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Sample records for belleville sur loire-1 reactor

  1. 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)

    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.)

  2. Experiments with the SUR 100 training reactor

    International Nuclear Information System (INIS)

    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.)

  3. Belleville rouge, Belleville noir, Belleville rose: The Complex Identity of a Parisian quartier

    Directory of Open Access Journals (Sweden)

    Carolyn Stott

    2015-03-01

    Full Text Available The Parisian quartier of Belleville has long been the subject of scholarly literature and popular culture due to its colourful history and diverse population. Its symbolic boundaries extend beyond the geographical limits imposed by its administrative demarcation. Myths abound as to the extent of its rebellious past, its contemporary image as a melting pot and its prevalence as a décor for the noir genre. In this article a three-tiered categorisation of Belleville is adopted which corresponds to various representations of the suburb in literature, popular culture and from the perspective of its inhabitants. Belleville rouge reflects the quartier’s revolutionary past and the late 20th century struggle associated with its physical metamorphosis. Belleville noir focusses on the quartier’s criminal face, as it is depicted in Parisian film and roman noir and as it exists in reality. Belleville rose highlights the pleasures of the quartier: its cosmopolitan character whose representation verges at times on utopian.    In his Malaussène series (1985-1995, writer and former resident Daniel Pennac portrays Belleville as a unique blend of rouge, noir and rose. This fusion of fairy tale, detective fiction, myth and reality establishes a complex Bellevillois identity distinct from other contemporary representations. The article concludes that it is impossible to associate a single identity with Belleville. The quartier’s contemporary face is inextricably linked to its past, the memory of which is preserved by its inhabitants and by social and literary commentators such as Pennac. In keeping with historian Pierre Nora’s concept of cultural memory, Pennac thus assumes the role of guardian of Belleville’s cultural memory in the face of the quartier’s perpetual evolution.

  4. Belleville powerhouse electrical systems and controls

    Energy Technology Data Exchange (ETDEWEB)

    Clemen, D.M. [Harza Engineering Co., Chicago, IL (United States)

    1995-12-31

    The 42 MW Belleville Hydroelectric Project is a run-of-river plant located on the West Virginia side of the existing Corps of Engineers Belleville Lock and Dam on the Ohio River. The plant consists of two 21 MW bulb units with 7.3 meter diameter runners manufactured by Voest Alpine Machinery Construction Engineering (VAMCE). The plant will generate approximately 245 GWhr of electricity each year. Many unique features associated with the electrical power equipment at the Belleville Hydroelectric Project are a direct result of the FERC license requirement that allows flood waters to run over the top of the powerhouse. Consequently, no exterior decks, roofs, or adjacent lands were available as equipment areas for the Generator Step-Up (GSU) transformers or the 138 kV SF6 substation.

  5. Elastic guides reduce hysteresis effect in Belleville spring package

    Science.gov (United States)

    Mc Glashan, W. F., Jr.; Toth, L. R.

    1967-01-01

    Peripheral support guides that elastically flex with the slight breathing on radial displacement during actuation can greatly reduce the hysteresis present in a Belleville spring package. This technique provides a control device that enhances the precision of pressure regulating valves, pressure switches, and vacuum actuators.

  6. 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.)

  7. Public debate on the EPR reactor; Debat public sur le reacteur EPR

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-10-15

    In the framework of the new EPR European Pressurized Reactor implementation in France, the public asked the first Ministry on the protection of nuclear matters, transports and installations against the terrorism and the spiteful actions. This document provides information on the subject and shows the safety of the new reactor. (A.L.B.)

  8. Superelastic SMA Belleville washers for seismic resisting applications: experimental study and modelling strategy

    Science.gov (United States)

    Fang, Cheng; Zhou, Xiaoyi; Israel Osofero, Adelaja; Shu, Zhan; Corradi, Marco

    2016-10-01

    This study sheds considerable light on the potential of superelastic shape memory alloy Belleville washers for innovative seismic resisting applications. A series of experimental studies were conducted on washers with different stack combinations under varying temperatures and loading scenarios. The washers showed satisfactory self-centring and energy dissipation capacities at room temperature, although slight degradations of the hysteretic responses accompanied by residual deformations were induced. The hysteretic loops became stable after a few number of cycles, indicating good repeatability. The washers also showed good flexibility in terms of load resistance and deformation, which could be easily varied via changes in the stack combination. Compromised self-centring responses were observed at temperatures below 0 °C or above 40 °C, and a numerical study, validated by the experimental results, was adopted to further investigate the deformation mechanism of the washers. A further phenomenological model, taking account of the degradation effects under varied temperatures, was developed to enable effective and accurate simulation of devices incorporating the washers. Good agreements were observed between the test and simulation results, and the model was shown to have good numerical robustness for wide engineering applications.

  9. Finite Element Analysis on Belleville Spring in Flanged Joints%法兰接头用碟形弹簧的有限元分析

    Institute of Scientific and Technical Information of China (English)

    王俊和

    2015-01-01

    Normal belleville spring and belleville spring used in flanged joints are simulated through 2-D finite element analysis and the friction effect on the load of the belleville spring used in flanged joints is considered. The results show that the fraction has intense impact on the rigidity of the belleville spring used in flanged joints which is quite significant in the design process.%利用2-D有限元法模拟了普通碟形弹簧和法兰接头用碟形弹簧, 并考虑了摩擦对法兰接头用碟形弹簧承载的影响. 结果表明, 有限元法对碟簧的模拟十分精确. 此外, 摩擦对法兰接头用碟形弹簧的刚度影响较大, 这在设计过程中不容忽视.

  10. 5. french meeting on the gas-liquid and gas-liquid-solid reactors; 5. journees francophones sur les reacteurs gaz-liquide et gaz-liquide-solide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This presentation concerns the flow simulation in a vortex effect reactor and the oxalic precipitation of the plutonium oxalate simulation. It provides then the experimental validation and perspectives for future researches. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Barre, B.; Camarcat, N.

    1995-12-31

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

  12. Hanging core support system for a nuclear reactor. [LMFBR

    Science.gov (United States)

    Burelbach, J.P.; Kann, W.J.; Pan, Y.C.; Saiveau, J.G.; Seidensticker, R.W.

    1984-04-26

    For holding the reactor core in the confining reactor vessel, a support is disclosed that is structurally independent of the vessel, that is dimensionally accurate and stable, and that comprises tandem tension linkages that act redundantly of one another to maintain stabilized core support even in the unlikely event of the complete failure of one of the linkages. The core support has a mounting platform for the reactor core, and unitary structure including a flange overlying the top edge of the reactor vessels, and a skirt and box beams between the flange and platform for establishing one of the linkages. A plurality of tension rods connect between the deck closing the reactor vessel and the platform for establishing the redundant linkage. Loaded Belleville springs flexibly hold the tension rods at the deck and separable bayonet-type connections hold the tension rods at the platform.

  13. El Banco del Sur

    OpenAIRE

    Espejo, Silvana

    2012-01-01

    En este trabajo abordaremos las características principales del Banco del Sur como una institución financiera sudamericana. Primero presentaremos sus principales características y explicaremos las características de un banco de desarrollo regional. Luego, expondremos el proceso de conformación del mismo haciendo un recorrido por sus principales antecedentes. Por último, cerraremos con una evaluación sobre el estado actual del Banco del Sur. (Párrafo extraído del texto a modo de resumen)...

  14. Failure analysis for fatigue fracture of tractor clutch belleville spring%拖拉机离合器碟形弹簧疲劳断裂失效分析

    Institute of Scientific and Technical Information of China (English)

    严正峰; 李盖华; 夏建新

    2014-01-01

    通过对拖拉机碟形弹簧的化学成分、热处理和表面机械强化工艺、硬度、金相分析及强化疲劳试验,发现弹簧脱碳层、硬度和表面机械强化工艺不足是产生弹簧疲劳断裂的主要原因。通过对脱碳层、硬度的控制及挤压圆角、抛丸等表面机械强化工艺的改善,产品性能满足了使用要求。%Based on chemical composition, heat treatment and surface strengthening technology, hardness, metallographic analysis of the tractor belleville spring, combined with the intensifying fatigue test, it was found that the decarburization layer of materials, hardness of belleville spring and insufficient of strengthening technology were the principal causes of fatigue fracture.By the control of the material decarburization layer, the hardness of belleville spring and surface strengthening technology improvement such as rounded corners extrusion and surface shot peening, the product performance can meet the use requirement.

  15. Three-Dimensional Numerical Analysis for the Pipe Flanged Jiont with Belleville Spring in Delayed Coking Unit%延迟焦化装置中带碟簧的管法兰接头三维数值分析

    Institute of Scientific and Technical Information of China (English)

    董智; 仇性启; 赵宗彬

    2011-01-01

    FEA was used to analyze the force and deformation of coke tower and the pipe in delayed coking unit. Three - dimensional numerical analysis for the pipe flanged joint with belleville spring was carried on to investigate belleville spring's effects on gasket stress under the elevated temperature condition of coking stage. The results of the simulation show that coke tower produces thermal expansion, so induces the bend deformation of pipeline in the coking stage. High temperature's effects on them are more obvious than the pressure's. Proper use of belleville spring is more favourable for maintaining the working stress of gasket of the pipe flanged joint under the condition of elevated temperature.%应用有限元法分析延迟焦化装置中焦炭塔和管道的受力和变形,并针对生焦高温工况,对带有碟形弹簧的管法兰接头进行三维数值模拟,分析碟形弹簧对垫片应力的影响.模拟结果表明,生焦时焦炭塔受高温膨胀,导致管道弯曲变形,而内压对此影响相对要小很多;高温下选用适当的碟形弹簧,有利于维持管法兰接头的垫片工作应力.

  16. Comentarios desde el Sur

    Directory of Open Access Journals (Sweden)

    Tatiana Cordero Velásquez

    2011-05-01

    Full Text Available Este texto ahonda en las preguntas que plantea el Dossier: ¿Cómo se piensa lo queer en AméricaLatina? La autora analiza los contenidos de lo político en lo queer, sus aportes y limites, y la pertinenciadel concepto. Subraya la ausencia de una perspectiva de género en los estudios gay yqueer anteriores, y la relación entre sujetos LGBTI y la academia en la trayectoria de lo queer ennuestro contexto. Analiza el lugar de lo femenino en tres de los cinco artículos que abordan lasidentidades gay y trans y la ausencia de análisis sobre lo masculino en lo lésbico, bisexual o transmasculino como reflejo de la estratificación en la producción de conocimiento en torno al ‘cuerpopolítico queer’. A la vez, destaca la contribución de este dossier a la producción de conocimientoen el Sur así como a la complejización de este debate.

  17. ALIBABA, an assistance system for the detection of confinement leaks in a PWR reactor; ALIBABA, un systeme d`aide a la detection des voies de fuites du confinement sur un reacteur a eau sous pression

    Energy Technology Data Exchange (ETDEWEB)

    Bedier, P.O.; Libmann, M. [CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie

    1995-12-31

    The objective of the Crisis Technical Center (CTC) of the French Institute for Nuclear Protection and Safety (IPSN) is to estimates the consequences of a given nuclear accident on the populations and the environment. ALIBABA is a data processing tool available at the CTC and devoted to the detection of confinement leaks in 900 MWe PWR reactors using the activity values measured by the captors of the installation. The heart of this expert system is a structural and functional representation of the different components directly involved in the leak detection (isolating valves, ventilation systems, electric boards etc..). This tool can manage the availability of each component to make qualitative and quantitative balance-sheets. This paper presents the ALIBABA software, an industrial prototype realized with the SPIRAL knowledge base systems generator at the CEA Reactor Studies and Applied Mathematics Service (SERMA) and commercialized by CRIL-Ingenierie Society. It describes the techniques used for the modeling of PWR systems and for the visualization of the survey. The functionality of the man-machine interface is discussed and the means used for the validation of the software are summarized. (J.S.). 6 refs.

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

    Energy Technology Data Exchange (ETDEWEB)

    Pastina, B

    1997-07-01

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

  19. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

    This pamphlet describes how reactors work; discusses reactor design; describes research, teaching, and materials testing reactors; production reactors; reactors for electric power generation; reactors for supply heat; reactors for propulsion; reactors for space; reactor safety; and reactors of tomorrow. The appendix discusses characteristics of U.S. civilian power reactor concepts and lists some of the U.S. reactor power projects, with location, type, capacity, owner, and startup date.

  20. First remarks on the initiative of conception and evaluation of the safety of the reactors of the fourth generation; Premieres reflexions sur la demarche de conception et d'evaluation de la surete des reacteurs de quatrieme generation

    Energy Technology Data Exchange (ETDEWEB)

    Clement, Ch.; Maliverney, B.; Mulet-Marquis, D.; Sauvage, J.F. [Electricite de France (EDF), 75 - Paris (France); Guesdon, B. [Technical Secretary (France); Carluec, B.; Ehster, S. [AREVA NP, 92 - Paris la Defense (France); Greneche, D. [AREVA NC, 78 - Velizy Villacoublay (France); Anzieu, P. [CEA Saclay, 91 - Gif sur Yvette (France); Fiorini, G.L. [CEA Cadarache, 13 - Saint Paul lez Durance (France); Rozenholc, M.; Vitton, F.; Rouyer, J.L

    2007-09-15

    The objectives of the nuclear systems of the fourth generation impose ambitious requirements which concern the sustainable development, the competitiveness, the safety, the reliability, the resistance to proliferation and the physical protection. The examination of the policies of safety applicable to these systems is led at the same moment to the national and international levels. In France, thoughts on the safety is organized within the French consultative group of safety (G.C.F.S.) which collects the industrial actors and of research and development involved in the development of the new systems. Within the framework of the initiatives of international harmonization, the G.C.F.S. suggests defining recommendations common to all the concepts of the fourth generation reactors then on the basis of this neutral frame towards the technologies, establishing specific recommendations for each of the systems. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Journeau, Ch

    2008-01-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-07-01

    In the frame of the studies on next generation nuclear systems, and especially for the molten salt reactors and for the integrated fuel cycle (as IFR), the fuel cycle constraints must be taken into account in the preliminary studies of the system to improve the cycle and reactor optimisation. Among the purposes for next generation nuclear systems, sustainability and waste (radio-toxicity and mass) management are important goals. These goals imply reprocessing and recycling strategies. The objectives of this workshop are to present and to share the different strategies and scenarios, the needs based on these scenarios, the experimental facilities available today or in the future and their capabilities, the needs for demonstration. It aims at: identifying the needs for fuel cycle based on solid fuel or liquid fuel, and especially, the on-line reprocessing or clean up for the molten salt reactors; assessing the state-of-the-art on the pyro-chemistry applied to solid fuel and to present the research activities; assessing the state-of-the-art on liquid fuels (or others), and to present the research activities; expressing the R and D programs for pyro-chemistry, molten salt, and also to propose innovative processes; and proposing some joint activities in the frame of GEDEON and PRACTIS programs. This document brings together the transparencies of 18 contributions dealing with: scenario studies with AMSTER concept (Scenarios, MSR, breeders (Th) and burners); fuel cycle for innovative systems; current reprocessing of spent nuclear fuel (SNF) in molten salts (review of pyro-chemistry processes (non nuclear and nuclear)); high temperature NMR spectroscopies in molten salts; reductive extraction of An from molten fluorides (salt - liquid metal extraction); electrochemistry characterisation; characterisation with physical methods - extraction coefficient and kinetics; electrolytic extraction; dissolution-precipitation of plutonium in the eutectic LiCl-KCl (dissolution and

  3. Modelling of the hydrogen effects on the morphogenesis of hydrogenated silicon nano-structures in a plasma reactor; Modelisation des effets de l'hydrogene sur la morphogenese des nanostructures de silicium hydrogene dans un reacteur plasma

    Energy Technology Data Exchange (ETDEWEB)

    Brulin, Q

    2006-01-15

    This work pursues the goal of understanding mechanisms related to the morphogenesis of hydrogenated silicon nano-structures in a plasma reactor through modeling techniques. Current technologies are first reviewed with an aim to understand the purpose behind their development. Then follows a summary of the possible studies which are useful in this particular context. The various techniques which make it possible to simulate the trajectories of atoms by molecular dynamics are discussed. The quantum methods of calculation of the interaction potential between chemical species are then developed, reaching the conclusion that only semi-empirical quantum methods are sufficiently fast to be able to implement an algorithm of quantum molecular dynamics on a reasonable timescale. From the tools introduced, a reflection on the nature of molecular metastable energetic states is presented for the theoretical case of the self-organized growth of a linear chain of atoms. This model - which consists of propagating the growth of a chain by the successive addition of the atom which least increases the electronic energy of the chain - shows that the Fermi level is a parameter essential to self organization during growth. This model also shows that the structure formed is not necessarily a total minimum energy structure. From all these numerical tools, the molecular growth of clusters can be simulated by using parameters from magnetohydrodynamic calculation results of plasma reactor modeling (concentrations of the species, interval between chemical reactions, energy of impact of the reagents...). The formation of silicon-hydrogen clusters is thus simulated by the successive capture of silane molecules. The structures formed in simulation at the operating temperatures of the plasma reactor predict the formation of spherical clusters constituting an amorphous silicon core covered by hydrogen. These structures are thus not in a state of minimum energy, contrary to certain experimental

  4. California Sur, México

    Directory of Open Access Journals (Sweden)

    Francisco Higinio Ruiz Espinoza

    2008-01-01

    Full Text Available En la Universidad Autónoma de Baja California Sur situada al sur del Estado de Baja California Sur, México, se desarrolló un experimento durante 3 años (2002 – 2004. Evaluándose los datos climáticos en la zona, a partir de la información proporcionada por la Comisión Nacional del Agua. Las variables climáticas evaluadas fueron temperatura (T, humedad relativa (HR, evaporación (E, promediados por décadas para el período correspondiente al desarrollo de la investigación, mientras que las variables biológicas fueron rendimiento, área foliar (AF e índice de área foliar (IAF, tasa relativa de crecimiento (TRC, tasa de asimilación neta (TAN y masa seca. Se aplicó un análisis estadístico descriptivo y multivariado, las medias se compararon por Tukey al 5 % de probabilidad, con análisis factorial, empleando el programa STATISTICA 6.0. Los resultados mostraron la relación de la temperatura y la humedad relativa con el rendimiento, lo que establece que para el máximo rendimiento de albahaca en las condiciones en que se condujo el experimento la temperatura de 32 oC y la humedad relativa de 58 % fueron las mejores

  5. Les torsions sur testicules cryptorchides

    Science.gov (United States)

    Gharbi, Mohamed; Amri, Najmeddine; Chambeh, Wahib; Braiek, Salem; Kamel, Rafik El

    2010-01-01

    Résumé But : La cryptorchidie est une pathologie assez fréquente en urologie. Elle est associée à un risque élevé d’infertilité et de dégénérescence. Elle semble aussi être associée à un risque important de torsion. Cette entité est très peu abordée dans la littérature. Nous rapportons tous les cas de torsion sur testicule cryptorchide observés à notre service dans le but de mieux caractériser cette pathologie et de réduire ainsi le taux d’orchidectomies. Méthodologie : Il s’agit d’une étude rétrospective portant sur tous les cas de torsion sur testicule cryptorchide opérés dans notre service d’urologie entre 1999 et 2007. Les patients ont fait l’objet d’une description basée sur le résumé de leurs observations. Résultats : Les patients étaient âgés de 7 mois à 39 ans. La torsion touchait le testicule droit dans 53 % des cas. Le tableau clinique comportait une douleur au niveau de la région inguinale d’apparition soudaine avec une masse sous-cutanée inflammatoire et douloureuse à ce niveau et surtout un hémiscrotum homolatéral vide. Dans 60 % des cas, le diagnostic était tardif et une orchidectomie a été réalisée. Dans les autre cas, un abaissement du testicule a été réalisé avec orchidopexie controlatéral dans le même temps opératoire. Conclusion : Bien qu’il s’agisse d’une pathologie peu courante, la torsion sur testicule cryptorchide doit être étudiée davantage. Le diagnostic précoce permettra de sauver et d’abaisser le testicule et faciliter ainsi le dépistage d’une éventuelle dégénérescence. PMID:21191497

  6. La piraterie sur le web

    CERN Multimedia

    2002-01-01

    Les échanges de toutes sortes sont facilités à l'extrême par le web: des forums, des vidéoconférences, le commerce à distance, ou tout simplement la célérité des courriers électroniques ou la convivialité des chats, tout cela participe de la société de communication. Une certaine partie du monde découvre le nouvel horizon des échanges quasi instantanés, mais... les transactions sur le web sont-elles vraiment s res?

  7. Regards sur le Mozambique contemporain

    Directory of Open Access Journals (Sweden)

    Fabrice Folio

    2008-12-01

    Full Text Available Cet article esquisse un état des lieux géographique de la république du Mozambique. L’organisation spatiale de ce pays s’inscrit à la fois dans des mutations en cours et dans un héritage complexe. Une approche multiscalaire permet d’en rendre compte tout en recourant à la dimension géohistorique. L’influence d’enjeux et d’acteurs extérieurs sur l’aménagement de cet espace est prégnante. Les réalités spatiales et les logiques socio-économiques en cours peuvent en témoigner, que ce soit la forme singulière de ce pays ou encore le hiatus croissance/développement observé sur place. Les lignes de force originales, inscrites sur l’espace mozambicain, associent en fait des « pénétrantes » transnationales couplées à une excentration historique de sa première ville et de nouveaux pré-carrés dynamiques, inscrits dans la mondialisation, dont il faudra questionner la cohérence sociale et territoriale.The aim of this article is to draw out the geographical broad lines of the republic of Mozambique. The country’s spatial organisation is part of the present mutations as well as its complex heritages. Different scales will be considered. Moreover, we will point out both the historical and geographical background. The paper will try to demonstrate that lots of outer stakes as well as external actors have played a major role on the spatial reality of Mozambique. The contemporaneous spatial and socio-economical realities can attest to this point, such as the specific physiognomy of this territory or the gap between national growth and social development. Finally, the spatial Mozambican singularities display several internal “corridors” connected to foreign countries, the localisation of the capital-city, Maputo, at the extreme south periphery of the country and new strategic areas linked to globalisation. The social and spatial coherence of the latter will be issued.

  8. N Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The last of Hanfordqaodmasdkwaspemas7ajkqlsmdqpakldnzsdflss nine plutonium production reactors to be built was the N Reactor.This reactor was called a dual purpose...

  9. 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.

  10. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    2013-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  11. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  12. Report by the AERES on the unit: Reactor Study Department (DER) under the supervision of the establishments and bodies: Atomic Energy and Alternative Energies Commission (CEA); Rapport de l'AERES sur l'unite: Departement d'Etudes des Reacteurs (DER) sous tutelle des etablissements et organismes: CEA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-02-15

    This report is a kind of audit report on a research laboratory, the DER (Departement d'Etudes des Reacteurs, Reactor Study Department) whose activity if focused on four main themes: neutron transport simulation in reactor cores, thermal-hydraulic simulation of reactors, design and safety of innovative reactors, nuclear instrumentation for reactors. The authors discuss an assessment of the whole unit activities in terms of strengths and opportunities, aspects to be improved, risks and recommendations, productions and publications, scientific quality, influence and attractiveness (awards, recruitment capacity, capacity to obtain financing and to tender, participation to international programs), strategy and governance, and project. These same aspects are then discussed and commented for each theme

  13. Research reactors

    International Nuclear Information System (INIS)

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  14. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  15. Reports by the Parliamentary Office for scientific and technological assessments. Tuesday, May 24, 2011. Hearing on the protection of a reactor core and critical circuit; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Mardi 24 mai 2011. Audition sur la protection du coeur et des circuits critiques d'un reacteur

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-05-15

    In the context created by the Fukushima accident, members of the French Parliament, representatives of the French nuclear safety authority (ASN), of the French Institute for radiation protection and nuclear safety (IRSN), and of the CEA describe and discuss the technical aspects and mechanism of defence-in-depth of nuclear reactors (i.e. the different and successive levels of protection aimed at ensuring the reactor integrity to be maintained, even in case of failure of a critical circuit). Then, they discuss advances and researches in the field of protection of reactors. Several research programs are evoked which concern different elements of a nuclear plants such as the fuel, the reactor, loss of cooling system, and so on; these programs are based either on experiments or on simulations

  16. Analysis on Belleville Spring Fracture of Controlling Gear of Gas Insulated Switchgear in 220 kV Substation%220 kV 变电站气体绝缘金属封闭开关设备操作机构碟形弹簧断裂分析

    Institute of Scientific and Technical Information of China (English)

    李文胜; 董重里; 胡平; 王伟; 林介东

    2016-01-01

    通过宏观检查、金相试验、光谱分析、洛氏硬度试验、扫描电镜观察和能谱分析等试验,对一起220 kV变电站气体绝缘金属封闭开关设备(gas insulated switchgear,GIS)操作机构碟形弹簧断裂的原因进行分析。结果表明,碟形弹簧断裂的原因可以推断是弹簧下表面外径边缘至 U 形凹槽的区域在制造过程中形成原始缺陷,此处存在应力集中现象,在使用过程中,裂纹扩展并最终导致弹簧断裂。此外,碟形弹簧的显微组织保留了明显的马氏体针状形态,还出现了少量的羽毛状回火贝氏体,这些特征表明弹簧在使用过程中较易发生脆性断裂。%This paper analyzes reasons for Belleville spring fracture of controlling gear of gas insulated switchgear in 220 kV substation by experiments of microscopic test,metallographic test,spectral analysis,Rockwell hardness test,scanning elec-tron microscope observation,energy spectrum analysis,and so on. Results indicate that reasons for Belleville spring fracture may be deduced for original defect of the area along the edge of external diameter of the lower surface of the spring to the U-shaped groove in manufacturing process where exists stress concentration,and in use procedure,cracks extend and finally cause spring fracture. In addition,microscopic structure of the Belleville spring keeps obvious martensitic acicular form and there is a little featheriness tempered bainite,which indicates that brittle fracture is easy to occur on the spring in use procedure.

  17. The risk of shortage of radioelements at medical use must not lead to overlook the reactors safety that produce them; Le risque de penurie de radioelements a usage medical ne doit pas conduire a faire l'impasse sur la surete des reacteurs qui les produisent

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    As the reactors supplying the world production of radioelements for medical use have over 40 years of operation, the nuclear safety authority alerts the stake holders on the necessity to prevent the conflicts between public health and nuclear safety in the production of these elements; Asn estimates that the solution is not to extend the lifetime of the reactors but goes for a new international concerted approach. The most of the present production comes from five old reactors: N.R.U. at Chalk river (Canada, 40%), H.F.R. at Petten (Netherlands, 30%), Safari at Pelindaba (South Africa, 10%) B.R.2 at Mol (Belgium, 9%) and Osiris at Saclay (France, 5%). In this context, Asn organised in january 2009 a seminar on the safety-availability of facilities of radio-isotopes production with safety authorities of the concerned countries. Nea organised a seminar on the radiopharmaceuticals supply at the end of january 2009. (N.C.)

  18. Reactor building

    International Nuclear Information System (INIS)

    The whole reactor building is accommodated in a shaft and is sealed level with the earth's surface by a building ceiling, which provides protection against penetration due to external effects. The building ceiling is supported on walls of the reactor building, which line the shaft and transfer the vertical components of forces to the foundations. The thickness of the walls is designed to withstand horizontal pressure waves in the floor. The building ceiling has an opening above the reactor, which must be closed by cover plates. Operating equipment for the reactor can be situated above the building ceiling. (orig./HP)

  19. 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...

  20. Mise en oeuvre du krigeage sur arbre.

    OpenAIRE

    Polus, Edwige; de Fouquet, Chantal

    2010-01-01

    Un modèle de fonctions aléatoires définies sur une topologie d'arbre (de Fouquet & Bernard-Michel, 2006) a été développé pour l'estimation de concentrations le long d'un réseau hydrographique. Le principe consiste à décomposer le réseau en filets élémentaires joignant chaque " source " à " l'exutoire ". La concentration Z au point x s'exprime comme une combinaison linéaire Z(x)=$\\Sum$ wiYi(x) de variables aléatoires élémentaires Yi définies sur ces filets, dont les coefficients wi dépendent d...

  1. Influence of the flux axial form on the conversion rate and duration of cycle between recharging for ThPu and U{sub nat} fuels in CANDU reactors; Influence de la forme axiale du flux sur le taux de conversion et la duree du cycle entre rechargements pour du combustible ThPu et U{sub nat} dans les reacteurs CANDU

    Energy Technology Data Exchange (ETDEWEB)

    Chambon, Richard [Laboratoire de Physique Subatomique et de Cosmologie, Universite Joseph Fourier / CNRS-IN2P3, 53 Avenue des Martyrs, F-38026 Grenoble (France)

    2007-01-15

    To face the increasing world power demand the world nuclear sector must be continuously updated and developed as well. Thus reactors of new types are introduced and advanced fuel cycles are proposed. The technological and economic feasibility and the transition of the present power park to a renewed park require thorough studies and scenarios, which are highly dependent on the reactor performances. The conversion rate and cycle span between recharging are important parameters in the scenarios studies. In this frame, we have studied the utilisation of thorium in the CANDU type reactors and particularly the influence of axial form of the flux, i.e. of the recharging mode, on the conversion rate and duration of the cycle between recharging. The results show that up to a first approximation the axial form of the flux resulting from the neutron transport calculations for assessing the conversion rate is not necessary to be taken into account. However the time span between recharging differs up to several percents if the axial form of the flux is taken into consideration in transport calculations. Thus if the burnup or the recharging frequency are parameters which influence significantly the deployment scenarios of a nuclear park an approach more refined than a simple transport evolution in a typical cell/assembly is recommended. Finally, the results of this study are not more general than for the assumed conditions but they give a thorough calculation method valid for any recharging/fuel combination in a CANDU type reactor.

  2. Roles des contraintes sur les signaux de transition de phase

    CERN Document Server

    Regnard, V

    2003-01-01

    Ce papier presente la notion de signal de transition de phase pour un systeme de taille finie. Il se concentre sur le role des contraintes physiques sur ces signaux et la robustesse quant au changement d'ensemble statistique. Des resultats obtenus avec un modele de gaz sur reseau sont presentes en analogie avec les observations effectuees en collisions d'ions lourds aux energies intermediaires.

  3. Remesas Sur-Sur: Importancia del Corredor Costa Rica-Nicaragua

    OpenAIRE

    Ricardo Monge-González; Oswald Céspedes-Torres; Juan Carlos Vargas-Aguilar

    2009-01-01

    El presente estudio, procura brindar un poco de luz en el campo del impacto de los flujos de remesas en América Latina, al estudiar la importancia relativa del corredor Costa Rica-Nicaragua (sur-sur) mediante el análisis de los resultados de una encuesta estadísticamente representativa a una muestra de hogares nicaragüenses receptores de remesas desde Costa Rica, comisionada por los autores durante el primer semestre del año 2009, así como contrastar estos resultados con aquellos de la litera...

  4. Compact Reactor

    International Nuclear Information System (INIS)

    Weyl's Gauge Principle of 1929 has been used to establish Weyl's Quantum Principle (WQP) that requires that the Weyl scale factor should be unity. It has been shown that the WQP requires the following: quantum mechanics must be used to determine system states; the electrostatic potential must be non-singular and quantified; interactions between particles with different electric charges (i.e. electron and proton) do not obey Newton's Third Law at sub-nuclear separations, and nuclear particles may be much different than expected using the standard model. The above WQP requirements lead to a potential fusion reactor wherein deuterium nuclei are preferentially fused into helium nuclei. Because the deuterium nuclei are preferentially fused into helium nuclei at temperatures and energies lower than specified by the standard model there is no harmful radiation as a byproduct of this fusion process. Therefore, a reactor using this reaction does not need any shielding to contain such radiation. The energy released from each reaction and the absence of shielding makes the deuterium-plus-deuterium-to-helium (DDH) reactor very compact when compared to other reactors, both fission and fusion types. Moreover, the potential energy output per reactor weight and the absence of harmful radiation makes the DDH reactor an ideal candidate for space power. The logic is summarized by which the WQP requires the above conditions that make the prediction of DDH possible. The details of the DDH reaction will be presented along with the specifics of why the DDH reactor may be made to cause two deuterium nuclei to preferentially fuse to a helium nucleus. The presentation will also indicate the calculations needed to predict the reactor temperature as a function of fuel loading, reactor size, and desired output and will include the progress achieved to date

  5. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  6. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  7. Chemical Reactors.

    Science.gov (United States)

    Kenney, C. N.

    1980-01-01

    Describes a course, including content, reading list, and presentation on chemical reactors at Cambridge University, England. A brief comparison of chemical engineering education between the United States and England is also given. (JN)

  8. NUCLEAR REACTOR

    Science.gov (United States)

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  9. Nuclear reactor

    International Nuclear Information System (INIS)

    In order to reduce neutron embrittlement of the pressue vessel of an LWR, blanked off elements are fitted at the edge of the reactor core, with the same dimensions as the fuel elements. They are parallel to each other, and to the edge of the reactor taking the place of fuel rods, and are plates of neutron-absorbing material (stainless steel, boron steel, borated Al). (HP)

  10. COMPTABILITÉ BASÉE SUR LA CONNAISSANCE

    OpenAIRE

    Tugui, Alexandru

    2005-01-01

    International audience Dans la future société basée sur la connaissance, les connaissances constitueront des pièces de travails habituées qui seront manipulées très facilement. La comptabilité ne fait pas exception à cette pratique et aboutira à cet état suite à la standardisation des procédures, des pratiques et des méthodes comptables, au traitement intégré des données de l'entreprise, du niveau de plus en plus performant des technologies de communication, des réalisations du domaine de ...

  11. Sur8 mediates tumorigenesis and metastasis in colorectal cancer

    Science.gov (United States)

    Lee, Young-Mi; Kaduwal, Saluja; Lee, Kug Hwa; Park, Jong-Chan; Jeong, Woo-Jeong; Choi, Kang-Yell

    2016-01-01

    Sur8, a scaffold protein of the Ras pathway, interacts with Ras and Raf and modulates the Ras-extracellular signal-regulated kinase (ERK) pathway. Here we show that Sur8 is overexpressed in established human colorectal cancer (CRC) cell lines and CRC patient tissues. Moreover, Sur8 expression is increased during liver metastasis in CRC patients. Sur8 knockdown decreases ERK and Akt activities in CRC cell lines, regardless of their K-Ras, B-Raf or PI3K mutation status. Overexpression or knockdown of Sur8 increases or decreases, respectively, the proliferation or transformation of CRC cell lines. Sur8 knockdown attenuates the migration and invasion of HCT116 CRC cells. Subcutaneous or orthotopic injection of HCT116 cells harboring a doxycycline (Dox)-mediated Sur8 knockdown system in nude mice resulted in decreased tumorigenic potential and inhibited the liver metastatic potential of HCT116 cells. Taken together, our data support the role of Sur8 as a promoter of tumorigenesis and liver metastasis in CRC through its modulation of the Ras-ERK and PI3K-Akt signaling pathways. PMID:27469030

  12. Recherche sur les Juifs du Maroc

    OpenAIRE

    Michel Abitbol

    2008-01-01

    Le Centre de recherche sur les Juifs du Maroc (CRJM) a été créé, en mai 1994, à Paris à l’initiative de Monsieur Robert Assaraf, après de longs mois de concertations, de discussions et d’études préalables. Il s’agit d’une institution internationale, à vocation universitaire et scientifique qui s’est fixé pour but essentiel de développer, par tous les moyens, la connaissance et l’étude de l’histoire des Juifs du Maroc. Une histoire trois fois millénaire qui remonte à la destruction du premier ...

  13. Enquête LMD sur le web

    Directory of Open Access Journals (Sweden)

    Colette Cauvin

    2003-02-01

    Full Text Available En relation avec la mise en place des LMD, une enquête sur le web a été entreprise en janvier 2003 afin de connaître les orientations et les choix des diverses universités délivrant des diplômes de géographie ou d’une discipline similaire. Grâce à R. Schlumberger (laboratoire Image et Ville de nombreux sites ont été consultés et analysés. Qu’elle en soit remerciée.   Cependant, la lecture des informations a été plus malaisée que prévue en raison, en particulier, de la multiplicité des langue...

  14. Retour sur l'Etat local

    OpenAIRE

    REIGNER, H; Epstein, R.

    2011-01-01

    L'Etat local, dont l'étude a été à l'origine de travaux fondateurs sur le système politico-administratif, ne figure plus parmi les objets privilégiés de la science politique française. Ce constat renvoie moins à un désintérêt des politistes qu'à la fragmentation de leurs approches et à la dilution de l'objet qui en découle. L'hypothèse de cette Section Thématique est que l'Etat local demeure un objet fécond pour la recherche, permettant en particulier d'alimenter et d'articuler deux controver...

  15. Sonochemical Reactors.

    Science.gov (United States)

    Gogate, Parag R; Patil, Pankaj N

    2016-10-01

    Sonochemical reactors are based on the generation of cavitational events using ultrasound and offer immense potential for the intensification of physical and chemical processing applications. The present work presents a critical analysis of the underlying mechanisms for intensification, available reactor configurations and overview of the different applications exploited successfully, though mostly at laboratory scales. Guidelines have also been presented for optimum selection of the important operating parameters (frequency and intensity of irradiation, temperature and liquid physicochemical properties) as well as the geometric parameters (type of reactor configuration and the number/position of the transducers) so as to maximize the process intensification benefits. The key areas for future work so as to transform the successful technique at laboratory/pilot scale into commercial technology have also been discussed. Overall, it has been established that there is immense potential for sonochemical reactors for process intensification leading to greener processing and economic benefits. Combined efforts from a wide range of disciplines such as material science, physics, chemistry and chemical engineers are required to harness the benefits at commercial scale operation.

  16. Epistemologías del Sur

    Directory of Open Access Journals (Sweden)

    Boaventura de Sousa Santos

    2011-01-01

    Full Text Available Es un hecho irreversible que el logos eurocéntrico ha implosionado en sus propias fuentes de desarrollo político y económico. El peligro de esta crisis es total porque abarca su hegemonía y a la humanidad y a la naturaleza. ¿De qué alternativas disponemos para superar este fin de milenio y su hecatombe? Es evidente que estamos viviendo los "tiempos póstumos" o de "filosofía finisecular" de una Modernidad que luce, por otra parte, rebasable desde otra episteme histórico-cultural que reconozca la relación ecosistema del hombre en el conjunto de la diversidad existencial de los seres vivos que pueblan este planeta. Esta otra epistemología que tiene su génesis en la Teoría Crítica y se recrea enAmérica Latina, desde el Sur, se asume desde la praxis de un logos emancipador que fractura los límites hegemónicos del "capitalismo sin fin" y del "colonialismo sin fin", ya que hace posible recuperar desde la "sociología de las emergencias", la presencia de los pueblos milenarios que han logrado la recreación de su habitat a través de una relación simbiótica directa, con los ciclos o procesos de génesis y muerte de la Madre Tierra (Pachamama. La sabiduría ancestral que porta el pensamiento de estos pueblos originarios, expresados por sus tradiciones, ritos, magias, hasta sus representaciones antropomórficas de la realidad, son síntomas de que el ocaso de la civilización, nomuere con Occidente, sino que renace desde el Sur con el "Sumak Kawsay".

  17. Nitrogen treatment from digestat of biogas plants in a moving bed biofilm reactor; Projet de recherche pilote. Traitement de l'azote des digestats issus d'installations de biogaz au moyen d'un reacteur a biofilm sur support mobile - Rapport final

    Energy Technology Data Exchange (ETDEWEB)

    Roches, S.; Bakx, T.; Membrez, Y. [EREP SA, Aclens (Switzerland); Baggenstos, M.; Chappaz, A. [Wabag Water Technology Ltd, Winterthur (Switzerland); Holliger, Ch. [Swiss Federal Institute of Technology, EPFL, Laboratory for Environmental Biotechnology, Lausanne (Switzerland)

    2010-11-15

    Ammonia emissions are a source for polluting ecosystems, causing in particular acidification and eutrophication of the affected areas. In Switzerland 90% of the atmospheric ammonia emissions are due to agriculture, mostly during storage and use of animal manures and slurries. Anaerobic digestion of these manures and slurries produces renewable energy and stabilises the agricultural effluents. However, it does not solve the ammonia problem; on the contrary, it releases an additional amount of ammonium while mineralizing a large part of the organic nitrogen. A previous study dealing with the biological removal of ammonia from digested manures was conducted at the Laboratory of Environmental Biotechnology, EPFL. It has shown that it is possible to obtain simultaneously a conversion of ammonium and nitrogen removal in a same continuously aerated aerobic reactor, using a mobile support for fixing the biomass. The obtained efficiencies were high, with 90% of the ammonium being converted of which 80% as N{sub 2}-gas. This current study proposed to test the process at pilot scale, to evaluate the transferability of the technique to a full-scale application and to determine the operating parameter. The results are as follows: (i) It is possible to obtain high nitrification and denitrification rates without pre-treating the digestat or adding a carbon source; (ii) Biochemical reactions are extremely sensitive to the oxygenation rate, which in turn is very sensitive to the liquid characteristics in the reactor, such as the dry matter content. It fairly complicates maintaining simultaneous nitrification and denitrification; (iii) At a minimum hydraulic residence time of 4 days, over 90% of the ammonium is converted and 85% of it is removed. These results provide the basic design parameters for a full-scale installation. Depending on the performance desired, it would have a volume going from 30 to 60 m{sup 3} for a 400 m{sup 3} digester. The aeration rate would be between 300

  18. Assessment of a dynamic model of a pant-legged circulating fluidized bed reactor on Provence 250 MWE plant; Evaluation d`une modelisation dynamique d`un foyer de LFC a deux jambes sur la centrale LFC 250 MWE de Provence

    Energy Technology Data Exchange (ETDEWEB)

    Montat, D.

    1996-12-31

    A demonstration dynamic model of the pant-legged furnace of Provence CFB power plant was programmed. It enables characterization of the dynamic behaviour of the gas-particle flow in the furnace: memory effect, risk to half-leg drainage, dissymmetrical air injection effect. As to quality, there is good agreement between the model and measurements performed at the Provence plant during start-up tests (operating conditions differing from the initial conditions). From the quantity standpoint, after adaptation of a single adjustment parameter, the results are conclusive, but not totally adequate: after 1 hour, the model deviates from the measured values by more than 10 %. In its present state, the model provides, at the least, valuable assistance for interpretation of the dynamic behaviour of the Provence-reactor. Improving the model performances would entail adapting the flow laws to the Provence plant. This would require a systematic study of several operation points. Upgrading of the model could be obtained by its integration in the dynamic model of the Provence plant using the SICLE solver, or its programming using LEGO solver, or its integration in the plant control system. (author) 7 refs.

  19. 基于MATLAB7.0的无极绳绞车制动器碟形弹簧优化设计%Optimum Design of Belleville Springs of Brake on the Endless Rope Winch with MATLAB7.0

    Institute of Scientific and Technical Information of China (English)

    王成锋; 侯友夫; 胡志鹏

    2012-01-01

    The optimum design model of the belleville spring which is used in the hydraulic cylinder of safety brake of endless rope winch was established. To obtain the most minor volume and quality, the outside diameter, inside diameter, height, thickness, number flats as a group of design variable was taken for the process of optimized design using the function of MATLAB7. 0. The optimi-zation result shows that the method is simple and feasible.%建立了无极绳绞车安全制动器液压缸中的碟形弹簧优化设计模型.以体积、质量最小为目标,取碟簧的外径、内径、自由高度、厚度和组合片数为设计变量,运用MATLAB7.0软件中的fmincon函数对其进行了优化.优化结果表明,该方法简便可行.

  20. Reactor container

    International Nuclear Information System (INIS)

    A reactor container has a suppression chamber partitioned by concrete side walls, a reactor pedestal and a diaphragm floor. A plurality of partitioning walls are disposed in circumferential direction each at an interval inside the suppression chamber, so that independent chambers in a state being divided into plurality are formed inside the suppression chamber. The partition walls are formed from the bottom portion of the suppression chamber up to the diaphragm floor to isolate pool water in a divided state. Operation platforms are formed above the suppression chamber and connected to an access port. Upon conducting maintenance, inspection or repairing, a pump is disposed in the independent chamber to transfer pool water therein to one or a plurality of other independent chambers to make it vacant. (I.N.)

  1. NEUTRONIC REACTORS

    Science.gov (United States)

    Anderson, J.B.

    1960-01-01

    A reactor is described which comprises a tank, a plurality of coaxial steel sleeves in the tank, a mass of water in the tank, and wire grids in abutting relationship within a plurality of elongated parallel channels within the steel sleeves, the wire being provided with a plurality of bends in the same plane forming adjacent parallel sections between bends, and the sections of adjacent grids being normally disposed relative to each other.

  2. Modelling the cracking of pressurised water reactor fuel pellets and its consequences on the mechanical behaviour of the fuel rod; Etude de l'impact de la fissuration des combustibles nucleaires oxyde sur le comportement normal et incidentel des crayons combustible

    Energy Technology Data Exchange (ETDEWEB)

    Helfer, Th

    2006-03-15

    This thesis aims to model the cracking of pressurised water reactor fuel pellets and its consequences on the mechanical behaviour of the fuel rod. Fuel cracking has two main consequences. It relieves the stress in the pellet, upon which the majority of the mechanical and physico-chemical phenomena are dependent. It also leads to pellet fragmentation. Taking fuel cracking into account is therefore necessary to adequately predict the mechanical loading of the cladding during the course of an irradiation. The local approach to fracture was chosen to describe fuel pellet cracking. Practical considerations brought us to favour a quasi-static description of fuel cracking by means of a local damage models. These models describe the appearance of cracks by a local loss of rigidity of the material. Such a description leads to numerical difficulties, such as mesh dependency of the results and abrupt changes in the equilibrium state of the mechanical structure during unstable crack propagations. A particular attention was paid to these difficulties because they condition the use of such models in engineering studies. This work was performed within the framework of the ALCYONE fuel performance package developed at CEA/DEC/SESC which relies on the PLEIADES software platform. ALCYONE provides users with various approaches for modelling nuclear fuel behaviour, which differ in terms of the type geometry considered for the fuel rod. A specific model was developed and implemented to describe fuel cracking for each of these approaches. The 2D axisymmetric fuel rod model is the most innovative and was particularly studied. We show that it is able to assess, thanks to an appropriate description of fuel cracking, the main geometrical changes of the fuel rod occurring under normal and off-normal operating conditions. (author)

  3. Quelques commentaires sur les personnages de fiction

    Directory of Open Access Journals (Sweden)

    Umberto Eco

    2010-06-01

    Full Text Available L’auteur met en place des observations et développe des analyses sur le statut des personnages de fiction, mettant à contribution les ressources de l’histoire, de la littérature, de la sémiotique, de la logique et de la narratologie. De quelle vie particulière vivent les personnages de roman, qui fait que nous sommes capables de les tenir pour plus réels que des personnages réels, et que nous sommes enclins à éprouver les sentiments qu’ils éprouvent, même si nous savons qu’ils n’existent pas ? Comment ces personnages de fiction existent-ils, selon quelle « partition » leur existence se développe-t-elle au point d’interférer avec la nôtre ? L’interrogation porte sur la nature de ce flux émotionnel qui s’écoule du lecteur vers les personnages de fiction et les investit de valeur, sur ce qui se projette de la vie vers le roman, entraînant avec lui le lecteur qui se trouve de la sorte impliqué malgré lui dans l’histoire, et se trouve pris dans le mécanisme de l’identification et de la vie fictive.Some commentaries about fiction charactersPutting into form a number of observations and developing an analysis on the status of fiction characters, the author draws on resources coming from history, literature, semiotic, logic et narration. What is that particular life lived by fiction characters that enable us to consider them as being more real than real characters, and to experience the feelings that they experience, even though we know that they do not exist? How do these characters exist? In other words, according to what “script” does their existence develop to the point of interfering with ours? The questioning centres on the nature of the emotional flux which flows from the reader towards the fictional characters thus giving them value, and on what it is which is projected from real life towards the novel and which is capable of sweeping up the reader who, without having particularly intended to do

  4. Réflexions sur la science contemporaine

    CERN Document Server

    Darriulat, Pierre

    2007-01-01

    L'auteur y brosse à grands traits un tableau de la science contemporaine : réductionnisme, déterminisme, abstraction, méthodes, mécanismes de validation et interactions entre observation et théorie... ainsi qu'un portrait de ses artisans et une critique des stéréotypes les plus courants (philistin, iconoclaste, apprenti sorcier...) L'accent est mis sur le fait que la science, dont une des missions consiste à dénoncer les illusions du sens commun, ne poursuit pas une quête de vérité absolue mais se contente aujourd'hui d'une vérité simplement meilleure que celle d'hier. La circularité de la science lui interdit de répondre à des questions essentielles comme «Pourquoi ce monde plutôt que rien ?» Pour tenter d'y répondre, le physicien Pierre Darriulat entreprend, avec candeur et bienveillance, un voyage chez les philosophes. Comment la métaphysique s'évade-t-elle du cercle ? Quelle connaissance autre que scientifique nous propose-t-elle ? La circularité condamnant la science au silence...

  5. Nuclear research reactors

    International Nuclear Information System (INIS)

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.)

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    A nuclear reactor is described in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assemblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters in the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters in the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance

  7. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  8. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T.; Sahimi, Muhammad; Fayyaz-Najafi, Babak; Harale, Aadesh; Park, Byoung-Gi; Liu, Paul K. T.

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  9. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T. (Inventor); Sahimi, Muhammad (Inventor); Fayyaz-Najafi, Babak (Inventor); Harale, Aadesh (Inventor); Park, Byoung-Gi (Inventor); Liu, Paul K. T. (Inventor)

    2011-01-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-04-15

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

  11. Reactor container

    International Nuclear Information System (INIS)

    Purpose: To prevent shocks exerted on a vent head due to pool-swell caused within a pressure suppression chamber (disposed in a torus configuration around the dry well) upon loss of coolant accident in BWR type reactors. Constitution: The following relationship is established between the volume V (m3) of a dry well and the ruptured opening area A (m2) at the boundary expected upon loss of coolant accident: V >= 30340 (m) x A Then, the volume of the dry well is made larger than the ruptured open area, that is, the steam flow rate of leaking coolants upon loss of coolant accident to decrease the pressure rise in the dry well at the initial state where loss of coolant accident is resulted. Accordingly, the pressure of non-compressive gases jetted out from the lower end of the downcomer to the pool water is decreased to suppress the pool-swell. (Ikeda, J.)

  12. Retour sur la logique de l’usage

    OpenAIRE

    Perriault, Jacques

    2015-01-01

    Publié il y a vingt-cinq ans, l’ouvrage « La logique de l’usage » a connu un succès important dans les recherches portant sur les technologies de l’information et de la communication. Néanmoins, ce succès s’est souvent traduit par une assimilation à la sociologie des usages, dont l’ouvrage se distingue pourtant fortement. L’entretien, reposant sur le travail de retour sur les textes majeurs des SIC s’étant intéressés à la technique entrepris dans le séminaire Usages des Dispositifs Sociotechn...

  13. Sur les Ecrits de Jean Carbonnier (1908-2003

    Directory of Open Access Journals (Sweden)

    Robert Pageard

    2009-09-01

    Full Text Available Cette centaine de textes divers, présentés et commentés par une équipe de juristes, d’historiens, de sociologues ou d’anthropologues, donne une très vivante vision de la personnalité et des activités d’un penseur qui joua un rôle important dans l’enseignement et l’ évolution de la seconde moitié du XXe siècle.Tout est dit dans cet ouvrage sur l’exceptionnelle érudition de Jean Carbonnier en maints domaines, sur l’élégance et la finesse de sa langue, sur la clarté de son expression. Cette clar...

  14. Sur le concept d’engagement

    Directory of Open Access Journals (Sweden)

    Howard S. Becker

    2006-10-01

    Full Text Available Le terme « engagement » connaît un succès grandissant dans les débats sociologiques. Dans ce texte, l’auteur examine les utilisations du concept d'engagement afin de comprendre les raisons de sa popularité grandissante, il signale la nature d'un des mécanismes sociaux auquel le terme se réfère implicitement, et développe une théorie embryonnaire des conditions et des processus sociaux impliqués dans le fonctionnement de ce mécanisme. Étant donné la variété sémantique du terme, il s'avère infructueux de spéculer sur son « véritable » sens. Une des images évoquées par « l'engagement » a été retenue pour en préciser la signification.On the Concept of CommitmentThe term "commitment" is experiencing a growing success in sociological debates. In this article, the author examines the uses of the concept of commitment in order to understand the reasons for its growing popularity. He also points out the nature of one of the social mechanisms to which the term implicitly refers, and he develops a preliminary theory of the social conditions and processes implied in the functioning of this mechanism. Given the semantic variety of the term, it proves useless to speculate on its “true” meaning. In order to clarify the meaning of the term, the author adopts one of the images evoked by “commitment”.Sobre el concepto de compromisoEl término “compromiso” goza de un éxito creciente en los debates sociológicos. En este texto el autor analiza las utilizaciones de este concepto con el fin de comprender las razones de esta creciente popularidad e indica la naturaleza de uno de los mecanismos sociales indicados por ese término, desarrollando seguidamente una teoría embrionaria de las condiciones y de los procesos sociales inherentes a este mecanismo. Teniendo en cuenta la variedad semántica del término es inútil especular acerca de su “verdadero” significado. Con el fin de precisar su significado, el autor

  15. La fachada sur en clima mediterráneo

    OpenAIRE

    Soro Espín, Mikel

    2013-01-01

    Esta tesina investiga la fachada Sur del clima mediterráneo y los elementos constructivos flexibles que hacen que esta fachada tenga un correcto funcionamiento térmico durante los diferentes periodos climáticos del año. Concretamente, la tesina ha centrado la investigación en la fachada Sur de edificios residenciales plurifamiliares del clima Mediterráneo. Se ha definido la función térmica de la fachada, sus requerimientos térmicos en diferentes periodos del clima Mediterráneo ...

  16. Finding the SurPriSe: A Case Study of a Faculty Learning Community

    Science.gov (United States)

    Michel, Roberta M.

    2014-01-01

    This article details a faculty learning community (FLC) that started in 2009 on the campus of a Midwestern University and has evolved into an interdisciplinary research, teaching and social community of practice and learning called SurPriSe. SurPriSe is an acronym that reflects the interest area of the FLC; Sur for surveillance, Pri for privacy,…

  17. Remesas internacionales sur-sur y norte-sur en Paraguay: patrones sociodemográficos, destino de los fondos y medios de circulación

    Directory of Open Access Journals (Sweden)

    Pablo Sebastián Gómez

    2016-01-01

    Full Text Available El análisis de las remesas internacionales en los países receptores es un tema ampliamente debatido en la literatura especializada. Sin embargo, en las diferentes perspectivas analíticas y metodológicas no hay consenso sobre la dirección, magnitud e implicancias de estos procesos. Este artículo examina evidencia empírica con base en microdatos de la Encuesta Permanente de Hogares de Paraguay. En primer lugar, se analizan de manera comparativa los patrones sociodemográficos de los hogares receptores del sur y del norte, y de los no perceptores. En segundo lugar, se detallan los mecanismos de circulación y usos de las remesas internacionales en los diferentes circuitos migratorios. Los resultados obtenidos destacan las especificidades de los macrosistemas migratorios vinculados al sur y al norte globales.

  18. Seismic behaviour of gas cooled reactor components

    International Nuclear Information System (INIS)

    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

  19. Research Nuclear Reactors

    International Nuclear Information System (INIS)

    Published in English and in French, this large report first proposes an overview of the use and history of research nuclear reactors. It discusses their definition, and presents the various types of research reactors which can be either related to nuclear power (critical mock-ups, material test reactors, safety test reactors, training reactors, prototypes), or to research (basic research, industry, health), or to specific particle physics phenomena (neutron diffraction, isotope production, neutron activation, neutron radiography, semiconductor doping). It reports the history of the French research reactors by distinguishing the first atomic pile (ZOE), and the activities and achievements during the fifties, the sixties and the seventies. It also addresses the development of instrumentation for research reactors (neutron, thermal, mechanical and fission gas release measurements). The other parts of the report concern the validation of neutronics calculations for different reactors (the EOLE water critical mock-up, the MASURCA air critical mock-up dedicated to fast neutron reactor study, the MINERVE water critical mock-up, the CALIBAN pulsed research reactor), the testing of materials under irradiation (OSIRIS reactor, laboratories associated with research reactors, the Jules Horowitz reactor and its experimental programs and related devices, irradiation of materials with ion beams), the investigation of accident situations (on the CABRI, Phebus, Silene and Jules Horowitz reactors). The last part proposes a worldwide overview of research reactors

  20. 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.

  1. Influence de la Chine sur la culture francaise(1)

    Institute of Scientific and Technical Information of China (English)

    SHENDali

    2004-01-01

    I1 serait présomptueux de prétendre que la Chine a eu une influence déterminante sur certains aspects de la culture francaise, tant les civilisations des deux pays, s'avèrent différentes. Par ailleurs, au contraire de l'Europe oc-

  2. Reactor Physics Training

    International Nuclear Information System (INIS)

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  3. Safeguarding research reactors

    International Nuclear Information System (INIS)

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  4. 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.

  5. 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.

  6. 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.

  7. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  8. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

  9. Reactor System Design

    International Nuclear Information System (INIS)

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  10. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kawakami, Hiroto

    1995-02-07

    A reactor container of the present invention has a structure that the reactor container is entirely at the same temperature as that at the inlet of the reactor and, a hot pool is incorporated therein, and the reactor container has is entirely at the same temperature and has substantially uniform temperature follow-up property transiently. Namely, if the temperature at the inlet of the reactor core changes, the temperature of the entire reactor container changes following this change, but no great temperature gradient is caused in the axial direction and no great heat stresses due to axial temperature distribution is caused. Occurrence of thermal stresses caused by the axial temperature distribution can be suppressed to improve the reliability of the reactor container. In addition, since the laying of the reactor inlet pipelines over the inside of the reactor is eliminated, the reactor container is made compact and the heat shielding structures above the reactor and a protection structure of container walls are simplified. Further, secondary coolants are filled to the outside of the reactor container to simplify the shieldings. The combined effects described above can improve economical property and reliability. (N.H.).

  11. Fossil nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Maurette, M.

    1976-01-01

    The discussion of fossil nuclear reactors (the Oklo phenomenon) covers the earth science background, neutron-induced isotopes and reactor operating conditions, radiation-damage studies, and reactor modeling. In conclusion possible future studies are suggested and the significance of the data obtained in past studies is summarized. (JSR)

  12. Sur le nombre de points rationnels des variétés abéliennes et des Jacobiennes sur les corps finis

    DEFF Research Database (Denmark)

    Aubry, Yves; Haloui, Safia; Lachaud, Gilles

    2012-01-01

    Nous établissons de nouvelles majorations et minorations pour le nombre de points rationnels des variétés abéliennes et des Jacobiennes sur un corps fini. Nous déterminons de plus les nombres maximum et minimum de points rationnels des surfaces Jacobiennes sur un corps fini donné. We give upper a...

  13. Effet du sentiment de discrimination sur les trajectoires professionnelles

    OpenAIRE

    Joseph, Olivier; Lemière, Séverine; Lizé, Laurence; Rousset, Patrick

    2010-01-01

    Cette recherche porte sur les individus qui estiment avoir été victimes de discrimination, c'est-à-dire avoir subi un traitement inégal, de manière intentionnelle ou non, en raison de leur origine étrangère et/ou de leur couleur de peau. L'objectif est de s'intéresser au sentiment de discrimination et de chercher à évaluer son effet sur les parcours professionnels sept ans après la sortie du système éducatif. A partir de l'enquête Génération 98 du Céreq à 7 ans, nous avons utilisé la méthode ...

  14. Science et débat public sur le vivant

    Directory of Open Access Journals (Sweden)

    Piron Florence

    2015-01-01

    Full Text Available Quels sont les repères éthiques et politiques que les sociétés se donnent pour respecter la vie et le vivant selon leur culture ? D’où viennent les débats et les dissensus? Au-delà des débats de société suscités par le vivant aujourd’hui, il est essentiel de mettre au jour les présupposés épistémologiques qui, en plus des politiques scientifiques, orientent les recherches sur le vivant qui, ensuite, sont mobilisées comme moyen de légitimation des arguments dans ces débats. La science apparaît alors comme une institution non neutre, inscrite dans la culture, qui influence les débats publics sur le vivant, au lieu de seulement les éclairer.

  15. Etude des effets du martelage repetitif sur les contraintes residuelles

    Science.gov (United States)

    Hacini, Lyes

    L'assemblage par soudage peut engendrer des contraintes residuelles. Ces contraintes provoquent des fissurations prematurees et un raccourcissement de la duree de vie des composants. Dans ce contexte, le martelage robotise est utilise pour relaxer ces contraintes residuelles. Trois volets sont presentes: le premier est l'evaluation des effets des impacts unitaires repetes sur le champ de contraintes developpe dans des plaques d'acier inoxydable austenitique 304L vierges ou contenant des contraintes residuelles initiales. Dans la deuxieme partie de ce projet, le martelage est applique grace au robot SCOMPI. Les contraintes residuelles induites et relaxees par martelage sont ensuite mesurees par la methode des contours, qui a ete adaptee a cet effet. Dans la troisieme partie, le martelage est modelise par la methode des elements finis. Un modele axisymetrique developpe grace au logiciel ANSYS permet de simuler des impacts repetes d'un marteau elastique sur une plaque ayant un comportement elastoplastique.

  16. Optimisation Robuste du Routage IP avec Incertitude sur la Demande

    OpenAIRE

    Zied Ben Hamouda, Mohamed; Brun, Olivier; Garcia, Jean-Marie

    2010-01-01

    International audience Nous étudions le problème d'optimisation des métriques IP dans les réseaux de télécommunications où la demande est incertaine. Nous présentons une heuristique basée sur les techniques de recherche locale pour résoudre ce problème.

  17. Bottom-up Budgeting FY 2015 Assessment: Camarines Sur

    OpenAIRE

    Maramot, Joyce Anne; Yasay, Donald B.; de Guzman, Reinier

    2015-01-01

    Bottom-up budgeting (BUB) is an adaptation of the participatory budgeting model in identifying and providing solutions to poverty at the municipal/city level. Leaders of civil society organizations engage with LGU officials in formulating a poverty alleviation plan to be considered in preparing the budget of national agencies the following fiscal year. This paper reports on how the guideline was implemented in three municipalities in Camarines Sur. The study then presents suggestions and reco...

  18. 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.

  19. Recherches sur la flore pliocène de Java

    NARCIS (Netherlands)

    Crié, M.L.

    1888-01-01

    En publiant ces premières recherches sur les plantes pliocènes de Java, c’est un plaisir pour moi de remercier le savant directeur du musée géologique de Leyde, monsieur K. Martin, qui m’a fait l’honneur de m’en confier l’étude. Un tel sujet ne pouvait être traité prématurément, et j’ai dû recherche

  20. 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...

  1. 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 ...

  2. Nuclear reactor repairing device

    International Nuclear Information System (INIS)

    Purpose: To enable free repairing of an arbitrary position in an LMFBR reactor. Constitution: A laser light emitted from a laser oscillator installed out of a nuclear reactor is guided into a portion to be repaired in the reactor by using a reflecting mirror, thereby welding or cutting it. The guidance of the laser out of the reactor into the reactor is performed by an extension tube depending into a through hole of a rotary plug, and the guidance of the laser light into a portion to be repaired is performed by the transmitting and condensing action of the reflecting mirror. (Kamimura, M.)

  3. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  4. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  5. Spinning fluids reactor

    Science.gov (United States)

    Miller, Jan D; Hupka, Jan; Aranowski, Robert

    2012-11-20

    A spinning fluids reactor, includes a reactor body (24) having a circular cross-section and a fluid contactor screen (26) within the reactor body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the reactor body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the reactor body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the reactor body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the reactor body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.

  6. 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

  7. Langage du corps, corps du langage, sur une application wüsterienne

    OpenAIRE

    Narcis Zărnescu

    2008-01-01

    Les recherches sur le lexique, en particulier dans le cadre des pratiques terminologiques, sont soumises à des renouvellements sous l’influence conjointe des domaines théoriques, des développements technologiques et des demandes sociales. Mon texte tente d’aborder ces questions, à partir de points de vue et de compétences diversifiés, axés davantage sur le lexique comme objet théorique et sur les pratiques terminologiques.

  8. Reactor Vessel Surveillance Program for Advanced Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

    2008-10-15

    This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

  9. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

    Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

  10. Multipurpose research reactors

    International Nuclear Information System (INIS)

    The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  11. 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.

  12. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. 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. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  13. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  14. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kanbe, Mitsuru

    1997-04-04

    An LMFBR type reactor comprises a plurality of reactor cores in a reactor container. Namely, a plurality of pot containing vessels are disposed in the reactor vessel and a plurality of reactor cores are formed in a state where an integrated-type fuel assembly is each inserted to a pot, and a coolant pipeline is connected to each of the pot containing-vessel to cool the reactor core respectively. When fuels are exchanged, the integrated-type fuel assembly is taken out together with the pot from the reactor vessel in a state where the integrated-type fuel assembly is immersed in the coolants in the pot as it is. Accordingly, coolants are supplied to each of the pot containing-vessel connected with the coolant pipeline and circulate while cooling the integrated-type fuel assembly for every pot. Then, when the fuels are exchanged, the integrated type fuel assembly is taken out to the outside of the reactor together with the pot by taking up the pot from the pot-containing vessel. Then, neutron economy is improved to thereby improve reactor power and the breeding ratio. (N.H.)

  15. Actualités sur la vitamine D*

    Directory of Open Access Journals (Sweden)

    Souberbielle Jean-Claude

    2014-05-01

    Full Text Available Le déficit et l’insuffisance en vitamine D, définis respectivement par des concentrations sériques de 25 hydroxyvitamine D (25OHD inférieures à 20 ng/ml et entre 20 et 30 ng/ml, sont des situations très fréquentes qui sont associées à une augmentation du risque de développer différentes pathologies, pas seulement osseuses. Les effets d’une supplémentation en vitamine D sur la diminution du risque de fractures et de chutes sont documentés par différentes études d’intervention. Les autres effets potentiels extra-osseux de la vitamine D sont principalement documentés par des études observationnelles et expérimentales. Même s’il n’existe pas encore de consensus sur les besoins en vitamine D, tous les experts s’accordent pour considérer que les AJR (200 UI/J en France sont très insuffisants et doivent être augmentés. Cet article aborde successivement le métabolisme de la vitamine D et ses effets, la définition du statut vitaminique D basée sur la concentration sérique de 25OHD, les indications du dosage de la 25OHD (qui ne doit pas être prescrit à tout le monde et propose des modalités de traitement.

  16. 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...

  17. Zoom on India | Gros plan sur l’Inde

    Directory of Open Access Journals (Sweden)

    2012-05-01

    Full Text Available Indian Energy Production and Consumption (in Million Tonnes of Oil EquivalentProduction et consommation d’énergie en Inde (en millions de tonnes d’équivalent pétroleSource: World Bank, World Bank Development Indicators, 2010.Indian Oil, Gas and Coal Imports (in Million Tonnes of Oil Equivalent, 2008*Importations indiennes de pétrole, de gaz et de charbon (en millions de tonnes d’équivalent pétrole, 2008** 2009 for coal data | 2009 pour les données sur le charbon.Sources: British Petroleum...

  18. Observations sur l’indéterminabilité

    Directory of Open Access Journals (Sweden)

    Narcis Zărnescu

    2009-06-01

    Full Text Available Pour Aristote, une proposition est vraie si elle correspond à un fait. Pour les Stoïciens, un raisonnement est valide si et seulement s’il est conforme à la forme canonique d’un trope. Mais affirmer cela c’était oublier que la vérité résulte toujours d’un processus de recherche, souvent long et complexe, qui repose sur l’interrogation, le questionnement, bref le dialogue. Alors qu’en logique standard, la proposition excluait toute dimension énonciative pour se réduire à un simple porteur de valeur de vérité, en logique dialogique chaque proposition est véritablement une proposition émanant d’un interlocuteur qui s’engage sur elle par un acte d’assertion. De plus, un tel acte de discours prend place dans un jeu dialogique (dialogspiel entre proposant et opposant. Dès lors, chaque proposition prend sens en fonction de son utilisation opératoire dans le jeu dialogique. On ne pense plus en termes d’axiomes, mais de système opératoire. On a là un développement remarquable du paradigme actionnel inauguré notamment par le Frege des Recherches logiques.Notre intention est donc de démontrer comment en théorie standard des modèles la décision sur la valeur de vérité d’un connecteur ou d’une proposition atomique dans un univers de discours donné reste une décision extra-logique. Dès lors une modélisation adéquate de la dimension dialogique de l’indéterminabilité ou de la véridicité consiste à articuler de façon adéquate validité et vérité, cohérence interne du dialogue et sanction attestée de façon externe. L’indéterminabilité, ainsi que la véridicité, sera le résultat d’un accord dialogique qui suppose au niveau interactionnel que les interlocuteurs reconnaissent leur consistance mutuelle et au niveau transactionnel qu’ils acceptent mutuellement le jugement d’un tiers qui atteste de la vérité des propositions atomiques sur le monde en question.

  19. Nollywood llega al Sur de España

    OpenAIRE

    Moral, Marian

    2011-01-01

    Este trabajo se centra en cómo y por qué gentes nigerianas viviendo en las ciudades de Granada y Málaga (Sur de España), simultáneamente distribuyen y consumen Nollywood, proveniente de África. Para ello, se desentraña la naturaleza de esta industria de cine nigeriana, desde el propio contexto africano, hasta su extensión a nivel internacional. Pone especial atención en cómo este fenómeno cultural juega un rol relevante en las identidades de mujeres y hombres en la diáspora. Hay que resaltar ...

  20. Développement professionnel. Variations et usages sur Internet.

    OpenAIRE

    Guy, Daniel; Ortiz, Véronique

    2009-01-01

    La question de départ interroge les variations et usages observables sur l'Internet du concept de « développement professionnel » dans des productions sociales diverses : chartres d'entreprise, offres de service, programmes de formation, articles de presse, textes réglementaires, communications scientifiques… L'objectif opérationnel est de caractériser les univers de référence sémantique des usages et d'analyser leurs correspondances pour mettre à jour l'acception du concept de développement ...

  1. El volcanismo del Terciario superior del sur de Mendoza

    OpenAIRE

    F.E. Nullo; G. C. Stephens; J. Otamendi; P. E. Baldauf

    2002-01-01

    Se describe por primera vez la petrografía y geoquímica de unidades volcánicas terciarias del sur de la provincia de Mendoza. Se analizan la nomenclatura estratigráfica y sus edades, estableciéndose una secuencia de eventos magmáticos ocurridos durante el Neógeno, comenzando con la evolución de un retro-arco, seguido por un arco magmático más joven. Se intenta respetar la nomenclatura estratigráfica existente, sin embargo, la definición de unidades se ha realizado sobre la base de las edades ...

  2. Narrow band noise response of a Belleville spring resonator.

    Science.gov (United States)

    Lyon, Richard H

    2013-09-01

    This study of nonlinear dynamics includes (i) an identification of quasi-steady states of response using equivalent linearization, (ii) the temporal simulation of the system using Heun's time step procedure on time domain analytic signals, and (iii) a laboratory experiment. An attempt has been made to select material and measurement parameters so that nearly the same systems are used and analyzed for all three parts of the study. This study illustrates important features of nonlinear response to narrow band excitation: (a) states of response that the system can acquire with transitions of the system between those states, (b) the interaction between the noise source and the vibrating load in which the source transmits energy to or draws energy from the load as transitions occur; (c) the lag or lead of the system response relative to the source as transitions occur that causes the average frequencies of source and response to differ; and (d) the determination of the state of response (mass or stiffness controlled) by observation of the instantaneous phase of the influence function. These analyses take advantage of the use of time domain analytic signals that have a complementary role to functions that are analytic in the frequency domain.

  3. New package for Belleville spring permits rate change, easy disassembly

    Science.gov (United States)

    Mac Glashan, W. F.

    1964-01-01

    A spring package, with grooves to hold the spring washers at the inner and outer edges, reduces hysteresis to a minimum. Three-segment retainers permit easy disassembly so that the spring rate can be changed.

  4. Test du Module BECKHOFF (BK7420) Entrées/Sorties deportees sur FIPIO de SCHNEIDER

    CERN Document Server

    Palluel, J; CERN. Geneva. AB Department

    2004-01-01

    Cette note présente le test du nouveau coupleur I/O déporté sur FIPIO de Beckhoff référencé BK7420 (voir photo ci-dessous), et notamment son évaluation sur différentes longueurs par rapport à un module semblable de Schneider (Momentum 170 FNT 110 01).

  5. Retour d’expérience sur la co-construction d’un guide sur la gouvernance territoriale

    OpenAIRE

    Maurel, P.; Barbe, E.; Rey-Valette, H.; Chia, E; Soulard, C.; Michel, L.; Pinto, M.

    2014-01-01

    / La gouvernance territoriale est devenue un enjeu majeur et une question centrale pour la mise en oeuvre des politiques publiques. Dans le cadre du programme de recherche en partenariat PSDR, un collectif hybride composé de chercheurs, de professionnels du développement territorial et d’acteurs locaux s’est réuni au sein du projet Gouv.Innov. En s’appuyant sur plusieurs terrains d’étude, ce collectif a progressivement construit une définition de la gouvernance territo...

  6. Retour d’expérience sur la co-construction d’un guide sur la gouvernance territoriale

    OpenAIRE

    Maurel, Pierre; Rey-Valette, Hélène; Chia, Eduardo; Michel, Laura; Pinto, Mathilde; Soulard, Christophe-Toussaint; Barbe, Eric

    2014-01-01

    La gouvernance territoriale est devenue un enjeu majeur et une question centrale pour la mise en oeuvre des politiques publiques. Dans le cadre du programme de recherche en partenariat PSDR, un collectif hybride composé de chercheurs, de professionnels du développement territorial et d’acteurs locaux s’est réuni au sein du projet Gouv.Innov. En s’appuyant sur plusieurs terrains d’étude, ce collectif a progressivement construit une définition de la gouvernance territoriale ainsi qu’une grille ...

  7. One piece reactor removal

    International Nuclear Information System (INIS)

    Japan Research Reactor No.3 (JRR-3) was the first reactor consisting of 'Japanese-made' components alone except for fuel and heavy water. After reaching its initial critical state in September 1962, JRR-3 had been in operation for 21 years until March 1983. It was decided that the reactor be removed en-bloc in view of the work schedule, cost and management of the reactor following the removal. In the special method developed jointly by the Japanese Atomic Energy Research Institute and Shimizu Construction Co., Ltd., the reactor main unit was cut off from the building by continuous core boring, with its major components bound in the block with biological shield material (heavy concrete), and then conveyed and stored in a large waste store building constructed near the reactor building. Major work processes described in this report include the cutting off, lifting, horizontal conveyance and lowering of the reactor main unit. The removal of the JRR-3 reactor main unit was successfully carried out safely and quickly by the en-block removal method with radiation exposure dose of the workers being kept at a minimum. Thus the high performance of the en-bloc removal method was demonstrated and, in addition, valuable knowhow and other data were obtained from the work. (Nogami, K.)

  8. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  9. Light water reactor program

    Energy Technology Data Exchange (ETDEWEB)

    Franks, S.M.

    1994-12-31

    The US Department of Energy`s Light Water Reactor Program is outlined. The scope of the program consists of: design certification of evolutionary plants; design, development, and design certification of simplified passive plants; first-of-a-kind engineering to achieve commercial standardization; plant lifetime improvement; and advanced reactor severe accident program. These program activities of the Office of Nuclear Energy are discussed.

  10. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 1014 n/cm2/sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

  11. TRIGA research reactors

    International Nuclear Information System (INIS)

    TRIGA (Training, Research, Isotope production, General-Atomic) has become the most used research reactor in the world with 65 units operating in 24 countries. The original patent for TRIGA reactors was registered in 1958. The success of this reactor is due to its inherent level of safety that results from a prompt negative temperature coefficient. Most of the neutron moderation occurs in the nuclear fuel (UZrH) because of the presence of hydrogen atoms, so in case of an increase of fuel temperature, the neutron spectrum becomes harder and neutrons are less likely to fission uranium nuclei and as a consequence the power released decreases. This inherent level of safety has made this reactor fit for training tool in university laboratories. Some recent versions of TRIGA reactors have been designed for medicine and industrial isotope production, for neutron therapy of cancers and for providing a neutron source. (A.C.)

  12. Mirror reactor surface study

    International Nuclear Information System (INIS)

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included

  13. Iris reactor conceptual design

    Energy Technology Data Exchange (ETDEWEB)

    Carelli, M.D.; Conway, L.E.; Petrovic, B.; Paramonov, D.V. [Westinghouse Electric Comp., Pittsburgh, PA (United States); Galvin, M.; Todreas, N.E. [Massachusetts Inst. of Tech., Cambridge, MA (United States); Lombardi, C.V.; Maldari, F.; Ricotti, M.E. [Politecnico di Milano, Milan (Italy); Cinotti, L. [Ansaldo SpA, Genoa (Italy)

    2001-07-01

    IRIS (International Reactor Innovative and Secure) is a modular, integral, light water cooled, low-to-medium power (100-350 MWe) reactor which addresses the requirements defined by the US DOE for Generation IV reactors, i.e., proliferation resistance, enhanced safety, improved economics and fuel cycle sustainability. It relies on the proven technology of light water reactors and features innovative engineering, but it does not require new technology development. This paper discusses the current reference IRIS design, which features a 1000 MWt thermal core with proven 5%-enriched uranium oxide fuel and five-year long straight burn fuel cycle, integral reactor vessel housing helical tube steam generators and immersed spool pumps. Other major contributors to the high level of safety and economic attractiveness are the safety by design and optimized maintenance approaches, which allow elimination of some classes of accidents, lower capital cost, long operating cycle, and high capacity factors. (author)

  14. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.

  15. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  16. Nuclear reactor design

    CERN Document Server

    2014-01-01

    This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

  17. Lignes directrices simplifiées sur les lipides

    Science.gov (United States)

    Allan, G. Michael; Lindblad, Adrienne J.; Comeau, Ann; Coppola, John; Hudson, Brianne; Mannarino, Marco; McMinis, Cindy; Padwal, Raj; Schelstraete, Christine; Zarnke, Kelly; Garrison, Scott; Cotton, Candra; Korownyk, Christina; McCormack, James; Nickel, Sharon; Kolber, Michael R.

    2015-01-01

    Résumé Objectif Produire un guide de pratique clinique comportant une approche simplifiée à la prévention primaire des maladies cardiovasculaires (MCV), en insistant sur l’estimation du risque de MCV et la prise en charge des profils lipidiques à l’intention des cliniciens de soins primaires et leurs équipes; nous avons recherché la contribution de professionnels des soins primaires qui n’avaient que peu ou pas de conflits d’intérêts et nous nous sommes concentrés sur les données probantes de la plus haute qualité accessibles. Méthodes Neuf professionnels de la santé (4 médecins de famille, 2 internistes, 1 infirmière praticienne, 1 infirmière autorisée et 1 pharmacienne) et 1 membre non votant (pharmacienne gestionnaire de projet) formaient le comité principal appelé le Lipid Pathway Committee (le comité). La sélection des membres s’est fondée sur la profession, le milieu de pratique et son emplacement. Les membres ont divulgué tous leurs conflits d’intérêts potentiels ou réels. Le processus d’élaboration des lignes directrices était itératif et s’appuyait sur des affichages en ligne, une révision détaillée des données probantes, des réunions par téléphone et en ligne. Le comité a cerné 12 questions prioritaires à répondre. Le groupe de révision des données probantes a répondu à ces questions. À la suite d’un examen des réponses, les principales recommandations ont été formulées par consensus du comité. Nous avons produit une ébauche des lignes directrices qui a ensuite été peaufinée, distribuée à un groupe de cliniciens (médecins de famille, autres spécialistes, pharmaciens, infirmières et infirmières praticiennes) et à des patients pour obtenir de la rétroaction, la réviser en conséquence et le comité l’a ensuite finalisée. Recommandations Des recommandations sont présentées concernant le dépistage et les analyses, les évaluations du risque, le suivi, de même que le r

  18. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committee on Reactor Physics. (Author)

  19. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1983 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  20. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities conducted in Reactor Engineering Division in fiscal 1975 are summarized in this report. Works in the division are closely related to the development of multi-purpose High-temperature Gas Cooled Reactor, the development of Liquid Metal Fast Breeder Reactor by Power Reactor and Nuclear Fuel Development Corporation, and engineering research of thermonuclear fusion reactor. Many achievements are described concerning nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and activities of the Committee on Reactor Physics. (auth.)

  1. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    The principles of nuclear, thermal and hydraulic performance calculations for water cooled reactors are discussed. The principles are illustrated by describing their implementation in the UKAEA PATRIARCH scheme of computer codes. This material was originally delivered as a course of lectures at the Technical University of Helsinki in Summer of 1969.

  2. Safety of research reactors

    International Nuclear Information System (INIS)

    The number of research reactors that have been constructed worldwide for civilian applications is about 651. Of the reactors constructed, 284 are currently in operation, 258 are shut down and 109 have been decommissioned. More than half of all operating research reactors worldwide are over thirty years old. During this long period of time national priorities have changed. Facility ageing, if not properly managed, has a natural degrading effect. Many research reactors face concerns with the obsolescence of equipment, lack of experimental programmes, lack of funding for operation and maintenance and loss of expertise through ageing and retirement of the staff. Other reactors of the same vintage maintain effective ageing management programmes, conduct active research programmes, develop and retain high calibre personnel and make important contributions to society. Many countries that operate research reactors neither operate nor plan to operate power reactors. In most of these countries there is a tendency not to create a formal regulatory body. A safety committee, not always independent of the operating organization, may be responsible for regulatory oversight. Even in countries with nuclear power plants, a regulatory regime differing from the one used for the power plants may exist. Concern is therefore focused on one tail of a continuous spectrum of operational performance. The IAEA has been sending missions to review the safety of research reactors in Member States since 1972. Some of the reviews have been conducted pursuant to the IAEA' functions and responsibilities regarding research reactors that are operated within the framework of Project and Supply Agreements between Member States and the IAEA. Other reviews have been conducted upon request. All these reviews are conducted following procedures for Integrated Safety Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety

  3. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  4. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1989 (April 1, 1989 - March 31, 1990). One of major Department's programs is the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Development of a high energy proton linear accelerator for the nuclear engineering including is also TRU incineration promoted. Other major tasks of the Department are various basic researches on nuclear data and group constants, theoretical methods and code development, on reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  5. Slurry reactor design studies

    Energy Technology Data Exchange (ETDEWEB)

    Fox, J.M.; Degen, B.D.; Cady, G.; Deslate, F.D.; Summers, R.L. (Bechtel Group, Inc., San Francisco, CA (USA)); Akgerman, A. (Texas A and M Univ., College Station, TX (USA)); Smith, J.M. (California Univ., Davis, CA (USA))

    1990-06-01

    The objective of these studies was to perform a realistic evaluation of the relative costs of tublar-fixed-bed and slurry reactors for methanol, mixed alcohols and Fischer-Tropsch syntheses under conditions where they would realistically be expected to operate. The slurry Fischer-Tropsch reactor was, therefore, operated at low H{sub 2}/CO ratio on gas directly from a Shell gasifier. The fixed-bed reactor was operated on 2.0 H{sub 2}/CO ratio gas after adjustment by shift and CO{sub 2} removal. Every attempt was made to give each reactor the benefit of its optimum design condition and correlations were developed to extend the models beyond the range of the experimental pilot plant data. For the methanol design, comparisons were made for a recycle plant with high methanol yield, this being the standard design condition. It is recognized that this is not necessarily the optimum application for the slurry reactor, which is being proposed for a once-through operation, coproducing methanol and power. Consideration is also given to the applicability of the slurry reactor to mixed alcohols, based on conditions provided by Lurgi for an Octamix{trademark} plant using their standard tubular-fixed reactor technology. 7 figs., 26 tabs.

  6. Test reactor technology

    International Nuclear Information System (INIS)

    The Reactor Development Program created a need for engineering testing of fuels and materials. The Engineering Test Reactors were developed around the world in response to this demand. The design of the test reactors proved to be different from that of power reactors, carrying the fuel elements closer to the threshold of failure, requiring more responsive instrumentation, more rapid control element action, and inherent self-limiting behavior under accident conditions. The design of the experimental facilities to exploit these reactors evolved a new, specialized, branch of engineering, requiring a very high-lvel scientific and engineering team, established a meticulous concern with reliability, the provision for recovery from their own failures, and detailed attention to possible interactions with the test reactors. This paper presents this technology commencing with the Materials Testing Reactor (MTR) through the Fast Flux Test Facility, some of the unique experimental facilities developed to exploit them, but discusses only cursorily the experiments performed, since sample preparation and sample analyses were, and to some extent still are, either classified or proprietary. The Nuclear Engineering literature is filled with this information

  7. Fast Breeder Reactor studies

    International Nuclear Information System (INIS)

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts

  8. Fast Breeder Reactor studies

    Energy Technology Data Exchange (ETDEWEB)

    Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

    1980-07-01

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

  9. Licensed operating reactors

    International Nuclear Information System (INIS)

    The Operating Units Status Report --- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff on NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non- power reactors in the US

  10. nuclear reactor design calculations

    International Nuclear Information System (INIS)

    In this work , the sensitivity of different reactor calculation methods, and the effect of different assumptions and/or approximation are evaluated . A new concept named error map is developed to determine the relative importance of different factors affecting the accuracy of calculations. To achieve this goal a generalized, multigroup, multi dimension code UAR-DEPLETION is developed to calculate the spatial distribution of neutron flux, effective multiplication factor and the spatial composition of a reactor core for a period of time and for specified reactor operating conditions. The code also investigates the fuel management strategies and policies for the entire fuel cycle to meet the constraints of material and operating limitations

  11. Course on reactor physics

    International Nuclear Information System (INIS)

    In Germany only few students graduate in nuclear technology, therefore the NPP operating companies are forced to develop their own education and training concepts. AREVA NP has started together with the Technical University of Dresden a one-week course ''reactor physics'' that includes the know-how of the nuclear power plant construction company. The Technical University of Dresden has the training reactor AKR-2 that is retrofitted by modern digital instrumentation and control technology that allows the practical training of reactor control.

  12. PWR type reactor

    International Nuclear Information System (INIS)

    From a PWR with a primary circuit, consisting of a reactor pressure vessel, a steam generator and a reactor coolant pump, hot coolant is removed by means of an auxiliary system containing h.p. pumps for feeding water into the primary circuit and being connected with a pipe, originating at the upper part, which has got at least one isolating value. This is done by opening an outlet in a part of the auxiliary system that has got a lower pressure than the reactor vessel. Preferably a water jet pump is used for mixing with the water of the auxiliary system. (orig.)

  13. Microfluidic electrochemical reactors

    Science.gov (United States)

    Nuzzo, Ralph G.; Mitrovski, Svetlana M.

    2011-03-22

    A microfluidic electrochemical reactor includes an electrode and one or more microfluidic channels on the electrode, where the microfluidic channels are covered with a membrane containing a gas permeable polymer. The distance between the electrode and the membrane is less than 500 micrometers. The microfluidic electrochemical reactor can provide for increased reaction rates in electrochemical reactions using a gaseous reactant, as compared to conventional electrochemical cells. Microfluidic electrochemical reactors can be incorporated into devices for applications such as fuel cells, electrochemical analysis, microfluidic actuation, pH gradient formation.

  14. SUR1-Associated Mechanisms Are Not Involved in Ischemic Optic Neuropathy 1 Day Post-Injury.

    Science.gov (United States)

    Nicholson, James D; Guo, Yan; Bernstein, Steven L

    2016-01-01

    Ischemia-reperfusion injury after central nervous system (CNS) injury presents a major health care challenge with few promising treatments. Recently, it has become possible to reduce edema after CNS injury by antagonizing a sulfonylurea receptor 1 (SUR1) regulated ion channel expressed after injury. SUR1 upregulation after injury is a necessary precondition for the formation of this channel, and has been implicated in white matter injury after clinical spinal cord trauma. Glibenclamide, an SUR1 antagonist, appears to have neuroprotective effect against cerebral stroke in an open-label small clinical trial and great effectiveness in reducing damage after varied experimental CNS injury models. Despite its importance in CNS injuries, SUR1 upregulation appears to play no part in rodent anterior ischemic optic neuropathy (rAION) injury as tested by real-time PCR and immunohistochemical staining of rAION-injured rat optic nerve (ON). Furthermore, the SUR1 antagonist glibenclamide administered immediately after rAION injury provided no protection to proximal ON microvasculature 1 day post-injury but may reduce optic nerve head edema in a manner unrelated to ON SUR1 expression. Our results suggest that there may be fundamental differences between rAION optic nerve ischemia and other CNS white matter injuries where SUR1 appears to play a role.

  15. SUR1-Associated Mechanisms Are Not Involved in Ischemic Optic Neuropathy 1 Day Post-Injury.

    Science.gov (United States)

    Nicholson, James D; Guo, Yan; Bernstein, Steven L

    2016-01-01

    Ischemia-reperfusion injury after central nervous system (CNS) injury presents a major health care challenge with few promising treatments. Recently, it has become possible to reduce edema after CNS injury by antagonizing a sulfonylurea receptor 1 (SUR1) regulated ion channel expressed after injury. SUR1 upregulation after injury is a necessary precondition for the formation of this channel, and has been implicated in white matter injury after clinical spinal cord trauma. Glibenclamide, an SUR1 antagonist, appears to have neuroprotective effect against cerebral stroke in an open-label small clinical trial and great effectiveness in reducing damage after varied experimental CNS injury models. Despite its importance in CNS injuries, SUR1 upregulation appears to play no part in rodent anterior ischemic optic neuropathy (rAION) injury as tested by real-time PCR and immunohistochemical staining of rAION-injured rat optic nerve (ON). Furthermore, the SUR1 antagonist glibenclamide administered immediately after rAION injury provided no protection to proximal ON microvasculature 1 day post-injury but may reduce optic nerve head edema in a manner unrelated to ON SUR1 expression. Our results suggest that there may be fundamental differences between rAION optic nerve ischemia and other CNS white matter injuries where SUR1 appears to play a role. PMID:27560494

  16. Informations sur les personnages-clés

    OpenAIRE

    Hebbelinck, Thérèse

    2013-01-01

    Personnages-clés Nous proposons ci-dessous non pas des notices biographiques complètes sur les personnages cités mais nous mentionnons les fonctions qui étaient les leurs lors de la controverse du carmel d’Auschwitz. Barnas Thaddée (1944) : moine bénédictin du monastère œcuménique de Chevetogne, il prit une conscience accrue du problème des relations entre juifs et chrétiens à l’occasion de l’affaire du carmel d’Auschwitz. En 1986, il fut l’initiateur d’une importante pétition demandant le dé...

  17. Réflexions sur la nomination des juges

    OpenAIRE

    Masson, Louis; Champagne, Sylvie

    2011-01-01

    Au printemps 2010, le Barreau du Québec a décidé de participer à la réflexion menée par la Commission publique d’enquête sur le processus de nomination des juges du Québec. Il était nécessaire de revoir, après une trentaine d’années, le système québécois, qui a fait ses preuves et donné une magistrature de haute qualité. Pourquoi ? Afin de s’assurer, entre autres, d’augmenter la transparence du processus et de préserver la confiance des citoyens dans notre système de justice. Les auteurs prés...

  18. Commentaires sur la valeur piscicole du Canal de Roubaix (Nord

    Directory of Open Access Journals (Sweden)

    ARRIGNON J.

    1970-10-01

    Full Text Available La population piscicole du Canal de ROUBAIX a été inventoriée par pêche électrique. Trois passages, suivis chacun de l'enlèvement des poissons capturés, ont été opérés dans chacun des trois Secteurs d'inventaire. Le peuplement le plus probable ainsi estimé (par la méthode De Lury,est en rapport avec le degré de pollution du canal. On constate aussi queles poissons se cantonnent le long des berges, sur une largeur de 2 à 3mètres.L'estimation à l'hectare représente donc en réalité le stock d'une zone n'ayant que 25 % de la surface totale du Canal. Les poissons contrôlés sont pour la plupart des poissons de repeuplement.

  19. Sur les chemins des caféiers

    OpenAIRE

    Pinard, Fabrice

    2008-01-01

    Originaire d’Afrique tropicale, le café, plante et boisson, a conquis la planète à partir du xviie siècle. C’est aujourd’hui une des matières premières les plus consommées au monde, encore largement produite, sur un mode traditionnel, par la petite paysannerie du tiers-monde, sous la contrainte de la libéralisation et des aléas du négoce international. Mis en difficulté après des crises récentes, le secteur « café » tente d’évoluer pour s’adapter à une demande moderne tournée vers la qualité....

  20. [Marine algae of Baja California Sur, Mexico: nutritional value].

    Science.gov (United States)

    Carrillo Domínguez, Silvia; Casas Valdez, Margarita; Ramos Ramos, Felipe; Pérez-Gil, Fernando; Sánchez Rodríguez, Ignacio

    2002-12-01

    The Baja California Peninsula is one of the richest regions of seaweed resources in México. The objective of this study was to determine the chemical composition of some marine algae species of Baja California Sur, with an economical potential due to their abundance and distribution, and to promote their use as food for human consumption and animal feeding. The algae studied were Green (Ulva spp., Enteromorpha intestinalis, Caulerpa sertularoides, Bryopsis hypnoides), Red (Laurencia johnstonii, Spyridia filamentosa, Hypnea valentiae) and Brown (Sargassum herporizum, S. sinicola, Padina durvillaei, Hydroclathrus clathrathus, Colpomenia sinuosa). The algae were dried and ground before analysis. In general, the results showed that algae had a protein level less than 11%, except L. johnstonii with 18% and low energy content. The ether extract content was lower than 1%. However, the algae were a good source of carbohydrates and inorganic matter. PMID:12868282

  1. Les filarioses humaines sur le territoire français

    OpenAIRE

    2013-01-01

    1. La filariose lymphatique 1.1. Cycle de la maladie 1.1.1. Agent Sur les territoires français, l’agent est le nématode Wuchereria bancrofti, Onchocercidae, Filarioidea. Mais deux autres espèces de filaires provoquent des filarioses lymphatiques similaires : Brugia malayi, dont l'aire d'extension va de l'Inde et du Sud-Est asiatique à la Corée, et B. timori, limité à quelques îles d'Indonésie. Les filaires mâles de W. bancrofti sont longues de 40 mm et larges de 0,1 mm, les femelles de 80-100...

  2. ``Astrophysique sur Mesure'', E-learning in Astronomy and Astrophysics

    Science.gov (United States)

    Mosser, Benoît; Delsanti, Audrey; Guillaume, Damien; Balança, Christian; Balkowski, Chantal

    2011-06-01

    ``Astrophysique sur Mesure'' (astrophysics made-to-measure) is a set of e-learning programmes started 4 years ago at the Paris Observatory. In order to deliver attractive and efficient programmes, we have added many multimedia tools to usual lectures: animations, Java applets. The programmes are presented on two different platforms. The first one offers the content of all the lectures in free access. A second platform with restricted access is provided to registered students taking part in the e-learning program and benefiting from the help of tutors. The development of these programs helps to increase the sphere of influence of astronomy taught at the Paris Observatory, hence to increase the presence of astronomy in various degree courses. Instead of teaching classical astronomy lectures to a happy few, we can bring astronomy and astrophysics to a wider audience.

  3. Bordeaux parie sur les centres d’appels

    Directory of Open Access Journals (Sweden)

    Gilles Puel

    2003-06-01

    Full Text Available Les acteurs territoriaux de la métropole bordelaise ont parié depuis peu sur le développement des centres d’appels en dépit d’une concurrence de plus en plus vive et planétaire. Les logiques de localisation des entreprises favorisent la métropolisation des téléservices. L’espace métropolitain privilégié par cet aspect de la « nouvelle économie » est en périphérie urbaine dans les zones d’activités à proximité des grands réseaux de communication (rocades, aéroports, etc..

  4. Films nématiques minces sur substrats liquides

    OpenAIRE

    Delabre, Ulysse

    2009-01-01

    Ce travail de thèse analyse l'organisation des films de cristaux liquides nématiques sur substrats liquides (eau et glycérol). Dans ce cas, l'ancrage planaire au niveau du substrat liquide est plus fort que l'ancrage homéotrope à l'interface libre. En dessous d'une épaisseur critique de l'ordre de 0.5-0.6 µm, des stries qui correspondent à une modulation de l'orientation du directeur, apparaissent. La longueur d'onde de ces stries est largement supérieure à l'épaisseur du film. Nous avons ana...

  5. La femme invisible. Sur l’imaginaire du pouvoir politique

    OpenAIRE

    Derville, Grégory; Pionchon, Sylvie

    2008-01-01

    La sous-représentation politique des femmes est souvent mise sur le compte d’une résistance du champ politique à la féminisation. Si un tel sexisme est bien repérable, l’explication de ce phénomène tient surtout à la persistance de représentations sociales très largement diffusées, et qui rendent l’engagement politique au féminin difficile à penser et à admettre pour nombre de citoyens : l’image de la femme comme pivot de l’espace domestique, et plus encore l’image de la politique comme une a...

  6. Le dernier Wittgenstein et le dernier Husserl sur le langage

    Directory of Open Access Journals (Sweden)

    Paul Ricoeur

    2014-07-01

    Full Text Available This article presents an edited version of lectures given by Paul Ricœur at Johns Hopkins University in April 1966. Ricœur offers a comparative analysis of Wittgenstein’s and Husserl’s late works, taking the problem of language as the common ground of investigation for these two central figures of phenomenology and analytic philosophy. Ricœur develops his study in two parts. The first part considers Husserl’s approach to language after the Logical Investigations and concentrates on Formal and Transcendental Logic; leaving a transcendental reflection on language behind it re-examines a phenomenological conception, according to which the sphere of logic is not separable from that of experience. The main focus of the second part is Wittgenstein’s later philosophy as it moved on from the conception of an isomorphic relation between language and the world, as set out in the picture theory in the Tractatus Logico-Philosophicus, to the more pragmatic notion of a language-game in the Philosophical Investigations. In order to get beyond the irrevocable differences between the two philosophies and the unresolved theoretical issues on both sides, Ricœur suggests turning to a semiological paradigm based on the Saussurean distinction between “language” and “speaking.” Keyword: Analytic Philosophy, Husserl, Phenomenology, Semiology, Wittgenstein.  Résumé Cet article est une version éditée de conférences données par Paul Ricœur à la Johns Hopkins University en avril 1966. Ricœur propose une analyse comparée des dernières œuvres de Wittgenstein et Husserl, avec le problème du langage comme sol commun d’investigations pour ces deux figures centrales de la phénoménologie et la philosophie analytique. Cette analyse de Ricœur se joue à travers deux parties. La première partie revient sur l'approche du langage chez Husserl depuis Recherches logiques avec une attention particulière aux développements de Logique formelle et

  7. Observation et analyse d'attaques sur Internet

    OpenAIRE

    Studnia, Ivan

    2011-01-01

    Dans le domaine de la sécurité informatique, un pot de miel est un outil dont le but est d'attirer les attaquants et d'enregistrer leurs activités, afin de mieux connaître leurs techniques et objectifs. Dans cette optique, un pot de miel a été conçu et déployé au LAAS depuis 2006 afin d'observer le trafic malveillant utilisant le protocole ssh sur Internet. De nombreuses analyses ont été réalisées et concernent exclusivement ce site géographique. Pour compléter et enrichir ces analyses, de no...

  8. Un copiste inattendu à Vic-sur-Cère (Cantal

    Directory of Open Access Journals (Sweden)

    Renaud Benoit-Cattin

    2012-02-01

    Full Text Available A Vic-sur-Cère, petit bourg du Cantal, l’hôtel du Pont et du Parc abrite au rez-de-chaussée une salle de restaurant dont les quatre murs sont ornés de dix-sept peintures d’un caractère peu ou prou monumental. Leur hauteur est d’environ 1,50 m, leur largeur variant de 0,6 à 3,5 m. Quatorze d’entre elles ont été exécutées par Antoine Cayrol entre 1909 et 1914, les trois dernières par son petit-fils, Roger Cayrol, en 1954.Le grand-père, Antoine, né en 1864, est élevé à Paris. Après son service m...

  9. Regards sur les cambriolages et les tentatives de cambriolages

    OpenAIRE

    Heinz, Andreas; Steffgen, Georges; Frising, Armande; Reichmann, Liliane

    2015-01-01

    Selon l’enquête sur la sécurité 2013, 10% des ménages ont été victimes d’un cambriolage et 9% ont subi une tentative de cambriolage au cours des 5 dernières années. Il s’agit d’introductions ou de tentatives d’introduction dans leur bien immobilier au Luxembourg ou à l’étranger. La grande majorité des effractions (83%) a eu lieu au Grand-Duché et près d’un tiers (35%) se sont produites entre 22h et 6h. Dans 73% des cas, l’habitation était visée ; les installations extérieures, annexes et abri...

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

    Directory of Open Access Journals (Sweden)

    Kristin M Watts

    Full Text Available BACKGROUND: 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. METHODOLOGY/PRINCIPAL FINDINGS: 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. CONCLUSIONS/SIGNIFICANCE: Our results confirm the core module of E. coli SurA as a potential target for novel anti-infective development.

  11. The Production of the Pastora in Camarines Sur, Philippines

    Directory of Open Access Journals (Sweden)

    JIYE A. MARGATE

    2014-04-01

    Full Text Available The purpose of the study was to document the pastora, a song-dance performance during Christmas season that calls to celebrate the birth of Jesus Christ in two towns of Camarines Sur, Philippines. Specifically, it focused on its production aspect. The categories include: the handing down of oral traditions which influenced the trainers' casting, choreography, costumes, props, musical accompaniment, and performances. The researcher made use of real time data: videotaped pastora dances, observer’s notes, ex post facto data: stimulated recall and interviews. There were similarities and differences in the production of these pastora. Both of the trainers were exposed to this activity at a young age. At present, their granddaughters are members of their respective pastora groups—one way of handing down the oral tradition to the younger generations. Both groups have dresses made of silks and laces. With regard to the choice of colors, Mimay prefers to use light colors such as white, light blue, and pink while Rita favors loud colors such as red, green, and golden yellow. At present they use only one kind of musical instrument in their pastora. Pastora Baao uses a saxophone while pastora Bombon uses a guitar. The trainers also differ in standards for recruiting members. Mimay prefers to invite girls with good singing voice, good dancing ability, and good physical appearance, while Rita believes that willingness is the most important quality of a pastora. The similarities in the production of these pastora reveal the possibility that pastora in Camarines Sur came from one source. The similarities also revealed the impact of pastora in maintaining religiosity and the socio-cultural environment. The differences are influenced by the tradition handed down to trainers, the trainers’ personal outlook, geographical locations, and economic condition.

  12. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    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

  13. NEUTRONIC REACTOR FUEL COMPOSITION

    Science.gov (United States)

    Thurber, W.C.

    1961-01-10

    Uranium-aluminum alloys in which boron is homogeneously dispersed by adding it as a nickel boride are described. These compositions have particular utility as fuels for neutronic reactors, boron being present as a burnable poison.

  14. Pulsed fusion reactors

    International Nuclear Information System (INIS)

    This summer school specialized in examining specific fusion center systems. Papers on scientific feasibility are first presented: confinement of high-beta plasma, liners, plasma focus, compression and heating and the use of high power electron beams for thermonuclear reactors. As for technological feasibility, lectures were on the theta-pinch toroidal reactors, toroidal diffuse pinch, electrical engineering problems in pulsed magnetically confined reactors, neutral gas layer for heat removal, the conceptual design of a series of laser fusion power plants with ''Saturn'', implosion experiments and the problem of the targets, the high brightness lasers for plasma generation, and topping and bottoming cycles. Some problems common to pulsed reactors were examined: energy storage and transfer, thermomechanical and erosion effects in the first wall and blanket, the problems of tritium production, radiation damage and neutron activation in blankets, and the magnetic and inertial confinement

  15. 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.

  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. Reactor Neutrino Spectra

    CERN Document Server

    Hayes, A C

    2016-01-01

    We present a review of the antineutrino spectra emitted from reactors. Knowledge of these and their associated uncertainties are crucial for neutrino oscillation studies. The spectra used to-date have been determined by either conversion of measured electron spectra to antineutrino spectra or by summing over all of the thousands of transitions that makeup the spectra using modern databases as input. The uncertainties in the subdominant corrections to beta-decay plague both methods, and we provide estimates of these uncertainties. Improving on current knowledge of the antineutrino spectra from reactors will require new experiments. Such experiments would also address the so-called reactor neutrino anomaly and the possible origin of the shoulder observed in the antineutrino spectra measured in recent high-statistics reactor neutrino experiments.

  18. Experience with Kamini reactor

    International Nuclear Information System (INIS)

    Kamini is a 233U fuelled, 30 kW(th) research reactor. It is one of the best neutron source facility with a core average flux of 1012 n/cm2/s in IGCAR used for neutron radiography of active and nonradioactive objects, activation analysis and radiation physics research. The core consists of nine plate type fuel elements with a total fuel inventory of 590 g of 233U. Two safety control plates made of cadmium are used for start up and shutdown of the reactor. Three beam tubes, two-thimble irradiation site outside reflector and one irradiation site nearer to the core constitute the testing facilities of Kamini. Kamini attained first criticality on 29th October 96 and nominal power of 30 kW in September 1997. This paper covers the design features of the reactor, irradiation facilities and their utilities and operating experience of the reactor. (author)

  19. Reactor pressure boundary materials

    International Nuclear Information System (INIS)

    With a long-term operation of nuclear power plants, the component materials are degraded under severe reactor conditions such as neutron irradiation, high temperature, high pressure and corrosive environment. It is necessary to establish the reliable and practical technologies for improving and developing the component materials and for evaluating the mechanical properties. Especially, it is very important to investigate the technologies for reactor pressure boundary materials such as reactor vessel and pipings in accordance with their critical roles. Therefore, this study was focused on developing and advancing the microstructural/micro-mechanical evaluation technologies, and on evaluating the neutron irradiation characteristics and radiation effects analysis technology of the reactor pressure boundary materials, and also on establishing a basis of nuclear material property database

  20. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2002-04-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed.

  1. New reactor type proposed

    CERN Multimedia

    2003-01-01

    "Russian scientists at the Research Institute of Nuclear Power Engineering in Moscow are hoping to develop a new reactor that will use lead and bismuth as fuel instead of uranium and plutonium" (1/2 page).

  2. Special lecture on nuclear reactor

    International Nuclear Information System (INIS)

    This book gives a special lecture on nuclear reactor, which is divided into two parts. The first part has explanation on nuclear design of nuclear reactor and analysis of core with theories of integral transports, diffusion Nodal, transports Nodal and Monte Carlo skill parallel computer and nuclear calculation and speciality of transmutation reactor. The second part deals with speciality of nuclear reactor and control with nonlinear stabilization of nuclear reactor, nonlinear control of nuclear reactor, neural network and control of nuclear reactor, control theory of observer and analysis method of Adomian.

  3. Jet-Stirred Reactors

    OpenAIRE

    Herbinet, Olivier; Guillaume, Dayma

    2013-01-01

    The jet-stirred reactor is a type of ideal continuously stirred-tank reactor which is well suited for gas phase kinetic studies. It is mainly used to study the oxidation and the pyrolysis of hydrocarbon and oxygenated fuels. These studies consist in recording the evolution of the conversion of the reactants and of the mole fractions of reaction products as a function of different parameters such as reaction temperature, residence time, pressure and composition of the inlet gas. Gas chromatogr...

  4. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    The operating nuclear reactors were built over a short period: no more than 10 years and today their average age rounds 18 years. EDF (French electricity company) plans to renew its reactor park over a far longer period : 30 years from 2020 to 2050. According to EDF this objective implies 3 constraints: 1) a service life of 50 to 60 years for a significant part of the present operating reactors, 2) to be ready to built a generation 3+ unit in 2020 which infers the third constraint: 3) to launch the construction of an EPR (European pressurized reactor) prototype as soon as possible in order to have it operating in 2010. In this scheme, generation 4 reactor will benefit the feedback experience of generation 3 and will take over in 2030. Economic analysis is an important tool that has been used by the generation 4 international forum to select the likely future reactor systems. This analysis is based on 4 independent criteria: the basic construction cost, the construction time, the operation and maintenance costs and the fuel cycle cost. This analysis leads to the evaluation of the global cost of electricity generation and of the total investment required for each of the reactor system. The former defines the economic competitiveness in a de-regulated energy market while the latter is linked to the financial risk taken by the investor. It appears, within the limits of the assumptions and models used, that generation 4 reactors will be characterized by a better competitiveness and an equivalent financial risk when compared with the previous generation. (A.C.)

  5. OECD Halden reactor project

    International Nuclear Information System (INIS)

    This report summarizes the activities of the OECD Halden Reactor Project for the year 1976. The main items reported on are: a) the process supervision and control which have focused on core monitoring and control, and operator-process communication; b) the fuel performance and safety behavior which have provided data and analytical descriptions of the thermal, mechanical and chemical behavior of fuel under various operating conditions; c) the reactor operations and d) the administration and finance

  6. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    A nuclear reactor fuel element comprising a column of vibration compacted fuel which is retained in consolidated condition by a thimble shaped plug. The plug is wedged into gripping engagement with the wall of the sheath by a wedge. The wedge material has a lower coefficient of expansion than the sheath material so that at reactor operating temperature the retainer can relax sufficient to accommodate thermal expansion of the column of fuel. (author)

  7. Department of Reactor Technology

    DEFF Research Database (Denmark)

    Risø National Laboratory, Roskilde

    The general development of the Department of Reactor Technology at Risø during 1981 is presented, and the activities within the major subject fields are described in some detail. Lists of staff, publications, and computer programs are included.......The general development of the Department of Reactor Technology at Risø during 1981 is presented, and the activities within the major subject fields are described in some detail. Lists of staff, publications, and computer programs are included....

  8. Langage du corps, corps du langage, sur une application wüsterienne

    Directory of Open Access Journals (Sweden)

    Narcis Zărnescu

    2008-06-01

    Full Text Available Les recherches sur le lexique, en particulier dans le cadre des pratiques terminologiques, sont soumises à des renouvellements sous l’influence conjointe des domaines théoriques, des développements technologiques et des demandes sociales. Mon texte tente d’aborder ces questions, à partir de points de vue et de compétences diversifiés, axés davantage sur le lexique comme objet théorique et sur les pratiques terminologiques.

  9. À la découverte des mangroves : regards multiples sur un objet de recherche mouvant

    OpenAIRE

    Cormier-Salem, Marie-Christine

    2013-01-01

    INTRODUCTION Les mangroves ont été découvertes très tardivement sur les plans écologique, esthétique et socio-économique par les observateurs étrangers. Avant le xxe siècle, les documents sur la mangrove sont peu nombreux et ce milieu suscite le plus souvent une réaction de perplexité, méfiance ou répulsion de la part des premiers explorateurs et voyageurs, des missionnaires et des colons mais également des scientifiques. A partir d’une recension bibliographique sur les mangroves et d’un trav...

  10. Observations introductives au colloque sur les transferts électroniques de fonds

    OpenAIRE

    Prüm, André

    2001-01-01

    Le présent ouvrage regroupe les actes de deux colloques sur les transferts électroniques de fonds et sur les aspects juridiques des paiements par WAP. L’idée du premier colloque est venue des nombreuses questions posées sur la sécurité tant technique que juridique des paiements effectués dans le cadre du commerce électronique. Le colloque a volontairement reçu le titre très neutre de « transferts électroniques de fonds » afin de permettre la couverture de sujets très différents sans particuli...

  11. Moon base reactor system

    Science.gov (United States)

    Chavez, H.; Flores, J.; Nguyen, M.; Carsen, K.

    1989-01-01

    The objective of our reactor design is to supply a lunar-based research facility with 20 MW(e). The fundamental layout of this lunar-based system includes the reactor, power conversion devices, and a radiator. The additional aim of this reactor is a longevity of 12 to 15 years. The reactor is a liquid metal fast breeder that has a breeding ratio very close to 1.0. The geometry of the core is cylindrical. The metallic fuel rods are of beryllium oxide enriched with varying degrees of uranium, with a beryllium core reflector. The liquid metal coolant chosen was natural lithium. After the liquid metal coolant leaves the reactor, it goes directly into the power conversion devices. The power conversion devices are Stirling engines. The heated coolant acts as a hot reservoir to the device. It then enters the radiator to be cooled and reenters the Stirling engine acting as a cold reservoir. The engines' operating fluid is helium, a highly conductive gas. These Stirling engines are hermetically sealed. Although natural lithium produces a lower breeding ratio, it does have a larger temperature range than sodium. It is also corrosive to steel. This is why the container material must be carefully chosen. One option is to use an expensive alloy of cerbium and zirconium. The radiator must be made of a highly conductive material whose melting point temperature is not exceeded in the reactor and whose structural strength can withstand meteor showers.

  12. BWR type nuclear reactor

    International Nuclear Information System (INIS)

    Purpose: To simplify the structure of an emergency core cooling system while suppressing the flow out of coolants upon rapture accidents in a coolant recycling device of BWR type reactors. Constitution: Recirculation pumps are located at a position higher than the reactor core in a pressure vessel, and the lower plenum is bisected vertically by a partition plate. Further, a gas-liquid separator is surrounded with a wall and the water level at the outer side of the wall is made higher than the water level in the inside of the wall. In this structure, coolants are introduced from the upper chamber in the lower plenum into the reactor core, and the steams generated in the reactor core are separated in the gas-liquid separator, whereby the separated liquid is introduced as coolants by way of the inner chamber into the lower chamber of the lower plenum and further sent by way of the outer chamber into the reactor core. Consequently, idle rotation of the recycling pumps due to the flow-in of saturated water is prevented and loss of coolants in the reactor core can also be prevented upon raptures in the pipeway and the driving section of the pump connected to the pressure vessel and in the bottom of the pressure vessel. (Horiuchi, T.)

  13. OECD Halden reactor project

    International Nuclear Information System (INIS)

    This is the nineteenth annual Report on the OECD Halden Reactor Project, describing activities at the Project during 1978, the last year of the 1976-1978 Halden Agreement. Work continued in two main fields: test fuel irradiation and fuel research, and computer-based process supervision and control. Project research on water reactor fuel focusses on various aspects of fuel behavior under normal, and off-normal transient conditions. In 1978, participating organisations continued to submit test fuel for irradiation in the Halden boiling heavy-water reactor, in instrumented test assemblies designed and manufactured by the Project. Work included analysis of the impact of fuel design and reactor operating conditions on fuel cladding behavior. Fuel performance modelling included characterization of thermal and mechanical behavior at high burn-up, of fuel failure modes, and improvement of data qualification procedures to reduce and quantify error bands on in-reactor measurements. Instrument development yielded new or improved designs for measuring rod temperature, internal pressure, axial neutron flux shape determination, and for detecting cladding defects. Work on computer-based methods of reactor supervision and control included continued development of a system for predictive core surveillance, and of special mathematical methods for core power distribution control

  14. Reactor physics and economic aspects of the CANDU reactor system

    International Nuclear Information System (INIS)

    A history of the development of the CANDU system is given along with a fairly detailed description of the 600 MW(e) CANDU reactor. Reactor physics calculation methods are described, as well as comparisons between calculated reactor physics parameters and those measured in research and power reactors. An examination of the economics of CANDU in the Ontario Hydro system and a comparison between fossil fuelled and light water reactors is presented. Some physics, economics and resources aspects are given for both low enriched uranium and thorium-fuelled CANDU reactors. Finally the RβD program in Advanced Fuel Cycles is briefly described

  15. Reactor Safety Planning for Prometheus Project, for Naval Reactors Information

    Energy Technology Data Exchange (ETDEWEB)

    P. Delmolino

    2005-05-06

    The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

  16. L’agriculture itinérante sur brûlis, une menace sur la forêt tropicale humide ?

    OpenAIRE

    BAHUCHET, Serge; Betsch, Jean-Marie

    2013-01-01

    L’attitude des scientifiques et des gestionnaires de l’aménagement et de la conservation face à l’agriculture sur brûlis, généralement idéologique, produit un discours ambigu basé sur une image homogène et hors contexte du terme « agriculture itinérante sur brûlis » (en anglais Slash-and-burn, la « défriche-brûlis », permanente, et Shifting cultivation, l’« agriculture itinérante »). L’ambiguïté entretenue entre défrichement permanent et agriculture itinérante occulte la diversité des système...

  17. CCALBATC - bathymetric contours for the central California region between Point Arena and Point Sur.

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — CCALBATC consists of bathymetric contours at 10-m and 50-m intervals for the area offshore of central California between Point Arena to the north and Point Sur to...

  18. L'UOIF:en face de la loi sur la la(i)cité

    Institute of Scientific and Technical Information of China (English)

    田俊雷; 申永杰

    2004-01-01

    La socié té francaise se caracté rise par le principe de la(i)cité. 《 L' affaire du foulard 》 existe en France depuisquelques anné es. Pour 1' instant, la question du voile se focalise sur les lycé es et sur quelques les colle ges. Le voile a causé un dé sé quilibre a 1'é cole. La France est cette socié té multiculturelle. Dans ce dossier, on pré sente la motivation et 1' objet dudossier en introduction. Ensuite dans deux parties distinctes, on dé crit le panorama des articles et on les analyse. Dans une autrepartie, on de veloppe son argumentation sur le sujet, et pour finir, la conclusion sur 1' objet du dossier.

  19. Bibliography on plutonium and its compounds; Bibliographie sur le plutonium et ses composes

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    Collection of bibliographical references on plutonium and its principal compounds from 1942 to end of 1957. (author) [French] Compilation de references bibliographiques sur le plutonium et ses principaux composes de 1942 a fin 1957. (auteur)

  20. Fast breeder reactor research

    International Nuclear Information System (INIS)

    Full text: The meeting was attended by 15 participants from seven countries and two international organizations. The Eighth Annual Meeting of the International Working Group on Fast Reactors (IWGFR) was attended by representatives from France, Fed. Rep. Germany, Italy, Japan, United Kingdom, Union of Soviet Socialist Republics and the United States of America - countries that have made significant progress in developing the technology and physics of sodium cooled fast reactors and have extensive national programmes in this field - as well as by representatives of the Commission of the European Communities and the IAEA. The design of fast-reactor power plants is a more difficult task than developing facilities with thermal reactors. Different reactor kinetics and dynamics, a hard neutron spectrum, larger integral doses of fuel and structural material irradiation, higher core temperatures, the use of an essentially novel coolant, and, as a result of all these factors, the additional reliability and safety requirements that are imposed on the planning and operation of sodium cooled fast reactors - all these factors pose problems that can be solved comprehensively only by countries with a high level of scientific and technical development. The exchange of experience between these countries and their combined efforts in solving the fundamental problems that arise in planning, constructing and operating fast reactors are promoting technical progress and reducing the relative expenditure required for various studies on developing and introducing commercial fast reactors. For this reason, the meeting concentrated on reviewing and discussing national fast reactor programmes. The situation with regard to planning, constructing and operating fast experimental and demonstration reactors in the countries concerned, the experience accumulated in operating them, the difficulties arising during operation and ways of over-coming them, the search for optimal designs for the power

  1. 46 CFR 7.130 - Point Conception, CA to Point Sur, CA.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false Point Conception, CA to Point Sur, CA. 7.130 Section 7.130 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY PROCEDURES APPLICABLE TO THE PUBLIC BOUNDARY LINES Pacific Coast § 7.130 Point Conception, CA to Point Sur, CA. (a) A line drawn from the southernmost extremity of Fossil Point at longitude...

  2. Modelisations des effets de surface sur les jets horizontaux subsoniques d'hydrogene et de methane

    Science.gov (United States)

    Gomez, Luis Fernando

    Le developpement des codes et de normes bases sur une methodologie scientifique requiert la capacite de predire l'etendue inflammable de deversements gazeux d'hydrogene sous differentes conditions. Des etudes anterieures ont deja etabli des modeles bases sur les lois de conservation de la mecanique des fluides basees sur des correlations experimentales qui permettent de predire la decroissance de la concentration et de la vitesse d'un gaz le long de l'axe d'un jet libre vertical. Cette etude s'interesse aux effets de proximite a une surface horizontale parallele sur un jet turbulent. Nous nous interessons a son impact sur l'etendue du champ de la concentration et sur l'enveloppe inflammable en particulier. Cette etude est comparative : l'hydrogene est compare au methane. Ceci permet de degager l'influence des effets de difference de la densite sur le comportement du jet, et de comparer le comportement de l'hydrogene aux correlations experimentales, qui ont ete essentiellement etablies pour le methane. Un modele decrivant l'evolution spatio-temporelle du champ de concentration du gaz dilue est propose, base sur la mecanique des fluides computationnelle. Cette approche permet de varier systematiquement les conditions aux frontieres (proximite du jet a la surface, par exemple) et de connaitre en detail les proprietes de l'ecoulement. Le modele est implemente dans le code de simulations par volumes finis de FLUENT. Les resultats des simulations sont compares avec les lois de similitudes decoulant de la theorie des jets d'ecoulements turbulents libres ainsi qu'avec les resultats experimentaux disponibles. L'effet de la difference des masses molaires des constituantes du jet et des constituantes du milieu de dispersion est egalement etudie dans le contexte du comportement d'echelle de la region developpee du jet.

  3. Des effets du divorce et du non divorce sur les enfants

    OpenAIRE

    Martin, Claude

    2007-01-01

    The issue of divorce and its effets on children has repeatedly been raised since the 18th century. This article synthesize the main findings of current international reserach and condider the effects of non-divorcing for couples who fall out of love and experience conflict. What happens to couples who decide not to divorce for the children's sake. What about the live together apart couples? Cet article propose de revenir sur les principales conclusions des recherches internationales sur le...

  4. Newly expressed SUR1-regulated NCCa-ATP channel mediates cerebral edema after ischemic stroke

    OpenAIRE

    Simard, J. Marc; Chen, Mingkui; Tarasov, Kirill V.; Bhatta, Sergei; Ivanova, Svetlana; Melnitchenko, Ludmila; Tsymbalyuk, Natalya; West, G. Alexander; Gerzanich, Volodymyr

    2006-01-01

    Pathological conditions in the central nervous system, including stroke and trauma, are often exacerbated by cerebral edema. We recently identified a nonselective cation channel, the NCCa-ATP channel, in ischemic astrocytes that is regulated by sulfonylurea receptor 1 (SUR1), is opened by depletion of ATP and, when opened, causes cytotoxic edema. Here, we evaluated involvement of this channel in rodent models of stroke. SUR1 protein and mRNA were newly expressed in ischemic neurons, astrocyte...

  5. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    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 3He, 6Li 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

  6. Scaleable, High Efficiency Microchannel Sabatier Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — A Microchannel Sabatier Reactor System (MSRS) consisting of cross connected arrays of isothermal or graded temperature reactors is proposed. The reactor array...

  7. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Shimizu, Takeshi; Iida, Masaaki; Moriki, Yasuyuki

    1994-10-18

    A reactor core is divided into a plurality of coolants flowrate regions, and electromagnetic pumps exclusively used for each of the flowrate regions are disposed to distribute coolants flowrates in the reactor core. Further, the flowrate of each of the electromagnetic pumps is automatically controlled depending on signals from a temperature detector disposed at the exit of the reactor core, so that the flowrate of the region can be controlled optimally depending on the burning of reactor core fuels. Then, the electromagnetic pumps disposed for every divided region are controlled respectively, so that the coolants flowrate distribution suitable to each of the regions can be attained. Margin for fuel design is decreased, fuels are used effectively, as well as an operation efficiency can be improved. Moreover, since the electromagnetic pump has less flow resistance compared with a mechanical type pump, and flow resistance of the reactor core flowrate control mechanism is eliminated, greater circulating flowrate can be ensured after occurrence of accident in a natural convection using a buoyancy of coolants utilizable for after-heat removal as a driving force. (N.H.).

  8. Reactor coolant cleanup facility

    International Nuclear Information System (INIS)

    A depressurization device is disposed in pipelines upstream of recycling pumps of a reactor coolant cleanup facility to reduce a pressure between the pressurization device and the recycling pump at the downstream, thereby enabling high pressure coolant injection from other systems by way of the recycling pumps. Upon emergency, the recycling pumps of the coolant cleanup facility can be used in common to an emergency reactor core cooling facility and a reactor shutdown facility. Since existent pumps of the emergency reactor core cooling facility and the reactor shutdown facility which are usually in a stand-by state can be removed, operation confirmation test and maintenance for equipments in both of facilities can be saved, so that maintenance and reliability of the plant are improved and burdens on operators can also be mitigated. Moreover, low pressure design can be adopted for a non-regenerative heat exchanger and recycling coolant pumps, which enables to improve the reliability and economical property due to reduction of possibility of leakage. (N.H.)

  9. EBT reactor analysis

    International Nuclear Information System (INIS)

    This report summarizes the results of a recent ELMO Bumpy Torus (EBT) reactor study that includes ring and core plasma properties with consistent treatment of coupled ring-core stability criteria and power balance requirements. The principal finding is that constraints imposed by these coupling and other physics and technology considerations permit a broad operating window for reactor design optimization. Within this operating window, physics and engineering systems analysis and cost sensitivity studies indicate that reactors with approx. 6 to 10%, P approx. 1200 to 1700 MW(e), wall loading approx. 1.0 to 2.5 MW/m2, and recirculating power fraction (including ring-sustaining power and all other reactors auxiliaries) approx. 10 to 15% are possible. A number of concept improvements are also proposed that are found to offer the potential for further improvement of the reactor size and parameters. These include, but are not limited to, the use of: (1) supplementary coils or noncircular mirror coils to improve magnetic geometry and reduce size, (2) energetic ion rings to improve ring power requirements, (3) positive potential to enhance confinement and reduce size, and (4) profile control to improve stability and overall fusion power density

  10. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    From Zoe, the first nuclear reactor, till the current EPR, the French nuclear industry has always advanced by profiting from the feedback from dozens of years of experience and operations, in particular by drawing lessons from the most significant events in its history, such as the Fukushima accident. The new generations of reactors must improve safety and economic performance so that the industry maintain its legitimacy and its share in the production of electricity. This article draws the history of nuclear power in France, gives a brief description of the pressurized water reactor design, lists the technical features of the different versions of PWR that operate in France and compares them with other types of reactors. The feedback experience concerning safety, learnt from the major nuclear accidents Three Miles Island (1979), Chernobyl (1986) and Fukushima (2011) is also detailed. Today there are 26 third generation reactors being built in the world: 4 EPR (1 in Finland, 1 in France and 2 in China); 2 VVER-1200 in Russia, 8 AP-1000 (4 in China and 4 in the Usa), 8 APR-1400 (4 in Korea and 4 in UAE), and 4 ABWR (2 in Japan and 2 in Taiwan)

  11. Las economías emergentes: nuevos escenarios en la integración y la cooperación sur-sur

    OpenAIRE

    Dupuy, Héctor Adolfo; Morgante, Martín Adolfo; Salessi, Maria Lucila

    2014-01-01

    Nos proponemos analizar la significación que alcanza la cooperación sur-sur, así como la situación del proceso de integración del Mercosur y su eje Argentina-Brasil, las políticas impulsadas por la Unasur y los logros de la Alianza del Pacífico, en cuanto territorios ampliados de alcance internacional. Esto en un marco de transición hacia un mundo multipolar en medio de una de las peores crisis del capitalismo, en un contexto de graves conflictos en muchos lugares del Planeta, la sostenida he...

  12. Bornes optimales pour la diff\\'erence entre la hauteur de Weil et la hauteur de N\\'eron-Tate sur les courbes elliptiques sur \\Qbar

    OpenAIRE

    Bruin, Peter

    2012-01-01

    We give an algorithm that, given an elliptic curve $E$ over $\\Qbar$ in Weierstra{\\ss} form, computes the infimum and supremum of the difference between the na\\"{\\i}ve and canonical height functions on $E(\\Qbar)$. ----- Nous donnons un algorithme qui, \\'etant donn\\'ee une courbe elliptique $E$ sur $\\Qbar$ sous la forme de Weierstra\\ss, calcule l'infimum et le supremum de la diff\\'erence entre la hauteur na\\"{\\i}ve et la hauteur canonique sur $E(\\Qbar)$.

  13. El surgimiento de la cooperación Sur-Sur: Hacia un nuevo ecosistema de cooperación para el desarrollo

    OpenAIRE

    Joaquim Tres

    2013-01-01

    La Cooperación Sur-Sur (CSS) ha surgido con gran ímpetu en los últimos cinco años e iniciado su consolidación en América Latina y el Caribe (ALC), contribuyendo al aumento del número de actores, de instrumentos de intercambio de conocimiento y experiencias de desarrollo y a la diversificación de enfoques, aspectos todos ellos de un ecosistema emergente de cooperación. Ante este contexto, muchos analistas se preguntan ¿por qué surgió la CSS en estos momentos? y ¿qué implicaciones puede tener p...

  14. Reactor Structural Materials: Reactor Pressure Vessel Steels

    Energy Technology Data Exchange (ETDEWEB)

    Chaouadi, R

    2000-07-01

    The objectives of SCK-CEN's R and D programme on Rector Pressure Vessel (RPV) Steels are:(1) to complete the fracture toughness data bank of various reactor pressure vessel steels by using precracked Charpy specimens that were tested statically as well as dynamically; (2) to implement the enhanced surveillance approach in a user-friendly software; (3) to improve the existing reconstitution technology by reducing the input energy (short cycle welding) and modifying the stud geometry. Progress and achievements in 1999 are reported.

  15. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    The Ohio State University research reactor (OSURR) is undergoing improvements in its research and educational capabilities. A computer-based digital data acquisition system, including a reactor system mimic, will be installed as part of these improvements. The system will monitor the reactor system parameters available to the reactor operator either in digital parameters available to the reactor operator either in digital or analog form. The system includes two computers. All the signals are sent to computer 1, which processes the data and sends the data through a serial port to computer 2 with a video graphics array VGA monitor, which is utilized to display the mimic system of the reactor

  16. Methanation assembly using multiple reactors

    Science.gov (United States)

    Jahnke, Fred C.; Parab, Sanjay C.

    2007-07-24

    A methanation assembly for use with a water supply and a gas supply containing gas to be methanated in which a reactor assembly has a plurality of methanation reactors each for methanating gas input to the assembly and a gas delivery and cooling assembly adapted to deliver gas from the gas supply to each of said methanation reactors and to combine water from the water supply with the output of each methanation reactor being conveyed to a next methanation reactor and carry the mixture to such next methanation reactor.

  17. MINT research reactor safety program

    Energy Technology Data Exchange (ETDEWEB)

    Mohamad Idris bin Taib [Division of Special Project, Malaysian Institute for Nuclear Technology Research (MINT), Bangi (Malaysia)

    2000-11-01

    Malaysian Institute for Nuclear Technology Research (MINT) Research Reactor Safety Program has been done along with Reactor Power Upgrading Project, Reactor Safety Upgrading Project and Development of Expert System for On-Line Nuclear Process Control Project. From 1993 up to date, Neutronic and Thermal-hydraulics analysis, Probabilistic Safety Assessment as well as installation of New 2 MW Secondary Cooling System were done. Installations of New Reactor Building Ventilation System, Reactor Monitoring System, Updating of Safety Analysis Report and Upgrading Primary Cooling System are in progress. For future activities, Reactor Modeling will be included to add present activities. (author)

  18. Hacia una Psicología Social Comunitaria del Sur

    Directory of Open Access Journals (Sweden)

    German Rozas

    2015-11-01

    Full Text Available Este artículo tiene como objetivo proponer algunos caminos hacia un ámbito que hemos llamado simbólicamente una “Psicología Social Comunitaria del Sur”, es decir una disciplina que deje atrás los planteamientos venidos desde los países desarrollados, dado que alojan principalmente una mirada eurocéntrica. La referencia del Sur, es una propuesta metafórica, que no tiene un asidero geográfico, sino que apela a un otro, los del Sur, que significan la relación entre países de una manera diferente, incorporando a todos aquellas poblaciones, países, comunidades, independientes de su ubicación en el globo, que no se sienten incluidos en la categoría de países industrializados, modernos, autodenominados del norte. Desde la visibilización en América Latina de movimientos sociales asociados a comunidades indígenas, afrodescendientes y otras, la disciplina debiera reconfigurarse cualitativamente de modo que dé cuenta de estas nuevas realidades. Por un lado, algunas propuestas señalan acentuar la definición del concepto de comunidad desde una óptica más relacional. Es decir, entender comunidad como una matriz de cosmovisiones de mundo, la cual se articula con otras comunidades en una determinación mutua. Por otro lado, la intervención comunitaria ya debiera dejar atrás la solución de problemas que promuevan el progreso y el bienestar occidental, sino dirigirse más bien a trabajar la subjetividad, en el sentido de deconstruir la colonización del saber, para luego fortalecer la interpretación que hace cada comunidad desde su propia particularidad y cosmovisión situada. Finalmente, otra línea a sugerir es poner énfasis en un tipo de transformación social dirigida a la construcción de otra epistemología, que incorpore la interculturalidad, la plurinacionalidad, los derechos colectivos y por último una temática hoy día presente y en debate, el buen vivir.

  19. Thermionic Reactor Design Studies

    Energy Technology Data Exchange (ETDEWEB)

    Schock, Alfred

    1994-08-01

    Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their (thermionic reactor) performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling.

  20. International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    An international design team comprised of members from Canada, Europe, Japan, the Soviet Union, and the United States of America, are designing an experimental fusion test reactor. The engineering and testing objectives of this International Thermonuclear Experimental Reactor (ITER) are to validate the design and to demonstrate controlled ignition, extended burn of a deuterium and tritium plasma, and achieve steady state using technology expected to be available by 1990. The concept maximizes flexibility while allowing for a variety of plasma configurations and operating scenarios. During physics phase operation, the machine produces a 22 MA plasma current. In the technology phase, the machine can be reconfigured with a thicker shield and a breeding blanket to operate with an 18 MA plasma current at a major radius of 5.5 meters. Canada's involvement in the areas of safety, facility design, reactor configuration and maintenance builds on our internationally recognized design and operational expertise in developing tritium processes and CANDU related technologies

  1. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  2. Licensed operating reactors

    International Nuclear Information System (INIS)

    THE OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

  3. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  4. Reactor safety equipments

    International Nuclear Information System (INIS)

    Purpose: To positively recover radioactive substances discharged in a dry well at the time of failure of a reactor. Constitution: In addition to the emergency gas treating system fitted to a reactor building, a purification system connected through a pipeline to the dry well is arranged in the reactor building. This purification system is connected through pipes fitted to the dry well to forced circulation device, heat exchanger, and purification device. The atmosphere of high pressure steam gases in the dry well is derived to the heat exchanger for cooling, and then radioactive substances which are contained in the gases are removed by filter sets charged with the HEPA filters and the HECA filters. At last, there gases are returned to dry well by circulation pump, repeat this process. (Kamimura, M.)

  5. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  6. Welding and reactor safety

    International Nuclear Information System (INIS)

    The high safety requirements which must be demanded of the quality of the welded joints in reactor technique have so far not been fulfilled in all cases. The errors occuring have caused considerable loss of availability and high material costs. They were not, however, so serious that one need have feared any immediate danger to the personnel or to the environment. The safety devices of reactor plants were only called upon in a few cases and to these they responded perfectly. The intensive efforts to complete and improve the specifications are to contribute to that in future, the reactor plants can be counted even more so as one of the safest technical plants ever. (orig./LH)

  7. Backfitting swimming pool reactors

    International Nuclear Information System (INIS)

    Calculations based on measurements in a critical assembly, and experiments to disclose fuel element surface temperatures in case of accidents like stopping of primary coolant flow during full power operation, have shown that the power of the swimming pool type research reactor FRG-2 (15 MW, operating since 1967) might be raised to 21 MW within the present rules of science and technology, without major alterations of the pool buildings and the cooling systems. A backfitting program is carried through to adjust the reactor control systems of FRG-2 and FRG-1 (5 MW, housed in the same reactor hall) to the present safety rules and recommendations, to ensure FRG-2 operation at 21 MW for the next decade. (author)

  8. Reactor operation experience

    International Nuclear Information System (INIS)

    Since the TRIGA Users Conference in Helsinki 1970 the TRIGA reactor Vienna was in operation without any larger undesired shutdown. The integrated thermal power production by August 15 1972 accumulated to 110 MWd. The TRIGA reactor is manly used for training of students, for scientific courses and research work. Cooperation with industry increased in the last two years either in form of research or in performing training courses. Close cooperation is also maintained with the IAEA, samples are irradiated and courses on various fields are arranged. Maintenance work was performed on the heat exchanger and to replace the shim rod magnet. With the view on the future power upgrading nine fuel elements type 110 have been ordered recently. Experiments, performed currently on the reactor are presented in details

  9. The MNSR reactor

    International Nuclear Information System (INIS)

    This tank-in-pool reactor is based on the same design concept as the Canadian Slowpoke. The core is a right circular cylinder, 24 cm diameter by 25 cm long, containing 411 fuel pin positions. The pins are HEU-Aluminium alloy, 0.5 cm in diameter. Critical mass is about 900 g. The reactor has a single cadmium control rod. The back-up shutdown system is the insertion of a cadmium capsule in a core position. Excess reactivity is limited to 3.5mk. In both the MNSR and Slowpoke, the insertion of the maximum excess reactivity results in a power transient limited by the coolant/moderator temperature to safe values, independent of any operator action. This reactor is used primarily in training and neutron activation analysis. Up to 64 elements have been analyzed in a great variety of different disciplines. (author)

  10. Nuclear Rocket Engine Reactor

    CERN Document Server

    Lanin, Anatoly

    2013-01-01

    The development of a nuclear rocket engine reactor (NRER ) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

  11. Fusion reactor materials

    International Nuclear Information System (INIS)

    This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  12. Safety systems of heavy water reactors and small power reactors

    International Nuclear Information System (INIS)

    After introductional descriptions of heavy water reactors and natural circulation boiling water reactors the safety philosophy and safety systems like ECCS, residual heat removal, protection systems etc., are described. (RW)

  13. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    A reasonable assumption for the estimated new build market for the next 25 years is over 340 GWe net. The number of prospect countries is growing almost each day. To address this new build market, AREVA is developing a comprehensive portfolio of reactors intended to meet a wide range of power requirements and of technology choices. The EPR reactor is the flagship of the fleet. Intended for large power requirements, the four first EPRs are being built in Finland, France and China. Other countries and customers are in view, citing just two examples: the Usa where the U.S. EPR has been selected as the technology of choice by several U.S utilities; and the United Kingdom where the Generic Design Acceptance process of the EPR design submitted by AREVA and EDF is well under way, and where there is a strong will to have a plant on line in 2017. For medium power ranges, the AREVA portfolio includes a boiling water reactor and a pressurized water reactor which both offer all of the advantages of an advanced plant design, with excellent safety performance and competitive power generation cost: -) KERENA (1250+ MWe), developed in collaboration with several European utilities, and in particular with Eon; -) ATMEA 1 (1100+ MWe), a 3-loop evolutionary PWR which is being developed by AREVA and Mitsubishi. AREVA is also preparing the future and is deeply involved into Gen IV concepts. It has developed the ANTARES modular HTR reactor (pre-conceptual design completed) and is building upon its vast Sodium Fast Reactor experience to take part into the development of the next prototype. (author)

  14. Oscillatory flow chemical reactors

    Directory of Open Access Journals (Sweden)

    Slavnić Danijela S.

    2014-01-01

    Full Text Available Global market competition, increase in energy and other production costs, demands for high quality products and reduction of waste are forcing pharmaceutical, fine chemicals and biochemical industries, to search for radical solutions. One of the most effective ways to improve the overall production (cost reduction and better control of reactions is a transition from batch to continuous processes. However, the reactions of interests for the mentioned industry sectors are often slow, thus continuous tubular reactors would be impractically long for flow regimes which provide sufficient heat and mass transfer and narrow residence time distribution. The oscillatory flow reactors (OFR are newer type of tube reactors which can offer solution by providing continuous operation with approximately plug flow pattern, low shear stress rates and enhanced mass and heat transfer. These benefits are the result of very good mixing in OFR achieved by vortex generation. OFR consists of cylindrical tube containing equally spaced orifice baffles. Fluid oscillations are superimposed on a net (laminar flow. Eddies are generated when oscillating fluid collides with baffles and passes through orifices. Generation and propagation of vortices create uniform mixing in each reactor cavity (between baffles, providing an overall flow pattern which is close to plug flow. Oscillations can be created by direct action of a piston or a diaphragm on fluid (or alternatively on baffles. This article provides an overview of oscillatory flow reactor technology, its operating principles and basic design and scale - up characteristics. Further, the article reviews the key research findings in heat and mass transfer, shear stress, residence time distribution in OFR, presenting their advantages over the conventional reactors. Finally, relevant process intensification examples from pharmaceutical, polymer and biofuels industries are presented.

  15. Reactor Materials Research

    International Nuclear Information System (INIS)

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel

  16. Nuclear reactor simulator

    International Nuclear Information System (INIS)

    The Nuclear Reactor Simulator was projected to help the basic training in the formation of the Nuclear Power Plants operators. It gives the trainee the opportunity to see the nuclear reactor dynamics. It's specially indicated to be used as the support tool to NPPT (Nuclear Power Preparatory Training) from NUS Corporation. The software was developed to Intel platform (80 x 86, Pentium and compatible ones) working under the Windows operational system from Microsoft. The program language used in development was Object Pascal and the compiler used was Delphi from Borland. During the development, computer algorithms were used, based in numeric methods, to the resolution of the differential equations involved in the process. (author)

  17. Diagnostics for hybrid reactors

    International Nuclear Information System (INIS)

    The Hybrid Reactor(HR) can be considered an attractive actinide-burner or a fusion assisted transmutation for destruction of transuranic(TRU) nuclear waste. The hybrid reactor has two important subsystems: the tokamak neutron source and the blanket which includes a fuel zone where the TRU are placed and a tritium breeding zone. The diagnostic system for a HR must be as simple and robust as possible to monitor and control the plasma scenario, guarantee the protection of the machine and monitor the transmutation.

  18. Small mirror fusion reactors

    International Nuclear Information System (INIS)

    Basic requirements for the pilot plants are that they produce a net product and that they have a potential for commercial upgrade. We have investigated a small standard mirror fusion-fission hybrid, a two-component tandem mirror hybrid, and two versions of a field-reversed mirror fusion reactor--one a steady state, single cell reactor with a neutral beam-sustained plasma, the other a moving ring field-reversed mirror where the plasma passes through a reaction chamber with no energy addition

  19. Reactor neutron dosimetry

    International Nuclear Information System (INIS)

    An analysis of requirements and possibilities for experimental neutron spectrum determination during the reactor pressure vessel surveil lance programme is given. Fast neutron spectrum and neutron dose rate were measured in the Fast neutron irradiation facility of our TRIGA reactor. It was shown that the facility can be used for calibration of neutron dosimeters and for irradiation of samples sensitive to neutron radiation. The investigation of the unfolding algorithm ITER was continued. Based on this investigations are two specialized unfolding program packages ITERAD and ITERGS written this year. They are able to unfold data from activation detectors and NaI(T1) gamma spectrometer respectively

  20. Perspectives on reactor safety

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  1. Perspectives on reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  2. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    A nuclear reactor construction comprising a reactor core submerged in a pool of liquid metal coolant in a primary vessel which is suspended from the roof structure of a containment vault. Control rods supported from the roof structure are insertable in the core which is carried on a support structure from the wall of the primary vessel. To prevent excessive relaxation of the support structure whereby the control rods would be displaced relative to the core, the support structure incorporates a normally inactive secondary structure designed to become effective in bracing the primary structure against further relaxation beyond a predetermined limit. (author)

  3. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2000-07-01

    SCK-CEN's research and development programme on fusion reactor materials includes: (1) the study of the mechanical behaviour of structural materials under neutron irradiation (including steels, inconel, molybdenum, chromium); (2) the determination and modelling of the characteristics of irradiated first wall materials such as beryllium; (3) the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; (4) the study of the dismantling and waste disposal strategy for fusion reactors.; (5) a feasibility study for the testing of blanket modules under neutron radiation. Main achievements in these topical areas in the year 1999 are summarised.

  4. Reactor gamma spectrometry: status

    International Nuclear Information System (INIS)

    Current work is described for Compton Recoil Gamma-Ray Spectrometry including developments in experimental technique as well as recent reactor spectrometry measurements. The current status of the method is described concerning gamma spectromoetry probe design and response characteristics. Emphasis is given to gamma spectrometry work in US LWR and BR programs. Gamma spectrometry in BR environments are outlined by focussing on start-up plans for the Fast Test Reactor (FTR). Gamma spectrometry results are presented for a LWR pressure vessel mockup in the Poolside Critical Assembly (PCA) at Oak Ridge National Laboratory

  5. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2002-04-01

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel.

  6. Periodismo ambiental en Canal Sur Televisión

    Directory of Open Access Journals (Sweden)

    Lic. Miguel Montaño Montaño

    1999-01-01

    Full Text Available El autor estudia el origen histórico del periodismo ambiental, la evolución en España y Andalucía y su aparición en Canal Sur TV Realiza un análisis sobre la información medioambiental, especialidad del periodismo que en la década de los noventa despierta nuevamente gran interés entre el público. La televisión autonómica ha dedicado, desde su creación numerosos programas sobre el medio ambiente. Actualmente sus Servicios Informativos tienen la sección Medio Ambiente. De la importancia que se concede a este tipo de información es un buen ejemplo el programa «Tierra y Mar», que incorpora progresivamente noticias medioambientales, referidas a la educación ambiental, el mantenimiento y recuperación de la biodiversidad y la presentación de modelos de conducta respetuosos.

  7. Uruguay: el sur también existe

    Directory of Open Access Journals (Sweden)

    Carmen Morente Muñoz

    2013-06-01

    Full Text Available La República Oriental del Uruguay resulta un país bastante desconocido. Creador del primer “Estado del Bienestar”, a principios del siglo XX, sus particularidades no lo hacen tan distinto al resto de países de América Latina. Padeció la dictadura más cruenta del Cono Sur y las inclemencias de las políticas neoliberales. En 2004, el Frente Amplio, conquista la mayoría parlamentaria y el gobierno, abriendo un camino de esperanzas y de reconstrucción económica y social. A través de sus políticas públicas, ahora desarrolladas por el segundo gobierno de la izquierda (2010, hace frente a la realidad heredada: más de un tercio de su población había sido condenada a la pobreza. Palabras-clave: Uruguay, dictadura, impunidad, derechos humanos.

  8. Cultura cabocla en el sur de Brasil un abordaje preliminar

    Directory of Open Access Journals (Sweden)

    Pedro Martins

    2003-12-01

    Full Text Available This text is a research report concerning the cabocla (mestizo population of southern Brazil, focusing on cultural aspects, seen here as a distinguishing system. This population is studied in terms of the migratory process that begins with their expulsion from the countryside, their adaptation to the small towns, passing through the periphery of the large cities and finally returning to the countryside. The article attempts to understand their musical practices, the technology that they have appropriated and their religiosity, all of which have been, symbolically and materially, reconstructed in their complexity.//Este texto es un reporte de la investigación sobre la población cabocla en el sur de Brasil, centrado en los aspectos culturales vistos como un sistema distintivo. Esta población es estudiada en los términos de un proceso migratorio que empieza con su expulsión del campo, su adaptación a pueblos pequeños, pasando por la periferia de las grandes ciudades y finalmente, retornando al campo. El artículo busca entender las prácticas musicales, la tecnología que apropiaron y sus prácticas religiosas, aspectos todos que han sido simbólica y materialmente reconstruidos en su complejidad.

  9. Wind power potential of Baja California Sur, Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Jaramilli, O.A.; Saldana, R.; Miranda, U. [Instituto de Investigaciones Electricas, Energias No Convencionales, Cuernavaca, Morelos (Mexico)

    2004-10-01

    This work is an analysis of wind characteristics of Baja California Sur (BCS), Mexico, during the period from February 1997 to February 1998. Fifteen wind stations located in the eastern coastal area recorded the wind speed and wind direction for this region. The wind resources of BCS were recorded and the annual average wind speed, power density, and annual energy density at 10 m above ground level are presented here. We considered the wind data from El Cardon, BCS, as a case study. This location can be considered to be representative of the 15 wind stations that were installed in BCS. Using the Weibull probability density function, we estimated the wind energy output and the capacity factor for two different wind turbines during the year. The capacity factors for both wind turbines were estimated at close to 25%. Considering the wind energy output and the capacity factor, we estimated the levelized production costs for both wind turbines. Taking into account two different discount rates of 7% and 10%, we developed data for the levelized production cost of both wind turbines. (Author)

  10. de La Ciénega, costa sur de Jalisco

    Directory of Open Access Journals (Sweden)

    Peter R. W. Gerritsen

    2008-01-01

    Full Text Available Hoy día la producción agroindustrial de alimentos es una actividad que está causando gran impacto tanto en los recursos naturales como en las culturas y los tejidos sociales; mientras que el modo campesino, opuesto al agroindustrial, propone una agricultura justa con base en las prácticas y experiencias campesinas generando así alternativas sustentables de producción.En este artículo se analizan cuatro estudios de caso de agricultores en el ejido de La Ciénega en la costa sur de Jalisco, los cuales se ubican en estos dos sistemas de producción. Los resultados exponen las técnicas de producción y estrategias campesinas que se desarrollan, así como la relación de los sistemas de producción ante las políticas agropecuarias. Terminamos resaltando la importancia de las prácticas y experiencias endógenas para el fortalecimiento de un desarrollo rural sustentable

  11. Den sande roman - og Sartres Notes sur 'Madame Bovary'

    DEFF Research Database (Denmark)

    Liisberg, Sune

    2005-01-01

    I artiklen undersøges forholdet imellem filosofi og romankunst; til det formål slår forfatteren ned på tre tænkere - Camus, Proust og Sartre - som alle udmærker sig ved både at have en praktisk erfaring med, og en filosofisk-teoretisk tilgang til, romankunsten. Grundtanken i Sartres store romanværk...... (forklaring findes i artiklen) om Gustave Flaubert, L'Idiot de la famille, har forfatterens særlige bevågenhed, idet han i lyset af denne torso slutteligt sigter mod en kommentar til Sartres efterladte Notes sur 'Madame Bovary'. For Flaubert var gennembrudsromanen om 'livet i provinsen' udtryk for en...... 'derealisationsakt', mener Sartre. I sidste ende bliver spørgsmålet om romanens sandhed til et spørgsmål om imaginaritetens sandhed, som igen må ses i forhold til, at det sandsynlige og det blot mulige gør sig gældende som ontologisk realitet i vores erfaringsliv.       Udgivelsesdato: Efterår...

  12. Contaminantes en los cuerpos de agua del sur de Sonora

    Directory of Open Access Journals (Sweden)

    López-Ríos Olga

    2001-01-01

    Full Text Available Objetivo. Ahondar en el conocimiento sobre la incidencia de las actividades productivas del hombre en su medio, y el riesgo potencial que representa el deterioro ambiental para su propia salud y la sobrevivencia de especies animales. Material y métodos. Se utilizó el paquete informático Decision Support System for Industrial Pollution Control DSS (IPC, desarrollado por el Banco Mundial, la Organización Panamericana de la Salud (OPS y la Organización Mundial de la Salud (OMS, que se aplicó a un estudio de caso sobre los cuerpos de agua del sur de Sonora, durante 1996. Resultados. Estos sugieren que existen al menos tres factores que han contribuido a la desaparición de criaderos naturales de pescado y camarón en el municipio de Huatabampo: a la filtración de fertilizantes y pesticidas en las aguas de los drenes; b el asolvamiento producido por el depósito continuo, en el pasado, de agua de cola de la industria, c y la descarga inapropiada de aguas negras en los drenes. El texto completo en inglés de este artículo está disponible en: http://www.insp.mx/salud/index.html

  13. About Chernobyl - Twenty Years Later; Propos sur Tchernobyl

    Energy Technology Data Exchange (ETDEWEB)

    Tubiana, M

    2006-07-01

    The author discusses the reactor accident of Chernobyl, the information on its consequences so contradictory in the former USSR countries, the status of the effects observed, the forecasting concerning the onset of cancers in the coming years among the populations that were exposed to radiations, the public opinion facing the pessimists. He concludes on the lessons which can be drawn from Chernobyl. (A.L.B.)

  14. Risk prevention during reactor shutdown

    International Nuclear Information System (INIS)

    During reactor shutdown potential risks are issued of a number of maintenance operations. In this text we analyse these operations and give the modifications of technical specifications to ameliorate the reactor safety. 4 figs

  15. Power calibrations for TRIGA reactors

    International Nuclear Information System (INIS)

    The purpose of this paper is to establish a framework for the calorimetric power calibration of TRIGA reactors so that reliable results can be obtained with a precision better than ± 5%. Careful application of the same procedures has produced power calibration results that have been reproducible to ± 1.5%. The procedures are equally applicable to the Mark I, Mark II and Mark III reactors as well as to reactors having much larger reactor tanks and to TRIGA reactors capable of forced cooling up to 3 MW in some cases and 15 MW in another case. In the case of forced cooled TRIGA reactors, the calorimetric power calibration is applicable in the natural convection mode for these reactors using exactly the same procedures as are discussed below for the smaller TRIGA reactors (< 2 MW)

  16. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1982 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Since fiscal 1982, Systematic research and development work on safeguards technology has been added to the activities of the Department. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  17. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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

  18. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

    Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

    1989-12-01

    The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

  19. High Flux Isotope Reactor (HFIR)

    Data.gov (United States)

    Federal Laboratory Consortium — The HFIR at Oak Ridge National Laboratory is a light-water cooled and moderated reactor that is the United States’ highest flux reactor-based neutron source. HFIR...

  20. Reactor operation safety information document

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  1. Reactor safety in Eastern Europe

    International Nuclear Information System (INIS)

    The papers presented to the GRS colloquium refer to the cooperative activities for reactor accident analysis and modification of the GRS computer codes for their application to reactors of the Russian design types of WWER or RBMK. Another topic is the safety of RBMK reactors in particular, and the current status of investigations and studies addressing the containment of unit 4 of the Chernobyl reactor station. All papers are indexed separately in report GRS--117. (HP)

  2. Dix choses a savoir sur les regions metropolitaines du Canada : synthese de la serie de Statistique Canada

    OpenAIRE

    Heisz, Andrew

    2005-01-01

    La serie de rapports intitulee fournit des renseignements de base importants sur les regions metropolitaines de recensement (RMR) du Canada pour la periode allant de 1981 a 2001. Fondee principalement sur des donnees de recensement, cette serie offre des renseignements et des analyses de fond portant sur plusieurs sujets, dont le faible revenu, la sante, l'immigration, la culture, le logement, les marches du travail, la structure industrielle, la mobilite, les transports en commun et le navet...

  3. Mice lacking sulfonylurea receptor 2 (SUR2) ATP sensitive potassium channels are resistant to acute cardiovascular stress

    OpenAIRE

    Stoller, Douglas; Kakkar, Rahul; Smelley, Matthew; Chalupsky, Karel; Earley, Judy U.; Shi, Nian-Qing; Makielski, Jonathan C.; McNally, Elizabeth M.

    2007-01-01

    Adenosine triphosphate sensitive potassium (KATP) channels are thought to mediate stress response by sensing intracellular ATP concentration. Cardiomyocyte KATP channels are composed of the pore-forming Kir6.2 subunit and the regulatory sulfonylurea receptor 2 (SUR2). We studied the response to acute isoproterenol in SUR2 null mice as a model of acute adrenergic stress and found that the episodic coronary vasospasm observed at baseline in SUR2 null mice was alleviated. Similar results were ob...

  4. Fast reactor programme

    International Nuclear Information System (INIS)

    This progress report summarizes the fast reactor research carried out by ECN during the period covering the year 1980. This research is mainly concerned with the cores of sodium-cooled breeders, in particular the SNR-300, and its related safety aspects. It comprises six items: A programme to determine relevant nuclear data of fission- and corrosion-products; A fuel performance programme comprising in-pile cladding failure experiments and a study of the consequences of loss-of-cooling and overpower; Basic research on fuel; Investigation of the changes in the mechanical properties of austenitic stainless steel DIN 1.4948 due to fast neutron doses, this material has been used in the manufacture of the reactor vessel and its internal components; Study of aerosols which could be formed at the time of a fast reactor accident and their progressive behaviour on leaking through cracks in the concrete containment; Studies on heat transfer in a sodium-cooled fast reactor core. As fast breeders operate at high power densities, an accurate knowledge of the heat transfer phenomena under single-phase and two-phase conditions is sought. (Auth.)

  5. Thermal Reactor Safety

    International Nuclear Information System (INIS)

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods

  6. NEUTRONIC REACTOR FUEL ELEMENT

    Science.gov (United States)

    Picklesimer, M.L.; Thurber, W.C.

    1961-01-01

    A chemically nonreactive fuel composition for incorporation in aluminum- clad, plate type fuel elements for neutronic reactors is described. The composition comprises a mixture of aluminum and uranium carbide particles, the uranium carbide particles containing at least 80 wt.% UC/sub 2/.

  7. Stabilized Spheromak Fusion Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Fowler, T

    2007-04-03

    The U.S. fusion energy program is focused on research with the potential for studying plasmas at thermonuclear temperatures, currently epitomized by the tokamak-based International Thermonuclear Experimental Reactor (ITER) but also continuing exploratory work on other plasma confinement concepts. Among the latter is the spheromak pursued on the SSPX facility at LLNL. Experiments in SSPX using electrostatic current drive by coaxial guns have now demonstrated stable spheromaks with good heat confinement, if the plasma is maintained near a Taylor state, but the anticipated high current amplification by gun injection has not yet been achieved. In future experiments and reactors, creating and maintaining a stable spheromak configuration at high magnetic field strength may require auxiliary current drive using neutral beams or RF power. Here we show that neutral beam current drive soon to be explored on SSPX could yield a compact spheromak reactor with current drive efficiency comparable to that of steady state tokamaks. Thus, while more will be learned about electrostatic current drive in coming months, results already achieved in SSPX could point to a productive parallel development path pursuing auxiliary current drive, consistent with plans to install neutral beams on SSPX in the near future. Among possible outcomes, spheromak research could also yield pulsed fusion reactors at lower capital cost than any fusion concept yet proposed.

  8. Reactors. Nuclear propulsion ships

    International Nuclear Information System (INIS)

    This article has for object the development of nuclear-powered ships and the conception of the nuclear-powered ship. The technology of the naval propulsion P.W.R. type reactor is described in the article B.N.3 141 'Nuclear Boilers ships'. (N.C.)

  9. Pressure tube type reactor

    International Nuclear Information System (INIS)

    Heretofore, a pressure tube type reactor has a problem in that the evaluation for the reactor core performance is complicate and no sufficient consideration is made for the economical property, to increase the size of a calandria tank and make the cost expensive. Then, in the present invention, the inner diameter of a pressure tube is set to greater than 50% of the lattice gap in a square lattice like arrangement, and the difference between the inner and the outer diameters of the calandria tube is set smaller than 20% of the lattice gap. Further, the inner diameter of the pressure tube is set to greater than 40% and the difference between the inner and the outer diameters of the calandria tube is set smaller than 30% of the lattice gap in a triangle lattice arrangement. Then, heavy water-to-fuel volume ratio can be determined appropriately and the value for the coolant void coefficient is made more negative side, to improve the self controllability inherent to the reactor. In particular, when 72 to 90 fuel rods are arranged per one pressure tube, the power density per one fuel rod is can be increased by about twice. Accordingly, the number of the pressure tubes can be reduced about to one-half, thereby enabling to remarkably decrease the diameter of the reactor core and to reduce the size of the calandria, which is economical. (N.H.)

  10. Fusion reactor materials

    International Nuclear Information System (INIS)

    At the Belgian Nuclear Research Centre SCK-CEN, activities related to fusion focus on environmental tolerance of opto-electronic components. The objective of this program is to contribute to the knowledge on the behaviour, during and after neutron irradiation, of fusion-reactor materials and components. The main scientific activities for 1997 are summarized

  11. Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

  12. Nuclear reactor building

    Science.gov (United States)

    Gou, Perng-Fei; Townsend, Harold E.; Barbanti, Giancarlo

    1994-01-01

    A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed thereabove. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define therebetween an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin.

  13. Studies on reactor physics

    International Nuclear Information System (INIS)

    Most of the peaceful applications of atomic energy are inherently dependent on advances in the science and technology of nuclear reactors, and aspects of this development are part of a major programme of the International Atomic Energy Agency. The most useful role that the Agency can play is as a co-ordinating body or central forum where the trends can be reviewed and the results assessed. Some of the basic studies are carried out by members of the Agency's own scientific staff. The Agency also convenes groups of experts from different countries to examine a particular problem in detail and make any necessary recommendations. Some of the important subjects are discussed at international scientific meetings held by the Agency. One of the subjects covered by such studies is the physics of nuclear reactors and a specific topic recently discussed was Codes for Reactor Computations, on which a seminar was held in Vienna in April this year. Another The members of the Panel described the development of heavy water reactors, the equipment and methods of research currently used, and plans for further development in their respective countries meeting of Panel of Experts on Heavy Water Lattices was held in Vienna in August 1959

  14. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    The purpose of this book is to explain the physical working conditions of nuclear reactors for the benefit of non-specialized engineers and engineering students. One of the leading ideas of this course is to distinguish between two fundamentally different concepts: - a science which could be called neutrodynamics (as distinct from neutron physics which covers the knowledge of the neutron considered as an elementary particle and the study of its interactions with nuclei); the aim of this science is to study the interaction of the neutron gas with real material media; the introduction will however be restricted to its simplified expression, the theory and equation of diffusion; - a special application: reactor physics, which is introduced when the diffusing and absorbing material medium is also multiplying. For this reason the chapter on fission is used to introduce this section. In practice the section on reactor physics is much longer than that devoted to neutrodynamics and it is developed in what seemed to be the most relevant direction: nuclear power reactors. Every effort was made to meet the following three requirements: to define the physical bases of neutron interaction with different materials, to give a correct mathematical treatment within the limit of necessary simplifying hypotheses clearly explained; to propose, whenever possible, numerical applications in order to fix orders of magnitude

  15. Cermet fuel reactors

    Energy Technology Data Exchange (ETDEWEB)

    Cowan, C.L.; Palmer, R.S.; Van Hoomissen, J.E.; Bhattacharyya, S.K.; Barner, J.O.

    1987-09-01

    Cermet fueled nuclear reactors are attractive candidates for high performance space power systems. The cermet fuel consists of tungsten-urania hexagonal fuel blocks characterized by high strength at elevated temperatures, a high thermal conductivity and resultant high thermal shock resistance. Key features of the cermet fueled reactor design are (1) the ability to achieve very high coolant exit temperatures, and (2) thermal shock resistance during rapid power changes, and (3) two barriers to fission product release - the cermet matrix and the fuel element cladding. Additionally, thre is a potential for achieving a long operating life because of (1) the neutronic insensitivity of the fast-spectrum core to the buildup of fission products and (2) the utilization of a high strength refractory metal matrix and structural materials. These materials also provide resistance against compression forces that potentially might compact and/or reconfigure the core. In addition, the neutronic properties of the refractory materials assure that the reactor remains substantially subcritical under conditions of water immersion. It is concluded that cermet fueled reactors can be utilized to meet the power requirements for a broad range of advanced space applications. 4 refs., 4 figs., 3 tabs.

  16. Cermet fuel reactors

    International Nuclear Information System (INIS)

    Cermet fueled nuclear reactors are attractive candidates for high performance space power systems. The cermet fuel consists of tungsten-urania hexagonal fuel blocks characterized by high strength at elevated temperatures, a high thermal conductivity and resultant high thermal shock resistance. Key features of the cermet fueled reactor design are (1) the ability to achieve very high coolant exit temperatures, and (2) thermal shock resistance during rapid power changes, and (3) two barriers to fission product release - the cermet matrix and the fuel element cladding. Additionally, thre is a potential for achieving a long operating life because of (1) the neutronic insensitivity of the fast-spectrum core to the buildup of fission products and (2) the utilization of a high strength refractory metal matrix and structural materials. These materials also provide resistance against compression forces that potentially might compact and/or reconfigure the core. In addition, the neutronic properties of the refractory materials assure that the reactor remains substantially subcritical under conditions of water immersion. It is concluded that cermet fueled reactors can be utilized to meet the power requirements for a broad range of advanced space applications. 4 refs., 4 figs., 3 tabs

  17. The Chernobyl reactor accident

    International Nuclear Information System (INIS)

    The documentation abstracted contains a complete survey of the broadcasts transmitted by the Russian wire service of the Deutsche Welle radio station between April 28 and Mai 15, 1986 on the occasion of the Chernobyl reactor accident. Access is given to extracts of the remarkable eastern and western echoes on the broadcasts of the Deutsche Welle. (HP)

  18. SRP reactor safety evolution

    International Nuclear Information System (INIS)

    The Savannah River Plant reactors have operated for over 100 reactor years without an incident of significant consequence to on or off-site personnel. The reactor safety posture incorporates a conservative, failure-tolerant design; extensive administrative controls carried out through detailed operating and emergency written procedures; and multiple engineered safety systems backed by comprehensive safety analyses, adapting through the years as operating experience, changes in reactor operational modes, equipment modernization, and experience in the nuclear power industry suggested. Independent technical reviews and audits as well as a strong organizational structure also contribute to the defense-in-depth safety posture. A complete review of safety history would discuss all of the above contributors and the interplay of roles. This report, however, is limited to evolution of the engineered safety features and some of the supporting analyses. The discussion of safety history is divided into finite periods of operating history for preservation of historical perspective and ease of understanding by the reader. Programs in progress are also included. The accident at Three Mile Island was assessed for its safety implications to SRP operation. Resulting recommendations and their current status are discussed separately at the end of the report. 16 refs., 3 figs

  19. Fusion reactor materials

    International Nuclear Information System (INIS)

    This paper discuses the following topics on fusion reactor materials: irradiation, facilities, test matrices, and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; fundamental mechanical behavior; radiation effects; development of structural alloys; solid breeding materials; and ceramics

  20. Thermal Reactor Safety

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

  1. Department of reactor technology

    International Nuclear Information System (INIS)

    The activities of the Department of Reactor Technology at Risoe during 1980 are described. The work is presented in three chapters: General Information on the Department, Summary of the Department's Development during 1980, and Activities of the Department. Lists of staff, publications, computer programs, and test facilities are included. (author)

  2. The AP1000 reactor

    International Nuclear Information System (INIS)

    The design of the AP1000 reactor began 20 years ago when Westinghouse launched the AP600 reactor project. In fact by re-assessing AP600's safety margins Westinghouse realized that the its power output could be raised without putting at risk its safety standard. The AP1000 was born, it yields 1100 MWe. The main AP1000's design features is its passive safety (particularly after the Fukushima accident) and its modularity. The passive safety of the AP1000 implies: -) no humane intervention needed for 72 hours at least after the incident; -) no necessity for redundant complex safety systems. The modularity means that the plant, the reactor and other buildings are constructed from a choice of 300 modular units. These units can be built off-site and fit together on site. The modularity allows more construction activities to be led simultaneously and more chances to cope with the construction schedule. The NRC has approved the operation license for 30 years of the first AP1000 being built in the Usa (Vogtle plant in Georgia). 4 AP1000 are being built in China (Sanmen and Haiyang sites) and 6 others are planned in the Usa. Westinghouse is convinced that the AP1000's passive safety makes it more attractive. Let us not forget that Westinghouse was at the origin of the concept of pressurized water reactors, an idea adopted for half the nuclear power stations in the world and for all the plants now active in France. (A.C.)

  3. Fast reactor programme

    International Nuclear Information System (INIS)

    This progress report summarises the fast reactor research carried out at the Netherlands Energy Research Centre during the year 1981. The neutron and fission product cross sections of various isotopes have been evaluated. In the fuel performance programme, some preliminary results are given and irradiation facilities described. Creep experiments on various stainless steel components are reported

  4. Nuclear rocket engine reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lanin, Anatoly

    2013-07-01

    Covers a new technology of nuclear reactors and the related materials aspects. Integrates physics, materials science and engineering Serves as a basic book for nuclear engineers and nuclear physicists. The development of a nuclear rocket engine reactor (NRER) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

  5. Nuclear Reactors and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Cason, D.L.; Hicks, S.C. [eds.

    1992-01-01

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  6. Fusion reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1989-01-01

    This paper discuses the following topics on fusion reactor materials: irradiation, facilities, test matrices, and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; fundamental mechanical behavior; radiation effects; development of structural alloys; solid breeding materials; and ceramics.

  7. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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 Management and Program Analysis

  8. Fast reactors: potential for power

    International Nuclear Information System (INIS)

    The subject is discussed as follows: basic facts about conventional and fast reactors; uranium economy; plutonium and fast reactors; cooling systems; sodium coolant; safety engineering; handling and recycling plutonium; safeguards; development of fast reactors in Britain and abroad; future progress. (U.K.)

  9. Reactor physics problems on HCPWR

    International Nuclear Information System (INIS)

    Reactor physics problems on high conversion pressurized water reactors (HCPWRs) are discussed. Described in this report are outline of the HCPWR, expected accuracy for the various reactor physical qualities, and method for K-effective calculation in the resonance energy area. And requested further research problems are shown. The target value of the conversion ratio are also discussed. (author)

  10. Exposition de soi et reconnaissance de singularités subjectives sur les sites de réseaux sociaux

    OpenAIRE

    Granjon, Fabien; Denouël, Julie

    2010-01-01

    Construit dans le prolongement du projet de recherche baptisé Sociogeek, portant sur les usages sociaux des sites de réseaux sociaux (sns) et les pratiques de mise en visibilité de soi sur Internet, cet article s’intéresse aux formes d’exposition de soi produites sur Facebook, et plus particulièrement celles qui s’inscrivent dans le cadre de l’impudeur corporelle (l’une des cinq modalités d’épanchement de soi décelée par l’enquête Sociogeek). Aussi, notre proposition s’appuie sur un travail d...

  11. Etude structure/fonction d'une proteine ABC : SUR, le récepteur des sulfonylurées

    OpenAIRE

    Gally, Fabienne

    2005-01-01

    ATP-sensitive K+ channels (KATP channels) are metabolic sensors formed by the association of an ATP-inhibited inwardlyrectifying K+ channel (Kir6.2) and a regulatory subunit, SUR, of the ABC protein family. SUR adjusts channel gating as afunction of internal ATP and ADP. It is also the target of pharmaceutical KATP channel openers (KCO) or blockers.We have worked on several structure/function relationships of SUR as a model of eucaryotic ABC protein. The naturalassociation of SUR with an ion ...

  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. Alternative approaches to fusion. [reactor design and reactor physics for Tokamak fusion reactors

    Science.gov (United States)

    Roth, R. J.

    1976-01-01

    The limitations of the Tokamak fusion reactor concept are discussed and various other fusion reactor concepts are considered that employ the containment of thermonuclear plasmas by magnetic fields (i.e., stellarators). Progress made in the containment of plasmas in toroidal devices is reported. Reactor design concepts are illustrated. The possibility of using fusion reactors as a power source in interplanetary space travel and electric power plants is briefly examined.

  14. Reactor vessel support system. [LMFBR

    Science.gov (United States)

    Golden, M.P.; Holley, J.C.

    1980-05-09

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  15. Reactor monitoring using antineutrino detectors

    Science.gov (United States)

    Bowden, N. S.

    2011-08-01

    Nuclear reactors have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Measurements made with antineutrino detectors could therefore offer an alternative means for verifying the power history and fissile inventory of a reactor as part of International Atomic Energy Agency (IAEA) and/or other reactor safeguards regimes. Several efforts to develop this monitoring technique are underway worldwide.

  16. Reactor physics activities in Japan

    International Nuclear Information System (INIS)

    This report reviews the research activity in reactor physics field in Japan during July, 1992 - July, 1993. The review was performed in the following fields : nuclear data evaluation, calculational method development, fast reactor physics, thermal reactor physics, advanced core design, fusion reactor neutronics, nuclear criticality safety, shielding, incineration of radioactive nuclear wastes, noise analysis and control and national programs. The main references were taken from journals and reports published during this period. The research committee of reactor physics is responsible for the review work. (author)

  17. y el Mercado Común del Sur (MERCOSUR

    Directory of Open Access Journals (Sweden)

    Ángel Moros

    2006-01-01

    Full Text Available Se analizan algunos indicadores propuestos por la Cumbre Mundial sobre la Sociedad de la Información con el fin de comparar el desarrollo de las políticas nacionales de información, los niveles de tecnologización y la funcionalidad en los países que conforman los bloques de la Comunidad Andina de Naciones y El Mercado Común del Sur. El primer bloque está constituido por Bolivia, Colombia, Ecuador, Perú y Venezuela y el segundo está conformado por Argentina, Brasil, Paraguay, Uruguay y Venezuela, para los efectos de este artículo también se incluye a Chile. Este estudio se desarrolla bajo las características del paradigma tecnológico preparado por la División Desarrollo Productivo y Empresarial de la CEPAL que reconocen ocho fundamentos, de los cuales, para este trabajo se aplicaron dos, el primero enfoca la exogeneidad de las trayectorias tecnológicas, que por sus características se puede aplicar a gran parte de los países de la región, teniendo en cuenta que sus trayectorias son determinadas fuera de los sistemas de innovación La endogeneidad institucional, política y normativa, se inserta en la complejidad y en la incertidumbre de los sistemas de información, parte de modelos enfrentados a trayectorias tecnológicas exógenas, en los cuales los países tienen sus respectivos grados de libertad y varían según su nivel de desarrollo

  18. Enco're une remarque sur le verbe voler = derober

    Directory of Open Access Journals (Sweden)

    Anton Grad

    1965-12-01

    Full Text Available L'article «A Note on French voler, to steal» de M. N.C. W. Spence' représente une nouvelle tentative pour trouver l'origine du verbe voler, employé transitivement au sens de dérober.  L'auteur y passe d'abord en revue les hypothèses émises jusqu'ici sur l'origine et l'histoire sémantique du verbe voler = dérober, surtout celle de M. Gamillscheg' qui - vu que le verbe voler = dérober n’est constaté qu'au 16e siécle - rejette la possibilité d'une dérivation de notre verbe du verbe latin involare (=prendre en. possession, anc. fr. embler, ainsi que celle d'une dérivation de notre verbe du nom vola «main creuse», proposée par Diez; Gamillscheg préfère y voir un emprunt à l'argot des malfaiteurs dans lequel le verbe intransitif voler = to fly, fliegen aurait subi un changement et pris le sens nouveau - celui de dérober – grâce à l'emploi euphémique du mot; mais, selon Gamillscheg, ce dernier sens de voler 'aurait été précédé du verbe voler employe factitivement au sens de «faire voler».

  19. Advanced reactor experimental facilities

    International Nuclear Information System (INIS)

    For many years, the NEA has been examining advanced reactor issues and disseminating information of use to regulators, designers and researchers on safety issues and research needed. Following the recommendation of participants at an NEA workshop, a Task Group on Advanced Reactor Experimental Facilities (TAREF) was initiated with the aim of providing an overview of facilities suitable for carrying out the safety research considered necessary for gas-cooled reactors (GCRs) and sodium fast reactors (SFRs), with other reactor systems possibly being considered in a subsequent phase. The TAREF was thus created in 2008 with the following participating countries: Canada, the Czech Republic, Finland, France, Germany, Hungary, Italy, Japan, Korea and the United States. In a second stage, India provided valuable information on its experimental facilities related to SFR safety research. The study method adopted entailed first identifying high-priority safety issues that require research and then categorizing the available facilities in terms of their ability to address the safety issues. For each of the technical areas, the task members agreed on a set of safety issues requiring research and established a ranking with regard to safety relevance (high, medium, low) and the status of knowledge based on the following scale relative to full knowledge: high (100%-75%), medium (75 - 25%) and low (25-0%). Only the issues identified as being of high safety relevance and for which the state of knowledge is low or medium were included in the discussion, as these issues would likely warrant further study. For each of the safety issues, the TAREF members identified appropriate facilities, providing relevant information such as operating conditions (in- or out-of reactor), operating range, description of the test section, type of testing, instrumentation, current status and availability, and uniqueness. Based on the information collected, the task members assessed prospects and priorities

  20. 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.

  1. 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)

  2. Reactor simulator development. Workshop material

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in reactor operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. This publication consists of course material for workshops on development of such reactor simulators. Participants in the workshops are provided with instruction and practice in the development of reactor simulation computer codes using a model development system that assembles integrated codes from a selection of pre-programmed and tested sub-components. This provides insight and understanding into the construction and assumptions of the codes that model the design and operational characteristics of various power reactor systems. The main objective is to demonstrate simple nuclear reactor dynamics with hands-on simulation experience. Using one of the modular development systems, CASSIMtm , a simple point kinetic reactor model is developed, followed by a model that simulates the Xenon/Iodine concentration on changes in reactor power. Lastly, an absorber and adjuster control rod, and a liquid zone model are developed to control reactivity. The built model is used to demonstrate reactor behavior in sub-critical, critical and supercritical states, and to observe the impact of malfunctions of various reactivity control mechanisms on reactor dynamics. Using a PHWR simulator, participants practice typical procedures for a reactor startup and approach to criticality. This workshop material consists of an introduction to systems used for developing reactor simulators, an overview of the dynamic simulation

  3. Reactor water spontaneous circulation structure in reactor pressure vessel

    International Nuclear Information System (INIS)

    The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

  4. Safety review, assessment and inspection on research reactors, experimental reactors, nuclear heating reactors and critical facilities

    International Nuclear Information System (INIS)

    In 1998, the NNSA organized to complete the nuclear safety review on the test loop in-reactor operation of the High-flux Engineering Experimental Reactor (HFEER) and the re-operation of the China Pulsed Reactor and the Uranium-water Criticality Facility. The NNSA conducted the nuclear safety review on the CP application of the China Experimental Fast Reactor (CEFR) and the siting of China Advanced Research Reactor (CARR), and carried out the construction supervision on HTR-10, and dealt with the event about the technological tube breakage of HWRR and other events

  5. Compact fusion reactors

    CERN Document Server

    CERN. Geneva

    2015-01-01

    Fusion research is currently to a large extent focused on tokamak (ITER) and inertial confinement (NIF) research. In addition to these large international or national efforts there are private companies performing fusion research using much smaller devices than ITER or NIF. The attempt to achieve fusion energy production through relatively small and compact devices compared to tokamaks decreases the costs and building time of the reactors and this has allowed some private companies to enter the field, like EMC2, General Fusion, Helion Energy, Lawrenceville Plasma Physics and Lockheed Martin. Some of these companies are trying to demonstrate net energy production within the next few years. If they are successful their next step is to attempt to commercialize their technology. In this presentation an overview of compact fusion reactor concepts is given.

  6. Elk River Reactor dismantling

    International Nuclear Information System (INIS)

    The dismantling program was carried out in three overlapping phases: the planning phase which included the preliminary planning and selection of the dismantling approach, the dismantling phase which included all work performed to remove the reactor facility and restore the site to its pre-reactor condition, and the closeout phase which included the final site survey and efforts necessary to terminate the AEC license and contract. Of particular interest was the use of a remotely operated plasma cutting torch to section the pressure vessel internals, the pressure vessel and the outer thermal shield, the use of explosives in removal of the biological shield and the method of establishment of the criteria for material disposal

  7. REACTOR MODERATOR STRUCTURE

    Science.gov (United States)

    Greenstreet, B.L.

    1963-12-31

    A system for maintaining the alignment of moderator block structures in reactors is presented. Integral restraining grids are placed between each layer of blocks in the moderator structure, at the top of the uppermost layer, and at the bottom of the lowermost layer. Slots are provided in the top and bottom surfaces of the moderator blocks so as to provide a keying action with the grids. The grids are maintained in alignment by vertical guiding members disposed about their peripheries. (AEC)

  8. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    SCK-CEN's programme on fusion reactor materials includes studies (1) to investigate fracture mechanics of neutron-irradiated beryllium; (2) to describe the helium behaviour in irradiated beryllium at atomic scale; (3) to define the kinetics of beryllium reacting with air or steam; (3) to perform a feasibility study for the testing of integrated blanket modules under neutron irradiation. Progress and achievements in 1997 are reported

  9. Decommissioning of research reactors

    International Nuclear Information System (INIS)

    Research reactors of WWR-S type were built in countries under Soviet influence in '60, last century and consequently reached their service life. Decommissioning implies removal of all radioactive components, processing, conditioning and final disposal in full safety of all sources on site of radiological pollution. The WWR-S reactor at Bucuresti-Magurele was put into function in 1957 and operated until 1997 when it was stopped and put into conservation in view of decommissioning. Presented are three decommissioning variants: 1. Reactor shut-down for a long period (30-50 years) what would entail a substantial decrease of contamination with lower costs in dismantling, mechanical, chemical and physical processing followed by final disposal of the radioactive wastes. The drawback of this solution is the life prolongation of a non-productive nuclear unit requiring funds for personnel, control, maintenance, etc; 2. Decommissioning in a single stage what implies large funds for a immediate investment; 3. Extending the operation on a series of stages rather phased in time to allow a more convenient flow of funds and also to gather technical solutions, better than the present ones. This latter option seems to be optimal for the case of the WWR-S Research at Bucharest-Magurele Reactor. Equipment and technologies should be developed in order to ensure the technical background of the first operations of decommissioning: equipment for scarification, dismantling, dismemberment in a highly radioactive environment; cutting-to-pieces and disassembling technologies; decontamination modern technologies. Concomitantly, nuclear safety and quality assurance regulations and programmes, specific to decommissioning projects should be implemented, as well as a modern, coherent and reliable system of data acquisition, recording and storing. Also the impact of decommissioning must be thoroughly evaluated. The national team of specialists will be assisted by IAEA experts to ensure the

  10. Nuclear reactor container

    International Nuclear Information System (INIS)

    Upon reactor accident, hydrogen and oxygen are generated by water-zirconium reaction and radiolysis of water, which are accumulated in the reactor. If the concentration of hydrogen and oxygen exceeds a burning limit, there is a possibility of hydrogen burning to cause a danger of deteriorating the integrity of the reactor container and the equipments therein. The limit for the occurrence of the detonation is determined by a relationship between the scale of a detonation cell and the size of the container, and if the scale is greater than the container, the detonation does not occur. The scale of the cell is determined by a gas combustion rate and, if the combustion reaction is suppressed, detonation does not occur even in a large container. Then, an appropriate diluent is added to increase heat capacity of a gas mixture to thereby suppress the temperature elevation of the gas. Incombustible gases having a great heat capacity are preferred for the diluent, and CO2 is used. As the concentration of the CO2 gas to be added is increased, the detonation cell is made greater. Thus, occurrence of detonation due to combustion of the accumulated hydrogen can be prevented. (N.H.)

  11. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    In the middle of 21st century, the population on the earth is expected to double, and the energy that mankind consumes to triple. The nuclear fusion which is said the ultimate energy source for mankind is expected to solve this energy problem. As for fusion reactors, fuel materials exist inexhaustibly, distributing evenly, they have high safety in principle, the product of burning is harmless nonradioactive substance that does not require the treatment and disposal, and the attenuation of induced radioactivity due to neutrons is quick and the effect to global environment is little. The basic plan of second stage nuclear fusion research and development was decided in 1975, aiming at attaining the critical plasma condition. JT-60 has attained it in 1987. The project of international thermonuclear fusion experimental reactor (ITER) was started, and the conceptual design was carried out. Under such background, the third stage basic plan was decided in 1992, and its objective is self ignition condition, long time burning and the basis of the reactor engineering technology. The engineering design of the ITER is investigated. (K.I.)

  12. High temperature gas reactor

    International Nuclear Information System (INIS)

    The present invention provides a reflector block structure of a high temperature gas reactor in which graphite blocks are not failed even a containing cylinder loaded to a fuel exchanger collides against to secured reflectors upon loading and withdrawing fuel constitutional elements. Namely, a protection plate made of a metal material such as stainless steel is covered on the secured reflector blocks disposed to the upper most step among secured graphite reflector blocks constituting the reactor core. In addition, positioning guide grooves are formed on the protection plate for guiding the containing cylinder loaded to the fuel exchanger to the column of the reactor core constitutional elements. With such a constitution, even if the containing cylinder of fuel exchanger is hoisted down and collided against the inner circumferential edge of the secured reflector blocks due to deviation of the position and the direction upon exchange of fuels, the reflector blocks are not failed since the above-mentioned portion is covered with the metal protection plate. In addition, the positioning guide grooves lead the fuel exchanger to a predetermined column correctly. (I.S.)

  13. BWR type reactor

    International Nuclear Information System (INIS)

    In a coolant circulation in BWR type reactors, since the mixed stream of steam fluid undergoes a great resistance, the pressure loss due to the flow rate distribution when the coolants flow from the upper plenum into the stand pipe is increased upon passing stand pipe. Also in the spontaneous recycling reactor, pressure loss is still left upon passing the swirling blade of a gas-liquid separator. In view of the above, a plurality of vertical members each having a lower end opened to a gas-liquid two phase boundary and an upper end directly suspended from a steam dryer to the gas-liquid separator. The liquid droplets from the 2-phase boundary heated in the reactor core and formed into a mixed gas-liquid 2-phase stream is directed in the vertical direction accompanied with the steam. The liquid droplets spontaneously fallen by gravity from greater ones successively and the droplets in the steam abutted against the vertical member are fallen as a liquid membrane. Thus, the gas-liquid separation is conducted, the dry steam is directly flown into the steam dryer, thereby capable of providing a gas-liquid separator having gas-liquid separation performance with lower loss than usual. (N.H.)

  14. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. Fusion reactor safety

    International Nuclear Information System (INIS)

    Nuclear fusion could soon become a viable energy source. Work in plasma physics, fusion technology and fusion safety is progressing rapidly in a number of Member States and international collaboration continues on work aiming at the demonstration of fusion power generation. Safety of fusion reactors and technological and radiological aspects of waste management are important aspects in the development and design of fusion machines. In order to provide an international forum to review and discuss the status and the progress made since 1983 in programmes related to operational safety aspects of fusion reactors, their waste management and decommissioning concepts, the IAEA had organized the Technical Committee on ''Fusion Reactor Safety'' in Culham, 3-7 November 1986. All presentations of this meeting were divided into four sessions: 1. Statements on National-International Fusion Safety Programmes (5 papers); 2. Operation and System Safety (15 papers); 3. Waste Management and Decommissioning (5 papers); 4. Environmental Impacts (6 papers). A separate abstract was prepared for each of these 31 papers. Refs, figs, tabs

  16. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units are provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  17. OECD Halden Reactor Project

    International Nuclear Information System (INIS)

    The OECD Halden Reactor project is an agreement between OECD member countries. It was first signed in 1958 and since then regularly renewed every third year. The activities at the Project is centred around the Halden heavy water rector, the HBWR. The reseach programme comprizes studies of fuel performance under various operating conditions, and the application of computers for process control. The HBWR is equipped for exposing fuel rods to temperatures and pressures, and at heat ratings met in modern BWR's and PWR's. A range of in-core instruments are available, permitting detailed measurements of the reactions of the fuel, including mechanical deformations, thermal behaviour, fission gas release, and corrosion. In the area of computer application, the studies of the communication between operator and process, and the surveillance and control of the reactor core, are of particular interst for reactor operation. 1988 represents the 30th year since the Project was started, and this publication is produced to mark this event. It gives and account of the activities and achievements of the Project through the years 1958-1988

  18. Effet de taille sur la capacité portante des fondations superficielles

    OpenAIRE

    Garnier, J.

    2003-01-01

    Il y a plus d'un demi siècle que les premières preuves expérimentales de l'effet de la taille sur la portance des fondations ont été apportées et des données nouvelles sont régulièrement produites. De nombreuses théories ont été avancées pour rendre compte de cet effet. Elles sont présentées et comparées dans cet article et des conclusions sont tirées tant pour la prévision de la portance des fondations que pour la conduite d'essais sur ouvrages en semi-grandeur ou sur modèles réduits. Siz...

  19. Etude statistique du rayonnement solaire sur un plan incliné

    OpenAIRE

    MOUHOUS-CHAOUCHI, Samira

    2012-01-01

    Ce travail présente une étude statistique des valeurs des rayonnements Diffus et Global mesurées et calculées sur un plan incliné à la latitude du lieu à Bouzaréah (36.8°). Pour le calcul du rayonnement diffus sur plan incliné cinq modèles ont été choisis ; le modèle isotrope de la première génération, le modèle de Hay et le modèle de Reindl de la deuxième génération et le modèle de Gueymard et le modèle de Perez de la troisième génération. Les modèles sont évalués sur une base graphique et s...

  20. Etude in vitro de l'efficacité antifongique de la Piroctone olamine sur Malassezia pachydermatis

    OpenAIRE

    Tané, Elisabeth

    2006-01-01

    Le but de cette étude est d évaluer l'action antifongique de la Piroctone olamine sur Malassezia pachydermatis in vitro. De la Piroctone olamine en poudre, à différentes concentrations allant de 43 à 344 mg/m , est solubilisée puis déposée sur des boîtes de Pétri. Dans un premier temps, l'auteur étudie l'effet préventif antifongique de la Piroctone olamine en répartissant le principe actif sur la gélose de Sabouraud, avant d'ensemencer les levures. Dans un deuxième temps, il applique la Piroc...

  1. Quels impacts des TIC sur le développement durable ?

    Directory of Open Access Journals (Sweden)

    Benoît Dumolin

    2015-07-01

    Full Text Available La première partie de l’étude examine quels sont les impacts des TIC sur le développement durable. A l’inverse d’une approche sectorielle, l’objectif du développement durable s’inscrit à l’intersection des sphères sociétale, économique, environnementale et de la gouvernance. La dimension transversale des TIC rend l’analyse des interactions entre ces quatre piliers difficile d’autant plus que l’influence du numérique sur l’économie ou sur l’organisation sociale est complexe à mesurer. Les effe...

  2. L'influence de nos représentations sur le genre dans nos actions quotidiennes

    OpenAIRE

    Capt, Céline; Boulé, Christophe

    2008-01-01

    A travers ce mémoire de recherche, j’ai porté mon attention sur la manière dont nous, professionnel/les, avons de prendre en compte la problématique genre dans nos actions quotidiennes et l’influence que cela a sur les usagers. Dans ce cas précis, les usagers concernés sont une population de jeunes préadolescents, adolescents âgés de 9 à 16 ans fréquentant un accueil de jour éducatif. La première partie du travail comporte un apport théorique sur les différents concepts que j’ai trouvés pert...

  3. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  4. Chernobyl reactor transient simulation study

    International Nuclear Information System (INIS)

    This paper deals with the Chernobyl nuclear power station transient simulation study. The Chernobyl (RBMK) reactor is a graphite moderated pressure tube type reactor. It is cooled by circulating light water that boils in the upper parts of vertical pressure tubes to produce steam. At equilibrium fuel irradiation, the RBMK reactor has a positive void reactivity coefficient. However, the fuel temperature coefficient is negative and the net effect of a power change depends upon the power level. Under normal operating conditions the net effect (power coefficient) is negative at full power and becomes positive under certain transient conditions. A series of dynamic performance transient analysis for RBMK reactor, pressurized water reactor (PWR) and fast breeder reactor (FBR) have been performed using digital simulator codes, the purpose of this transient study is to show that an accident of Chernobyl's severity does not occur in PWR or FBR nuclear power reactors. This appears from the study of the inherent, stability of RBMK, PWR and FBR under certain transient conditions. This inherent stability is related to the effect of the feed back reactivity. The power distribution stability in the graphite RBMK reactor is difficult to maintain throughout its entire life, so the reactor has an inherent instability. PWR has larger negative temperature coefficient of reactivity, therefore, the PWR by itself has a large amount of natural stability, so PWR is inherently safe. FBR has positive sodium expansion coefficient, therefore it has insufficient stability it has been concluded that PWR has safe operation than FBR and RBMK reactors

  5. REGLES DE RECHERCE D\\'INFORMATION SUR L\\'INTERNET: SIMULATION AGENTS INTELLIGENTS

    Directory of Open Access Journals (Sweden)

    Dorin Militaru

    2007-10-01

    Full Text Available Les agents de recherche disponibles sur l’Internet sont des outils permettant aux consommateurs de comparer les prix d’un produit proposé par différents vendeurs. Les agents existants basent leur recherche sur une liste prédéfinie de vendeurs ŕ consulter, autrement dit, ils utilisent une rčgle de recherche avec une taille d’échantillon fixe (agent de recherche FSS. Toutefois, dans le futur, avec la mise en place de nouveaux systčmes de tarification des communications sur le réseau, cette rčgle de recherche est susceptible d’évoluer vers d’autres rčgles plus flexibles permettrant aux agents de faire un arbitrage entre les coűts de communication et le prix trouvé. Dans ce cadre, la rčgle de recherche séquentielle optimale (agent de recherche RP est une alternative possible. Néanmoins, son adoption va dépendre fortement de ses performances espérées. Dans cet article, nous analysons les performances relatives d’agents RP et FSS sur un marché oů l’accčs ŕ l’information est coűteux. A l’équilibre théorique du marché, nous montrons que les agents de recherche RP permettent toujours aux consommateurs de payer des coűts totaux moins élevés. Dans un second temps, nous testons la robustesse de ce résultat théorique en simulant un marché sur lequel les agents de recherche RP et les vendeurs n’ont qu’une information partielle sur sa structure.

  6. RÉFLEXION SUR LA FINALITÉ DES SYSTÈMES DE GOUVERNANCE D’ENTREPRISES ET LEUR CONVERGENCE

    OpenAIRE

    Du Boys, Céline; Tiberghien, Bruno

    2009-01-01

    Cet article porte sur la notion de gouvernance d’entreprise à travers ses contenus et son évolution. Depuis une vision disciplinaire jusque dans sa dimension cognitive nous nous interrogeons sur l’existence (ou non) d’un modèle unique vers lequel les systèmes de gouvernance tendent ou devraient tendre

  7. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The purpose of this technical paper is to provide status of the United State domestic Research Reactor Infrastructure (RRI) Program at the Idaho National Laboratory. This paper states the purpose of the program, lists the universities operating TRIGA reactors that are supported by the program, identifies anticipated fresh fuel needs for the reactor facilities, discusses spent fuel activities associated with the program, and addresses successes and planned activities for the program. (author)

  8. Thermionic Reactor Design Studies

    Energy Technology Data Exchange (ETDEWEB)

    Schock, Alfred

    1994-06-01

    During the 1960's and early 70's the author performed extensive design studies, analyses, and tests aimed at thermionic reactor concepts that differed significantly from those pursued by other investigators. Those studies, like most others under Atomic Energy Commission (AEC and DOE) and the National Aeronautics and Space Administration (NASA) sponsorship, were terminated in the early 1970's. Some of this work was previously published, but much of it was never made available in the open literature. U.S. interest in thermionic reactors resumed in the early 80's, and was greatly intensified by reports about Soviet ground and flight tests in the late 80's. This recent interest resulted in renewed U.S. thermionic reactor development programs, primarily under Department of Defense (DOD) and Department of Energy (DOE) sponsorship. Since most current investigators have not had an opportunity to study all of the author's previous work, a review of the highlights of that work may be of value to them. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling. Where the author's concepts differed from the later Topaz-2 design was in the relative location of the emitter and the collector. Placing the fueled emitter on the outside of the cylindrical diodes permits much higher axial conductances to reduce ohmic

  9. Applications of Research Reactors

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The purpose of the earlier publication, The Application of Research Reactors, IAEA-TECDOC-1234, was to present descriptions of the typical forms of research reactor use. The necessary criteria to enable an application to be performed were outlined for each one, and, in many cases, the minimum as well as the desirable requirements were given. This revision of the publication over a decade later maintains the original purpose and now specifically takes into account the changes in service requirements demanded by the relevant stakeholders. In particular, the significant improvements in

  10. El volcanismo del Terciario superior del sur de Mendoza

    Directory of Open Access Journals (Sweden)

    F. E. Nullo

    2002-06-01

    Full Text Available Se describe por primera vez la petrografía y geoquímica de unidades volcánicas terciarias del sur de la provincia de Mendoza. Se analizan la nomenclatura estratigráfica y sus edades, estableciéndose una secuencia de eventos magmáticos ocurridos durante el Neógeno, comenzando con la evolución de un retro-arco, seguido por un arco magmático más joven. Se intenta respetar la nomenclatura estratigráfica existente, sin embargo, la definición de unidades se ha realizado sobre la base de las edades radimétricas y sus edades de cristalización, más sobre sus características petrográficas. La actividad magmática se extiende desde el Oligoceno superior al Mioceno superior, correspondiendo a el Ciclo Eruptivo Molle y el Ciclo Eruptivo Huincán, y comenzó con un episodio magmático basáltico inicial (CEM. Esta actividad se generó en la corteza inferior dominada por la concentración de gabros, dioritas y rocas híbridas (granulitas máficas. Debido a un engrosamiento de la corteza como consecuencia de la actividad tectónica durante Mioceno superior o por el estancamiento de magmas o por la combinación de ambos procesos, la formación de granulitas granatíferas resultó un producto distintivo de la corteza inferior. Con el desarrollo del arco magmático (CEH en el Mioceno superior, los magmas ascendieron desde la fuente mantélica, encontrándose con una corteza inferior granatífera, perdiendo capacidad de ascenso por falta de contraste de densidades, produciéndose una fusión extendida, la homogeinización y el ascenso, en equilibrio con la corteza baja, proceso que caracteriza el volcanismo de un arco magmático.

  11. Une ombre planant sur les démocraties étrangères

    OpenAIRE

    Wu, Guoguang

    2011-01-01

    Cet article étudie comment le succès économique chinois en arrive à avoir un impact négatif sur les libertés civiles et la démocratie en Occident et pourquoi l’interdépendance croissante entre l’économie mondiale et la Chine permet à cette dernière d’influencer les positions politiques de grandes démocraties, alors que le contraire n’est pas possible. À partir de cas concrets, il montre comment la diplomatie chinoise joue sur les relations économiques avec certaines grandes démocraties pour l...

  12. Perspective anthropologique sur l'infanticide. : La notion de personne en Nouvelle-Guinée

    OpenAIRE

    Bonnemère, Pascale

    2009-01-01

    National audience Cet article cherche à décentrer le regard sur l'infanticide en présentant plusieurs travaux qui abordent de près ou de loin le sujet dans la littérature anthropologique sur la Nouvelle-Guinée. C'est à des conceptions différentes de la personne et du statut du nourrisson que nous renvoient ces travaux, ainsi que ceux, bien connus, consacrés à la Rome antique, par exemple.

  13. Entre chamailleries et violence, l'ambivalence du discours médiatique sur le rugby

    OpenAIRE

    Fragnon, Julien

    2007-01-01

    Cette communication souhaite étudier le rapport à la violence dans le discours médiatique sur le rugby professionnel. A partir d'un corpus tiré de questionnaires auxquels ont répondu des journalistes spécialisés, des articles du journal L'Equipe et Sud-Ouest (depuis 1995) et des publications annuelles de l'Année du Rugby, nous souhaiterions mettre en évidence la dialectique entre rugby et violence. En reprenant des analyses scientifiques déjà existantes sur les règles sportives (N. Elias, J.-...

  14. La simulation pour les recherches sur la lisibilité de la route

    OpenAIRE

    Bremond, Roland; Espie, Stéphane; Cavallo, Viola

    2007-01-01

    Les recherches sur la lisibilité de la route renvoient à la question de savoir comment l'usager perçoit son environnement (infrastructure, autres usagers) pour interagir avec lui, ce qui a un impact significatif sur la sécurité routière. La vision joue un rôle primordial dans la mesure où elle permet d'acquérir des informations à distance et ainsi réaliser des anticipations. Les simulateurs sont devenus un moyen incontournable pour améliorer les connaissances dans ce domaine. Les investigatio...

  15. Dispositifs de formation hybrides : quels effets sur le développement professionnel des enseignants ?

    OpenAIRE

    Charlier, Bernadette; Lameul, Geneviève; Peltier, Claire; Borruat, Stéphanie; Mancuso, Giovanna; Burton, Réginald

    2012-01-01

    Cette contribution présente le cadre théorique, la méthodologie et les premiers résultats de la recherche Hy-Sup relatifs aux effets des dispositifs de formation hybrides sur le développement professionnel des enseignants. Plus précisément, notre analyse porte sur la perception de l’évolution des pratiques d’enseignement et de l’engagement professionnel d’enseignants impliqués dans l’expérimentation d’un dispositif hybride. Dans cette perspective, des effets différenciés selon le type de disp...

  16. Ethnobotanique du cocotier (Cocos nucifera L.) sur l’île de Vanua Lava (Vanuatu)

    OpenAIRE

    Caillon, Sophie

    2012-01-01

    Depuis la fin du xixe siècle et jusqu’à nos jours, l’économie du Vanuatu est largement dépendante de l’industrie du coprah. L’extension des cocoteraies sur les rivages insulaires est une des évolutions les plus visibles causées par le développement de cette industrie. Même si les cocotiers étaient présents sur les îles avant l’installation des premiers hommes, la colonisation a transformé l’identité socioculturelle du cocotier. Dans cet article, nous traitons de l’ethnobotanique du cocotier d...

  17. Reactor technology: power conversion systems and reactor operation and maintenance

    International Nuclear Information System (INIS)

    The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

  18. Nuclear Reactor RA Safety Report, Vol. 4, Reactor

    International Nuclear Information System (INIS)

    RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices

  19. 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

  20. Les sondages archéologiques à l’église paroissiale de Gigny-sur-Suran (Jura

    Directory of Open Access Journals (Sweden)

    David Billoin

    2011-08-01

    Full Text Available Le village de Gigny-sur-Suran garde encore l’empreinte de la topographie monastique avec plusieurs bâtiments conservés, dont l’église abbatiale qui en est l’épicentre (fig. 1. Fig. 1 – Gigny-sur-Suran, localisation de l’église paroissiale sur le cadastre napoléonien (Dao D. Billoin, Inrap.Des recherches sont toujours en cours sur cet édifice cultuel, notamment sur le plan primitif, sous la responsabilité de Christian Sapin . L’église paroissiale, quant à elle, est restée en marge des recher...

  1. LES EFFETS DU BENEVOLAT SUR L'ACCES A L'EMPLOI : UNE EXPERIENCE CONTROLEE SUR DES JEUNES QUALIFIES D'ILE DE FRANCE

    OpenAIRE

    Bougard, Jonathan; Brodaty, Thomas; Emond, Céline; L'Horty, Yannick; Du Parquet, Loïc; Petit, Pascale

    2011-01-01

    L'objet de cette étude est d'évaluer l'effet d'activités de bénévolat pendant les études universitaires sur l'accès à l'emploi en Ile-de-France de jeunes qualifiés. L'étude est réalisée sur données expérimentales de testing. Elle rend compte de la valorisation par les employeurs de la mise en évidence dans une candidature d'activités de bénévolat dans l'une des associations suivantes : les Scouts et Guides de France, une fédération sportive, la Croix Rouge Française, la Protection Civile, l'A...

  2. Impact des aménagements sur la migration anadrome du saumon atlantique (Salmo salar L. sur le gave de Pau (France

    Directory of Open Access Journals (Sweden)

    CHANSEAU M.

    1999-04-01

    Full Text Available Le suivi par radiotélémétrie de la migration anadrome de 114 saumons atlantiques sur le Gave de Pau, réalisé de 1995 à 1997, a permis d'étudier l'impact de 31 des 37 obstacles érigés sur l'axe de migration. Cinq obstacles majeurs ont été identifiés en regard de leur faible perméabilité et/ou des retards qu'ils induisent ainsi que de leur position sur l'axe. La transparence de ces 5 aménagements permettrait à plus de 80 % (contre seulement 13 % dans la situation actuelle des saumons de parvenir sur de bonnes zones de frayères. L'accumulation des retards au niveau de chaque obstacle peut empêcher une proportion non négligeable des poissons de parvenir à temps sur les meilleures zones de frayères, notamment ceux qui se présentent à l'automne sur le gave, ou ceux qui, ralentis par les obstacles, effectuent un arrêt estival sur la partie aval du cours d'eau. Les seuils de stabilisation en enrochements de faible hauteur ( 2,5 m supérieure ont eu des impacts variables, imputables en grande partie au type de passe à poissons. Les passes à bassins et les rivières de contournement ont été les dispositifs de franchissement les plus performants. Les passés à ralentisseurs à chevrons épais se sont révélées peu performantes en raison de leur faible débit d'alimentation et de leur grande sensibilité aux variations des niveaux d'eau amont. L'impact des aménagements hydroélectriques sans dérivation dépend de l'emplacement de l'entrée de la passe à poissons et de son débit d'alimentation : des effets minimums sur la migration ont été observés lorsque les ouvrages étaient équipés d'un dispositif mobilisant des débits importants (2-4 m3/s et dont l'entrée se situait dans le canal de fuite. L'impact des aménagements hydroélectriques munis d'une dérivation, tous équipés d'un dispositif de franchissement au niveau des barrages de prise d'eau, dépend des débits réservés dans les parties court

  3. The research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Paper dwells upon the design and the operation of one of the German test reactors, namely, the TRIGA Mainz one (TRIGA: Training Research Isotope Production General Atomic). The TRIGA reactor is a pool test reactor the core of which contains a graphite reflector and is placed into 2 m diameter and 6.25 m height aluminum vessel. There are 75 fuel elements in the reactor core, and any of them contains about 36 g of 235U. The TRIGA reactors under the stable operation enjoy wide application to ensure tests and irradiation, namely: neutron activation analysis, radioisotope production, application of a neutron beam to ensure the physical, the chemical and the medical research efforts. Paper presents the reactor basic experimental program lines

  4. Recent developments concerning the fusion; Developpements recents sur la fusion

    Energy Technology Data Exchange (ETDEWEB)

    Jacquinot, J. [CEA/Cadarache, Dept. de Recherches sur la Fusion Controlee, DRFC, 13 - Saint Paul lez Durance (France); Andre, M. [CEA/DAM Ile de France, 91 - Bruyeres Le Chatel (France); Aymar, R. [ITER Joint Central Team Garching, Muenchen (Germany)] [and others

    2000-09-04

    Organized the 9 march 2000 by the SFEN, this meeting on the european program concerning the fusion, showed the utility of the exploitation and the enhancement of the actual technology (JET, Tore Supra, ASDEX) and the importance of the Europe engagement in the ITER program. The physical stakes for the magnetic fusion have been developed with a presentation of the progresses in the knowledge of the stability limits. A paper on the inertial fusion was based on the LMJ (Laser MegaJoule) project. The two blanket concepts chosen in the scope of the european program on the tritium blankets, have been discussed. These concepts will be validated by irradiation tests in the ITER-FEAT and adapted for a future reactor. (A.L.B.)

  5. Tricotecenos y calidad de granos del Cono Sur

    Directory of Open Access Journals (Sweden)

    Jacqueline Cea

    2011-04-01

    Full Text Available Fusarium es un género de hongo complejo con especies que se adaptan a un amplio rango de habitats. ( Summerell et al.2001. Aunque hay docenas de especies de Fusarium, sólo un número limitado son responsables de la contaminación por micotoxinas en alimentos y raciones ( Marasas et al.1984b. Parte de estas micotoxinas son denominadas tricotecenos , involucrando mayoritariamente al deoxinivalenol (DON, sus derivados acetilados (3-acetyldeoxinivalenol y 15 acetildeoxinivalenol, T2,  HT2 y nivalenol. Según JECFA, los estudios realizados demuestran que el DON aparece predominantemente en granos tales como trigo, cebada, avena, centeno y maíz, y menos frecuentemente en arroz y sorgo. En la mayoría de las regiones del mundo, incluyendo el Cono Sur, Fusarium graminearum es el mayor agente causal de enfermedades de Fusaium en granos y cereales denominadas: Fusarium Head Blight en cereales y  Giberella ear rot en maíz. Se ha encontrado una relación directa entre la incidencia de Fusarium Head Blight y la contaminación de trigo con DON. La incidencia de la enfermedad esta afectada por las condiciones climáticas de lluvia y humedad en el período de la floración. El factor más crítico es el momento de la lluvia más que la cantidad. F. graminearum crece a una temperatura óptima de 25°C y a una actividad de agua de 0.88.Ejemplo de las consecuencias de Fusarium Head Blight en trigo, es lo ocurrido en la zafra 2001-2002 en Uruguay.  El trigo nacional sufrió contaminación con la consecuente producción de DON en valores comprometedores para la salud, tanto humana como animal. Esta situación sirvió como punto de partida para la concientización y toma de decisiones por parte de las autoridades. Es así que el MSP y MGAP establecieron  reglamentaciones con el objetivo de proteger la salud humana y animal. En forma paralela se implementó un Proyecto FAOPCT/URU/2801 de "Apoyo en la prevención y control de Fusarium y micotoxinas en granos

  6. Spiral-shaped disinfection reactors

    KAUST Repository

    Ghaffour, Noreddine

    2015-08-20

    This disclosure includes disinfection reactors and processes for the disinfection of water. Some disinfection reactors include a body that defines an inlet, an outlet, and a spiral flow path between the inlet and the outlet, in which the body is configured to receive water and a disinfectant at the inlet such that the water is exposed to the disinfectant as the water flows through the spiral flow path. Also disclosed are processes for disinfecting water in such disinfection reactors.

  7. Industrializing the liquid metal reactor

    International Nuclear Information System (INIS)

    Commercial acceptance of the liquid metal reactor had its beginning with the Fermi reactor, over two decades ago. The pattern of industrialization since that time is discussed, contrasting domestic and foreign experience. The recent termination of the Clinch River reactor project marks a watershed in the U.S. approach towards commercialization. The increased emphasis on achieving cost competitive designs reflects an awareness that barriers to industrialization are institutional and financial, and not technological

  8. Acceptability of reactors in space

    Energy Technology Data Exchange (ETDEWEB)

    Buden, D.

    1981-04-01

    Reactors are the key to our future expansion into space. However, there has been some confusion in the public as to whether they are a safe and acceptable technology for use in space. The answer to these questions is explored. The US position is that when reactors are the preferred technical choice, that they can be used safely. In fact, it dies not appear that reactors add measurably to the risk associated with the Space Transportation System.

  9. Hydrogen Production in Fusion Reactors

    OpenAIRE

    Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Momota, H.; Motojima, O.; Okamoto, M; Ohnishi, M.; Onozuka, M.; Uenosono, C.

    1993-01-01

    As one of methods of innovative energy production in fusion reactors without having a conventional turbine-type generator, an efficient use of radiation produced in a fusion reactor with utilizing semiconductor and supplying clean fuel in a form of hydrogen gas are studied. Taking the candidates of reactors such as a toroidal system and an open system for application of the new concepts, the expected efficiency and a concept of plant system are investigated.

  10. Fast reactor programme in India

    Indian Academy of Sciences (India)

    P Chellapandi; P R Vasudeva Rao; Prabhat Kumar

    2015-09-01

    Role of fast breeder reactor (FBR) in the Indian context has been discussed with appropriate justification. The FBR programme since 1985 till 2030 is highlighted focussing on the current status and future direction of fast breeder test reactor (FBTR), prototype fast breeder reactor (PFBR) and FBR-1 and 2. Design and technological challenges of PFBR and design and safety targets with means to achieve the same are the major highlights of this paper.

  11. Turning points in reactor design

    International Nuclear Information System (INIS)

    This article provides some historical aspects on nuclear reactor design, beginning with PWR development for Naval Propulsion and the first commercial application at Yankee Rowe. Five turning points in reactor design and some safety problems associated with them are reviewed: (1) stability of Dresden-1, (2) ECCS, (3) PRA, (4) TMI-2, and (5) advanced passive LWR designs. While the emphasis is on the thermal-hydraulic aspects, the discussion is also about reactor systems

  12. Optimal control of nuclear reactors

    International Nuclear Information System (INIS)

    The modern control theory is applied to the design of control systems for experimental nuclear reactors that do not belong to power reactors, the component forms of optimal control systems for nuclear reactors are demonstrated. The adoption of output quadratic integral criterion and incomplete state feedback technique can make these systems both efficient and economical. Moreover, approximate handling methods are given so as to simplify the calculations in design. In addition, the adoptable reference values of parameters are given in the illustration

  13. Turning points in reactor design

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-09-01

    This article provides some historical aspects on nuclear reactor design, beginning with PWR development for Naval Propulsion and the first commercial application at Yankee Rowe. Five turning points in reactor design and some safety problems associated with them are reviewed: (1) stability of Dresden-1, (2) ECCS, (3) PRA, (4) TMI-2, and (5) advanced passive LWR designs. While the emphasis is on the thermal-hydraulic aspects, the discussion is also about reactor systems.

  14. Acceptability of reactors in space

    International Nuclear Information System (INIS)

    Reactors are the key to our future expansion into space. However, there has been some confusion in the public as to whether they are a safe and acceptable technology for use in space. The answer to these questions is explored. The US position is that when reactors are the preferred technical choice, that they can be used safely. In fact, it does not appear that reactors add measurably to the risk associated with the Space Transportation System

  15. Políticas culturales: Francia y Europa del Sur Políticas culturales: Francia y Europa del Sur

    Directory of Open Access Journals (Sweden)

    Emmanuel Négrier

    2008-04-01

    Full Text Available In this paper, we propose a comparative analysis of five national models of cultural policy. The four first ones constitute Southern Europe: Greece, Italy, Portugal and Spain. The fifth one is France. These countries share a tradition of direct intervention in the cultural field, contrary to anglo-saxon or Scandinavian countries. The aim of such a comparison is to assess convergences but also disparities between these countries, in spite of their common traditions. We focus on the historical paths, the ways of institutionalization of the cultural public domain, and the different kinds of territorial management of cultural policies. France, which is often considered as a singular model the other countries would have try to imitate, is also analyzed in a comparative perspective. The assessment of convergences and divergences allows, in conclusion, to establish the common goals that share these five countries, as well as the major part of occidental countries in order to define the cultural policy for the 21st century.En este artículo ofrecemos un análisis comparado de cinco modelos nacionales de política cultural. Los cuatro primeros pertenecen a la Europa del sur: España, Grecia, Italia, Portugal; Francia es el quinto. A diferencia de los países anglosajones o escandinavos, los países mencionados tienen en común una tradición de intervención directa en materia de cultura. Nuestra comparación se propone demostrar las convergencias y las diferencias en las trayectorias históricas de dichas políticas culturales, su forma de institucionalización y su modo de gestión territorial. Abordamos el caso francés aparte y desde una perspectiva comparada, pues suele constituir un modelo que los otros cuatro países han intentado imitar. A modo de conclusión, el balance de las convergencias y divergencias permite establecer retos comunes para el conjunto de dichos países, y quizá también para todos los países occidentales, de cara a definir

  16. Advanced Fission Reactor Program objectives

    International Nuclear Information System (INIS)

    The objective of an advanced fission reactor program should be to develop an economically attractive, safe, proliferation-resistant fission reactor. To achieve this objective, an aggressive and broad-based research and development program is needed. Preliminary work at Brookhaven National Laboratory shows that a reasonable goal for a research program would be a reactor combining as many as possible of the following features: (1) initial loading of uranium enriched to less than 15% uranium 235, (2) no handling of fuel for the full 30-year nominal core life, (3) inherent safety ensured by core physics, and (4) utilization of natural uranium at least 5 times as efficiently as light water reactors

  17. Reactor safety - an international task

    International Nuclear Information System (INIS)

    The dimensions and the significance of the task of ensuring reactor safety can be defined on the basis of experiences gained from Harrisburg and Chernobyl. The countries that use nuclear energy are tied together to a community by virtue of the risk they share. Therefore the GRS is working in close cooperation with the EC, OECD, IAEO and COMECON. This results in safety examinations of the Greifswald reactor, safety analyses of nuclear reactors in Germany, France and the USA and also considerations on the safety demands to be placed on new reactor concepts. (DG)

  18. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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 Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  19. Integrated modular water reactor: IMR

    International Nuclear Information System (INIS)

    The Mitsubishi Heavy Industries, Ltd. Has investigated on a concept on small scale reactor with economical efficiency comparable with large scale one. Aims of development on the integrated modular water reactor (IMR) of a small scale reactor plant concept consist in large construction cost reduction through adoption of technique specific to the small scale reactor and integrated production of plural units and in establishment of high safety target without reality in a large scale reactor to realize reduction of operation and maintenance costs by this reduction to simplification of operation and maintenance. Its concrete developmental targets are to make an integrated reactor with vessel size actually producible and the largest output, to remove feasibility of coolant loss accident (LOCA), to remove an accident with feasibility related to fuel fracture, to remove feasibility of nuclear reactor coolant to leak out from a storage vessel, to secure safety of plant without necessity of human and physical assistances from other plants at all on an accident, to make numbers of operators per unit output equal to those of large scale reactor, and to make working amounts at maintenance per unit output equal to large scale reactor by simplification of apparatus practice of rotation on main apparatus such as SG, and so on. Here were described on design concept and plan to realization. (G.K.)

  20. 3. Interindustry conference on reactor materials science

    International Nuclear Information System (INIS)

    This document contains abstracts on papers presented at the Third Interindustry Conference on Reactor Materials Science (Dimitrovgrad, 27-30 October 1992). The subject scope of the papers is a follows: fuel and fuel elements of power reactors; structural materials of fast breeder reactors and thermonuclear reactors; structural materials of WWER and RBMK type reactors; absorbers and moderators

  1. Helias reactor studies

    International Nuclear Information System (INIS)

    The Helias reactor is an upgraded version of the Wendelstein 7-X experiment. The magnetic field has 5 field periods and the main optimization principle is the reduction of the Pfirsch-Schlueter currents and the Shafranov shift, which has been verified by computations with the NEMEC and MFBE-codes. The modular coil system comprises 50 coils, which are constructed using NbTi-superconducting cables. The basic dimensions are: major radius 22 m, average plasma radius 1.8 m, magnetic field on axis 5 T, maximum field on the coils 10 T. Forces and stresses in the coil system have been investigated with the aid of the ANSYS code, which found maximum stress values of about 650 MPa in the coil casing. Helias configurations with 4 and 3 field periods have been constructed by starting from the 5-period case and by eliminating one or two periods while the shape of the coils is kept nearly invariant. In a first survey blanket concepts, developed for the DEMO tokamak, have been adapted to the Helias geometry, in particular, the solid breeder concept developed by FZK (Karlsruhe) has been extrapolated to the Helias geometry identifying the drawbacks and advantages of this concept. Furthermore, the liquid breeder concept using Li7-Pb83 and water-cooling is an interesting alternative for the Helias reactor. Maintenance of blanket and plasma facing components is possible through the portholes between modular coils. Numerical simulations of the start-up phase of the Helias reactor using the TOTAL-P code have confirmed the zero-dimensional modeling of the fusion plasma with the aid of empirical scaling laws. (author)

  2. Reactor coolant pump flywheel

    Science.gov (United States)

    Finegan, John Raymond; Kreke, Francis Joseph; Casamassa, John Joseph

    2013-11-26

    A flywheel for a pump, and in particular a flywheel having a number of high density segments for use in a nuclear reactor coolant pump. The flywheel includes an inner member and an outer member. A number of high density segments are provided between the inner and outer members. The high density segments may be formed from a tungsten based alloy. A preselected gap is provided between each of the number of high density segments. The gap accommodates thermal expansion of each of the number of segments and resists the hoop stress effect/keystoning of the segments.

  3. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the errata page

  4. FUEL ASSAY REACTOR

    Science.gov (United States)

    Spinrad, B.I.; Sandmeier, H.A.; Martens, F.H.

    1962-12-25

    A reactor having maximum sensitivity to perturbations is described comprising a core consisting of a horizontally disposed, rectangular, annular fuel zone containing enriched uranium dioxide dispersed in graphite, the concentration of uranium dioxide increasing from the outside to the inside of the fuel zone, an internal reflector of graphite containing an axial test opening disposed within the fuel zone, an external graphite reflector, means for changing the neutron spectrum in the test opening, and means for measuring perturbations in the neutron flux caused by the introduction of different fuel elements into the test opening. (AEC)

  5. Shutting down two reactors

    International Nuclear Information System (INIS)

    Nuclear power will be phased out of the swedish energy system during the first decades of the next century. Commissioned by the swedish government, the National Energy Administration reports a study on the possibilities for, and consequences of, an earlier shut down (1994-1996) of two of the twelve swedish power reactors. Some of the questions studied are: How much will the electricity price raise ?; How will the electricity consumption be affected ?; What are the alternatives to nuclear power ?; What will the cost be ? and What will the environmental effects be ?. (L.E.)

  6. Measurement in nuclear reactors

    International Nuclear Information System (INIS)

    A nuclear reactor construction has a flux detector comprising a bundle of fibre optics each having a bead incorporating a substance which scintillates on being struck by neutrons or gamma radiations. The other ends of the fibre optics terminate at an image intensifier. The optical fibres may be of glass made from a mixture of silica, alkaline earth metal oxide, cerous oxide and alkali metal oxide. The beads may be incorporated in a disc forming a detector head, which is in a protective guide tube, through which an inert gas may be passed. (author)

  7. TRIGA reactor operating experience

    International Nuclear Information System (INIS)

    The Oregon State TRIGA Reactor (OSTR) has been in operation 3 years. Last August it was upgraded from 250 kW to 1000 kW. This was accomplished with little difficulty. During the 3 years of operation no major problems have been experienced. Most of the problems have been minor in nature and easily corrected. They came from lazy susan (dry bearing), Westronics Recorder (dead spots in the range), The Reg Rod Magnet Lead-in Circuit (a new type lead-in wire that does not require the lead-in cord to coil during rod withdrawal hss been delivered, much better than the original) and other small corrections

  8. Reactor system safety assurance

    International Nuclear Information System (INIS)

    The philosophy of reactor safety is that design should follow established and conservative engineering practices, there should be safety margins in all modes of plant operation, special systems should be provided for accidents, and safety systems should have redundant components. This philosophy provides ''defense in depth.'' Additionally, the safety of nuclear power plants relies on ''safety systems'' to assure acceptable response to design basis events. Operating experience has shown the need to study plant response to more frequent upset conditions and to account for the influence of operators and non-safety systems on overall performance. Defense in depth is being supplemented by risk and reliability assessment

  9. The Oklo reactors

    International Nuclear Information System (INIS)

    The Oklo reactors comprise up to nine 235-U depleted zones in an uranium ore in the Republic of Gabon in West Africa. The depletion in fissile U-235 has been proved to have caused by nuclear chain reactions. The study of the Oklo phenomenon indicates that very efficient retardation mechanisms may operate in nature - at least under special conditions. A closer study of these processes ought to be made to establish the limitations to their occurrence. The Oklo sandstone formation today would probably be considered unacceptable as a host rock for a repository. (EG)

  10. Licensed reactor nuclear safety criteria applicable to DOE reactors

    Energy Technology Data Exchange (ETDEWEB)

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.

  11. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

  12. Comment enquêter sur une émeute ?

    Directory of Open Access Journals (Sweden)

    Olivier Galland

    2007-08-01

    Full Text Available En novembre 2005, la France a été touchée par une vague de violences urbaines inédites. Issu d’une enquête monographique menée dans la ville d’Aulnay-sous-Bois (au nord de Paris, cet article souhaite revenir sur le terrain, en mettant en lumière d’une part ses aspérités, en prenant d’autre part très au sérieux la parole des jeunes impliqués, directement ou pas, dans ces évènements. Considérant les interviewés comme « capables » de dire leur expérience (en leur donnant un sens, nous avons fait état de la pluralité des versions que les jeunes ont donné de ces évènements, en formalisant leurs tentatives au travers de trois grandes figures explicatives (l’émeute déviante, l’émeute protestataire et l’émeute ludique.France was affected by an unseen wave of riots in November 2005. This paper comes from a monographic survey made in Aulnay-sous-Bois (a town in the north of Paris. This paper aims to focus on some significant difficulties during the fieldwork. We also attempt to take seriously the discourse of the young interviewees (those actively involved as well as those not actively involved in these events. We have considered our interviewees as “able” to tell their experiences and to give them a meaning. Thanks to this attitude, this survey found out that young people gave several versions of the riots summarised in three great explanations: for them these riots were the result of deviance, protest or a game.En Noviembre de 2005 Francia fue afectada por una oleada de violencia urbana inédita hasta entonces. Fruto de una investigación monográfica realizada en la ciudad de Aulnay-sous-Bois (al norte de París, este artículo desea volver a estos hechos, por un lado para poner de relieve la dificultad de la investigación, y por otro, para dar voz  a los jóvenes implicados, directamente o no, en estos acontecimientos. Considerando a los protagonistas sociales “capaces” de contar su experiencia

  13. Virtual nuclear reactor for education of nuclear reactor physics

    International Nuclear Information System (INIS)

    As one of projects that were programmed in the cultivation program for human resources in nuclear engineering sponsored by the Ministry of Economy, Trade and Industry, the development of a virtual reactor for education of nuclear reactor physics started in 2007. The purpose of the virtual nuclear reactor is to make nuclear reactor physics easily understood with aid of visualization. In the first year of this project, the neutron slowing down process was visualized. The data needed for visualization are provided by Monte Carlo calculations; The flights of the respective neutrons generated by nuclear fissions are traced through a reactor core until they disappear by neutron absorption or slow down to a thermal energy. With this visualization and an attached supplement textbook, it is expected that the learners can learn more clearly the physical implication of neutron slowing process that is mathematically described by the Boltzmann neutron transport equation. (author)

  14. Reactor Physics Analysis Models for a CANDU Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hang Bok

    2007-10-15

    Canada deuterium uranium (CANDU) reactor physics analysis is typically performed in three steps. At first, macroscopic cross-sections of the reference lattice is produced by modeling the reference fuel channel. Secondly macroscopic cross-sections of reactivity devices in the reactor are generated. The macroscopic cross-sections of a reactivity device are calculated as incremental cross-sections by subtracting macroscopic cross-sections of a three-dimensional lattice without reactivity device from those of a three-dimensional lattice with a reactivity device. Using the macroscopic cross-sections of the reference lattice and incremental cross-sections of the reactivity devices, reactor physics calculations are performed. This report summarizes input data of typical CANDU reactor physics codes, which can be utilized for the future CANDU reactor physics analysis.

  15. Lois du travail applicables sur les sites CERN, notamment le site de Meyrin

    CERN Document Server

    López-Hernandez, L A

    2005-01-01

    Le CERN passe des contrats avec des entreprises dont le personnel peut être amené à travailler sur le domaine de l’Organisation. Comme principe général, ces entreprises sont soumises au Droit de leur pays d’origine, mais elles doivent respecter aussi les dispositions d’ordre public du pays où elles exercent leur activité, c’est à dire les dispositions suisses sur la partie suisse et les dispositions françaises sur la partie française du domaine. Les dispositions d’ordre public sont des dispositions de droit fondamental qui couvrent, entre autres, des aspects relatifs aux conditions de travail (durée du travail, rémunération), la sécurité et la protection de la santé. La situation particulière du CERN, dont les sites sont situés aussi bien en France qu’en Suisse, fait que les entreprises sous contrat peuvent être amenées à travailler sur ces deux pays, parfois simultanément, avec des dispositions de droit du travail complètement différentes. L’application stricte de la lé...

  16. Reflections on "Petit Battement sur le Cou de Pied": Is It Still Relevant?

    Science.gov (United States)

    Paskevska, Anna

    2007-01-01

    This article presents multiple perspectives of "petit battement sur le cou de pied". These perspectives include historical, biomechanical, and pedagogic points of view. The article offers useful information for ballet specialists and applied research studies aimed at ballet pedagogy. (Contains 2 tables and 5 figures.)

  17. El arte y la ayuda humanitaria suiza en el sur de Francia (1939-1943)

    OpenAIRE

    Schmöller, Natascha

    2015-01-01

    El presente trabajo analiza la relación que se produjo en el sur de Francia, durante el período bélico 1939-1943, entre la ayuda humanitaria suiza y el arte, y que implicó creativamente a voluntarios, personas socorridas y artistas ajenos a la organ

  18. Le prix du transport : quels impacts sur le comportement des utilisateurs ?

    OpenAIRE

    MADRE,JL

    2004-01-01

    Cet article évoque les problèmes soulevés par l'augmentation du prix du carburant et des transports en commun. Quel est l'impact de ces évolutions sur le budget et les comportements des usagers ? Et comment les maitriser ?

  19. 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.

  20. The use of seemingly unrelated regression (SUR) to predict the carcass composition of lambs

    DEFF Research Database (Denmark)

    Cadavez, Vasco A. P.; Henningsen, Arne

    fat, and bone plus remainder were otained. Our models for carcass composition were fitted using the SUR estimator which is novel in this area. The results were compared to OLS estimates and evaluated by several statistical measures. As the models are intended to predict carcass composition, we...

  1. Reactor system on barge

    International Nuclear Information System (INIS)

    Floating electrical power plants or power plant barges add new dimensions to utility planners and agencies in the world. Intrinsically safe and economical reactors (ISER) employ steel reactor pressure vessels, which significantly reduce the weight as compared with PIUS, and provide siting versatility including barge-mounted plants. In this paper, the outline of power plant barges and barge-mounted ISERs is described. Besides their mobility, power plant barges have the salient advantages such as short delivery time and better quality control due to the outfitting in shipyards. These power plant barges may be temporarily moored or permanently grounded in shallow water at the centers of industrial complexes or the suitable areas adjacent to them, and satisfy the increasing needs for electric power. A cost-effective and technically perfect barge positioning system should be designed to meet the specific requirement for the location and its condition. Offshore siting away from coast may be applicable only to large plants of 1,000 MWe or more, and inshore siting and coastal or river siting are considered for an ISER-200 barge-mounted plant. The system of a barge-mounted ISER plant is discussed in the case of a floating type and the type on a seismic base isolator. (Kako, I.)

  2. Tokamak experimental power reactor

    International Nuclear Information System (INIS)

    A tokamak experimental power reactor has been designed that is capable of producing net electric power over a wide range of possible operating conditions. A net production of 81 MW of electricity is expected from the design reference conditions that assume a value of 0.07 for beta-toroidal, a maximum toroidal magnetic field of 9 T and a thermal conversion efficiency of 30%. Impurity control is achieved through the use of a low-Z first wall coating. This approach allows a burn time of 60 seconds without the incorporation of a divertor. The system is cooled by a dual pressurized water/steam system that could potentially provide thermal efficiencies as high as 39%. The first surface facing the plasma is a low-Z coated water cooled panel that is attached to a 20 cm thick blanket module. The vacuum boundary is removed a total of 22 cm from the plasma, thereby minimizing the amount of radiation damage in this vital component. Consideration is given in the design to the possible use of the EPR as a materials test reactor. It is estimated that the total system could be built for less than 550 million dollars

  3. The EPR reactor NDE

    International Nuclear Information System (INIS)

    In May 2006, Electricite de France decided to launch the building of the first EPRR Reactor on the Flamanville site in Normandy. The 'Flamanville 3' EPR unit is the first one to be subjected to the French Ministerial Orders of the 10 November 1999 and of the 13 December 2005 from the design phase. According to these orders, the non destructive examination (NDE) planned for the in service inspection (ISI) and for the pre service inspection (PSI) must be operational with a compulsory formal qualification. The PSI is a complete inspection of the main primary and secondary systems. The PSI's objective is to perform before the first core loading all the NDE planned for the future ISI in the same conditions, in order to have a reliable reference for the detection or for the evaluation of the possible damages during the ISI. The 'Flamanville 3' PSI is planned to start end 2010. The program consists of the development and the qualification of the NDE compatible with this new generation reactor's challenges. The paper is about: - the main EPR's objectives and the technological evolutions, - the main component modifications (which have an impact on the NDE), - the place of ISI in the general safety demonstration, - the main inspection objectives, - the NDE qualification process, - the approach to set up the ISI program, - the ISI program. (authors)

  4. Transformations, évolution : un regard sur la dynamique de notre métier

    Directory of Open Access Journals (Sweden)

    Gail Taillefer

    2012-02-01

    Full Text Available Le XXVIIIe Congrès de l’APLIUT en 2006 a soulevé plusieurs questions à propos des concepts de normalisation et de certification en langues dans l’enseignement supérieur, notamment sur la mise en œuvre du Cadre européen commun de référence. Mais cet outil ne représente qu’un élément de la méta-réflexion sur le rôle de l’enseignant en LANSAD à laquelle nous invitent plusieurs développements observés depuis un an, en France et ailleurs : l’inadéquation constatée entre l’« offre » de candidats formés dans l’esprit LANSAD et la « demande » de postes ainsi profilés, le débat sur l’évaluation et la certification en langues, la parution de rapports sur l’utilisation et l’impact économique des langues dans la vie professionnelle, les travaux menés sur la démarche qualité en LANSAD (notamment sur la formation des formateurs... Nous proposons une réflexion sur le chemin récemment parcouru – et qui reste à parcourir – en termes conceptuels, institutionnels et politiques.Change and development : insight into the workings of our own professionThe XXVIIIth APLIUT Congress in 2006 raised numerous questions about standardisation and language certification in higher education, particularly on the implementation of the Common European Framework of Reference. But the Framework is only one element among many recent developments, in France and elsewhere, which encourage LSP teachers to engage in meta-reflection on their own profession. Among them, the observed mismatch between the « supply » of appropriately trained applicants for posts in LSP and the « demand » of the job market for such teachers, the ongoing discussion on language assessment and certification, the publication of reports on the use of foreign languages in professional life and the economic issues at stake, the work carried out on quality assurance in LSP (particularly in teacher training... In conceptual, institutional and

  5. Status of Japanese university reactors

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, Yoshiaki [Research Reactor Institute, Kyoto Univ., Kumatori, Osaka (Japan)

    1999-08-01

    Status of Japanese university reactors, their role and value in research and education, and the spent fuel problem are presented. Some of the reactors are now faced by severe difficulties in continuing their operation services. The point of measures to solve the difficulties is suggested. (author)

  6. Brookhaven leak reactor to close

    CERN Multimedia

    MacIlwain, C

    1999-01-01

    The DOE has announced that the High Flux Beam Reactor at Brookhaven is to close for good. Though the news was not unexpected researchers were angry the decision had been taken before the review to assess the impact of reopening the reactor had been concluded (1 page).

  7. Reactor Neutrino Physics -- An Update

    OpenAIRE

    Boehm, Felix

    1999-01-01

    We review the status and the results of reactor neutrino experiments. Long baseline oscillation experiments at Palo Verde and Chooz have provided limits for the oscillation parameters while the recently proposed Kamland experiment at a baseline of more than 100km is now in the planning stage. We also describe the status of neutrino magnetic moment experiments at reactors.

  8. Chemical-vapor-deposition reactor

    Science.gov (United States)

    Chern, S.

    1979-01-01

    Reactor utilizes multiple stacked trays compactly arranged in paths of horizontally channeled reactant gas streams. Design allows faster and more efficient deposits of film on substrates, and reduces gas and energy consumption. Lack of dead spots that trap reactive gases reduces reactor purge time.

  9. Ficus sur (Moraceae and Gymnanthemum coloratum (Asteraceae: Vernonieae – first distribution records for Namibia

    Directory of Open Access Journals (Sweden)

    Wessel Swanepoel

    2015-03-01

    Full Text Available Background: The distribution of Ficus sur includes most of tropical Africa, but whilst this species was suspected to occur in Namibia, this has not been verified. Gymnanthemum coloratum is a tropical African savannah shrub or tree that has been recorded for Botswana, Swaziland and South Africa, but which has not previously been recorded for Namibia.Objectives: To formally document the first records of two plant species from Namibia and provide habitat details of the localities from which these species were recorded.Method: The data presented have resulted from botanical expeditions to the poorly known Baynes Mountains in the Koakoveld region of Namibia. Specimens of the two species in the National Herbarium, Pretoria were examined to verify the identity in the case of G. coloratum, and to document additional records in Namibia for F. sur.Results: Ficus sur was recorded from two localities, and a third locality based on a specimen in the National Herbarium, Pretoria, was verified. Gymnanthemum coloratum, a member of the Asteraceae, was recorded from a single locality.Conclusion: The fact that F. sur was collected at more than one location in the Kaokoveld suggests that it is probably more widespread in suitable microhabitats. Ficus sur also occurs further north in Angola, suggesting that the Kaokoveld plants represent a cross-border outlier of the much more widespread Angolan population. Gymnanthemum coloratum was only recorded from the one locality in the Koakoveld. The species also occurs in Angola, which suggests that the Kaokoveld plant represents a cross-border outlier of the population in that country.

  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. Eisosomes promote the ability of Sur7 to regulate plasma membrane organization in Candida albicans

    Science.gov (United States)

    Wang, Hong X.; Douglas, Lois M.; Veselá, Petra; Rachel, Reinhard; Malinsky, Jan; Konopka, James B.

    2016-01-01

    The plasma membrane of the fungal pathogen Candida albicans forms a protective barrier that also mediates many processes needed for virulence, including cell wall synthesis, invasive hyphal morphogenesis, and nutrient uptake. Because compartmentalization of the plasma membrane is believed to coordinate these diverse activities, we examined plasma membrane microdomains termed eisosomes or membrane compartment of Can1 (MCC), which correspond to ∼200-nm-long furrows in the plasma membrane. A pil1∆ lsp1∆ mutant failed to form eisosomes and displayed strong defects in plasma membrane organization and morphogenesis, including extensive cell wall invaginations. Mutation of eisosome proteins Slm2, Pkh2, and Pkh3 did not cause similar cell wall defects, although pkh2∆ cells formed chains of furrows and pkh3∆ cells formed wider furrows, identifying novel roles for the Pkh protein kinases in regulating furrows. In contrast, the sur7∆ mutant formed cell wall invaginations similar to those for the pil1∆ lsp1∆ mutant even though it could form eisosomes and furrows. A PH-domain probe revealed that the regulatory lipid phosphatidylinositol 4,5-bisphosphate was enriched at sites of cell wall invaginations in both the sur7∆ and pil1∆ lsp1∆ cells, indicating that this contributes to the defects. The sur7∆ and pil1∆ lsp1∆ mutants displayed differential susceptibility to various types of stress, indicating that they affect overlapping but distinct functions. In support of this, many mutant phenotypes of the pil1∆ lsp1∆ cells were rescued by overexpressing SUR7. These results demonstrate that C. albicans eisosomes promote the ability of Sur7 to regulate plasma membrane organization. PMID:27009204

  12. Cooling system for reactor container

    International Nuclear Information System (INIS)

    Purpose: To effectively cool a reactor container upon reactor shutdown with no intrusion of metal corrosion products in coolants into the main steam pipe in a BWR type reactor. Constitution: A clean up system comprising a pipeway, a recycling pump, a non-regenerative heat exchanger and a primary coolant purifier and a regenerative heat exchanger is provided branched from a residual heat removing system and the clean up system is connected by way of a valve to a feedwater pipeway, as well as connected by way of the pipeway to the main steam pipeway at the midway of two main steam separation valves outside of the reactor container. This enables to prevent metal corrosion products floating on the surface of reactor water from introducing into the main steam pipe when the pressure vessel is filled with water. Then, since the pressure vessel is filled with primary coolants, the pressure vessel can be cooled uniformly in a short time. (Ikeda, J.)

  13. Engineering reactors for catalytic reactions

    Indian Academy of Sciences (India)

    Vivek V Ranade

    2014-03-01

    Catalytic reactions are ubiquitous in chemical and allied industries. A homogeneous or heterogeneous catalyst which provides an alternative route of reaction with lower activation energy and better control on selectivity can make substantial impact on process viability and economics. Extensive studies have been conducted to establish sound basis for design and engineering of reactors for practising such catalytic reactions and for realizing improvements in reactor performance. In this article, application of recent (and not so recent) developments in engineering reactors for catalytic reactions is discussed. Some examples where performance enhancement was realized by catalyst design, appropriate choice of reactor, better injection and dispersion strategies and recent advances in process intensification/ multifunctional reactors are discussed to illustrate the approach.

  14. Directions in advanced reactor technology

    International Nuclear Information System (INIS)

    Successful nuclear power plant concepts must simultaneously performance in terms of both safety and economics. To be attractive to both electric utility companies and the public, such plants must produce economical electric energy consistent with a level of safety which is acceptable to both the public and the plant owner. Programs for reactor development worldwide can be classified according to whether the reactor concept pursues improved safety or improved economic performance as the primary objective. When improved safety is the primary goal, safety enters the solution of the design problem as a constraint which restricts the set of allowed solutions. Conversely, when improved economic performance is the primary goal, it is allowed to be pursued only to an extent which is compatible with stringent safety requirements. The three major reactor coolants under consideration for future advanced reactor use are water, helium and sodium. Reactor development programs focuses upon safety and upon economics using each coolant are being pursued worldwide. These programs are discussed

  15. Simulator for materials testing reactors

    International Nuclear Information System (INIS)

    A real-time simulator for both reactor and irradiation facilities of a materials testing reactor, “Simulator of Materials Testing Reactors”, was developed for understanding reactor behavior and operational training in order to utilize it for nuclear human resource development and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the JMTR (Japan Materials Testing Reactor), and it simulates operation, irradiation tests and various kinds of anticipated operational transients and accident conditions caused by the reactor and irradiation facilities. The development of the simulator was sponsored by the Japanese government as one of the specialized projects of advanced research infrastructure in order to promote basic as well as applied researches. This report summarizes the simulation components, hardware specification and operation procedure of the simulator. (author)

  16. Antineutrino Monitoring of Thorium Reactors

    CERN Document Server

    Akindele, Oluwatomi A; Norman, Eric B

    2015-01-01

    Various groups have demonstrated that antineutrino monitoring can be successful in assessing the plutonium content in water-cooled nuclear reactors for nonproliferation applications. New reactor designs and concepts incorporate nontraditional fuels types and chemistry. Understanding how these properties affect the antineutrino emission from a reactor can extend the applicability of antineutrino monitoring.Thorium molten salt reactors (MSR) breed U-233, that if diverted constitute an IAEA direct use material. The antineutrino spectrum from the fission of U-233 has been determined, the feasibility of detecting the diversion of a significant quantity, 8 kg of U-233, within the IAEA timeliness goal of 30 days has been evaluated. The antineutrino emission from a thorium reactor operating under normal conditions is compared to a diversion scenario at a 25 meter standoff by evaluating the daily antineutrino count rate and the energy spectrum of the detected antineutrinos. It was found that the diversion of a signifi...

  17. Fast reactors and nuclear nonproliferation

    International Nuclear Information System (INIS)

    Problems are discussed with regard to nuclear fuel cycle resistance in fast reactors to nuclear proliferation risk due to the potential for use in military programs of the knowledge, technologies and materials gained from peaceful nuclear power applications. Advantages are addressed for fast reactors in the creation of a more reliable mode of nonproliferation in the closed nuclear fuel cycle in comparison with the existing fully open and partially closed fuel cycles of thermal reactors. Advantages and shortcomings are also discussed from the point of view of nonproliferation from the start with fast reactors using plutonium of thermal reactor spent fuel and enriched uranium fuel to the gradual transition using their own plutonium as fuel. (author)

  18. Automated reactor records evaluation framework

    International Nuclear Information System (INIS)

    The only truly reliable method for core physics code validation is comparison against experimental data – and for power nuclear reactors, the only reasonably acquirable kind of experimental data are the reactor records. However, the amount of the data coming from the reactor operation is often so vast that it can be discouraging for the code developers to use it properly. Thus, the validation package is further reduced because the data is hard to use. This paper presents an elaborate, fully automated framework, which was designed and implemented in our institute, for reactor records processing and its use for core physics code validation. The workflow, implemented as a Web 2.0 application, provides a practical and painless solution for use of reactor records data for code development and validation. (author)

  19. Strategic planning for research reactors. Guidance for reactor managers

    International Nuclear Information System (INIS)

    The purpose of this publication is to provide guidance on how to develop a strategic plan for a research reactor. The IAEA is convinced of the need for research reactors to have strategic plans and is issuing a series of publications to help owners and operators in this regard. One of these covers the applications of research reactors. That report brings together all of the current uses of research reactors and enables a reactor owner or operator to evaluate which applications might be possible with a particular facility. An analysis of research reactor capabilities is an early phase in the strategic planning process. The current document provides the rationale for a strategic plan, outlines the methodology of developing such a plan and then gives a model that may be followed. While there are many purposes for research reactor strategic plans, this report emphasizes the use of strategic planning in order to increase utilization. A number of examples are given in order to clearly illustrate this function

  20. Evolution de la déflexion observée sur les chaussées souples modernes

    OpenAIRE

    LEPERT, P

    2006-01-01

    La mesure de deflexion a conservé un rôle important dans les campagnes d'auscultation et de suvi des chaussées. Or, bien qu'ayant fait l'objet d'études multiples, la question de l'évolution de la déflexion sur les chaussées modernes reste ouverte. Cette question est abordée avec des moyens statistiques en utilisant les nombreuses observations recueillies sur ces chaussées depuis plus de dix ans. L'analyse porte sur une population de 1 680 sections dites souples, c'est-à-dire essentiellement à...

  1. Mechanisms of anticonvulsant and sedative actions of the ethanolic stem-bark extract of Ficus sur Forssk (Moraceae) in rodents.

    Science.gov (United States)

    Ishola, Ismail O; Olayemi, Sunday O; Yemitan, Omoniyi K; Ekpemandudiri, Ngozi K

    2013-11-01

    Ficus sur Forssk (Moraceae) is used in traditional African medicine in the treatment of epilepsy, pain and inflammations. Anticonvulsant activity was investigated using picrotoxin (PTX), strychnine (SCN), isoniazid (INZ), pentylenetetrazole (PTZ) and N-methyl-D-aspartic acid NMDA models of convulsion. The phytochemical analysis of the extract revealed the presence of flavonoids, saponins, tannins, alkaloids and anthraquinone. Oral administration of Ficus sur, 1 h before intraperitoneal injection of chemical convulsants significantly (p uses of Ficus sur in the treatment of epilepsies; mechanisms of which could involve interaction with GABAergic, glycinergic, serotonergic and glutaminergic system barks. PMID:24511736

  2. Neutrino Experiments at Reactors

    Science.gov (United States)

    Reines, F.; Gurr, H. S.; Jenkins, T. L.; Munsee, J. H.

    1968-09-09

    A description is given of the electron-antineutrino program using a large fission reactor. A search has been made for a neutral weak interaction via the reaction (electron antineutrino + d .> p + n + electron antineutrino), the reaction (electron antineutrino + d .> n + n + e{sup +}) has now been detected, and an effort is underway to observe the elastic scattering reaction (electron antineutrino + e{sup -} .> electron antineutrino + e{sup -}) as well as to measure more precisely the reaction (electron antineutrino + p .> n + e{sup+}). The upper limit on the elastic scattering reaction which we have obtained with our large composite NaI, plastic, liquid scintillation detector is now about 50 times the predicted value.

  3. Licensed operating reactors

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar 1990) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  4. Reactor safety systems

    International Nuclear Information System (INIS)

    The spectrum of possible accidents may become characterized by the 'maximum credible accident', which will/will not happen. Similary, the performance of safety systems in a multitude of situations is sometimes simplified to 'the emergency system will/will not work' or even 'reactors are/ are not safe'. In assessing safety, one must avoid this fallacy of reducing a complicated situation to the simple black-and-white picture of yes/no. Similarly, there is a natural tendency continually to improve the safety of a system to assure that it is 'safe enough'. Any system can be made safer and there is usually some additional cost. It is important to balance the increased safety against the increased costs. (orig.)

  5. Reactor control rod

    International Nuclear Information System (INIS)

    Object: To enable quick descent of a control rod body even when some relative phase deviation between upper drive means and wrapper tube is produced, while permitting a coolant to effectively flow into a protective tube irrespective of the position of the control rod body. Structure: In a control rod used for a nuclear reactor such as a fast breeder, an orifice which dispenses with a cylindrical guide tube and has a greater inner diameter than the outer diameter of the protective tube of the control rod body is provided on the inner side of a wrapper tube, thus permitting smooth operation of the control rod body and also permitting the coolant to effectively flow into the protective tube irrespective of the control rod body. (Horiuchi, T.)

  6. Nuclear reactor spacer assembly

    International Nuclear Information System (INIS)

    A fuel assembly for a nuclear reactor is disclosed wherein the fuel element receiving and supporting grid is comprised of a first metal, the guide tubes which pass through the grid assembly are comprised of a second metal and the grid is supported on the guide tubes by means of expanded sleeves located intermediate the grid and guide tubes. The fuel assembly is fabricated by inserting the sleeves, of initial outer diameter commensurate with the guide tube outer diameters, through the holes in the grid assembly provided for the guide tubes and thereafter expanding the sleeves radially outwardly along their entire length such that the guide tubes can subsequently be passed through the sleeves. The step of radial expansion, as a result of windows provided in the sleeves having dimensions commensurate with the geometry of the grid, mechanically captures the grid and simultaneously preloads the sleeve against the grid whereby relative motion between the grid and guide tube will be precluded

  7. Nuclear reactor measurement system

    International Nuclear Information System (INIS)

    An instrument to detect the temperature and flow-rate of the liquid metal current of a coolant fluid sample from adjacent sub-assemblies of a liquid metal-cooled nuclear reactor is described. It includes three thermocouple hot junctions mounted in series, each intended for exposure to a sample-current from a single sub-assembly, electromagnetic coils being mounted around an induction core which detects variations in the liquid metal flow-rate by deformation of the lines of flux. The instrument may also include a thermocouple to detect the mean temperature of the sample-current of coolant fluid from several sources, the result being that the temperature of the coolant fluid current in a sub-assembly may be inferred from the three temperature readings associated with this sub-assembly

  8. OECD: Halden reactor project

    International Nuclear Information System (INIS)

    The work at the Project has continued in the two main fields: test fuel irradiation and fuel research, and computer based process supervision and control. Organizations participating in the Project continue to have their fuel irradiated in the Halden Reactor in instrumented test assemblies designed and manufactured by the Project. The Project's fuel studies continue to focus on specific subjects such as fuel pellet/cladding interaction and heat transfer, fission product release and fuel behavior under loss of coolant conditions. The work on process control and supervision continues in the highly relevant fields of core control and operator-process communication. A system for predictive core control is being developed while special mathematical methods for core power distribution control are being studied. Operator-process communication studies comprise use of computer simulation on colour display as important ingredients, while the work on developing a system for interactive plant disturbance analysis continues

  9. Tokamak fusion reactor exhaust

    International Nuclear Information System (INIS)

    This report presents a compilation of papers dealing with reactor exhaust which were produced as part of the TIGER Tokamak Installation for Generating Electricity study at Culham. The papers are entitled: (1) Exhaust impurity control and refuelling. (2) Consideration of the physical problems of a self-consistent exhaust and divertor system for a long burn Tokamak. (3) Possible bundle divertors for INTOR and TIGER. (4) Consideration of various magnetic divertor configurations for INTOR and TIGER. (5) A appraisal of divertor experiments. (6) Hybrid divertors on INTOR. (7) Refuelling and the scrape-off layer of INTOR. (8) Simple modelling of the scrape-off layer. (9) Power flow in the scrape-off layer. (10) A model of particle transport within the scrape-off plasma and divertor. (11) Controlled recirculation of exhaust gas from the divertor into the scrape-off plasma. (U.K.)

  10. Safety review, assessment and inspection on research reactors, experimental reactors, nuclear heating reactors and critical facilities

    International Nuclear Information System (INIS)

    The NNSA organized mainly in 1999 to complete the verification loop in core of the high flux experimental reactor with the 2000 kW fuel elements, the re-starting of China Pulsed Reactor, review and assessment on nuclear safety for the restarting of the Uranium-water critical Facility and treat the fracture event with the fuel tubes in the HWRR

  11. Power Reactors. Appendix VIII

    International Nuclear Information System (INIS)

    Decommissioning of nuclear facilities in many countries has evolved into a mature industry that has benefited from experience gained from previous projects and decommissioning costs can now be estimated to a good degree of accuracy. As a result of lessons learned, future decommissioning projects can be performed with higher levels of efficiency. Decommissioning of old power reactors is in progress in several countries. In some cases, decommissioning has been completed (i.e. plant sites have been released from regulatory control), while in other countries decommissioning is still in progress. Several large power reactors have been successfully decommissioned since 1995. The key areas of particular importance for decommissioning are decontamination, radiation protection, dismantling and demolition. The technologies which can be used for these tasks are commonly available on the market, but effective decommissioning still depends on an optimal choice of technologies, including site specific developments. It is not possible to recommend the use of a single specific technology for dismantling, demolition, segmentation or decontamination; rather, it is good practice to take into account as much information as possible from other decommissioning projects and to draw comparisons between various techniques in order to choose the one with the best performance in a particular situation. The exchange of information on all types of decommissioning experience, including decommissioning techniques and their applicability as well as disadvantages for specific tasks, is taking place on various levels, such as: — Collaborative working groups established by international organizations such as the IAEA, the OECD Nuclear Energy Agency and the European Commission and the publication of technical reports by such organizations; — National and international conferences; — Bilateral or multilateral cooperation and information exchange between organizations with responsibilities for

  12. Advanced fusion reactor

    Energy Technology Data Exchange (ETDEWEB)

    Tomita, Yukihiro [National Inst. for Fusion Science, Toki, Gifu (Japan)

    2003-04-01

    The main subjects on fusion research are now on D-T fueled fusion, mainly due to its high fusion reaction rate. However, many issues are still remained on the wall loading by the 14 MeV neutrons. In the case of D-D fueled fusion, the neutron wall loading is still remained, though the technology related to tritium breeding is not needed. The p-{sup 6}Li and p-{sup 11}B fueled fusions are not estimated to be the next generation candidate until the innovated plasma confinement technologies come in useful to achieve the high performance plasma parameters. The fusion reactor of D-{sup 3}He fuels has merits on the smaller neutron wall loading and tritium handling. However, there are difficulties on achieving the high temperature plasma more than 100 keV. Furthermore the high beta plasma is needed to decrease synchrotron radiation loss. In addition, the efficiency of the direct energy conversion from protons coming out from fusion reaction is one of the key parameters in keeping overall power balance. Therefore, open magnetic filed lines should surround the plasma column. In this paper, we outlined the design of the commercial base reactor (ARTEMIS) of 1 GW electric output power configured by D-{sup 3}He fueled FRC (Field Reversed Configuration). The ARTEMIS needs 64 kg of {sup 3}He per a year. On the other hand, 1 million tons of {sup 3}He is estimated to be in the moon. The {sup 3}He of about 10{sup 23} kg are to exist in gaseous planets such as Jupiter and Saturn. (Y. Tanaka)

  13. Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Following the accident at Chernobyl nuclear reactor, WHO organized on 6 May 1986 in Copenhagen a one day consultation of experts with knowledge in the fields of meteorology, radiation protection, biological effects, reactor technology, emergency procedures, public health and psychology in order to analyse the development of events and their consequences and to provide guidance as to the needs for immediate public health action. The present report provides detailed information on the transportation and dispersion of the radioactive material in the atmosphere, especially volatile elements, during the release period 26 April - 5 May. Presented are the calculated directions and locations of the radioactive plume over Europe in the first 5 days after the accident, submitted by the Swedish Meteorological and Hydrological Institute. The calculations have been made for two heights, 1500m and 750m and the plume directions are grouped into five periods, covering five European areas. The consequences of the accident inside the USSR and the radiological consequences outside the USSR are presented including the exposure routes and the biological effects, paying particular attention to iodine-131 effects. Summarized are the first reported measured exposure rates above background, iodine-131 deposition and concentrations in milk and the remedial actions taken in various European countries. Concerning the cesium-137 problem, based on the UNSCEAR assessment of the consequences of the nuclear fallout, one concludes that the cesium contamination outside the USSR is not likely to cause any serious problems. Finally, the conclusions and the recommendations of the meeting, taking into account both the short-term and longer term considerations are presented

  14. Nuclear reactor fuelling machine

    International Nuclear Information System (INIS)

    The refuelling machine described comprises a rotatable support structure having a guide tube attached to it by a parellel linkage mechanism, whereby the guide tube can be displaced sideways from the support structure. A gripper unit is housed within the guide tube for gripping the end of a fuel assembly or other reactor component and has means for maintenance in the engaging condition during travel of the unit along the guide tube, except for a small portion of the travel at one end of the guide tube, where the inner surface of the guide tube is shaped so as to maintain the gripper unit in a disengaging condition. The gripper unit has a rotatable head, means for moving it linearly within the guide tube so that a component carried by the unit can be housed in the guide tube, and means for rotating the head of the unit through 1800 relative to its body, to effect rotation of a component carried by the unit. The means for rotating the head of the gripper unit comprises ring and pinion gearing, operable through a series of rotatable shafts interconnected by universal couplings. The reason for provision for 1800 rotation is that due to the variation in the neutron flux across the reactor core the side of a fuel assembly towards the outside of the core will be subjected to a lower neutron flux and therefore will grow less than the side of the fuel assembly towards the inside of the core. This can lead to bowing and possible jamming of the fuel assemblies. Full constructional details are given. See also BP 1112384. (U.K.)

  15. Reliability of reactor materials

    International Nuclear Information System (INIS)

    This report is the final technical report of the fracture mechanics part of the Reliability of Reactor Materials Programme, which was carried out at the Technical Research Centre of Finland (VTT) through the years 1981 to 1983. Research and development work was carried out in five major areas, viz. statistical treatment and modelling of cleavage fracture, crack arrest, ductile fracture, instrumented impact testing as well as comparison of numerical and experimental elastic-plastic fracture mechanics. In the area of cleavage fracture the critical variables affecting the fracture of steels are considered in the frames of a statistical model, so called WST-model. Comparison of fracture toughness values predicted by the model and corresponding experimental values shows excellent agreement for a variety of microstructures. different posibilities for using the model are discussed. The development work in the area of crack arrest testing was concentrated in the crack starter properties, test arrangement and computer control. A computerized elastic-plastic fracture testing method with a variety of test specimen geometries in a large temperature range was developed for a routine stage. Ductile fracture characteristics of reactor pressure vessel steel A533B and comparable weld material are given. The features of a new, patented instrumented impact tester are described. Experimental and theoretical comparisons between the new and conventional testers indicated clearly the improvements achieved with the new tester. A comparison of numerical and experimental elastic-plastic fracture mechanics capabilities at VTT was carried out. The comparison consisted of two-dimensional linear elastic as well as elastic-plastic finite element analysis of four specimen geometries and equivalent experimental tests. (author)

  16. Regard sur les groupes d'equite en matiere d'emploi chez ceux ayant recemment obtenu un diplome d'etudes postsecondaires : minorites visibles, peuples autochtones et personnes limitees dans leurs activites quotidiennes

    OpenAIRE

    Caron, Nathalie; Wannell, Ted

    1994-01-01

    Les reglements sur l'equite en matiere d'emploi prennent de plus en plus d'importance sur les marches du travail au Canada. Cependant, outre des donnees globales sur la disponibilite, il existe peu de documents sur les experiences des groupes designes sur ces marches. Le present rapport, qui se fonde sur l'Enquete nationale aupres des diplomes de 1992, etablit le profil des premieres experiences sur le marche du travail des minorites visibles, des autochtones et des personnes atteintes d'une ...

  17. Licensed reactor nuclear safety criteria applicable to DOE reactors

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

  18. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards

  19. Souci du social et action publique sur mesure

    Directory of Open Access Journals (Sweden)

    Bertrand Ravon

    2008-10-01

    Full Text Available L’engagement dans la lutte contre les problèmes sociaux s’est transformé. Avec l’individualisation et la territorialisation du traitement public des problèmes sociaux, se pose de plus en plus nettement la question d’une action publique de proximité, intersubjective. Mais plutôt que de renvoyer immédiatement les raisons de cette action publique sur mesure à une critique de la psychologisation des rapports sociaux ou du déclin des institutions, il s’agit de l’analyser comme une expérience publique, avec son lot d’actions et d’affects, de convictions et d’inquiétudes, de ressources et de préoccupations. La notion de souci s’impose alors pour tenir ce double mouvement de l’engagement, entre agir et subir, des épreuves qui nous conduisent dans l’action aux attentes qui nous y maintiennent. À partir de plusieurs exemples de formation de problèmes sociaux, l’article décline alors le souci des acteurs dans deux directions. D’une part, le souci de soi est analysé comme un engagement public au sens d’un travail d’orientation de soi dans un monde incertain via la reprise d’expériences sociales négatives. D’autre part, le souci commun est envisagé comme une « communauté de charge », c’est-à-dire comme un collectif d’action publique fondé non pas à partir de propriétés communes mais à partir d’affects partagés.“Concern” in the social sphere and public action adapted to the client: singular and critical public experience of social problemsCommitment in the struggle against social problems has changed. Along with the individualisation and territorial decentralisation of the public treatment of social problems, the question of very local and intersubjective public action has come more and more into focus. But rather than immediately relegating the reasons for this tailor-made version of social action to a critique of the increasing influence of psychological methods in social relations

  20. Influence des effets de température quasi-statiques du premier ordre sur les dispositifs à ondes de surface transverses sur sillons gravés

    Science.gov (United States)

    Ballandras, S.; Gavignet, E.; Bigler, E.

    1995-02-01

    The present study is devoted to the theoretical calculation of the first order quasi-static temperature coefficient of surface transverse waves which can propagate under shallow groove gratings. The model presented here associates an analytical description of non-perturbed surface transverse waves on an anisotropic substrate developed by Auld and Tiersten's perturbation method. This approach has been implemented in the case of quartz delay lines corrugated with rectangular grooves. It is shown that singly rotated quartz cuts can be theoretically found exhibiting a first-order temperature coefficient close to zero. The sensitivity of this coefficient versus the groove depth is also theoretically demonstrated. La présente étude consiste à calculer le coefficient de température du premier ordre d'un résonateur à ondes transverses de surface se propageant sous un réseau de sillons gravés de forme quelconque. Ce calcul fait intervenir un modèle analytique de propagation des ondes sur un substrat anisotrope développé par Auld et une méthode de perturbation mise au point par Tiersten. Cette approche théorique a été mise en oeuvre pour traiter le cas des dispositifs à sillons gravés de profil rectangulaire sur quartz. On montre ainsi qu'il existe des coupes de quartz à simple rotation présentant un coefficient de température du premier ordre théorique proche de zéro. L'influence de la profondeur de gravure des sillons sur ce coefficient est également mise en évidence théoriquement.

  1. Oradour-sur-Glane: On the emergence of a glocal site of memory in France

    Directory of Open Access Journals (Sweden)

    Léger, Eva

    2014-12-01

    Full Text Available Oradour-sur-Glane (France is the memorial site of a massacre perpetrated by the Second SS Panzer Division Das Reich on June 10th, 1944. It preserves the memory of the 642 people slaughtered there, including 18 Spanish refugees. In 1945, the French State, led by General de Gaulle, decided to preserve the ruins of Oradour-sur- Glane. Since then, a series of commemorative processes have ensued at the site, corresponding to different temporalities. Over time, this site of national memory has been linked both with European memory discourse and with the private memory of exiled Spaniards and, consequently, with the memory of the Spanish Civil War and Francoism. In this article, I analyze the different appropriations and interpretations of the site, focusing in particular on the memory of the exiles. To do so, I will look into the initiatives undertaken between 2008 and 2014, considering both the institutions and the associations related to Oradour-sur-Glane.Oradour-sur-Glane (Francia es el lugar de memoria de una masacre perpetrada por la segunda división blindada S.S. Das Reich el 10 de junio de 1944 que conserva el recuerdo de sus 642 supliciados, entre los cuales 18 españoles refugiados. En 1945, el Estado francés encabezado por el General de Gaulle decidió preservar las ruinas de Oradour-sur-Glane. Desde entonces, diferentes procesos conmemorativos, correspondientes a temporalidades destacadas, se han sucedido en el sitio. Con el tiempo, este lugar de memoria nacional, se ha vinculado tanto con un discurso de memoria europeo como con la memoria particular de los españoles exiliados y a través de ello con la memoria de la Guerra Civil española y del franquismo. En este estudio analizaré las diferentes apropiaciones e interpretaciones de este lugar, enfocándome especialmente en la memoria de los exiliados. Para esto, contemplaré las iniciativas que se han desarrollado entre los años 2008 y 2014, atendiendo tanto a las instituciones como a

  2. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  3. On reactor type comparisons for the next generation of reactors

    International Nuclear Information System (INIS)

    In this paper, we present a broad comparison of studies for a selected set of parameters for different nuclear reactor types including the next generation. This serves as an overview of key parameters which provide a semi-quantitative decision basis for selecting nuclear strategies. Out of a number of advanced reactor designs of the LWR type, gas cooled type, and FBR type, currently on the drawing board, the Advanced Light Water Reactors (ALWR) seem to have some edge over other types of the next generation of reactors for the near-term application. This is based on a number of attributes related to the benefit of the vast operating experience with LWRs coupled with an estimated low risk profile, economics of scale, degree of utilization of passive systems, simplification in the plant design and layout, modular fabrication and manufacturing. 32 refs., 1 fig., 3 tabs

  4. Liste annexe : ouvrages et articles sur l’internationalisation de l’économie suisse ou sur certains secteurs spécifiques

    OpenAIRE

    2013-01-01

    ACHLEITNER, Paul Michael.– Sozio-politische Strategien multinationaler Unternehmungen : ein Ansatz gezielten Umweltmanagements.– Bern : Haupt, 1985.– 334 p.– (Diss. Hochschule St. Gallen)liens entre la FT et son environnement socio-économique, politique/ stratégie des FT face aux critiques/ brève étude de cas sur le boycott des produits Nestlé/ ANDREF, Wladimir ; MASINI, Jean.– Multinationales et développement. Quelles perspectives ? (publication collective)Revue Tiers Monde.– Paris, PUF, tom...

  5. Calculation of over-temperatures produced by a heterogeneous reaction; Sur le calcul des sur-temperatures produites par une reaction heterogene

    Energy Technology Data Exchange (ETDEWEB)

    Besson, J.; Herrmann, F.J.; Zankel, K. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1968-07-01

    It is shown that, when introducing some simplifying hypothesis which are generally valid, the evolution of the over-temperature by an heterogeneous reaction can be exactly calculated. The published curves make it possible to estimate its value in different cases. (authors) [French] Moyennant quelques hypotheses simplificatrices generalement valables, on montre la possibilite de calculer numeriquement l'evolution de la sur-temperature pour une reaction heterogene. Les courbes publiees permettent d'en evaluer l'importance dans differents cas. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1968-07-01

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

  7. Ageing management for research reactors

    International Nuclear Information System (INIS)

    During the past several years, ageing of research reactor facilities continues to be an important safety issue. Despite the efforts exerted by operating organizations and regulatory authorities worldwide to address this issue, the need for an improved strategy as well as the need for establishing and implementing a systematic approach to ageing management at research reactors was identified. This paper discusses, on the basis of the IAEA Safety Standards, the effect of ageing on the safety of research reactors and presents a proactive strategy for ageing management. A systematic approach for ageing management is developed and presented together with its key elements, along with practical examples for their application. (author)

  8. Fueling of tandem mirror reactors

    International Nuclear Information System (INIS)

    This paper summarizes the fueling requirements for experimental and demonstration tandem mirror reactors (TMRs), reviews the status of conventional pellet injectors, and identifies some candidate accelerators that may be needed for fueling tandem mirror reactors. Characteristics and limitations of three types of accelerators are described; neutral beam injectors, electromagnetic rail guns, and laser beam drivers. Based on these characteristics and limitations, a computer module was developed for the Tandem Mirror Reactor Systems Code (TMRSC) to select the pellet injector/accelerator combination which most nearly satisfies the fueling requirements for a given machine design

  9. Concept for LEU Burst Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Klein, Steven Karl [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kimpland, Robert Herbert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-07

    Design and performance of a proposed LEU burst reactor are sketched. Salient conclusions reached are the following: size would be ~1,500 kg or greater, depending on the size of the central cavity; internal stresses during burst require split rings for relief; the reactor would likely require multiple control and safety rods for fine control; the energy spectrum would be comparable to that of HEU machines; and burst yields and steady-state power levels will be significantly greater in an LEU reactor.

  10. Random processes in nuclear reactors

    CERN Document Server

    Williams, M M R

    1974-01-01

    Random Processes in Nuclear Reactors describes the problems that a nuclear engineer may meet which involve random fluctuations and sets out in detail how they may be interpreted in terms of various models of the reactor system. Chapters set out to discuss topics on the origins of random processes and sources; the general technique to zero-power problems and bring out the basic effect of fission, and fluctuations in the lifetime of neutrons, on the measured response; the interpretation of power reactor noise; and associated problems connected with mechanical, hydraulic and thermal noise sources

  11. Safety of VVER-440 reactors

    CERN Document Server

    Slugen, Vladimir

    2011-01-01

    Safety of VVER-440 Reactors endeavours to promote an increase in the safety of VVER-440 nuclear reactors via the improvement of fission products limitation systems and the implementation of special non-destructive spectroscopic methods for materials testing. All theoretical and experimental studies performed the by author over the last 25 years have been undertaken with the aim of improving VVER-440 defence in depth, which is one of the most important principle for ensuring safety in nuclear power plants. Safety of VVER-440 Reactors is focused on the barrier system through which the safety pri

  12. BR2 reactor neutron beams

    International Nuclear Information System (INIS)

    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. Inférence basée sur le plan pour l'estimation de petits domaines

    OpenAIRE

    RANDRIANASOLO, Toky; Tillé, Yves; Madre, Jean-Loup

    2014-01-01

    La forte demande de résultats à un niveau géographique fin, notamment à partir d’enquêtes nationales, a mis en évidence la fragilité des estimations sur petits domaines. Cette thèse propose d’y remédier avec des méthodes spécifiques basées sur le plan de sondage. Celles-ci reposent sur la construction de nouvelles pondérations pour chaque unité statistique. La première méthode consiste à optimiser le redressement du sous-échantillon d’une enquête inclus dans un domaine. La deuxième repose sur...

  14. 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...... effets des réglementations relatives à l’environnement sur la compétitivité des éleveurs laitiers de six pays de l’OCDE : le Canada, le Danemark, le Japon, la Nouvelle-Zélande, les PaysBas et la Suisse. Ces pays ont été choisis parce qu’ils représentent les principales régions productrices de lait de l...

  15. Nuclear reactor PBMR and cogeneration; Reactor nuclear PBMR y cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J. R.; Alonso V, G., E-mail: ramon.ramirez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    In recent years the nuclear reactor designs for the electricity generation have increased their costs, so that at the moment costs are managed of around the 5000 US D for installed kw, reason for which a big nuclear plant requires of investments of the order of billions of dollars, the designed reactors as modular of low power seek to lighten the initial investment of a big reactor dividing the power in parts and dividing in modules the components to lower the production costs, this way it can begin to build a module and finished this to build other, differing the long term investment, getting less risk therefore in the investment. On the other hand the reactors of low power can be very useful in regions where is difficult to have access to the electric net being able to take advantage of the thermal energy of the reactor to feed other processes like the water desalination or the vapor generation for the processes industry like the petrochemical, or even more the possible hydrogen production to be used as fuel. In this work the possibility to generate vapor of high quality for the petrochemical industry is described using a spheres bed reactor of high temperature. (Author)

  16. Reactor Safety Commission Code of Practice for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

  17. Breeder Reactors, Understanding the Atom Series.

    Science.gov (United States)

    Mitchell, Walter, III; Turner, Stanley E.

    The theory of breeder reactors in relationship to a discussion of fission is presented. Different kinds of reactors are characterized by the cooling fluids used, such as liquid metal, gas, and molten salt. The historical development of breeder reactors over the past twenty-five years includes specific examples of reactors. The location and a brief…

  18. FASTER test reactor preconceptual design report summary

    Energy Technology Data Exchange (ETDEWEB)

    Grandy, C. [Argonne National Lab. (ANL), Argonne, IL (United States); Belch, H. [Argonne National Lab. (ANL), Argonne, IL (United States); Brunett, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Heidet, F. [Argonne National Lab. (ANL), Argonne, IL (United States); Hill, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hoffman, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Jin, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Mohamed, W. [Argonne National Lab. (ANL), Argonne, IL (United States); Moisseytsev, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Passerini, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Sienicki, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Sumner, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Vilim, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hayes, Steven [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-02-29

    The FASTER reactor plant is a sodium-cooled fast spectrum test reactor that provides high levels of fast and thermal neutron flux for scientific research and development. The 120MWe FASTER reactor plant has a superheated steam power conversion system which provides electrical power to a local grid allowing for recovery of operating costs for the reactor plant.

  19. Research reactors: design, safety requirements and applications

    International Nuclear Information System (INIS)

    There are two types of reactors: research reactors or power reactors. The difference between the research reactor and energy reactor is that the research reactor has working temperature and fuel less than the power reactor. The research reactors cooling uses light or heavy water and also research reactors need reflector of graphite or beryllium to reduce the loss of neutrons from the reactor core. Research reactors are used for research training as well as testing of materials and the production of radioisotopes for medical uses and for industrial application. The difference is also that the research reactor smaller in terms of capacity than that of power plant. Research reactors produce radioactive isotopes are not used for energy production, the power plant generates electrical energy. In the world there are more than 284 reactor research in 56 countries, operates as source of neutron for scientific research. Among the incidents related to nuclear reactors leak radiation partial reactor which took place in three mile island nuclear near pennsylvania in 1979, due to result of the loss of control of the fission reaction, which led to the explosion emitting hug amounts of radiation. However, there was control of radiation inside the building, and so no occurred then, another accident that lead to radiation leakage similar in nuclear power plant Chernobyl in Russia in 1986, has led to deaths of 4000 people and exposing hundreds of thousands to radiation, and can continue to be effect of harmful radiation to affect future generations. (author)

  20. Conceptual design study of JSFR reactor building

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, T.; Katoh, A.; Chikazawa, Y. [Japan Atomic Energy Agency (JAEA), 4002 Narita, Oarai, Ibaraki 311-1393 (Japan); Ohya, T.; Iwasaki, M.; Hara, H.; Akiyama, Y. [Mitsubishi FBR Systems, Inc. MFBR, 34-17, Jingumae 2-chome, Shibuya, Tokyo 150-0001 (Japan)

    2012-07-01

    Japan Sodium-cooled Fast Reactor (JSFR) is planning to adopt the new concepts of reactor building. One is that the steel plate reinforced concrete is adopted for containment vessel and reactor building. The other is the advanced seismic isolation system. This paper describes the detail of new concepts for JSFR reactor building and engineering evaluation of the new concepts. (authors)

  1. FASTER test reactor preconceptual design report summary

    International Nuclear Information System (INIS)

    The FASTER reactor plant is a sodium-cooled fast spectrum test reactor that provides high levels of fast and thermal neutron flux for scientific research and development. The 120MWe FASTER reactor plant has a superheated steam power conversion system which provides electrical power to a local grid allowing for recovery of operating costs for the reactor plant.

  2. artographie des risques naturels dans les Pyrénées et sur leur piémont

    Directory of Open Access Journals (Sweden)

    Jean-Marc ANTOINE

    1994-12-01

    Full Text Available Les recherches menées par le CIMA URA-366 sur les risques naturels dans les Pyrénées privilégient leur dimension historique et l’étude des contextes socio-écologiques dans lesquels ils s’inscrivent. Cette approche novatrice débouche sur une cartographie historique des phénomènes, conjugant plusieurs niveaux d’analyse spatiotemporels.

  3. The 14 october 1999 nuclear accident simulation drill at Nogent-sur-Seine NPP role of the local information committee (C.L.I.)

    International Nuclear Information System (INIS)

    The EDF nuclear power plant at Nogent-sur-Seine consists in two 1 300 MWe pressurised water reactor units. It is located 120 km south-east of Paris. The Local Information Committee, which brigs 120 members together, was created when the plant started operating in 1988. The 14 October 1999 nuclear accident simulation drill, the sequence of which started from an incident in the virtual Unit 3, was intended to testing the reacting capacities of the local and national emergency PCs (command post). The main objective was to actually implement the evacuation of a 500 inhabitants village near the plant in order to manage their rallying in a reception centre about 15 kilometers from there. The aim was to assess the speed and accuracy of the alert to the population, the requisitioning of human and practical resources, the affected area cordoning off, the evacuation of two schools, the activation of the reception centre with firemen, doctors and finally direct work with the media. The CLI was involved from the initial stages in the 6 preparatory meetings and, on the day of the drill, put observers in the strategic places. After the drill it was invited to give its opinion during feedback meetings organised by authorities, both the Aube Prefecture in Troyes and the Nuclear Installation Safety Directorate in Paris. Our CLI had prepared in 1997 reactor cards 'fiches reflexes' for local representatives, which in the light of this drill, could be improved. CLI participation to the rewriting - at national level - PPI (offsite emergency plans) is all the more active since it is done in the light of this drill. Il will be the same with the reissue of our public information brochure dealing with security instructions. In a more general way, it appears that such a drill would have been completely excluded only ten years ago. (author)

  4. Light water reactor safety research

    International Nuclear Information System (INIS)

    As the technology of light water reactors (LWR) was being commercialized, the German Federal Government funded the reactor safety research program, which was conducted by national research centers, universities, and industry, and which led to the establishment, in early 1972, of the Nuclear Safety Project in Karlsruhe. In the seventies, the PNS project mainly studied the loss-of-coolant accident. Numerous experiments were run and computer codes developed for this purpose. In the eighties, the Karlsruhe Nuclear Research Center contributed to the German Risk Study, investigating especially core meltdown accidents under the impact of the events at Three Mile Island-2 and Chernobyl-4. Safety research in the nineties is concentrated on the requirements of future reactor generations, such as the European Pressurized Water Reactor (EPR) or potential approaches which, at the present time, are discernible only as tentative theoretical designs. (orig.)

  5. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, L.R.; Hayes, D.W.; Hunter, C.H.; Marter, W.L.; Moyer, R.A.

    1989-12-01

    This volume is a reactor operation environmental information document for the Savannah River Plant. Topics include meteorology, surface hydrology, transport, environmental impacts, and radiation effects. 48 figs., 56 tabs. (KD)

  6. Fuel for advanced CANDU reactors

    International Nuclear Information System (INIS)

    The CANDU reactor system has proven itself to be a world leader in terms of station availability and low total unit energy cost. In 1985 for example, four of the top ten reactor units in the world were CANDU reactors operating in South Korea and Canada. This excellent operating record requires an equivalent performance record of the low-cost, natural uranium fuel. Future CANDU reactors will be an evolution of the present design. Engineering work is under way to refine the existing CANDU 600 and to incorporate state-of-the-art technology, reducing the capital cost and construction schedule. In addition, a smaller CANDU 300 plant has been designed using proven CANDU 600 technology and components but with an innovative new plant layout that makes it cost competitive with coal fired plants. For the long term, work on advanced fuel cycles and major system improvements is underway ensuring that CANDU plants will stay competitive well into the next century

  7. Conceptual design of RFC reactor

    International Nuclear Information System (INIS)

    A parametic analysis and a preliminary conceptual design for RFC reactor (including cusp field) with and without alpha particle heating are described. Steady state operations can be obtained for various RF ponderomotive potential in cases of alpha particle heating. (author)

  8. Methanogenesis in Thermophilic Biogas Reactors

    DEFF Research Database (Denmark)

    Ahring, Birgitte Kiær

    1995-01-01

    against Methanothrix soehngenii or Methanothrix CALS-I in any of the thermophilic biogas reactors examined. Studies using 2-14C-labeled acetate showed that at high concentrations (more than approx. 1 mM) acetate was metabolized via the aceticlastic pathway, transforming the methyl-group of acetate...... microorganism into methane. In thermophilic biogas reactors,, acetate oxidizing cultures occupied the niche of Methanothrix species, aceticlastic methanogens which dominate at low acetate concentrations in mesophilic systems. Normally, thermophilic biogas reactors are operated at temperatures from 52 to 560 C....... Experiments using biogas reactors fed with cow manure showed that the same biogas yield found at 550 C could be obtained at 610 C after a long adaptation period. However, propionate degradation was inhibited by increasing the temperature....

  9. Teaching About Nature's Nuclear Reactors

    CERN Document Server

    Herndon, J M

    2005-01-01

    Naturally occurring nuclear reactors existed in uranium deposits on Earth long before Enrico Fermi built the first man-made nuclear reactor beneath Staggs Field in 1942. In the story of their discovery, there are important lessons to be learned about scientific inquiry and scientific discovery. Now, there is evidence to suggest that the Earth's magnetic field and Jupiter's atmospheric turbulence are driven by planetary-scale nuclear reactors. The subject of planetocentric nuclear fission reactors can be a jumping off point for stimulating classroom discussions about the nature and implications of planetary energy sources and about the geomagnetic field. But more importantly, the subject can help to bring into focus the importance of discussing, debating, and challenging current thinking in a variety of areas.

  10. RA reactor operation and maintenance

    International Nuclear Information System (INIS)

    This volume includes the final report on RA reactor operation and utilization of the experimental facilities in 1962, detailed analysis of the system for heavy water distillation and calibration of the system for measuring the activity of the air

  11. Technique of nuclear reactors controls

    International Nuclear Information System (INIS)

    This report deal about 'Techniques of control of the nuclear reactors' in the goal to achieve the control of natural uranium reactors and especially the one of Saclay. This work is mainly about the measurement into nuclear parameters and go further in the measurement of thermodynamic variables,etc... putting in relief the new features required on behalf of the detectors because of their use in the thermal neutrons flux. In the domain of nuclear measurement, we indicate the realizations and the results obtained with thermal neutron detectors and for the measurement of ionizations currents. We also treat the technical problem of the start-up of a reactor and of the reactivity measurement. We give the necessary details for the comprehension of all essential diagrams and plans put on, in particular, for the reactor of Saclay. (author)

  12. Jules Horowitz Reactor, basic design

    Energy Technology Data Exchange (ETDEWEB)

    Bergamaschi, Y.; Bouilloux, Y.; Chantoin, P.; Guigon, B.; Bravo, X.; Germain, C.; Rommens, M.; Tremodeux, P

    2003-07-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it. It has the ambition to provide the necessary nuclear data and maintain a fission research capacity in Europe after 2010. This capacity should be service-oriented. It will be established in Cadarache. The Jules Horowitz reactor will also: - represent a significant step in term of performances and experimental capabilities, - be designed with a high flexibility, in order to satisfy the current demand from European industry, research and be able to accommodate future requirements, - reach a high level of safety, according to the best current practice. This paper will present the main functionalities and the design options resulting from the 'preliminary design' studies. (authors)

  13. Unique features of space reactors

    Science.gov (United States)

    Buden, David

    Space reactors are designed to meet a unique set of requirements; they must be sufficiently compact to be launched in a rocket to their operational location, operate for many years without maintenance and servicing, operate in extreme environments, and reject heat by radiation to space. To meet these restrictions, operating temperatures are much greater than in terrestrial power plants, and the reactors tend to have a fast neutron spectrum. Currently, a new generation of space reactor power plants is being developed. The major effort is in the SP-100 program, where the power plant is being designed for seven years of full power, and no maintenance operation at a reactor outlet operating temperature of 1350 K.

  14. Advanced Catalytic Hydrogenation Retrofit Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Reinaldo M. Machado

    2002-08-15

    Industrial hydrogenation is often performed using a slurry catalyst in large stirred-tank reactors. These systems are inherently problematic in a number of areas, including industrial hygiene, process safety, environmental contamination, waste production, process operability and productivity. This program proposed the development of a practical replacement for the slurry catalysts using a novel fixed-bed monolith catalyst reactor, which could be retrofitted onto an existing stirred-tank reactor and would mitigate many of the minitations and problems associated with slurry catalysts. The full retrofit monolith system, consisting of a recirculation pump, gas/liquid ejector and monolith catalyst, is described as a monolith loop reactor or MLR. The MLR technology can reduce waste and increase raw material efficiency, which reduces the overall energy required to produce specialty and fine chemicals.

  15. Advanced Carbothermal Electric Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — ORBITEC proposes to develop the Advanced Carbothermal Electric (ACE) reactor to efficiently extract oxygen from lunar regolith. Unlike state-of-the-art carbothermal...

  16. Advanced Carbothermal Electric Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The overall objective of the Phase 1 effort was to demonstrate the technical feasibility of the Advanced Carbothermal Electric (ACE) Reactor concept. Unlike...

  17. Gas-cooled fast breeder reactor

    International Nuclear Information System (INIS)

    Almost all the R D works of gas-cooled fast breeder reactor in the world were terminated at the end of the year 1980. In order to show that the R D termination was not due to technical difficulties of the reactor itself, the present paper describes the reactor plant concept, reactor performances, safety, economics and fuel cycle characteristics of the reactor, and also describes the reactor technologies developed so far, technological problems remained to be solved and planned development schedules of the reactor. (author)

  18. Solid State Reactor Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Mays, G.T.

    2004-03-10

    The Solid State Reactor (SSR) is an advanced reactor concept designed to take advantage of Oak Ridge National Laboratory's (ORNL's) recently developed graphite foam that has enhanced heat transfer characteristics and excellent high-temperature mechanical properties, to provide an inherently safe, self-regulated, source of heat for power and other potential applications. This work was funded by the U.S. Department of Energy's Nuclear Energy Research Initiative (NERI) program (Project No. 99-064) from August 1999 through September 30, 2002. The initial concept of utilizing the graphite foam as a basis for developing an advanced reactor concept envisioned that a suite of reactor configurations and power levels could be developed for several different applications. The initial focus was looking at the reactor as a heat source that was scalable, independent of any heat removal/power conversion process. These applications might include conventional power generation, isotope production and destruction (actinides), and hydrogen production. Having conducted the initial research on the graphite foam and having performed the scoping parametric analyses from neutronics and thermal-hydraulic perspectives, it was necessary to focus on a particular application that would (1) demonstrate the viability of the overall concept and (2) require a reasonably structured design analysis process that would synthesize those important parameters that influence the concept the most as part of a feasible, working reactor system. Thus, the application targeted for this concept was supplying power for remote/harsh environments and a design that was easily deployable, simplistic from an operational standpoint, and utilized the new graphite foam. Specifically, a 500-kW(t) reactor concept was pursued that is naturally load following, inherently safe, optimized via neutronic studies to achieve near-zero reactivity change with burnup, and proliferation resistant. These four major areas

  19. Réalisation de réseaux sur polymères par laser UV

    Science.gov (United States)

    Castex, M. C.; Fischer, A.; Simeonov, D.; Adès, D.; Siove, A.

    2003-06-01

    Nous présentons ici une méthode très simple de réalisation de réseaux d'amplitude de pas sub-micronique sur des films polymères à base de carbazote déposés sur des substrat de silice. Les réseaux sont fabriqués en irradiant avec un faisceau laser à 193nm un masque de phase placé au contact du film. La qualité des réseaux obtenus permet désormais d'envisager la réalisation de micro-cavités lasers de type planaire permettant de sélectionner une émission laser monomode autour de 400nm.

  20. Synthèse des systèmes guidés sur pneus

    OpenAIRE

    SOULAS,C

    2002-01-01

    Depuis quelques années, il est beaucoup question des systèmes guidés de surface dits systèmes 'intermédiaires' (intermédiaires entre bus/trolley et tramway). En France, les transports guidés urbains sur pneus sont également bien représentés avec le métro sur pneus et avec les systèmes automatiques. En règle générale, tous ces systèmes sont à traction électrique. Il est d'ailleurs intéressant de remarquer qu'en France comme dans d'autres pays (Etats-Unis, Japon) la plupart des systèmes automat...

  1. Cancer mortality in the commune of Pargny sur Saulx in France

    International Nuclear Information System (INIS)

    Radioactive thorium wastes were found in April 1997 at the former industrial site of 'Orflam-Plast' in the commune of Pargny sur Saulx in the Northeast of France, where industrial activity began in 1934. On this site, between 1934 and 1970, cerium for lighter stones and thorium nitrate were extracted from imported monazite sand, a mineral containing elevated levels of natural radioactivity. We decided to study cancer mortality in the surrounding population. We found an excess of mortality due to lung and bladder cancer in the commune of Pargny sur Saulx and its neighbours, between 1968 and 1994. This excess did not seem to be linked to the river of Saulx which was a possible source of contamination. We conclude that a cancer incidence study of the former workers of this industrial site is necessary in order to investigate the role of natural radioactivity from monazite processing in the risk of cancer mortality among this workforce. (author)

  2. Whitehead et Schröder, sur l’algèbre de la logique

    OpenAIRE

    Barraya, Patrice

    2009-01-01

    Nous allons dans ce papier comparer l’algèbre de la logique exposée par Schröder dans les leçons sur l’algèbre de la logique (Vorlesungen über die Algebra der Logik) et celle explicitée par Whitehead dans son traité sur l’algèbre universelle (A Treatise on Universal Algebra) ainsi que dans son ouvrage majeur Principia mathematica coécrit avec Russell. Pour ce faire, nous allons tout d’abord nous intéresser au problème d’élimination qui constitue un des points d’orgue du traité de Schröder. Pa...

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

    Directory of Open Access Journals (Sweden)

    Attia Nicole

    2006-01-01

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

  4. Malarce-sur-La-Thines, Sainte-Marguerite-La-Figère

    OpenAIRE

    Dumoulin, François; Girard, Jérôme

    2013-01-01

    Identifiant de l'opération archéologique : 10037 Date de l'opération : 2009 (SP) La mise en sécurité des mines de Sainte-Marguerite-Lafigère a été précédé d'une intervention d'archéologie préventive de fouille, visant à renseigner cet important secteur minier. L'intervention menée par la société Iker archéologie durant 5 semaines de terrain, a porté essentiellement sur la quartier de la Rouvière, le Vallat du Colombier, mais aussi sur le secteur du Vert, qui s'est révélé particulièrement rich...

  5. Comprendre et intervenir sur le stress au travail : une étude de cas

    OpenAIRE

    Poirel, Emmanuel; Yvon, Frédéric

    2012-01-01

    Cet article tente de mettre à l’épreuve le modèle émotivo-transactionnel sur la base de données recueillies grâce à un dispositif de confrontation vidéo (autoconfrontation). Il met en évidence une distorsion classique de ce modèle qui sert à légitimer des interventions psycho-organisationnelles centrées sur l’individu. L’analyse précise et détaillée d’un incident prenant place dans le cadre des missions de sécurité d’agent de train montre que le stress pathologique est de l’ordre d’une expéri...

  6. La littérature sur l’industrialisation colombienne: bilan et perspective

    OpenAIRE

    León Palacios, Paulo César

    2011-01-01

    L'article révise de façon profonde et analytique la littérature consacrée au thème de l'industrie en Colombie, dans les domaines théoriques, méthodologiques et de la gnoséologie. Il constitue une référence nécessaire autant pour les experts - car il propose un débat global et critique sur le thème - que pour des étudiants ou des chercheurs qui désirent avoir une vision panoramique de l'état de l'art sur l'industrialisation sans approfondir le thème.

  7. ProVoc : une ontologie pour décrire des produits sur le Web

    OpenAIRE

    Lopez, Cédric; Nooralahzadeh, Farhad; Cabrio, Elena; Segond, Frédérique; Gandon, Fabien

    2016-01-01

    De nombreuses recherches ont depuis longtemps motivé l'utilisation d'ontologies pour répondre aux besoins de représentation du e-Commerce. Dans cet article, nous présentons ProVoc (Product Vocabulary), une ontologie ayant pour objectif de décrire des produits sur le Web. Complémentaire à GoodRelations (Hepp, 2008), l'ontologie au format du Web sémantique la plus utilisée dans le monde du e-Commerce, Provoc se concentre sur une représentation fine des produits et de leurs entités relatives (ga...

  8. La diffusion de l’information sur la biodiversité en France

    Directory of Open Access Journals (Sweden)

    Laurent Poncet

    2014-06-01

    Full Text Available Le contexte L’inventaire du patrimoine naturel est institué pour l’ensemble du territoire national terrestre, fluvial et marin par le code de l’environnement (L411-5. Le ministère en charge de l’écologie en assure la gouvernance globale, définit les objectifs et organise un système de partage de l’information. Il a ainsi organisé la mise en place d’une part du Système d’Information sur la nature et le paysage (SINP qui organise la production et la diffusion des informations sur la biodivers...

  9. L'information routière sur les durées de parcours

    OpenAIRE

    Cambon-De-Lavalette, B.

    2002-01-01

    Depuis quelques années, les voies rapides urbaines sont équipées de dispositifs appréciés des usagers, qui informent sur les durées de parcours. Des observations de l'incidence des messages sur les conducteurs ont été réalisées : ces messages permettraient de prendre des décisions adaptées, de mieux gérer le temps et, de là, l'activité dans les encombrements. Afin de comprendre les raisons pour lesquelles le contenu de ces messages incite à ce comportement, nous avons cherché à élaborer, sous...

  10. A new species of Rhadinella (Serpentes: Colubridae) from the Sierra Madre del Sur of Guerrero, Mexico.

    Science.gov (United States)

    Campillo, Gustavo; Dávila-Galavíz, Luis Fernando; Flores-Villela, Oscar; Campbell, Jonathan A

    2016-01-01

    We describe a new species of Rhadinella from the Sierra Madre del Sur of Guerrero, Mexico, a region where the genus was previously unknown. This diminutive species is a member of a group of snakes previously allocated in the Rhadinaea godmani group, and more recently transferred to the genus Rhadinella. These snakes may have conspicuous dark longitudinal striping on a pale brown to orange background or may have dark brown to blackish dorsal ground coloration, which mostly or completely obfuscates a pattern of longitudinal striping. The new species is mostly dark with barely discernible slightly paler or darker striping (depending on how striping is interpreted). The closest relative of the new species, on the basis of morphological similarities and biogeography, appears to be Rhadinella donaji which occurs to the east in the Sierra Madre del Sur of Oaxaca about 275 km from the type-locality of the new species.

  11. Évaluation et impact du sentiment de discrimination sur les trajectoires professionnelles

    OpenAIRE

    Lizé, Laurence; Joseph, Olivier; Lemière, Séverine; Rousset, Patrick

    2010-01-01

    Cette recherche porte sur les individus qui estiment avoir été victimes de discrimination, c'est-à-dire avoir subi un traitement inégal, de manière intentionnelle ou non, en raison de leur origine étrangère et/ou de leur couleur de peau. L'objectif est de s'intéresser au sentiment de discrimination et de chercher à évaluer son effet sur les parcours professionnels sept ans après la sortie du système éducatif. À partir de l'enquête Génération 98 du Céreq à 7 ans, nous avons utilisé la méthode ...

  12. Analyse du frottement dans les essais de compression sur barres d'Hopkinson

    OpenAIRE

    Lichtenberger, A.; Lach, E.; Bohmann, A.

    1994-01-01

    Une étude a été menée sur l'influence du frottement sur les résultats d'essais de compressions statique et dynamique. Un relevé du profil après déformation plastique d'éprouvettes cylindriques a été effectué afin d'évaluer l'importance du frottement dans les essais. Une simulation numérique de cet essai permet avec un coefficient de frottement adapté de retrouver la forme de l'échantillon déformé. Par ailleurs, le coefficient de frottement a été déterminé à partir d'essais de compressions d'a...

  13. Deux disques sur les minorités du Viêt-Nam

    OpenAIRE

    Rappoport, Dana

    2011-01-01

    Depuis 1993, Patrick Kersalé se rend régulièrement au Viêt-nam : il a déjà réalisé dix disques sur les musiques traditionnelles du Viêt-nam, et un onzième — sur les musiques Joraï — sortira sous peu. La variété et la quantité de ces enregistrements font du catalogue de Kersalé l’un des plus riches concernant le Viêt-nam dans le domaine de l’édition discographique française. Le Viêt-nam ne constitue pourtant pas sa seule aire d’investigation puisque depuis six ans, il a déjà fait paraître 48 d...

  14. Débat – Faut-il tirer sur les tapis volants ?

    OpenAIRE

    Benoist, Jean

    2009-01-01

    Le débat sur l’homéopathie amorcé récemment par l’Académie de médecine a entraîné la réaction du Ministre de la santé et les protestations de certains laboratoires spécialisés ; assorti du bruit soulevé parmi les patients et des positions contradictoires du corps médical, tout cela a pour les anthropologues la valeur d’une expérimentation grandeur nature sur la place, qui étonne hors de France, de l’homéopathie dans la société française. Beau sujet de réflexion. Espérons que quelque chercheur...

  15. Conception d'Antenne Spirale intégrée sur SOI à 60 GHz

    OpenAIRE

    Barakat, Moussa; Delaveaud, Christophe; Dussopt, Laurent; Ndagijimana, Fabien

    2009-01-01

    La conception d'une antenne spirale intégrée sur SOI est décrite. L'impact de la structure d'alimentation de l'antenne spirale à double brin sur le coefficient de réflexion et le rapport axial est analysé. Un bon coefficient de réflexion avec une bande passante de 35 GHz à -10 dB et une bonne polarisation circulaire couvrant une intervalle d'angle élévation de 120° indépendamment de l'angle d'azimut sont obtenus. L'efficacité de rayonnement simulée est de 80 % avec un gain simulé de 4.3 dBi....

  16. Etude de l'influence des granulats recyclés sur le comportement des MBE

    OpenAIRE

    TAHAR, Zine el abidine; KADRI, El-Hadj; NGO, Tien-Tung; BOUVET, Adrien; KACI, Abdelhak; Aggoun, Salima

    2015-01-01

    International audience L'élargissement de l'utilisation des matériaux cimentaires comportant des granulats recyclés, dont les propriétés physico-chimiques sont différentes de ceux à base de granulats naturels, est inévitablement cautionné par une maitrise accrue, d'une part, de leurs propriétés mécaniques, d'autre part, de leur mise en œuvre. Afin d'optimiser ces derniers, l'étude menée porte principalement sur l'impact de la nature et du dosage en granulats recyclés sur la mise en œuvre e...

  17. L’impact des pratiques de Supply Chain Management sur la performance de l’entreprise

    OpenAIRE

    Frank Brulhart; Btissam Moncef

    2010-01-01

    (VF)S’il existe de nombreuses études reliant le Supply Chain Management (SCM) et le développement d’un avantage concurrentiel, elles restent néanmoins à la fois dispersées et incomplètes. Cet article vise tout d’abord à expliciter la notion de pratiques de SCM (PSCM) puis à identifier l’impact de ces pratiques sur la performance. Au final, le modèle teste l’influence de 3 PSCM sur 8 dimensions complémentaires (financières et non financières) de la performance de la firme dans le contexte fran...

  18. Material test reactor fuel research at the BR2 reactor

    International Nuclear Information System (INIS)

    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

  19. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Iwashige, Kengo

    1996-06-21

    In an LMFBR type reactor, partitions are disposed to a coolant channel at positions lower than the free liquid level, and the width of the partitions is adapted to have a predetermined condition. Namely, when low temperature fluid overflowing the wall of the coolant channel, flows down and collided against the free liquid surface in the coolant channel, since the dropping speed thereof is reduced abruptly, large pressure waves are caused by kinetic force of the low temperature fluid. However, if appropriate numbers of partitions having an appropriate shape are formed, the dropping speed of the low temperature fluid is moderated to reduce the pressure waves. In addition, since the pressure waves are dispersed to the circumferential and lateral directions of the coolant flow channel respectively, the propagation of the pressure waves can be prevented effectively. Further, when the flow of the low temperature fluid is changed to the circumferential direction, for example, by earthquakes, since the partitions act as members resisting against the circumferential change of the low temperature fluid, the change of the direction can be suppressed. (N.H.)

  20. Natural convection type reactor

    International Nuclear Information System (INIS)

    In a natural convection type nuclear reactor, recycling flow rate of coolants is increased and the amount of entrained bubbles are increased as the driving force is increased, so that bubbles are not separated completely even if a stagnation region is disposed. Then, a space opened only at the upper portion is disposed at the outer circumference of the upper end of a riser for storing overflown coolants temporarily. The flow of coolants incorporating steam bubbles uprising in the riser turns into the horizontal direction at the upper end of the riser wall and flows into the coolant reservoir. In the coolant reservoir, since the momentum of the coolants is lost and the flow is stagnated, the bubbles are easily released to the upper space. Coolants, after releasing the bubbles, further overflow and descend in the downcomer. Then, the bubbles can be separated undergoing no influence of the driving force caused as the sum of the uprising force in the riser and the water head pressure in the downcomer, to prevent increase of carry under due to increase of the driving force. (N.H.)

  1. Reactor Simulator Testing Overview

    Science.gov (United States)

    Schoenfeld, Michael P.

    2013-01-01

    Test Objectives Summary: a) Verify operation of the core simulator, the instrumentation & control system, and the ground support gas and vacuum test equipment. b) Examine cooling & heat regeneration performance of the cold trap purification. c) Test the ALIP pump at voltages beyond 120V to see if the targeted mass flow rate of 1.75 kg/s can be obtained in the RxSim. Testing Highlights: a) Gas and vacuum ground support test equipment performed effectively for operations (NaK fill, loop pressurization, and NaK drain). b) Instrumentation & Control system effectively controlled loop temperature and flow rates or pump voltage to targeted settings and ramped within prescribed constraints. It effectively interacted with reactor simulator control model and defaulted back to temperature control mode if the transient fluctuations didn't dampen. c) Cold trap design was able to obtain the targeted cold temperature of 480 K. An outlet temperature of 636 K was obtained which was lower than the predicted 750 K but 156 K higher than the minimum temperature indicating the design provided some heat regeneration. d) ALIP produce a maximum flow rate of 1.53 kg/s at 800 K when operated at 150 V and 53 Hz.

  2. Reactor Simulator Testing

    Science.gov (United States)

    Schoenfeld, Michael P.; Webster, Kenny L.; Pearson, Boise J.

    2013-01-01

    As part of the Nuclear Systems Office Fission Surface Power Technology Demonstration Unit (TDU) project, a reactor simulator test loop (RxSim) was design & built to perform integrated testing of the TDU components. In particular, the objectives of RxSim testing was to verify the operation of the core simulator, the instrumentation and control system, and the ground support gas and vacuum test equipment. In addition, it was decided to include a thermal test of a cold trap purification design and a pump performance test at pump voltages up to 150 V since the targeted mass flow rate of 1.75 kg/s was not obtained in the RxSim at the originally constrained voltage of 120 V. This paper summarizes RxSim testing. The gas and vacuum ground support test equipment performed effectively in NaK fill, loop pressurization, and NaK drain operations. The instrumentation and control system effectively controlled loop temperature and flow rates or pump voltage to targeted settings. The cold trap design was able to obtain the targeted cold temperature of 480 K. An outlet temperature of 636 K was obtained which was lower than the predicted 750 K but 156 K higher than the cold temperature indicating the design provided some heat regeneration. The annular linear induction pump (ALIP) tested was able to produce a maximum flow rate of 1.53 kg/s at 800 K when operated at 150 V and 53 Hz.

  3. Novel Catalytic Membrane Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Stuart Nemser, PhD

    2010-10-01

    There are many industrial catalytic organic reversible reactions with amines or alcohols that have water as one of the products. Many of these reactions are homogeneously catalyzed. In all cases removal of water facilitates the reaction and produces more of the desired chemical product. By shifting the reaction to right we produce more chemical product with little or no additional capital investment. Many of these reactions can also relate to bioprocesses. Given the large number of water-organic compound separations achievable and the ability of the Compact Membrane Systems, Inc. (CMS) perfluoro membranes to withstand these harsh operating conditions, this is an ideal demonstration system for the water-of-reaction removal using a membrane reactor. Enhanced reaction synthesis is consistent with the DOE objective to lower the energy intensity of U.S. industry 25% by 2017 in accord with the Energy Policy Act of 2005 and to improve the United States manufacturing competitiveness. The objective of this program is to develop the platform technology for enhancing homogeneous catalytic chemical syntheses.

  4. OECD Halden Reactor Project

    International Nuclear Information System (INIS)

    The OECD Halden Reactor Project is both the oldest and the only one still in operation of the three major joint undertakings established at the inception of the OECD Nuclear Energy Agency. This publication has been printed in connection with its twenty-fifth anniversary as an international project. After presentation of the history and organization of the project, a thorough description of the past and present activities in the field of fuel performance and process control and surveillance is given. The projects's fuel testing programme is now focuessed on an investigation to define safety margins under normal operations as well as under various kinds of accident situations. Fuel research is also concerned with the characterisation of long term effects with regard to efficiency, operational safety and mapping of reliability and durability in the case of accidents with loss of coolant. In the field of process control and surveillance, research work is directly linked to the use of computers and colour graphics as tools in the control room. A fullscale simulator-based model and experimental control room has been constructed. The first experiments to be carried out in this laboratory will investigate the advantage of analysing alarms before they are presented to the operator. (RF)

  5. Nuclear reactor container

    International Nuclear Information System (INIS)

    A gas containing vessel has a water pool which is in communication with a dry well containing a reactor pressure vessel by way of a communication pipe is disposed. A capacity of a gas phase portion of the gas containing chamber, a capacity of the dry well, a water depth of a bent tube communicating the dry well with a pressure suppression pool of a pressure suppression chamber and a water depth of the communication pipe are determined so as to satisfy specific conditions. Since the water depth of the communication pipe is less than the water depth of the bent tube, incondensible gases and steams in the dry well flow into the water pool of the gas containing chamber at the initial stage of loss of coolant accident. Subsequently, steams in the dry well flow into the pressure suppression pool of the pressure suppression chamber by way of the bent tube. Accordingly, since the incondensible gases in the dry well do not flow into the pressure suppression chamber, pool swelling phenomenon in the pressure suppression chamber is not caused even if the water depth of the bent tube which leads to the pressure suppression chamber is great. Further, pressure increase due to transfer of the incondensible gases is decreased. (I.N.)

  6. OECD Halden reactor project

    International Nuclear Information System (INIS)

    A major part of the current research programme is devoted to irradiation experiments with a wide variety of heavily instrumented test fuel assemblies, in order to study the thermal and mechanical behavior of fuel rods through in-core measurements, in particular various forms of deformation of cladding and fuel as related to operational conditions and fuel rod design parameters. From these measurements mathematical models are being developed to explain quantitatively the deformation behavior, as well as the thermal properties of the fuel. During 1974, fifty-six instrumented fuel assemblies were irradiated in these experiments. Another major part of the Halden programme is aimed at the development and demonstration of advanced computer-based methods for plant and reactor core control, for safety and protection, and for overall supervision of nuclear power stations. Both the control methods themselves and the associated measurement and control apparatus are being elaborated, and during the year particular progress was made with the ''OPCOM'' process operator communication system

  7. MOLTEN FLUORIDE NUCLEAR REACTOR FUEL

    Science.gov (United States)

    Barton, C.J.; Grimes, W.R.

    1960-01-01

    Molten-salt reactor fuel compositions consisting of mixtures of fluoride salts are reported. In its broadest form, the composition contains an alkali fluoride such as sodium fluoride, zirconium tetrafluoride, and a uranium fluoride, the latter being the tetrafluoride or trifluoride or a mixture of the two. An outstanding property of these fuel compositions is a high coeffieient of thermal expansion which provides a negative temperature coefficient of reactivity in reactors in which they are used.

  8. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.)

  9. Fractals in Power Reactor Noise

    International Nuclear Information System (INIS)

    In this work the non- lineal dynamic problem of power reactor is analyzed using classic concepts of fractal analysis as: attractors, Hausdorff-Besikovics dimension, phase space, etc. A new non-linear problem is also analyzed: the discrimination of chaotic signals from random neutron noise signals and processing for diagnosis purposes. The advantages of a fractal analysis approach in the power reactor noise are commented in details

  10. Un caso de xantismo parcial en Aplodactylus punctatus (Teleostei: Aplodactylidae del sur de Perú

    Directory of Open Access Journals (Sweden)

    Philippe Béarez

    2006-10-01

    Full Text Available Se reporta por primera vez en Ilo, sur del Perú, una jerguilla amarilla (Aplodactylus punctatus. Esa condición de tener una piel de color amarillo se denomina xantismo. Este registro, único, corresponde probablemente a una extensión hacia el norte del rango de distribución de la «jerguilla reina», conocida de la costa central de Chile.

  11. DIVERSITY OF HELMINTHS OF FRESHWATER FISH IN THE OASES OF BAJA CALIFORNIA SUR, MEXICO

    OpenAIRE

    Mendez, Oscar

    2013-01-01

    Some oases have been evaluated and characterized on the basis of certain biological groups. However, there is nothing known of the helminths in these freshwater environments. We analyzed the diversity of helminths of freshwater fish in thirteen desert oases of Baja California Sur (BCS), Mexico. There were 472 individuals of nine species of fish examined. 24 helminth species were recorded on 273 fish (58%); of these, 176 (64%) were parasitized with a single species and 97 (36%) ...

  12. COMPTABILITE ET VALORISATION A L'INTRODUCTION SUR ALTERNEXT (2005-2006)

    OpenAIRE

    Boisselier, Patrick; Dufour, Dominique

    2007-01-01

    International audience Les introductions en Bourse au cours de la période 1999-2001 avaient vu une importante remise en cause de la comptabilité en tant qu'outil de valorisation des entreprises. Cette étude tente d'apprécier le rôle des grandeurs comptables dans la valorisation des sociétés introduites en 2005-2006 sur le compartiment Alternext du marché boursier parisien.

  13. Internalization and cooperation in higher education. The case of Universidad Nacional del Sur

    Directory of Open Access Journals (Sweden)

    Silvia Morresi

    2015-05-01

    Full Text Available Historically, education has evolved hand in hand with socio-technological changes. Nowadays, advances in information technology and media promote a new educational paradigm whereby the search for quality, relevance and internationalization in higher education has a prominent place. In this context, this work´s aim is to investigate the characteristics of higher education´s internationalization process and present some indicators to analyze the evolution and depth of this process in the Universidad Nacional del Sur.

  14. Les impacts d'une colostomie définitive sur le conjoint

    OpenAIRE

    Cornu, Laetitia

    2008-01-01

    Une colostomie qui initie une crise dans la vie du patient peut être surmontée de différentes manières selon les ressources internes et externes du patient. L'impact des stomies sur le conjoint et la prise en charge de l'infirmière sont étudiées dans ce mémoire.

  15. Notice sur les Lépidoptères des îles Natuna

    NARCIS (Netherlands)

    Snellen, P.C.T.

    1895-01-01

    Mr. Ritsema, Conservateur de la collection d’Insectes du Musée de Leyde, ayant reçu quelques Lépidoptères que Mr. A. L. van Hasselt, Résident de Riouw et de ses dépendances, avait recueillis aux îles Natuna, me pria d’en dresser la liste, parce que jusqu’ici rien n’avait été publié sur les insectes

  16. Stellarator fusion reactors - an overview

    International Nuclear Information System (INIS)

    The stellarator system offers a distinct alternative to the mainline approaches to magnetic fusion power and has several potentially major advantages. Since the first proposal of the stellarator concept many reactor studies have been published and these studies reflect the large variety of stellarator configurations. The main representatives are the continuous-coil configurations and the modular-coil configurations. As a continuation of the LHD experiment two reactor configurations, FFHR1 and FFHR2, have been investigated, which use continuous helical windings for providing the magnetic field. The modular coil concept has been realized in the MHH-reactor study (USA 1997) and in the Helias reactor. The Helias reactor combines the principle of plasma optimisation with a modular coil system. The paper also discusses the issues associated with the blanket and the maintenance process. Stellarator configurations with continuous coils such as LHD possess a natural helical divertor, which can be used favourably for impurity control. In advanced stellarators with modular coils the same goal can be achieved by the island divertor. Plasma parameters in the various stellarator reactors are computed on the basis of presently known scaling laws showing that confinement is sufficiently good to provide ignition and self-sustained burn. (author)

  17. Materials requirements for fusion reactors

    International Nuclear Information System (INIS)

    Once the physics of fusion devices is understood, one or more experimental power reactors (EPR) are planned which will produce net electrical power. The structural material for the device will probably be a modification of an austenitic stainless steel. Unlike fission reactors, whose pressure boundaries are subjected to no or only light irradiation, the pressure boundary of a fusion reactor is subjected to high atomic displacement-damage and high production rates of transmutation products, e.g., helium and hydrogen. The design data base must include irradiated materials. Since in situ testing to obtain tensile, fatigue, creep, crack-growth, stress-rupture, and swelling data is currently impossible for fusion reactor conditions, a program of service-temperature irradiations in fission reactors followed by postirradiation testing, simulation of fusion conditions, and low-fluence 14 MeV neutron-irradiation tests are planned. For the Demonstration Reactor (DEMO) expected to be built within ten years after theEPR, higher heat fluxes may require the use of refractory metals, at least for the first 20 cm. A partial data base may be provided by high-flux 14 MeV neutron sources being planned. Many materials other than those for structural components will be required in the EPR and DEMO. These include superconducting magnets, insulators, neutron reflectors and shields, and breeding materials. The rest of the device should utilize conventional materials except that portion involved in tritium confinement and recovery

  18. The safety of light water reactors

    International Nuclear Information System (INIS)

    The book describes the principles and practices of reactor safety as applied to the design, regulation and operation of both pressurized water reactors and boiling water reactors. The central part of the book is devoted to methods and results of safety analysis. Some significant events are described, notably the Three Mile Island accident. The book concludes with a chapter on the PIUS principle of inherent reactor safety as applied to the SECURE type of reactor developed in Sweden. (G.B.)

  19. Three dimensional diffusion calculations of nuclear reactors

    International Nuclear Information System (INIS)

    This work deals with the three dimensional calculation of nuclear reactors using the code TRITON. The purposes of the work were to perform three-dimensional computations of the core of the Soreq nuclear reactor and of the power reactor ZION and to validate the TRITON code. Possible applications of the TRITON code in Soreq reactor calculations and in power reactor research are suggested. (H.K.)

  20. ICONE-4: Proceedings. Volume 2: Advanced reactors

    International Nuclear Information System (INIS)

    The proceedings for this conference are contained in 5 volumes. This volume is divided into the following areas: advanced reactor requirements; advanced reactor design and analysis; arrangement and construction; specific reactor designs; demonstration testing; safety systems and analysis; component demonstration testing; advanced reactor containment design; licensing topics and updates; accelerator applications and spallation sources; and advanced reactor development. Separate abstracts were prepared for most papers in this volume