontamination process

    Energy Technology Data Exchange (ETDEWEB)

    Dougherty, D.; Adams, J. W.

    1983-08-01

    Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation.

  1. Evaluation of the Three Mile Island Unit 2 reactor building decontamination process

    International Nuclear Information System (INIS)

    Dougherty, D.; Adams, J.W.

    1983-08-01

    Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation

  2. Rapport annuel au Parlement Loi sur l'accès à l'information Centre ...

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

    leonardi

    accès à l'information. Source. Nombre de demandes. 0. Médias. 1. Rapport statistique sur la Loi sur l'accès à l'information. Nom de l'institution : Centre de recherches pour le développement international. Période visée par le ...

  3. Inmigración alemana en el sur de Chile, siglo XIX

    OpenAIRE

    Winkler, Lisette

    2009-01-01

    Presentación (en español) Durante aproximadamente un mes de trabajo de campo en Chile, Lisette Winkler (EScoM-FMSH) ha grabado una serie de entrevistas que les hizo a los descendientes de los colonos alemanes quienes se instalaron en los alrededores del lago Llanquihue en el siglo XIX. Los documentos audiovisuales fueron recopilados en dos aldeas del sur del país, Frutillar y Puerto Octay. Recogen tanto testimonios orales de los descendientes como tomas panorámicas de los paisajes del sur, qu...

  4. Technical Training: Cycle d'Information/Formation sur l'Environnement d'Automatisme SCHNEIDER

    CERN Multimedia

    Raymond Brun

    2005-01-01

    Après la présention technique du 2 mars 2005 sur UNITY-Pro, deux autres présentations sur les nouveautés Schneider 2004/2005, dédiées aux utilisateurs CERN, auront lieu dans les locaux de l'enseignement technique (bât. 593, salle 13) aux dates suivantes : Mercredi 13 avril de 9h à 12h : Gamme Dialogue Homme-Machine (HMI) => Présentation et démonstration. Nouveaux terminaux tactiles Gamme XBT-G Logiciel de configuration visio-Designer Factory-Cast-HMI Distributed HMI Smart IPC (PC-Indusriel avec écran tactile rackable) Mercredi 11 Mai de 9h à 12h : Gamme Entrées/Sorties => Présentation et démonstration ADVANTIS (STB, OTB, ...) TWIDO (Nouvel UC et Connexion Ethernet) Nota : Ces formations, essentiellement techniques et pratiques, sont destinées aux personnes du CERN qui : ·  veulent connaître les nouvelles possibilités o...

  5. Effets du Cloud computing sur les relations inter-organisationnelles dans la supply chain en France

    OpenAIRE

    AGHHAVANI-SHAJARI, Benyamin

    2016-01-01

    National audience; Le cloud computing (CC) est en train de changer la façon dont les entreprises déploient et exploitent leur système d’information. 55% des entreprises françaises utilisent le Service Cloud type Software as a service (Saas). Les recherches se sont surtout focalisées sur la question de l'adoption du CC (ACC) dans une organisation ou encore sur les difficultés techniques et informatiques. À notre connaissance il existe peu de recherches portant sur l'ACC au niveau de la supply ...

  6. Heavy water reactors physics; Physique des reacteurs a eau lourde

    Energy Technology Data Exchange (ETDEWEB)

    Girard, Y; Lourme, P; Naudet, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    An important research programme on heavy water reactor physics has been carried out in France for quite a few years. The decision to build the EL 4 prototype and so to choose the heavy water gas cooled type has renewed the interest in this programme and at the same time given to it a more specific orientation A summary of the results gained in this field is presented in this paper. In the first part are described the experimental investigations, most of them were carried out in the criticality facility AQUILON II. The experiments are grouped in four parts - Systematic studies of lattices Buckling measurements. - Specific studies of gas-cooled lattices. - Fine structure, spectral indices measurements etc... - Measurements on lattices or samples containing Uranium of various enrichment or Plutonium. The second part is devoted to a summary of the theoretical studies. The whole results have allowed an improvement of the calculation methods, have led to a better understanding of the neutron balance in lattices, and have permitted the establishment of a set of formula to predict not only the clean fuel conditions but also the evolution of the nuclear properties with irradiation. Some specific studies on power reactor are quoted. (authors) [French] Un important programme d'etudes sur la physique des reacteurs a eau lourde est mene en France depuis assez longtemps. La decision de construire le prototype EL 4 et de s'engager ainsi dans la filiere des reacteurs a eau lourde refroidis par gaz a redonne un nouvel interet a ce programme et l'a en meme temps oriente dans une direction plus particuliere. La presente communication, rassemble les resultats des etudes faites dans ce domaine depuis la derniere conference de Geneve. Dans la premiere partie on decrit les etudes experimentales dont la plupart ont ete effectuees dans la pile d'experiences critiques Aquilon II. Les experiences sont groupees en quatre ensembles: etude systematique de reseaux (mesures de laplaciens) etudes

  7. A review of calculation methods for fast and intermediate reactors; Expose des methodes pour le calcul de reacteurs a neutrons rapides et intermediaires; Obzor metodov rascheta reaktorov na promezhutochnykh i bystrykh nejtronakh; Estudio panoramico de los metodos de calculo de los reactores rapidos e intermedios

    Energy Technology Data Exchange (ETDEWEB)

    Marchuk, G I [Akademiya Nauk, Moskva, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    This paper discusses the development of methods for calculating intermediate and fast reactors. It deals with various approaches to the problems of physical calculation. The calculation of resonance effects is discussed. Consideration is given to multi-group systems of fundamental and conjugate equations, various applications of perturbation theory to the problems of physical reactor calculation, and numerical methods of solving fundamental and conjugate reactor equations, which approximate the method of spherical harmonics. The paper describes an application of the response method to the solution of critical-mass problems, and methods of calculating reactors with hydrogeneous moderators. The fundamental features of an effective one-group reactor model are described. (author) [French] L'auteur examine la mise au point de methodes pour le calcul de reacteurs a neutrons rapides et intermediaires . Il decrit diverses manieres d'aborder les problemes des calculs sur la physique des reacteurs, notamment le calcul des effets de resonance. Il s'attache particulierement aux points suivants: systemes d'equations fondamentales et conjuguees a plusieurs groupes; diverses applications de la theorie des perturbations aux problemes de calculs sur la physique des reacteurs; methodes numeriques pour resoudre les equations fondamentales et conjuguees, voisines de la methode des harmoniques spheriques. L'auteur decrit ensuite une maniere d'appliquer la methode de la reponse aux problemes de la masse critique ainsi que des methodes pour le calcul de reacteurs ralentis a l'hydrogene. Il decrit les caracteristique s fondamentale s d'un modele de reacteur a un groupe effectif. (author) [Spanish] El autor analiza el desarrollo de los metodos de calculo de los reactores nucleares que trabajan con neutrones rapidos y con neutrones intermedios. Examina diversos planteos de los problemas del calculo fisico. Indica la forma de tomar en cuenta los efectos de resonancia y menciona los sistemas

  8. HERESY, 2-D Few-Group Static Eigenvalues Calculation for Thermal Reactor

    International Nuclear Information System (INIS)

    Finch, D.R.

    1965-01-01

    1 - Description of problem or function: HERESY3 solves the two- dimensional, few-group, static reactor eigenvalue problem using the heterogeneous (source-sink or Feinburg-Galanin) formalism. The solution yields the reactor k-effective and absorption reaction rates for each rod normalized to the most absorptive rod in the thermal level. Epithermal fissions are allowed at each resonance level, and lattice-averaged values of thermal utilization, resonance escape probability, thermal and resonance eta values, and the fast fission factor are calculated. Kernels in the calculation are based on age-diffusion theory. Both finite reactor lattices and infinitely repeating reactor super-cells may be calculated. Rod parameters may be calculated by several internal options, and a direct interface is provided to a HAMMER system (NESC Abstract 277) lattice library tape to obtain cell parameters. Criticality searches are provided on thermal utilization, thermal eta, and axial leakage buckling. 2 - Method of solution: Direct power iteration on matrix form of the heterogeneous critical equation is used. 3 - Restrictions on the complexity of the problem: Maxima of - 50 flux/geometry symmetry positions; 20 physically different assemblies; 9 resonance levels; 5000 rod coordinate positions

  9. Les articles de 2017 à lire absolument sur CRDI.ca | CRDI - Centre ...

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

    Les articles de 2017 à lire absolument sur CRDI.ca. 02 janvier 2018. Le contenu le plus populaire publié cette année sur notre site Web offre un bon aperçu des défis en matière de développement revêtant une importance capitale pour nos lecteurs. Il démontre également la diversité du travail effectué par le CRDI de même ...

  10. Urbanismo y arquitectura moderna en madera en el sur de Chile: 1930-1970

    Directory of Open Access Journals (Sweden)

    Gonzalo Cerda Brintrup

    2005-07-01

    Full Text Available La investigación que se presenta tiene como objetivos estudiar el desarrollo de la arquitectura moderna en madera en el sur de Chile; indagar acerca de como esta se incerta en la tradición maderera de la arquitectura del sur; investigar su relación con el desarrollo de una identidad arquitectónica local;localizar y analizar sus ejemplos más significativos. El área de estudio es desde la VIII hasta la X Región, específicamente desde la Provincia de Concepción hasta Chiloé, por cuanto allí se concentra la mayor parte de la arquitectura en madera del sur del país.

  11. Les différences culturelles et leur impact sur la relation soignant-soigné

    OpenAIRE

    Uysal, Ayse; Matter, Catherine

    2011-01-01

    Ce travail porte sur les différences culturelles et leur impact sur la relation soignant-soigné lors d’une hospitalisation. Ainsi la problématique de recherche est centrée sur l’identification des difficultés et des spécificités présentes lorsque le soignant entre en relation avec un patient d’une culture différente. Le but de cette étude est d’identifier les difficultés et les obstacles liés à la culture, présents dans la relation soignant-soigné. Le deuxième but est de mettre en évidence le...

  12. Influence intra-blogosphérique et visibilité sur les réseaux sociaux

    Directory of Open Access Journals (Sweden)

    Damien Renard

    2015-10-01

    Full Text Available Cette recherche vise à mieux comprendre le fonctionnement des blogueurs influents et leur rôle dans la diffusion de la connaissance culinaire sur les réseaux sociaux numériques. Nous construisons un modèle pour observer le processus d’influence, de la position du blogueur à l’intérieur de la communauté jusqu’au partage du contenu sur Facebook. A partir de l’étude quantitative de 952 blogs culinaires, nous montrons que l’influence intra-blogosphérique conditionne la stratégie éditoriale du blogueur mais également sa visibilité sur les réseaux sociaux.

  13. G2 and G3 reactors design; Description des reacteurs G2 et G3

    Energy Technology Data Exchange (ETDEWEB)

    Herreng,; Ertaud,; Pasquet, [Societe Alsacienne de Constructions Mecaniques (France)

    1958-07-01

    'FRANCE ATOME' Manufacturers Party has been entrusted with the G2 and G3 reactors engineering by the french A.E.C., for the first-five-year french project. Although these reactors are essentially plutonium generators, everyone has been linked with a power station which is supposed to supply with 40 MW, 'Electricite de France' has taken the liability upon itself. The reactor core includes most of G1 reactor parts (central gap excluded): horizontal channels, graphite parallelepipedic bricks stacking, steel thermal shield. The cooling is provided with CO{sub 2} under a 15 atmospheres pressure. This pressure is kept steady in a press-stressed concrete packing-case which is a cylinder horizontally shaped. Steel strips tightened encircle the concrete cylinder; itself protected by sole-plates. The cylinder bottom has brought about unusual problems which have been solved by the choice of an hemispheric shape. Packing-case tightness is provided by a 30 mm iron-plate connected with the inner wall of concrete. One of the reactor's special characteristics is the possibility of loading and unloading while operating. On loading side, barrel locks, each weighting 50 tons, allow new cans, at a pressure of 15 atmospheres, to pass. The cans process almost in a steady way through the channel, and finally drop down through bent spouts, then through spiral toboggans into a new lock. The cooling CO{sub 2} flow is provided with 3 turbo-bellows, these are actuated by average pressure-steam, obtained from exchangers. Every reactor supplies 4 exchangers which have been very difficult to build and to set up. The secondary cycle is standard and contains 3 stages (pressure 10,3: 2 and 0,5 kg/cm{sup 2}). Steam can be condensed in the event of a group turbo-generator stopping, with no modifion for the normal operating conditions of the reactor. Auxiliary circuits have to assure the continuous purifying of cooling CO{sub 2}, its storage and drain. 49 boron carbide rods are used to control the

  14. Investigation of hydrogen-burn damage in the Three Mile Island Unit 2 reactor building

    International Nuclear Information System (INIS)

    Alvares, N.J.; Beason, D.G.; Eidem, G.R.

    1982-06-01

    About 10 hours after the March 28, 1979 Loss-of-Coolant Accident began at Three Mile Island Unit 2, a hydrogen deflagration of undetermined extent occurred inside the reactor building. Examinations of photographic evidence, available from the first fifteen entries into the reactor building, yielded preliminary data on the possible extent and range of hydrogen burn damage. These data, although sparse, contributed to development of a possible damage path and to an estimate of the extent of damage to susceptible reactor building items. Further information gathered from analysis of additional photographs and samples can provide the means for estimating hydrogen source and production rate data crucial to developing a complete understanding of the TMI-2 hydrogen deflagration. 34 figures

  15. A review of the probabilistic safety assessment application to the TR-2 research reactor

    International Nuclear Information System (INIS)

    Goektepe, G.; Adalioglu, U.; Anac, H.; Sevdik, B.; Menteseoglu, S.

    2001-01-01

    A review of the Probabilistic Safety Assessment (PSA) to the TR-2 Research Reactor is presented. The level 1 PSA application involved: selection of accident initiators, mitigating functions and system definitions, event tree constructions and quantification, fault tree constructions and quantification, human reliability, component failure data base development, dependent failure analysis. Each of the steps of the analysis given above is reviewed briefly with highlights from the selected results. PSA application is found to be a practical tool for research reactor safety due to intense involvement of human interactions in an experimental facility. Insights gained from the application of PSA methodology to the TR-2 research reactor led to a significant safety review of the system

  16. Solid-state track recorder neutron dosimetry in the Three-Mile Island Unit-2 reactor cavity

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.

    1985-04-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit (TMI-2) reactor cavity (i.e., the annular gap between the pressure vessel and the biological shield) for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that there are at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, at the bottom of the vessel. The existence of significant neutron streaming also explains the high count rate observed with the source range monitors (SRMs) that are located in the TMI-2 reactor cavity

  17. Mise en pratique du schéma 2BSvs dans le groupe industriel Sofiprotéol : étude de cas sur toute la filière (de l’agriculteur au pétrolier

    Directory of Open Access Journals (Sweden)

    Guizouarn Kristell

    2015-01-01

    Full Text Available Pour réduire sensiblement les émissions de CO liées aux transports routiers, l’Union européenne mise sur le développement des biocarburants, en respectant des conditions de durabilité. Afin de répondre à cette obligation et d’être en mesure de démontrer la conformité du biodiesel à ces critères, depuis l’agriculteur jusqu’au distributeur pétrolier, la filière des oléagineux a engagé la rédaction d’un schéma de vérification volontaire : 2BSvs, pour Biomasse Biocarburant Schéma volontaire sur la durabilité. Reconnu par la Commission Européenne le 19 juillet 2011, le schéma 2BSvs couvre l’ensemble de la chaîne de production des biocarburants, du producteur de biomasse à l’entrée dans un entrepôt sous douanes. À travers une étude de cas sur toute la filière, de l’agriculteur au pétrolier, cet article présente les implications pour les acteurs de la filière oléagineuse, les changements intervenus depuis avril 2013, et les défis futurs à relever.

  18. Neutron dosimetry in the Three-Mile Island Unit 2 reactor cavity with solid-state track recorders

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.; Rao, S.V.; Greenborg, J.; Fricke, V.R.

    1986-01-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit 2 (TMI-2) reactor cavity, for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, is lying at the bottom of the vessel. This existence of significant neutron streaming also explains the high count rate observed with the source range monitors that are located in the TMI-2 reactor cavity. (author)

  19. Degradation of gas-phase trichloroethylene over thin-film TiO2 photocatalyst in multi-modules reactor

    International Nuclear Information System (INIS)

    Kim, Sang Bum; Lee, Jun Yub; Kim, Gyung Soo; Hong, Sung Chang

    2009-01-01

    The present paper examined the photocatalytic degradation (PCD) of gas-phase trichloroethylene (TCE) over thin-film TiO 2 . A large-scale treatment of TCE was carried out using scale-up continuous flow photo-reactor in which nine reactors were arranged in parallel and series. The parallel or serial arrangement is a significant factor to determine the special arrangement of whole reactor module as well as to compact the multi-modules in a continuous flow reactor. The conversion of TCE according to the space time was nearly same for parallel and serial connection of the reactors.

  20. Inmigración alemana en el sur de Chile, siglo XIX

    Directory of Open Access Journals (Sweden)

    Lisette Winkler

    2009-01-01

    Full Text Available Presentación (en español Durante aproximadamente un mes de trabajo de campo en Chile, Lisette Winkler (EScoM-FMSH ha grabado una serie de entrevistas que les hizo a los descendientes de los colonos alemanes quienes se instalaron en los alrededores del lago Llanquihue en el siglo XIX. Los documentos audiovisuales fueron recopilados en dos aldeas del sur del país, Frutillar y Puerto Octay. Recogen tanto testimonios orales de los descendientes como tomas panorámicas de los paisajes del sur, qu...

  1. Effet de la salinité sur les paramètres morpho- physiologiques de ...

    African Journals Online (AJOL)

    SARAH

    31 oct. 2013 ... Effet du Stress Salin sur l'accumulation de Proline chez deux espèces d'Atriplex halimus L. et Atriplex canescens (Pursh) Nutt. European Journal of Scientific Research: Vol.41, n°2, pp 249-260. Durnete, 1960 simplified by El Midaoui and BenBella,. 1996);. EL-iklil Y, Karrou M, Mrabet R, Benichou M, 2002.

  2. Levels and distributions of organic pollutants in subtidal sediments from the Loire estuary: Are there any relationships with TTR-binding activity?

    Science.gov (United States)

    Couderc, M.; Gandolfi, F.; Zalouk-Vergnoux, A.; Beyeler, N.; Malleret, L.; Ambidina, I.; Kamari, A.; Blanchet-Letrouvé, I.; Mouneyrac, C.; Hamers, T.; Poirier, L.

    2016-12-01

    The Loire estuary runs through important urban sites with shipping, industrial and agricultural activities, being the receptacle of diffusive pollutants comprising, a mixture of contaminants such as persistent organic pollutants (POPs). This work was set out to evaluate the occurrence of thyroid endocrine disruptors in sediments of this estuary. Sediments were collected in September 2012 and April 2013, in subtidal zones along the estuary. Targeted chemical analyses of five classes of pollutants, i.e. polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs), polycyclic aromatic hydrocarbons (PAHs), alkylphenols (APs), and bisphenol A (BPA) were performed in sediment extracts. Extracts were further tested for their thyroid hormone (TH) disrupting potency to compete with TH for binding to its transporter protein transthyretin (TTR). The Haute-Indre site was characterized by a significant PAH contamination whereas Saint-Nazaire, Bellevue and Rezé would be particularly contaminated by PCBs. These observations could be linked to the different type of anthropogenic activities taking place close to these sites. Donges, Mindin and Paimboeuf were the sampling sites displaying the lowest contamination in PAHs, APs, PCBs and PBDEs. No inter-site difference could be observed for TTR-binding activity, which should be attributed to different compounds than the chemically analyzed compounds, as confirmed by PCA analyses. Furthermore, the TTR-binding potencies of the extracts were relatively low compared to data from literature. More investigations on the quantification of PCB and PBDE hydroxylated metabolites and other known endocrine disruptors such as pesticides or perfluorinated compounds could be considered, as well as bioassays highlighting other endocrine disrupting effects.

  3. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  4. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-07-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  5. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

  6. A gas-phase reactor powered by solar energy and ethanol for H2 production

    International Nuclear Information System (INIS)

    Ampelli, Claudio; Genovese, Chiara; Passalacqua, Rosalba; Perathoner, Siglinda; Centi, Gabriele

    2014-01-01

    In the view of H 2 as the future energy vector, we presented here the development of a homemade photo-reactor working in gas phase and easily interfacing with fuel cell devices, for H 2 production by ethanol dehydrogenation. The process generates acetaldehyde as the main co-product, which is more economically advantageous with respect to the low valuable CO 2 produced in the alternative pathway of ethanol photoreforming. The materials adopted as photocatalysts are based on TiO 2 substrates but properly modified with noble (Au) and not-noble (Cu) metals to enhance light harvesting in the visible region. The samples were characterized by BET surface area analysis, Transmission Electron Microscopy (TEM) and UV–visible Diffusive Reflectance Spectroscopy, and finally tested in our homemade photo-reactor by simulated solar irradiation. We discussed about the benefits of operating in gas phase with respect to a conventional slurry photo-reactor (minimization of scattering phenomena, no metal leaching, easy product recovery, etc.). Results showed that high H 2 productivity can be obtained in gas phase conditions, also irradiating titania photocatalysts doped with not-noble metals. - Highlights: • A gas-phase photoreactor for H 2 production by ethanol dehydrogenation was developed. • The photocatalytic behaviours of Au and Cu metal-doped TiO 2 thin layers are compared. • Benefits of operating in gas phase with respect to a slurry reactor are presented. • Gas phase conditions and use of not-noble metals are the best economic solution

  7. Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

    International Nuclear Information System (INIS)

    Reuscher, J.A.; Pickard, P.S.

    1976-01-01

    The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

  8. Impact de la restructuration de la taxe d'accise sur le tabac aux ...

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

    Aux Philippines, le taux de tabagisme est élevé et les taxes sur les produits du tabac, peu élevées. La meilleure façon de redresser la situation consiste à adopter des lois qui aug- mentent considérablement les taxes. Une loi restructurant les taxes sur les produits du tabac, qui comporte une forte hausse de la taxe d'accise ...

  9. Graphite reactor physics; Physique des piles a graphite

    Energy Technology Data Exchange (ETDEWEB)

    Bacher, P; Cogne, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Noc, B [Electricite de France (EDF), 75 - Paris (France)

    1964-07-01

    The study of graphite-natural uranium power reactor physics, undertaken ten years ago when the Marcoule piles were built, has continued to keep in step with the development of this type of pile. From 1960 onwards the critical facility Marius has been available for a systematic study of the properties of lattices as a function of their pitch, of fuel geometry and of the diameter of cooling channels. This study has covered a very wide field: lattice pitch varying from 19 to 38 cm. uranium rods and tubes of cross-sections from 6 to 35 cm{sup 2}, channels with diameters between 70 and 140 mm. The lattice calculation methods could thus be checked and where necessary adapted. The running of the Marcoule piles and the experiments carried out on them during the last few years have supplied valuable information on the overall evolution of the neutronic properties of the fuel as a function of irradiation. More detailed experiments have also been performed in Marius with plutonium-containing fuels (irradiated or synthetic fuels), and will be undertaken at the beginning of 1965 at high temperature in the critical facility Cesar, which is just being completed at Cadarache. Spent fuel analyses complement these results and help in their interpretation. The thermalization and spectra theories developed in France can thus be verified over the whole valid temperature range. The efficiency of control rods as a function of their dimensions, the materials of which they are made and the lattices surrounding them has been measured in Marius, and the results compared with calculation on the one hand and with the measurements carried out in EDF 1 on the other. Studies on the control proper of graphite piles were concerned essentially with the risks of spatial instability and the means of detecting and controlling them, and with flux distortions caused by the control rods. (authors) [French] Entreprise il y a dix ans a l'occasion de la construction des piles de Marcoule, l'etude de la

  10. The Sur7 protein regulates plasma membrane organization and prevents intracellular cell wall growth in Candida albicans.

    Science.gov (United States)

    Alvarez, Francisco J; Douglas, Lois M; Rosebrock, Adam; Konopka, James B

    2008-12-01

    The Candida albicans plasma membrane plays important roles in cell growth and as a target for antifungal drugs. Analysis of Ca-Sur7 showed that this four transmembrane domain protein localized to stable punctate patches, similar to the plasma membrane subdomains known as eisosomes or MCC that were discovered in S. cerevisiae. The localization of Ca-Sur7 depended on sphingolipid synthesis. In contrast to S. cerevisiae, a C. albicans sur7Delta mutant displayed defects in endocytosis and morphogenesis. Septins and actin were mislocalized, and cell wall synthesis was very abnormal, including long projections of cell wall into the cytoplasm. Several phenotypes of the sur7Delta mutant are similar to the effects of inhibiting beta-glucan synthase, suggesting that the abnormal cell wall synthesis is related to activation of chitin synthase activity seen under stress conditions. These results expand the roles of eisosomes by demonstrating that Sur7 is needed for proper plasma membrane organization and cell wall synthesis. A conserved Cys motif in the first extracellular loop of fungal Sur7 proteins is similar to a characteristic motif of the claudin proteins that form tight junctions in animal cells, suggesting a common role for these tetraspanning membrane proteins in forming specialized plasma membrane domains.

  11. The Sur7 Protein Regulates Plasma Membrane Organization and Prevents Intracellular Cell Wall Growth in Candida albicans

    Science.gov (United States)

    Alvarez, Francisco J.; Douglas, Lois M.; Rosebrock, Adam

    2008-01-01

    The Candida albicans plasma membrane plays important roles in cell growth and as a target for antifungal drugs. Analysis of Ca-Sur7 showed that this four transmembrane domain protein localized to stable punctate patches, similar to the plasma membrane subdomains known as eisosomes or MCC that were discovered in S. cerevisiae. The localization of Ca-Sur7 depended on sphingolipid synthesis. In contrast to S. cerevisiae, a C. albicans sur7Δ mutant displayed defects in endocytosis and morphogenesis. Septins and actin were mislocalized, and cell wall synthesis was very abnormal, including long projections of cell wall into the cytoplasm. Several phenotypes of the sur7Δ mutant are similar to the effects of inhibiting β-glucan synthase, suggesting that the abnormal cell wall synthesis is related to activation of chitin synthase activity seen under stress conditions. These results expand the roles of eisosomes by demonstrating that Sur7 is needed for proper plasma membrane organization and cell wall synthesis. A conserved Cys motif in the first extracellular loop of fungal Sur7 proteins is similar to a characteristic motif of the claudin proteins that form tight junctions in animal cells, suggesting a common role for these tetraspanning membrane proteins in forming specialized plasma membrane domains. PMID:18799621

  12. Neutron dosimetry in the Three-Mile Island Unit 2 reactor cavity with solid-state track recorders

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.; Rao, S.V.; Greenborg, J.; Fricke, V.R.

    1985-01-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit 2 (TMI-2) reactor cavity (i.e., the annular gap between the pressure vessel and the biological shield) for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, is lying at the bottom of the vessel. The existence of significant neutron streaming also explains the high count rate observed with the source range monitors (SRMs) that are located in the TMI-2 reactor cavity

  13. A Conceptual Study of a Supercritical CO2-Cooled Micro Modular Reactor

    Directory of Open Access Journals (Sweden)

    Hwanyeal Yu

    2015-12-01

    Full Text Available A neutronics conceptual study of a supercritical CO2-cooled micro modular reactor (MMR has been performed in this work. The suggested MMR is an extremely compact and truck-transportable nuclear reactor. The thermal power of the MMR is 36.2 MWth and it is designed to have a 20-year lifetime without refueling. A salient feature of the MMR is that all the components including the generator are integrated in a small reactor vessel. For a minimal volume and long lifetime of the MMR core, a fast neutron spectrum is utilized in this work. To enhance neutron economy and maximize the fuel volume fraction in the core, a high-density uranium mono-nitride U15N fuel is used in the fast-spectrum MMR. Unlike the conventional supercritical CO2-cooled fast reactors, a replaceable fixed absorber (RFA is introduced in a unique way to minimize the excess reactivity and the power peaking factor of the core. For a compact core design, the drum-type control absorber is adopted as the primary reactivity control mechanism. In this study, the neutronics analyses and depletions have been performed by using the continuous energy Monte Carlo Serpent code with the evaluated nuclear data file ENDF/B-VII.1 Library. The MMR core is characterized in view of several important safety parameters such as control system worth, fuel temperature coefficient (FTC and coolant void reactivity (CVR, etc. In addition, a preliminary thermal-hydraulic analysis has also been performed for the hottest channel of the Korea Advanced Institute of Science and Technology (KAIST MMR.

  14. Le livre sur le livre traité de documentation

    CERN Document Server

    Otlet, Paul

    2015-01-01

    Paul Otlet est considéré comme le père des sciences de l'information. Ouvrage fondateur et fondamental, le Traité de documentation. Le livre sur le livre (1934) est l'aboutissement de son travail inlassable pour rassembler, classer et partager les connaissances. Otlet y propose une remarquable synthèse du savoir sur le livre et le document en même temps qu'il anticipe Internet et l'hypertexte. La réédition du Traité de documentation, 70 ans après la disparition de son auteur, coïncide avec la réouverture du Mundaneum à Mons, où le fabuleux héritage documentaire légué par Paul Otlet et Henri La Fontaine est conservé. « Ici, la table de travail n'est plus chargée d'aucun livre. À leur place se dresse un écran et à portée un téléphone. Là-bas, au loin, dans un édifice immense, sont tous les livres et tous les renseignements. De là, on fait apparaître sur l'écran la page à lire pour connaître la réponse aux questions posées par téléphone. » Préfaces de Benoît Peeters (éc...

  15. Multi isotopic characterization (Li-Cu-Zn-Pb) of waste waters pollution in a small watershed (Loire River basin, France)

    Science.gov (United States)

    Millot, R.; Desaulty, A. M.; Perret, S.; Bourrain, X.

    2016-12-01

    The goal of this study is to use multi-isotopic signature to track the pollution in surface waters, and to understand the complex processes causing the metals mobilization and transport in the environment. In the present study, we investigate waste water releases from a hospital water treatment plant and its potential impact in a small river basin near Orléans in France (Egoutier watershed: 15 km²and 5 km long). We decided to monitor this small watershed which is poorly urbanized in the Loire river basin. Its spring is located in a pristine area (forested area), while it is only impacted some kilometers further by the releases rich in metals coming from a hospital water treatment plant. A sampling of these liquid effluents as well as dissolved load and sediment from upstream to downstream was realized and their concentrations and isotopic data were determined. Isotopic ratios were measured using a MC-ICP-MS at BRGM, after a specific protocol of purification for each isotopic systematics. Lithium isotopic compositions are rather homogeneous in river waters along the main course of the stream. The waste water signal is very different from the natural background with significant heavy lithium contribution (high δ7Li). Lead isotopic compositions are rather homogenous in river waters and sediments with values close to geologic background. For Zn, the sediments with high concentrations and depleted isotopic compositions (low δ66Zn), typical of an anthropic pollution, are strongly impacted. The analyses of Cu isotopes in sediments show the impact of waster waters, but also isotopic fractionations due to redox processes in the watershed. To better understand these processes controlling the release of metals in water, sequential extractions on sediments are in progress under laboratory conditions and will provide important constraints for metal distribution in this river basin.

  16. TeleSUR: la creación televisiva de “lo latinoamericano”

    Directory of Open Access Journals (Sweden)

    Günther Maihold

    2014-06-01

    Full Text Available Nueva Televisión del Sur C. A. (Tele-SUR es el nombre de la empresa interestatal que ha iniciado sus transmisiones en el año 2005, en el marco de las nuevas iniciativas integracionistas del presidente venezolano Hugo Chávez, enfocada fundamentalmente al área noticiera para el continente americano. Concebida por su director general, el periodista uruguayo Aram Aharonian, como “alternativa a la hegemonía comunicacional, al pensamiento y la imagen únicas”, TeleSUR es parte de un proceso político más amplio, recubierto de barniz bolivariano, para reencontrar, a través de los medios electrónicos, la unidad e identidad latinoamericana frente a las grandes cadenas y corporaciones informativas internacionales, entre las cuales cuentan CNN en español, Fox News, ESPN y la BBC, con sus programas en castellano, y las grandes empresas nacionales como Televisa de México, Globo en Brasil y tanto el grupo Cisneros en Venezuela como Clarín en Argentina.

  17. Rapport de 2010 sur l'état de l'évaluation du développement en Inde ...

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

    En Inde, des données empiriques donnent à penser que l'évaluation du développement est en déclin, tant sur le plan du nombre que de la qualité des évaluations. Toutefois, il existe très peu de données écrites, voire aucune, sur la situation de l'évaluation en Inde, ni sur les facteurs en cause. Ce projet permettra donc de ...

  18. A instrução pública na França revolucionária: considerações a partir do Essais sur l’enseignement en general et sur celui des mathématiques en particulier, de Sylvestre-François Lacroix - The public instruction in revolutionary France: some remarks accord

    Directory of Open Access Journals (Sweden)

    Antonio Vicente Marafioti Garnica

    2013-04-01

    Full Text Available O artigo aborda o livro Essais sur l'enseignement en général, et sur celui des mathématiques en particulier, de Sylvestre-François Lacroix, publicado originalmente na França em 1805, enfatizando sua primeira parte, na qual o autor discute a instrução pública e, particularmente, as escolas centrais da França revolucionária.Palavras-chave: Sylvestre-François Lacroix (1765-1843, instrução pública, Essais sur l'enseigne-ment en général, et sur celui des mathématiques en particulier, iluminismo, França. The public instruction in revolutionary France: some remarks according to Lacroix’s Essais sur l’enseignement en general et sur celui des mathématiques en particulierAbstractThe article discusses the book Essais sur l'enseignement en général, et sur celui des mathématiques en particulier, by Sylvestre-François Lacroix, originally published in France in 1805. The first part of the book, in which the author discusses public education, and particularly the central schools of revolutionary France, is emphasized.Key-words: Sylvestre-François Lacroix (1765-1843, public instruction, Essais sur l'enseignement en général, et sur celui des mathématiques en particulier, enlightenment, France. Instrucción pública en Francia revolucionaria: consideraciones a la vista del libro Essais sur l’enseignement en general et sur celui des mathématiques en particulier, de Sylvestre-François LacroixResumenEl artículo aborda el libro Essais sur l'enseignement en général, et sur celui des mathématiques en particulier de Sylvestre-François Lacroix, publicado originalmente en Francia, en 1805, haciendo hincapié en su primera parte, en la que el autor habla de la instrucción pública y en particular de las escuelas centrales en Francia en el período revolucionario.Palabras-clave: Sylvestre-François Lacroix (1765-1843, instrucción pública, Essais sur l'enseigne-ment en général, et sur celui des mathématiques en particulier

  19. Regard sur les Lazarets en Terre Canadienne

    Directory of Open Access Journals (Sweden)

    Jean Milot

    2008-01-01

    Full Text Available Puisant dans les nombreuses références qu’offrent les publications médicales canadiennes du milieu du XIXe siècle à nos jours, l’auteur fait découvrir l’existence de lazarets en terre canadienne, décrit l’impact de la maladie sur les conditions vie des lépreux qui y étaient confinés et en souligne les contrecoups tant sur le plan physique et psychologique que social. Il présente un bref aperçu de la maladie, ses symptômes, ses signes ainsi que ses complications oculaires et rappelle les premiers moyens thérapeutiques à base d’huile de chaulmoogra introduits dans la colonie de Tracadie vers 1901. Il illustre son propos en évoquant la vie dans les lazarets de l’île de Sheldrake (1844–1848 et de Tracadie (1848–1965 au Nouveau-Brunswick, puis dans ceux des îles D’Arcy (1891–1924 et de Bentinck (1924–1957 en Colombie-Britannique.

  20. Institutions de recherche sur les politiques et ODD liés à la santé ...

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

    Institutions de recherche sur les politiques et ODD liés à la santé ... Ce projet permettra de tirer des enseignements sur l'utilité des think tanks pour soutenir la sensibilisation et la mobilisation des citoyens eu égard à la mise en ... Site internet.