WorldWideScience

Sample records for reacteurs ungg avant

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  2. Mechanical, chemical and radiological characterization of the graphite of the UNGG reactors type

    International Nuclear Information System (INIS)

    Bresard, I.; Bonal, J.P.

    2000-01-01

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

  3. Technical evolution and operation of French CO2 cooled reactors (UNGG)

    International Nuclear Information System (INIS)

    Berthion, Y.

    1986-10-01

    The technical evolution of the five French CO 2 cooled reactors (UNGG) from 1981 to 1986 needs to be outlined. These technical evolutions concerned the fuel element of Bugey 1 which is now slightly enriched, as well as the load reduction operation required by the grid. In addition work in underway to increase the safety at the two St Laurent units, or to repair the hot steel upper-structures of Chinon-3 unit

  4. The Second Avant-Garde

    DEFF Research Database (Denmark)

    Karpova, Yulia

    envisioned a new role of things as agents of progressive social relations, as “comrades” rather than mere possessions. My book will identify the second historical attempt at creating a powerful alternative to capitalist commodities in the Cold War era. It will be, however, not a history of Soviet industrial......My book will explore the specific legacy of the avant-garde in design and decorative art of post-war Soviet Russia. It will be centered on the notion of socialist objects that was pivotal in the particular stream of the 1920s Russian avant-garde, known as productivism. The theorists of productivism...... aim: first, to highlight the legacy of the avant-garde beyond the celebrated non-conformist art, within the official sphere of artistic and industrial production; second, to explore the beliefs of the late Soviet artistic and technical intelligentsia and its positions vis-à-vis the state. It will be...

  5. Operational experience of the Marcoule reactors; Experience d'exploitation des reacteurs de Marcoule

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    The results obtaining from three years operation of the reactors G-2, G-3 have made it possible to accumulate a considerable amount of operational experience of these reactors. The main original points: - the pre-stressed concrete casing - the possibility of loading while under power - automatic temperature control have been perfectly justified by the results of operation. The author confirms the importance of these original solutions and draws conclusions concerning the study of future nuclear power stations. (author) [French] Les resultats atteints apres trois ans de fonctionnement des reacteurs G-2/G-3 permettent une accumulation considerable de l'experience d'exploitation de ces reacteurs. Les principales originalites: - caisson en beton precontraint - chargement en marche - surveillance automatique des temperatures sont largement justifiees par l'exploitation actuelle. L'auteur confirme l'interet de ces solutions d'avant-garde et en tire des conclusions pour les etudes de futures centrales nucleaires. (auteur)

  6. Avant-Garde Film: Cinema as Discourse.

    Science.gov (United States)

    MacDonald, Scott

    1988-01-01

    Considers the state of the avant-garde film movement. Contends that for those who are convinced of the potential importance of the broadest articulation of cinema, it is necessary to demonstrate the excitement and value of using avant-garde films in a wide range of academic contexts and as one of academic film activity's essential components. (MS)

  7. Die Asta and the Avant-Garde

    DEFF Research Database (Denmark)

    Thomsen, Bodil Marie Stavning

    2013-01-01

    The Danish film actress, Asta Nielsen, who became the first world famous film star after her success with The Abyss (1910), had a remarcable influence on what became the European avant-garde.......The Danish film actress, Asta Nielsen, who became the first world famous film star after her success with The Abyss (1910), had a remarcable influence on what became the European avant-garde....

  8. The Unheard Avant-garde in Scandinavia

    DEFF Research Database (Denmark)

    Søndergaard, Morten

    2012-01-01

    of a user's files and the data pertaining to them, also known as metadata. The importance of remote collaboration as an emerging work pattern is acknowledged by the integration of the concepts of users, sharing and permissions into the design from the outset. By leveraging the CHAOS cloud framework...... collections of data. Becoming unheard… again Presenter: Morten Søndergaard (Panel Chair) What is an unheard avant-garde? Of course, the answer may be tautological: no one has ever heard of the unheard avant-garde, as it were. And then again – rumours and curatorial intuition has it that private and ‘small...

  9. Corrosion Behaviour of Mg Alloys in Various Basic Media: Application of Waste Encapsulation of Fuel Decanning from UNGG Nuclear Reactor

    Science.gov (United States)

    Lambertin, David; Frizon, Fabien; Blachere, Adrien; Bart, Florence

    The dismantling of UNGG nuclear reactor generates a large volume of fuel decanning. These materials are based on Mg-Zr alloy. The dismantling strategy could be to encapsulate these wastes into an ordinary Portland cement (OPC) or geopolymer (aluminosilicate material) in a form suitable for storage. Studies have been performed on Mg or Mg-Al alloy in basic media but no data are available on Mg-Zr behaviour. The influence of representative pore solution of both OPC and geopolymer with Mg-Zr alloy has been studied on corrosion behaviour. Electrochemical methods have been used to determine the corrosion densities at room temperature. Results show that the corrosion densities of Mg-Zr alloy in OPC solution is one order of magnitude more important than in a geopolymer solution environment and the effect of an inhibiting agent has been undertaken with Mg-Zr alloy. Evaluation of corrosion hydrogen production during the encapsulation of Mg-Zr alloy in both OPC and geopolymer has also been done.

  10. Scouting the Desert of the Real: Avant-Gardism of the Avant-Pop

    Directory of Open Access Journals (Sweden)

    Mojca Krevel

    2010-05-01

    Full Text Available The paper examines the legacy of the European historical Avant-Gardes from the perspective of the shift of paradigms immanent in the formation of the Postmodern epoch. The existing theories generally regard the Avant-Gardes as an unsuccessful attempt to redefine the function of art in the social, cultural and economic environment of the early 20th century. Examining the productivity and relevance of the historical Avant-Gardes from the perspective of the Avant-Pop, the first thoroughly Postmodern literary movement, I intend to show how the strategies of fragmentation and the breaking of organicity not only quintessentially defined the manner in which Modernity and its art came to an end, but how they also provided the basis forthe formation of culture and art that no longer functions according to Cartesian principles.

  11. Temperature and radiolytic corrosion effects on the chlorine behaviour in nuclear graphite: consequences for the disposable of irradiated graphite from UNGG reactors

    International Nuclear Information System (INIS)

    Vaudey, C.E.

    2010-10-01

    This work concerns the dismantling of the UNGG reactor which have produced around 23 000 t of graphite wastes that ave to be disposed of according to the French law of June 206. These wastes contain two long-lived radionuclides ( 14 C and 36 Cl) which are the main long term dose contributors. In order to get information about their inventory and their long term behaviour in case of water ingress into the repository, it is necessary to determine their location and speciation in the irradiated graphite after the reactor shutdown. This work concerns the study of 36 Cl. The main objective is to reproduce its behaviour during reactor operation. For that purpose, we have studied the effects of temperature and radiolytic corrosion independently. Our results show a rapid release of around 20% 36 Cl during the first hours of reactor operation whereas a much slower release occurs afterwards. We have put in evidence two types of chlorine corresponding to two different chemical forms (of different thermal stabilities) or to two locations (of different accessibilities). We have also shown that the radiolytic corrosion seems to enhance chlorine release, whatever the irradiation dose. Moreover, the major chemical form of chlorine is inorganic. (author)

  12. John Zorn: Autonomy and the Avant-Garde (excerpt

    Directory of Open Access Journals (Sweden)

    Ted Gordon

    2012-06-01

    Full Text Available This essay is an excerpt for a larger paper exploring the concept of autonomy as it emerges in the life and work of the composer, performer, record label executive and club-owner John Zorn. Zorn’s activities over his wide-ranging career span from performing at jazz lofts in the 1970s to winning the MacArthur “genius” grant in 2008, while maintaining his status as a prolific composer and producer of avant-garde music. In interviews, documentaries, and in his music, Zorn often comments on his status as an avant-garde producer, specifically within the context of the record industry and within New York City’s so-called “Downtown” scene. Economics take the forefront in determining artistic attitudes towards both production of music and the music itself, as Zorn has, seemingly, been forced by the “mainstream market” to create a parallel, vertically-integrated economic system to support the livelihood of himself and his collaborators. This excerpt, from the first third of the essay, unpacks Zorn’s relationship with Downtown scene, his conception of the avant-garde, and his attitude towards artists who have set precedents for Zorn’s version of autonomous cultural production. It also notes the idiosyncratic way that both Zorn and his critics have placed Zorn’s music both within and without two distinct traditions: Avant-Garde composition and free Jazz.

  13. Cosmologie L'Univers avant le Big Bang

    CERN Multimedia

    Rouat, Sylvie

    2003-01-01

    Tout n'a pas commencé par une explosion. L'histoire du cosmos avait débuté bien avant le Big Bang, si l'on suit la théorie défendue par les partisans d'une nouvelle cosmologie issue de la mystérieuse théorie des cordes

  14. A Cultural History of the Avant-Garde in the Nordic Countries 1900-1925

    DEFF Research Database (Denmark)

    The first publication to deal with the avant-garde in the Nordic countries at the start of the twentieth century. It is the first major historical work to consider the Nordic avant-garde in a transnational perspective which includes all the arts and to discuss the role of the avant-garde not only...

  15. Avant-garde: Making war, revolutionary politics and art

    Directory of Open Access Journals (Sweden)

    Jeremić-Molnar Dragana

    2008-01-01

    Full Text Available In the article the authors are dealing with the militant potential of the concept of avant-garde. Emerging in the politics and art in the first half of the 19th century and designed to ruin almost the whole tradition of 'bourgeois' enlightenment, political and artistic avant-garde was never capable of emancipating itself from its roots in strategic military thinking. Its true essence was to create battlefields in every domain of public life where the chance was given to ruin civil society - its politics, its art, its way of thinking, its civilization. In the name of freedom never heard of before, it spread violence and spread totalitarian seeds on the scorched soil. And in the end it was not defeated by its numerous enemies because it became victim of its own destructiveness.

  16. Avant-garde: The Convulsions of a Concept

    Directory of Open Access Journals (Sweden)

    Michael T. Jones

    1980-09-01

    Full Text Available The current status of the «avant-garde» provokes many questions, which include both inner-artistic matters and matters of history and society commonly associated with Marxist or reception-oriented thinkers. The convolution of questions cannot be disentangled; efforts to confront the dilemmas of the avant-garde cannot abstract from matters of commodification, recent reception, or the complex dialectic of «classical» and «modern.» The essay deals with the most recent manifestations of avant-garde aesthetic impulses. It emphasizes the historical and social aspects of German theorizing in contrast to purely formalist or ahistorical conceptions commonly found elsewhere. It insists that such «materialist» theory does greater justice than formalist conceptualizations to the proverbial connections of «art» and «life.» It tries to integrate the present phenomenon of proliferating theory into the theoretical exposition, as a characteristic trait of the current situation. It warns against abandoning the subversive content of classical modernism in the course of developing a theory of post-modernism.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

  19. The Avant-Gardist, the Male Genius and the Proprietor

    Directory of Open Access Journals (Sweden)

    Martin Fredriksson

    2007-05-01

    Full Text Available As the title suggests, this article will deal not only with the avant-garde and the romantic idea of geniality but also with the much more mundane concept of literary property. Even though the law might seem alien to the lofty ideals of the avant-garde artist, the construction of the creative genius and the birth of copyright will eventually prove to be quite closely connected. But before I move on to the legal part I would like to start with the essentials: with the author, or the artist. The American artist John de Andreas sculpture The Artist and his model from 1980 is probably one of the most revealing pictures of the avant-gardist selfconception ever made. This is a picture of the artist at work, but I will argue it can also be regarded as a legal character. What meets the eye is however very far from the law as we know it. de Andreas sculpture is a self-portrait of the artist at work: a highly naturalistic full-scale portrait of two people. One of them is a naked woman, resting casually on a white socket and looking down on the other who is a fully dressed man. As the title clearly states, the sculpture depicts the classical relation between The Artist and his Model, and it is no coincidence that the artist has a male pronoun and the model a female body. The roles of the artist and his model are traditional stereotypes which we can find in most books on art history - one is an artist and the other is a model; one is a man and the other is a woman; one is dressed and the other one is undressed.

  20. Serbian Literary Magazine and avant-garde music

    Directory of Open Access Journals (Sweden)

    Vasić Aleksandar N.

    2005-01-01

    Full Text Available One of the most excellent periodicals in the history of Serbian literature Serbian Literary Magazine (1901-1914, 1920-1941, also played an exceptionally important part in the history of Serbian music criticism and essay literature. During the period of 35 years, SLM had released nearly 800 articles about music. Majority of that number belongs to the music criticism, but there are also studies and essays about music ethno musicological treatises, polemics, obituary notices, as well as many ample and diverse notes. SLM was published during the time when Serbian society, culture and art were influenced by strong challenges of Europeanization and modernization. Therefore, one of the most complicated questions that music writers of this magazine were confronted with was the question of avant-garde music evaluation. Relation of critics and essay writers to the avant-garde was ambiguous. On one side, SLM's authors accepted modern art in principle, but, on the other side, they questioned that acceptance when facing even a bit radical music composition. This ambivalence as a whole marked the work of Dr Miloje Milojević, the leading music writer of SLM. It is not the same with other critics and essayists Kosta Manojlović was more tolerant, and Dragutin Čolić and Stanislav Vinaver were true protectors of the most avant-garde aspirations in music. First of all SLM was a literary magazine. In the light of that fact it has to be pointed out that very early, way back in 1912, critics wrote about Arnold Schoenberg, and that until the end of existence of this magazine the readers were regularly informed about all important avant-garde styles and composers of European, Serbian and Yugoslav music. The fact that Schoenberg Stravinsky, Honegger or Josip Slavenski mostly were not accepted by critics and essayists, expresses the basic aesthetic position of this magazine. Namely, SLM remained loyal to the moderate wing of modern music, music that had not rejected

  1. Nordic game subcultures: between LARPers and avant-garde

    Directory of Open Access Journals (Sweden)

    Mathias Fuchs

    2014-03-01

    Full Text Available This article is about structural resemblances, linguistic and rhetoric similarities and media-strategic as well as tactical operations, that Nordic LARPers and 20th century avant-garde artists share. Many of the 20th century avant-garde movements and subcultural formations started from a shared collective experience and then branches out into refined, diversified and individualized forms of expression. Futurism, DADA and Fluxus, Punk, Emo and Goth did originally constitute a dress code, a toolset, a jargon, a mission statement and a territorial assignment within the cities they choose as the center of their activities. Manifestos defined what a Futurist, Dadaist or Punk would most probably think and say, and how he or she would say it. A similar observation can be made for the communities that engage with live action role playing games (LARPs in the Nordic countries. The Turku manifesto and the Dogma 99 manifesto influenced directly and indirectly how the Nordic LARP subculture framed defined itself and presented itself to the world. The initiating, collective experiences of Cafe Voltaire, the Wuppertal art galleries, SOHO, and respective locations for Nordic LARPers have been constitutive for the process of identity building and identity shaping for artists and gamers alike.

  2. Chinese Avant-garde Art in the Late Twentieth Century

    Directory of Open Access Journals (Sweden)

    Nataša Vampelj Suhadolnik

    2014-12-01

    Full Text Available The main topic of the present paper is the '85 Art Movement, which was the first significant nationwide Avant-garde art movement in China. This movement, which arose in the mid-80s, defined the aesthetic foundations and identity of contemporary Chinese art, and represented Chinese globalized society on the threshold of the 21st century. Whilst focusing on China’s specific cultural and political contexts, the present paper analyses the concepts of humanism (renwen 人文 and idea (guannian 觀念. The spirit of humanism, with a rationalist connotation, and the desire for a revolution of ideas were the two main factors underpinning the Chinese Avant-garde movement and its artistic expressions. The paper also shows that the '85 Art Movement did not stem solely from the socio-political challenges of the 1980s, but should be regarded in the wider context of the “modernization project of Chinese art”, in the early 20th century.

  3. Art-House Cinema, Avant-Garde Film, and Dramatic Modernism

    Science.gov (United States)

    Cardullo, Bert

    2011-01-01

    In this article, the author talks about art-house cinema, avant-garde film, and dramatic modernism. He believes that the most important modes of film practice are art-house cinema and the avant-garde, both of which contrast with the classical Hollywood mode of film practice. While the latter is characterized by its commercial imperative, corporate…

  4. 'Nothing is Certain': Czech Post-War Literature Between the Avant-Garde and Expressionism

    Czech Academy of Sciences Publication Activity Database

    Říhová, Zuzana

    2016-01-01

    Roč. 14, č. 2 (2016), s. 125-140 ISSN 1479-0963 Institutional support: RVO:68378068 Keywords : collectivism, individualism, avant-garde, expressionism, Czech literature, short fiction, anxiety , fear, anthropomorphization * individualism * avant-garde * expressionism * Czech literature * short fiction * anxiety * fear * anthropomorphization Subject RIV: AJ - Letters, Mass-media, Audiovision OBOR OECD: Specific literatures

  5. Cosmologie l'univers avant le Big Bang

    CERN Multimedia

    Larousserie, David

    2003-01-01

    Tout n'a pas commencé par une explosion. L'histoire du cosmos avait débuté bien avant le Big Bang, si l'on suit la théorie défendue par les partisans d'une nouvelle cosmologie issue de la mystérieuse théorie des cords. A l'heure où vacillent les scénarios classiques du XXe siècle, se prépare un grand chamboulement de nos idées sur la naissance de l'Univers et son devenir, sur l'existence possible d'univers parallèles.

  6. Oklo 2 Billion Years Before Fermi; Les reacteurs naturels d'Oklo (Gabon): 2 milliards d'annees avant Fermi

    Energy Technology Data Exchange (ETDEWEB)

    Barre, B

    2005-02-15

    The author aims to present the little-known story of the Oklo natural reactors. He recalls the historical aspects of the Oklo reactors discovery by the CEA in 1972, he explains the scientific phenomenon and the interest, notably as a 'natural analogue' for the geological disposal of high level radioactive wastes. (A.L.B.)

  7. Heavy water reactors physics; Physique des reacteurs a eau lourde

    Energy Technology Data Exchange (ETDEWEB)

    Girard, Y; Lourme, P; Naudet, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    An important research programme on heavy water reactor physics has been carried out in France for quite a few years. The decision to build the EL 4 prototype and so to choose the heavy water gas cooled type has renewed the interest in this programme and at the same time given to it a more specific orientation A summary of the results gained in this field is presented in this paper. In the first part are described the experimental investigations, most of them were carried out in the criticality facility AQUILON II. The experiments are grouped in four parts - Systematic studies of lattices Buckling measurements. - Specific studies of gas-cooled lattices. - Fine structure, spectral indices measurements etc... - Measurements on lattices or samples containing Uranium of various enrichment or Plutonium. The second part is devoted to a summary of the theoretical studies. The whole results have allowed an improvement of the calculation methods, have led to a better understanding of the neutron balance in lattices, and have permitted the establishment of a set of formula to predict not only the clean fuel conditions but also the evolution of the nuclear properties with irradiation. Some specific studies on power reactor are quoted. (authors) [French] Un important programme d'etudes sur la physique des reacteurs a eau lourde est mene en France depuis assez longtemps. La decision de construire le prototype EL 4 et de s'engager ainsi dans la filiere des reacteurs a eau lourde refroidis par gaz a redonne un nouvel interet a ce programme et l'a en meme temps oriente dans une direction plus particuliere. La presente communication, rassemble les resultats des etudes faites dans ce domaine depuis la derniere conference de Geneve. Dans la premiere partie on decrit les etudes experimentales dont la plupart ont ete effectuees dans la pile d'experiences critiques Aquilon II. Les experiences sont groupees en quatre ensembles: etude systematique de reseaux (mesures de laplaciens) etudes

  8. 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)

  9. Beyond the Score: Timbre Analysis in Avant-garde Music

    Directory of Open Access Journals (Sweden)

    Mario Baroni

    2016-02-01

    Full Text Available The article examines perceptual aspects of timbre within the context of avant-garde XX century music. An excerpt from a work by Luciano Berio was taken into account. We recorded it on 8 separate channels each of them devoted to small groups of homogeneous sounds, in order to obtain a global result that we could modify by subtracting one or more of the recorded groups. We prepared four different excerpts: one with the original version and three with modified versions. 50 participants (25 experts, 25 non-experts were invited to fill in a semantic differential bipolar scale made of 12 adjectives, 6 concerning emotional and 6 sensorial aspects of perception. We interpreted the subjects’ responses with the help of a spectrographic analysis and of studies on timbre verbalization. The main aim of our research was to explore the possibilities of timbre analysis, a field that so far has no solid scientific background. The research obtained promising responses from expert listeners, while non-experts manifested a sort of aesthetic refusal of this genre of music. Positive results were obtained also in the critical observations of possibilities and limits of spectrographic analysis and verbalizations of timbre. We hope that our initial data can be useful for future studies on timbre perception.

  10. A Cultural History of the Avant-Garde in the Nordic Countries 1950-1975

    DEFF Research Database (Denmark)

    , radio, television and the performative arts. It is the first major historical work to consider the Nordic avant-garde in a transnational perspective that includes all the arts and to discuss the role of the avant-garde not only within the aesthetic field but in a broader cultural and political context......: The cultural politics, institutions and new cultural geographies after World War II, new technologies and media, performative strategies, interventions into everyday life and tensions between market and counterculture....

  11. "Machines to generate desire": Avant-garde Manifestos and Guerrilla Advertising

    OpenAIRE

    Hanna, Julian

    2011-01-01

    The association between the avant-garde and advertising is longstanding and bidirectional. Advertising, after all, is one of the “shocks” of modernity described by Walter Benjamin in his writings on Baudelaire. Avant-garde art reproduces the primary urban shock effects of crowds, advertisements, and other stimuli. The manifesto has always functioned as an advertisement for artistic movements, as for political and social ones. In this study I examine the relationship between the historic...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-02-15

    choisi soit des montages exponentiels, soit des assemblages critiques non empoisonnes, soit des maquettes de puissance nulle, soit des experiences in situ pour obtenir les donnees necessaires, et indiquent quel role ont joue les travaux analytique' complementaires. Ils montrent, par des exemples precis, dans quelle mesure on peut obtenir des donnees sur la physique d'un reacteur avant son fonctionnement en puissance. Ces donnees comprennent la marge d'arret, l'excedent de reactivite pour les besoins de l'exploitation, les coefficients de temperature, l'efficacite des barres de reglage et de securite, la cinetique du reacteur, le regime de la production d'energie, les conditions a remplir en ce qui concerne la source pour le demarrage et la sensibilite des appareils, les besoins en matiere de protection et l'economie des neutrons. Cet expose des experiences faites recemment a la puissance zero montre que par le passe le Laboratoire national d'Argonne s'est largement fonde sur les systemes exponentiels et critiques pour mener a bien ses travaux dans le domaine des etudes de reacteurs. Les auteurs donnent une indication sur le role futur de ces systemes en resumant brievement les programmes de travaux, en cours d'execution ou en projet, au moyen des reacteurs de puissance zero qui existent actuellement a Argonne et de ceux que le Laboratoire se propose de construire. (author) [Spanish] Con el reactor de potencia nula de Argonne se han investigado los diseflos de numerosos reactores de investigacidn, de potencia, de propulsion, de produccion, de isotopos y de ensayo de materiales, habiendose obtenido los datos de caracter fundamental correspondientes en los conjuntos asociados-exponenciales y criticos sin envenenamiento. Con el fin de describir los experimentos mas recientes y demostrar el gran nuemero de datos sobre fisica de reactores que pueden obtenerse en sistemas de flujo debil, los autores exponen los siguientes programas experimentales: 1. Estudio de las propiedades

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-12-15

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

  15. China’s Second World of Poetry : The Sichuan Avant-Garde, 1982-1992

    NARCIS (Netherlands)

    Day, Michael

    2005-01-01

    China's Second World of Poetry remedies a deficiency in scholarship to date. In post-Mao China, types of poetry variously dubbed underground, unofficial, experimental, avant-garde, non-mainstream and so on have outshined texts produced by a state-sanctioned politico-cultural establishment that

  16. The Avant-Garde Film: A Reader of Theory and Criticism. Anthology Film Archives Series: 3.

    Science.gov (United States)

    Sitney, P. Adams, Ed.

    This anthology is both a history of the avant-garde film genre and a compendium of theories of cinema articulated by major filmmakers. The 33 selections include several previously unpublished theoretical and critical articles and many articles that were especially translated into English for this collection. Other selections were drawn from…

  17. THE BIRTH OF AVANT-GARDE FROM THE SPIRIT OF MODERNISM

    Directory of Open Access Journals (Sweden)

    Yuri N. Girin

    2016-12-01

    Full Text Available The article focuses on the problem of spirituality in the avant-garde culture of the beginning of the 20 th Century. Everyone — artists, writers, theologians, philosophers, and reformers — wrote about the peculiar spirituality of the New World. At the same time, the concept of the spiritual was as widespread and universal as it was controversial. The interest in the peculiar spiritual situation of the avant-garde epoch in the public conscience since the end of the 20 th Century is symptomatic — a man of the Novecento haven chosen the sign of modernity as an emblem endeavors to understand his age and his place in it. That is why it seems extremely important to be able to find a proper balance between the negative and the assertive tendencies of the avant-garde culture that formed the cultural basis of the 20 th Century. The author attempts to understand the meaning of Spirituality at the beginning of the 20 th Century. The essay suggests that the entire avant-garde age, taken broadly, may be considered as a great Mystery act given the inherent inseparability of the intuitive and the sensory, on the one hand, and historical and social aspects, on the other hand: creative work was understood in terms of Creation.

  18. De as Brussel-Wenen 1900: De wederzijdse receptie van de Brusselse en Weense avant-garde in vier tijdschriften

    Directory of Open Access Journals (Sweden)

    Christophe Schellekens

    2011-12-01

    Full Text Available This article investigates the mutual reception of the Brussels and Viennese avant-garde in four periodicals: the Viennese magazine Ver Sacrum and the Brussels periodicals Van Nu & Straks, L‟Art Moderne and La Jeune Belgique. Ver Sacrum, the magazine of the Secession, claimed to be the first avant-garde periodical in Vienna and this article thus deals with its reports on Belgian avant-garde artists. Van Nu & Straks is considered to be the first Flemish avant-garde journal, while L‟Art Moderne and La Jeune Belgique were two Brussels periodicals written in French. With respect to these three Brussels periodicals, this article pays particular attention to their documentation of the upcoming Viennese avant-garde. In special editions, articles and references on Belgian artists in Ver Sacrum, the lack of biographical references is the most noteworthy aspect. In L‟Art Moderne the reporting on Viennese art, artists and avant-garde institutes is very concise and mainly related to Belgian artists. Despite its interest in other artistic developments in Europe, Van Nu & Straks and La Jeune Belgique did not report on Viennese avant-gardism.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

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

  20. Sensus communis aestheticus and the project of emancipation: The Utopian frame of the avant-gardes.

    Directory of Open Access Journals (Sweden)

    Loredana Niculet

    2011-07-01

    Full Text Available The conceptual basis which would be later developed by the artistic avant-gardes was settled by German Romantic and Idealist thought, whose utopian dimension could be easily recognized in The oldest systemprogram of German Idealism (1796, a text which provided Idealist thought with the claim of a new rationality or a mythology of reason in Hegel, an intellectual intuition in Schelling and the Humanity in Schiller. Although this emancipation project developed later by the avant-garde has lost its credibility for us, we still have to investigate to what extent today’s art can maintain a social function. This article point out certain idealist concepts in light of a philosophy of art modeled along lines sketched out in Kant’s Critique of Judgement and that have contributed to the history of the “advanced” art.

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

    Science.gov (United States)

    Mahjoub, Mehdi

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

  2. Transient regimes in a heavy water reactor; Regimes transitoires dans un reacteur a eau lourde

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-07-01

    We studied the variations of power and reactivity of a reactor when we raise in a continuous way the starting plates. During the subcritical regime (negative reactivity), the power is determined by reactivity and by the intensity of the sources of photo neutrons, produced during the previous work of the reactor. When, during the rise of the plates, the reactor, pass by the critical regime (zero reactivity), one notes that the reached power is independent of the initial reactivity. During the sur-critical regime (positive reactivity), the elevation of temperature of the uranium bars slows down the growth of reactivity due to the movements of the plates. The power stretches then toward a value that depends only on the regime of cooling of the reactor and the excess of the available reactivity. This survey permits to choose such a rise speed, that reactivity remains constantly lower to a value beyond which the piloting of the reactor becomes difficult. This result is not more valid, if the intensity of the sources is insufficient, what takes place during the first divergences and after a stop of long length. (author) [French] On etudie les variations de puissance et de reactivite d'un reacteur quand on leve d'une facon continue les plaques de demarrage. Pendant le regime subcritique (reactivite negative), la puissance est determinee par la reactivite et par l'intensite des sources de photoneutrons, produites pendant la marche anterieure du reacteur. Quand, au cours de la montee des plaques, le reacteur passe par le regime critique (reactivite nulle), on constate que la puissance atteinte est independante de la reactivite initiale. Pendant le regime surcritique (reactivite positive), l'elevation de temperature des barres d'uranium ralentit l'accroissement de reactivite due aux mouvements des plaques. La puissance tend alors vers une valeur qui ne depend plus que du regime de refroidissement du reacteur et de l'exces de la reactivite disponible. Cette etude permet de

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-06-15

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

  4. Transmental Sheherazade on the interwar avant-garde balls in Belgrade and Paris

    Directory of Open Access Journals (Sweden)

    Jović Bojan

    2013-01-01

    Full Text Available In expert circles, attention has been drawn to the “1002nd Night Ball” created by the protagonists of Yugoslav and Serbian avant-garde, in particular on its dance and musical segments, moreover, the ballet “Le balai du valet” by Marko Ristić and Miloje Milojević, as well as the ensuing series of balls related to the Association of Friends of Art “Cvijeta Zuzorić”. On the other hand, it is an (almost completely unknown fact that Rade Drainac’s original idea to throw a ball for the benefit of artists and writers that needed financial assistance because of difficult financial situation (later replaced with an initiative to raise funds to build an art pavilion “Cvijeta Zuzorić” matched the idea of the Union of Russian artists in Paris to organize a ball with the aim of contributing to mutual aid. The ball in Paris, with the participation of the most prominent avant-garde artists, took place exactly one week after the Belgrade ball, which also suggests the possible connection / synchronization of these two artistic events. Having this in mind, I offer a brief analysis of the concept and scope of the aforementioned artistic events from the perspective of the intermedia and multimedia strategies. I demonstrate that the Belgrade spectacle was envisioned and performed far more ambitiously than the Parisian one, and the thoroughness of the interweaving of various arts ranks it among those works (including Parade by Cocteau, Picasso and Satie, Skating-Rink by Canudo, Leger, and Honegger, La creation du monde by Cendrars, Léger and Milhaud, with Russian and Swedish Ballet that aimed to achieve a Gesamtkunstwerk, i.e. a total work of avant-garde art. [Projekat Ministarstva nauke Republike Srbije, br. ON 178008: Srpska književnost u evropskom kulturnom prostoru

  5. China’s Second World of Poetry: The Sichuan Avant-Garde, 1982-1992

    OpenAIRE

    Day, Michael

    2005-01-01

    China's Second World of Poetry remedies a deficiency in scholarship to date. In post-Mao China, types of poetry variously dubbed underground, unofficial, experimental, avant-garde, non-mainstream and so on have outshined texts produced by a state-sanctioned politico-cultural establishment that continues to pay lip service to maoist literary doctrine. For the 1980s and the early 1990s, most foreign-language scholarship has Beijing - and exile poetry scenes - as its focus, failing to do justice...

  6. The Caribbean and the Avant-Garde: Luciano Berio's Rhumba-Ramble

    OpenAIRE

    Calzada, Orlando Manuel

    2015-01-01

    ABSTRACT OF THE DISSERTATIONThe Caribbean and the Avant-Garde:Luciano Berio’s Rhumba-RamblebyOrlando Manuel CalzadaDoctor of Philosophy in MusicUniversity of California, Los Angeles, 2015Abstract With the establishment of the first Spanish settlement in Las Am?ricas called La Navidad – in what is today Dominican Republic – Cristobal Col?n established official domination of Europe over the newly discovered land. A new era of worldwide exchange started to reshape territories, societies, cultur...

  7. Matter-Reality in Cinema: Realism, Counter-Realism and the Avant-Gardes

    OpenAIRE

    Walldén, Rea

    2012-01-01

    The present text investigates the dialectics of reality and materiality in cin­ema theory and practice. It attempts an epistemological and meta-semiotic approach. Based on Louis Hjelmslev's model of sign-function, it reformu­lates both the haunting of cinema by reality and the avant-gardes' focus on materiality as problematising the relation of cinematic semiosis to the exo-semiotic[1] realm. It starts by laying down the philosophical background of the issues investigated. It then explores th...

  8. Croatie: le tourisme avant et après la guerre

    Directory of Open Access Journals (Sweden)

    Snezana PROKIC

    1998-09-01

    Full Text Available Les conflits armés ont profondément modifié l'espace touristique croate. Par rapport à l'espace touristique de référence (avant 1991, l'article montre les changements dans les lieux, leur capacité d'accueil, la nature et l'ampleur de la fréquentation touristique, et identifie les logiques d'atteintes (spatiales et matérielles qui en modifient la structure.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

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

  10. The experiments of composers of the Russian avant-garde epoch in the field of arts synthesis

    Directory of Open Access Journals (Sweden)

    Zaytseva Marina

    2016-04-01

    Full Text Available The article scientifically substantiates the features of avant-garde art that is aimed at finding synesthesian community of art languages and aesthetic transformation of reality. It identifies the main features of the Russian avant-garde composers Mikhail Matyushin’s and Alexander Mosolov’s experimental creativity. It is proved that the dominant feature of their work is the creation of a new model of art that brings together all types of human exposure and returns the fullness of perception and cognition.

  11. The Death of Georges Seurat: Neo-Impressionism and the Fate of the Avant-Garde in 1891

    Directory of Open Access Journals (Sweden)

    Young, Marnin

    2012-07-01

    Full Text Available This essay examines the critical and artistic responses to the death of Georges Seurat in 1891. While some at the time saw the avant-garde divided between scientifically-oriented neo-impressionism and mystical symbolism, the posthumous understanding of Seurat's work increasingly collapsed the two categories. In particular, the neo-impressionist embrace of the aesthetic of Charles Henry, in which compositional lines produced predictable effects on the viewer, made it possible to see Seurat's paintings in purely formal, indeed idealist, terms. The neo-impressionist avant-garde consequently struggled to define its distinctive nature over the course of the year, with important consequences for later art.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  13. G2 and G3 reactors design; Description des reacteurs G2 et G3

    Energy Technology Data Exchange (ETDEWEB)

    Herreng,; Ertaud,; Pasquet, [Societe Alsacienne de Constructions Mecaniques (France)

    1958-07-01

    operating power levels of reactor. The regulating system has brought about difficult problems; experimental examination, while operating, will solve them. Special meetings will be held concerning the burst slug system and fuel elements. (author) [French] La construction des reacteurs G2 et G3, dans le cadre du premier plan quinquennal francais, a ete confiee par le C.E.A. au groupement d'industriels FRANCE-ATOME. Bien que ces reacteurs restent essentiellement plutonigenes, on a accole a chacun d'eux une centrale electrique devant fournir 40 MW, dont la responsabilite a ete assumee par l'E.D.F. Le coeur du reacteur adopte la plupart des solutions du reacteur G1 (excepte la fente centrale): canaux horizontaux, empilement de briques parallelepipediques de graphite, protection thermique en acier. Le refroidissement est assure par du gaz carbonique sous 15 atmospheres. Cette pression est tenue par un caisson en beton precontraint, ayant la forme d'un cylindre horizontal. Des cables d'acier sous tension entourent le cylindre de beton, dont ils sont isoles par des patins. Les fonds du cylindre ont pose des problemes particuliers qui ont conduit a la forme hemispherique adoptee. L'etancheite du caisson est assuree par une tole de 30 mm liee a la face interne du beton. Un des aspects les plus originaux de ces reacteurs est la possibilite de charger et decharger en marche. Cote chargement, des sas a barillets, pesant chacun 50 tonnes; permettent de faire passer les cartouches neuves sous la pression de 15 atmospheres. Ces cartouches progressent de facon quasi continue dans le canal pour tomber finalement par des goulottes inclinees et des toboggans helicoidaux dans un nouveau sas. La circulation du gaz carbonique est assuree par trois turbo-soufflantes, actionnees elles-memes par la vapeur moyenne pression obtenue dans echangeurs, chaque reacteur alimente quatre echangeurs ayant pose de difficiles problemes de construction et de mise en place. Le cycle secondaire est un cycle

  14. From material science to avant-garde cuisine. The art of shaping liquids into spheres.

    Science.gov (United States)

    Fu, Haohao; Liu, Yingzhe; Adrià, Ferran; Shao, Xueguang; Cai, Wensheng; Chipot, Christophe

    2014-10-09

    Employing avant-garde cuisine techniques, in particular sodium alginates, liquid food can be shaped into spheres, thereby conferring to the former original and sometimes unexpected forms and textures. To achieve this result, rational understanding of the science that underlies food physical chemistry is of paramount importance. In this contribution, the process of spherification is dissected for the first time at the atomic level by means of classical molecular dynamics simulations. Our results show that a thin membrane consisting of intertwined alginate chains forms in an aqueous solution containing calcium ions, thereby encapsulating in a sphere the aliment in its liquid state. They also show why the polysaccharide chains will not cohere into such a membrane in a solution of sodium ions. Analysis of the trajectories reveals the emergence of so-called egg-box spatial arrangements, which connect the alginate chains by means of repeated chelation of one calcium ion by two carboxylate groups. Free-energy calculations delineating the formation of these egg-box structures further illuminate the remarkable stability of such tridimensional organizations, which ensures at room temperature the spontaneous growth of the polysaccharide membrane. Spherification has been also examined for liquid aliments of different nature, modeled by charged, hydrophilic and hydrophobic compounds. The membrane-encapsulated food is shaped into robust and durable spheres, irrespective of the liquid core material. By reconciling the views of spherification at small and large scales, the present study lays the groundwork for the rational design of innovative cooking techniques relevant to avant-garde cuisine.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-07-01

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

  18. 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

  19. Dynamic problems of power reactors and analogic devices; Les problemes dynamiques du reacteur de puissance et les machines analogiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The raise of the nuclear physics came with heavy mathematical developments. The analogical installations became especially useful for precise calculations of parameters which depend the running of a reactor. They permit between other to study of kinetic problems and especially ''cybernetics'' of nuclear reactors. It doesn't make a doubt that their use will become widespread, not only in the calculations laboratories, in services for servo-mechanisms study, but also in the control panels of the reactors themselves. (M.B.) [French] L'essor de la physique nucleaire s'est accompagne de lourds developpements mathematiques. Les montages analogiques sont devenus particulierement utiles pour les calculs precis des parametres dont depend le fonctionnement d'un reacteur. Elles permettent entre autre l'etude des problemes cinetiques et surtout ''cybernetiques'' des reacteurs nucleaires. Il ne fait pas de doute que leur usage se generalisera, non seulement dans les laboratoires de calculs, les services d'etudes de servomecanismes, mais aussi pres des tableaux de commande des reacteurs eux-memes. (M.B.)

  20. Un système d'avant-garde rend l'accès à l'information abordable ...

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

    27 oct. 2010 ... Bien avant l'avènement des ordinateurs personnels et d'Internet, les énormes collections et bases de données des organismes des Nations Unies étaient consultables sous forme numérique par le truchement d'un système appelé ISIS. Par contre, ce système ne pouvant fonctionner qu'au moyen ...

  1. Development and testing of the EDF-2 reactor fuel element; Essais et mise au point de l'element combustible pour le reacteur EDF-2

    Energy Technology Data Exchange (ETDEWEB)

    Delpeyroux, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Furhmann, R [Societe Industrielle de Combustible Nucleaire (France)

    1964-07-01

    rassemble les etudes qui ont ete necessaires pour mener a bien la definition de l'element combustible EdF 2. Apres un bref rappel des caracteristiques du reacteur EdF 2 et des options preliminaires ayant permis de fixer un avant-projet d'element combustible, on aborde les etudes proprement dites: - Etudes uranium: essais de passage d'une couronne interne du tube en phase {beta}, flechage du tube sous l'action d'une force concentree, soudage des pastilles d'extremites et verification de leur etancheite. La tenue du tube a l'ecrasement et la resistance des pastilles a l'enfoncement sous l'action de la pression externe sont etudiees en detail dans un autre rapport CEA - Etudes gaine: rappel des conditions de fabrication et verification de l'etancheite de la gaine, tenue des ailettes au fluage sous l'action du courant gazeux - Etudes d'extremites: fluage en compression et soudage des bouchons a la gaine. - Etudes cartouche: determination des caracteristiques des gorges d'ancrage gaine-combustible et des conditions de gainage, verification de la tenue au cyclage thermique de l'element combustible, determination de la chute de temperature au contact gaine-combustible traitee en detail dans un autre rapport CEA, - Etudes de l'ensemble: les etudes se rapportant a la chemise de graphite, au support et aux vibrations de la cartouche ont ete traitees par le service des Etudes Mecaniques et Thermiques (Section de Mecanique), Dans ce domaine, la Section d'Etude d'Elements Combustibles a etudie la tenue des centreurs sous l'action du courant gazeux. L'aboutissement des etudes est constitue par le dessin de l'element combustible, le schema de fabrication et les normes de fabrication. La validite de l'ensemble de ces essais hors pile sera confirmee par des assais en pile qui sont en cours et par l'irradiation des elements dans le reacteur EdF 2 lui-meme. En conclusion, on donne l'orientation des etudes pour l'amelioration de l'element combustible et la definition d'un element combustible

  2. The Role of Non-Destructive Testing in Test-Reactor Operation at the National Reactor Testing Station; Role des Essais Non Destructifs dans l'Exploitation des Reacteurs d'Essai au Centre National d'Essais de Reacteurs; Rol' nedestruktivnykh ispytanij pri ehkspluatatsii ispytatel'nykh reaktorov na natsional'noj stantsii po ispytaniyam reaktorov; Papel de los Metodos No Destructivos en la Explotacion de los Reactores de la National Reactor Testing Station

    Energy Technology Data Exchange (ETDEWEB)

    Francis, W. C.; Brown, E. S.; Burdick, E. E.; Gibson, G. W.; Tingey, F. H. [Phillips Petroleum Company, Atomic Energy Division, Idaho Falls, Idaho (United States)

    1965-10-15

    surface cracks, thermal anneal tests for blistering, and gamma-scanning of irradiated plates. Hydraulic testing of statistical sampling of fuel elements is used to confirm structural integrity, particularly the fuel plate-side plate-joint strength. A continuous effort is made to improve existing techniques and to develop new non-destructive inspection procedures. (author) [French] Les investissements tres importants (plus de 100 millions de dollars) consacres aux reacteurs d'essai du Centre national d'essais de reacteurs et la necessite d'exploiter ces reacteurs en toute securite exigent un controle extremement strict de la qualite des reacteurs et de leurs parties constitutives, notamment des elements combustibles et du dispositif de commande. Les essais non destructifs ont donc joue un role essentiel dans le controle de la qualite de ces pieces avant leur utilisation dans les. reacteurs d'essai. Bien qu'un grand nombre de ces essais non destructifs soient executes selon des procedures bien etablies, on a mis au point de nombreuses methodes inedites et introduit de nouvelles utilisations du materiel classique. On applique depuis longtemps au Centre d'essais les methodes ultrasonores pour la detection des cavites, des defauts de liaison et des craquelures internes. Recemment, on a etendu ces methodes a l'exploration automatique des plaques courbes et a l'inspection des elements combustibles irradies dans les canaux de stockage. Des travaux tres interessants ont permis d'appliquer la methode des ultrasons a la detection des fractures qui peuvent se produire dans l'ame lors du faconnement. Une methode d'exploration par rayons gamma, pour determiner la teneur d'elements combustibles en {sup 23}5{sup U}, s'est revelee tellement fiable qu'elle a ete adoptee pour calculer les penalisations financieres pour les articles non conformes aux specifications. Les radiographies de plaques de combustible donnent les dimensions de l'ame et, associees aux explorations'a l'aide d

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  4. The Application of Non-Metallic Core Materials in a High-Temperature Reactor Experiment; Utilisation de materes non metalliques dans le coeur d'un reacteur experimental a haute temperature; Ispol'zovanie nemetallicheskikh materialov dlya aktivnoj zony vysokotemperaturnogo opytnogo reaktora; Empleo de materiales no metalicos en el nucleo de un reactor experimental de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Huddle, R. A.U.; Shepherd, L. R. [Organization for Economic Co-Operation and Development, Dragon Project, Atomic Energy Establishment, Winfrith, Dorset (United Kingdom)

    1963-11-15

    refroidis par un gaz, construire et exploiter, dans le cadre de ce projet, un reacteur experimental de 20 MWth. Le reacteur - dont la construction touche a sa fin - est refroidi a l'helium; la temperature de sortie du coeur est de 750{sup o}C; il emploie de l'uranium-235 comme combustible et du thorium comme matiere fertile. Il est caracterise par l'absence de tout metal dans le coeur du reacteur. En raison'des hautes temperatures, qui peuvent atteindre 1050{sup o}C a la surface des elements combustibles et s'elever au dessus de 1500{sup o}C dans les regions les plus chaudes du combustible, on emploie des materiaux refractaires non metalliques. Le fait que tous les constituants du coeur sont reunis dans l'element combustible permet d'obtenir un rapport eleve entre la surface de transfert de la chaleur et le volume du coeur, d'ou une puissance specifique moyenne elevee pour un ensemble de dimension relativement faible. Chaque element combustible est constitue par un faisceau de tubes de graphite contenant les matieres fissiles et fertiles sous forme de carbure incorpore a des pastilles de graphite. Un courant refroidisseur d'helium traverse le centre de chaque barreau de combustible d'ou il ressort par la base pour etre conduit dans une installation de purification dans laquelle il est debarrasse des produits de fission et autres impuretes avant d'etre achemine de nouveau vers le reacteur. Cette methode permet de reduire la fuite des produits de fission qui, s'echappant du combustible ceramique porte a tres haute temperature, entrent dans le circuit de refroidissement primaire. Les auteurs exposent les problemes lies a la mise au point et a la fabrication du graphite et des elements combustibles ceramiques destines a ce reacteur ainsi que le comportement de ces materiaux dans les conditions de fonctionnement. Ils indiquent les resultats de recherches en pile et dans des boucles d'irradiation. Dans ce programme, tout l'effort se concentre sur la mise au point de reacteurs a

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-07-01

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

  7. Distilled Avant-Garde Echoes: Word and Image in Architectural Periodicals of the 1920s and 1930s

    Directory of Open Access Journals (Sweden)

    Hélène Jannière

    2016-12-01

    Full Text Available Since the 1980s, architectural avant-garde publications, seen as a laboratory for artists and architects, have given rise to numerous research projects. Although recent scholarship tends toward a more balanced interpretation of architectural publications of the interwar period than studies from the 1980s, most research on architectural books and journals continues to point out only the parallels, or even just the ‘alliances’, between the innovative visual form – typography and photography – of those books and magazines and the ‘new architecture’ they intended to promote: relationships between form and contents. This article tackles the issue of this historical and aesthetical convergence. It draws on a new generation of studies that takes into account photography, graphic design and texts, simultaneously, and focuses on their association in the space of the book. By examining several case studies, it brings to light relationships of texts and images di erent from those dramatic and disruptive ones elaborated by the avant-garde. This is done, rst, by considering a wider range of professional periodicals of the late 1920s and 1930s – both avant-garde and traditional – and second, by focusing more on the modes of perception photography introduced within the space of the book than on photographic or typographic experiments. The driving hypothesis is that in periodicals of the late 1920s and 1930s, even in those of a rather traditional form ('L’Architecte, L’Architecture vivante, Quadrante', new modes of perceiving the space of the book as a whole gave rise to semantic associations generated by juxtapositions or e ects of distance between word and image. This article also puts into question the way two periodicals in particular, 'L’Architecture d’aujourd’hui' and 'Casabella', both deemed ‘modernist’, integrated some of the lessons of contemporary typography and photography.

  8. Initiatives canadiennes d'avant-garde en matière de systèmes de ...

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

    Initiatives canadiennes d'avant-garde en matière de systèmes de santé équitables et d'amélioration de la santé des mères et des enfants ... renforcement des systèmes de santé : d'une part, le recrutement des travailleurs de la santé, le maintien de cet effectif et, d'autre part, le rôle des systèmes d'information sur la santé.

  9. Concept of transfer functions for a nuclear reactor; Notion de fonction de transfert pour un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Dalfes, Abdi [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires. Departement d' Electronique Generale, Service d' Electronique des Reacteurs

    1966-07-01

    The solution to the correlation equations are expressed in terms of the eigenvalues and Eigen-matrices of the transport operator, for a subcritical zero power reactor. This allows to define, for each point of the reactor and for detectors detecting neutrons of given velocities, correlation and transfer functions driven by the same white-noise source. A precise meaning is also given to the importance operator, which is the adjoin of the transport operator. (author) [French] La solution des equations regissant les matrices de correlation est exprimee en fonction des valeurs et matrices propres de l'operateur de transport pour un reacteur sous-critique et de puissance nulle. Ceci permet de definir, en chaque point du reacteur et pour des detecteurs repondant a des neutrons de vitesse definie, des fonctions de correlation et de transfert dont les entrees sont attaquees par une meme source de bruit blanc. Le role joue par l'operateur importance, adjoint de l'operateur de transport, est aussi precise. (auteur)

  10. The dangers of irradiate uranium in nuclear reactors; Les dangers de l'uranium irradie dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The danger of the uranium cans sur-activated by the use in the nuclear reactors is triple: - Irradiation from afar, during manipulations of the cans. - Contamination of air when decladding. - Contamination of air by fire of uranium in a reactor in function The first two dangers are usual and can be treated thanks to the rules of security in use in the atomic industry. The third has an accidental character and claimed for the use of special and exceptional rules, overflowing the industrial setting, to reach the surrounding populations. (authors) [French] Le danger des cartouches d'uranium suractive par utilisation dans les reacteurs nucleaires est triple: - Irradiation a distance, lors des manipulations des cartouches. - Contamination de l'air au moment de leur degainage. - Contamination de l'air par incendie d'uranium dans un reacteur en fonctionnement. Les deux premiers dangers sont habituels et peuvent etre traites grace aux regles de securite en usage dans l'industrie atomique. Le troisieme revet un caractere accidentel et reclame l'emploi de regles speciales et exceptionnelles, debordant le cadre industriel, pour atteindre celui des populations environnantes. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-09-15

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

  12. From Research on the Musical “Trans-avant-garde”: A Contribution to the Discussion on the Terminology Concerning the Historiography of 20th Century Polish Music

    Directory of Open Access Journals (Sweden)

    Monika Karwaszewska

    2006-10-01

    Full Text Available The research article discusses the concept of “the trans-avant-garde” (a term coined by the Italian art critic Achille Bonito Oliva to describe certain phenomena in visual arts, especially painting, which have appeared since the end of the 1970s and attempts to adapt it for a discussion of twentieth century Polish music. The trans-avant-garde (Italian la transavanguardia is an Italian form of expressionism in art (neo-expressionism, originating as a rejection of modernism, formalism, innovation, originality, and stylistic coherence, which began to treat tradition in a new way, extensively referring to 16th century mannerisms, ambiguity, stylistic pluralism and polysemy. While, on the one hand, trans-avant-garde artists are fully aware of the crisis of the avantgarde experiment, on the other, they aim to create content-packed works of deeply expressive and romantic character. The trans-avant-garde is widely considered to be an early stage of postmodernism, or simply its synonym. There is a difference, though, between the trans-avant-garde and the postmodern. Oliva speaks of a journey from America to Europe and back. My article discusses these differences, systematizes the most important stylistic aspects and aesthetic ideas, and applies these observations to the study of music—a discipline Oliva did not take into consideration. A key issue in the description of the trans-avant-garde in Polish music is analysis of the trends that precede it, are synchronous with it, and follow it in history. It is also important to trace borrowings and differences along this time axis. In order to offer an insight of this kind, I first present the different concepts of “modernity” and “postmodernity” that have appeared in music (and art of the twentieth century, and I then juxtapose those with the Italian original idea of la transavanguardia.

  13. From ancient to avant-garde: a review of traditional and modern multimodal approaches to surgical anatomy education.

    Science.gov (United States)

    Hu, Minhao; Wattchow, David; de Fontgalland, Dayan

    2018-03-01

    The landscape of surgical anatomy education is progressively changing. Traditional methods, such as cadaveric dissection and didacticism are being increasingly phased out in undergraduate courses for multimodal approaches incorporating problem-based learning, radiology and computer-based simulations. Although effective at clinically contextualizing and integrating anatomical information, these approaches may be a poor substitute for fostering a grasp of foundational 'pure' anatomy. Dissection is ideal for this purpose and hence remains the cornerstone of anatomical education. However, novel methods and technological advancements continually give way to adjuncts such as cadaveric surgery, three-dimensional printing, virtual simulation and live surgical streaming, which have demonstrated significant efficacy alone or alongside dissection. Therefore, although divergent paradigms of 'new versus old' approaches have engulfed and divided the community, educators should seek to integrate the ancient and avant-garde to comprehensively satisfy all of the modern anatomy learner's educational needs. © 2017 Royal Australasian College of Surgeons.

  14. Training for Better Management: Avante Zambézia, PEPFAR and Improving the Quality of Administrative Services

    Science.gov (United States)

    Schwarcz, Sandra K.; Rutherford, George W.; Horvath, Hacsi

    2015-01-01

    The United States President’s Emergency Plan for AIDS Relief (PEPFAR) emphasizes health systems strengthening as a cornerstone of programmatic success. Health systems strengthening, among other things, includes effective capacity building for clinical care, administrative management and public health practice. Avante Zambézia is a district-level in-service training program for administrative staff. It is associated with improved accounting practices and human resources and transportation management but not monitoring and evaluation. We discuss other examples of successful administrative training programs that vary in the proportion of time that is spent learning on the job and the proportion of time spent in classrooms. We suggest that these programs be more rigorously evaluated so that lessons learned can be generalized to other countries and regions. PMID:26673340

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

  16. Description of the french graphite reactor and of the experiments performed in 1956; Presentation du premier reacteur a graphite francais et des experiences effectuees en 1956

    Energy Technology Data Exchange (ETDEWEB)

    Bussac, J; Leduc, C; Zaleski, C P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    This paper is an introduction to the experiments performed on the G1 reactor, experiments fully described in the papers following (670 'B to P'). The main results are given together with some comments. The neutronic parameters of the core, a description of the most important structures, and a few words of the tests leading to normal operation of the reactor under load complete our survey. (author) [French] Ce rapport presente les experiences qui furent faites sur le reacteur G1 et dont la description en detail fait l'objet des rapports suivants (670 'B a P'). Les principaux resultats sont fournis ici et commentes. On trouvera en outre les caracteristiques neutroniques du coeur actif de la pile, une description des principales installations et une mention des essais qui ont conduit au fonctionnement normal du reacteur en puissance. (auteur)

  17. Neutron flux determinations in the reactors G2 and G3 during operation; Releves du flux neutronique dans les reacteurs G2 et G3 en puissance

    Energy Technology Data Exchange (ETDEWEB)

    Boulinier, C; Faurot, P; Sagot, M; Teste du Bailler, A [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1961-07-01

    After demonstrating the sensitivity of the distribution of power in a production reactor to a deformation caused by dissymmetries of reactivity in the reactor, the authors describe the method of neutron flux determination devised for the reactors G2 and G3 under working conditions; the detector used is a tungsten or nickel wire, the {gamma} activity of which is measured with an ionisation chamber. Several flux determinations are given as examples to illustrate the sensitivity of the method. (author) [French] Apres avoir mis en evidence la sensibilite de la repartition de la puissance dans un reacteur de production a une deformation provoquee par de faibles dissymetries de reactivite dans le reacteur, les auteurs decrivent la methode de releve du flux neutronique mise au point pour les reacteurs G2 et G3 en puissance; le detecteur utilise est un fil de tungstene ou de nickel dont l'activite {gamma} est mesuree a l'aide d'une chambre d'ionisation. Quelques releves de flux illustrant la sensibilite de la methode sont donnes a titre d'exemple. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

  20. "El cuento ficticio": la especularidad como expresión de la vanguardia hispanoamericana "The fictitious short story": metafiction as an expression of Spanish American Avant-Garde

    Directory of Open Access Journals (Sweden)

    Margarita Figueroa

    2008-12-01

    Full Text Available El objetivo de este estudio es examinar el funcionamiento de la especularidad o metaficción en la cual se concentra "El cuento ficticio" (1927 de Julio Garmendia para determinar que su especularidad es una expresión de la vanguardia hispanoamericana de las décadas del veinte y treinta o primera vanguardia. Primeramente, se estudia el texto de Garmendia como modelo de especularidad vanguardista por cuanto responde a la ruptura con la tradición realista y al experimentalismo. Experimentalismo de la estructura especular de "El cuento ficticio" porque se vale de un discurso expositivo en tiempo presente y futuro que sustituye el discurso narrativo en tiempo pasado como forma verbal característica de la narración (Weinrich. En la última parte, el texto de Garmendia se relaciona con novelas hispanoamericanas de la primera vanguardia que presentan la misma estructura especular. El texto de Garmendia es el primer relato especular hispanoamericano que responde a las innovaciones vanguardistas derivadas de la especularidad presente en novelas hispanoamericanas vanguardistas.The objective of this study is to analyze how metafiction, on which Julio Garmendia’s "El cuento ficticio" (1927 is concentrated, works in order to determine that its metafiction is an expression of the Spanish American Avant-Garde of the twenties and thirties, or first Avant-Garde. Firstly, Garmendia’s text is studied as a model of avant-garde metafiction because it responds to the breaking with the realist tradition and to experimentalism. Experimentalism of the metafictional structure of "El cuento ficticio" because it uses an expositive discourse in the present and future tenses that replaces the narrative discourse in the past tense as a verbal form which characterizes narration (Weinrich. In the last part, Garmendia’s text is related to the Spanish American first avant-garde novels that have the same metafictional structure. Garmendia’s text is the first Spanish

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    This report presents the results of studies which seemed important to undertake in connexion with the development of fast neutron reactors. - It points out the advantage of high internal breeding ratios ({approx}1, 1) which are necessary in order to get a small change in time both in power distribution and reactivity (less: than 0.005 {delta}k/k in 18 months). - It shows how to achieve this goal, when simultaneously power distribution flattening is obtained. These results in a higher mean specific power (which is an economic gain) and therefore in a smaller doubling time (about 10 years). - It attempts to find criteria concerning the specific power that should be used in future reactor designs -It presents a conceptional design of a 1000 MWe fast neutron reactor, for the realisation of which no technological impossibility appears. - It shows that the dynamic behaviour seems satisfactory despite a positive total isothermal sodium coefficient. - It tries to predict the development of fast reactors within the future total nuclear program. It does not appear that fissile materials supply problems should in France slow down the development of fast neutron reactors, which will be essentially tied up to its economical ability to produce cheap electric power. (authors) [French] Ce rapport presente les etudes qu'il nous a paru important d'aborder dans le cadre du developpement des reacteurs a neutrons rapides. - Il met en evidence l'interet des taux de regeneration internes eleves ({approx}1, 1) pour obtenir une bonne evolution dans le temps de la distribution de puissance et de la reactivite (moins de 0,005 {delta}k/k pour 18 mois). - Il montre la possibilite d'y parvenir tout en applatissant la distribution des fissions, ce qui se traduit par une puissance specifique moyenne plus elevee (gain economique), et donc un temps de doublement plus faible de l'ordte de 10 ans - Il tente de definir un optimum de la puissance specifique valable pour les

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    This report presents the results of studies which seemed important to undertake in connexion with the development of fast neutron reactors. - It points out the advantage of high internal breeding ratios ({approx}1, 1) which are necessary in order to get a small change in time both in power distribution and reactivity (less: than 0.005 {delta}k/k in 18 months). - It shows how to achieve this goal, when simultaneously power distribution flattening is obtained. These results in a higher mean specific power (which is an economic gain) and therefore in a smaller doubling time (about 10 years). - It attempts to find criteria concerning the specific power that should be used in future reactor designs -It presents a conceptional design of a 1000 MWe fast neutron reactor, for the realisation of which no technological impossibility appears. - It shows that the dynamic behaviour seems satisfactory despite a positive total isothermal sodium coefficient. - It tries to predict the development of fast reactors within the future total nuclear program. It does not appear that fissile materials supply problems should in France slow down the development of fast neutron reactors, which will be essentially tied up to its economical ability to produce cheap electric power. (authors) [French] Ce rapport presente les etudes qu'il nous a paru important d'aborder dans le cadre du developpement des reacteurs a neutrons rapides. - Il met en evidence l'interet des taux de regeneration internes eleves ({approx}1, 1) pour obtenir une bonne evolution dans le temps de la distribution de puissance et de la reactivite (moins de 0,005 {delta}k/k pour 18 mois). - Il montre la possibilite d'y parvenir tout en applatissant la distribution des fissions, ce qui se traduit par une puissance specifique moyenne plus elevee (gain economique), et donc un temps de doublement plus faible de l'ordte de 10 ans - Il tente de definir un optimum de la puissance specifique valable pour les projets de reacteurs futurs

  3. Intérêts de la description des variantes vasculaires avant chirurgie hépatique pancréatique et rénale

    OpenAIRE

    Leloup , Sarah Smahel

    2015-01-01

    Non disponible / Not available; Une imagerie complète associant au moins un scanner multi-phasique et une IRM doit être réalisée avant toute chirurgie hépatique (pour carcinome hépato-cellulaire ou métastasectomie hépatique), transplantation hépatique, duodéno-pancréatectomie céphalique, et avant toute greffe rénale. Elle n’a plus seulement pour but de fournir des éléments de caractérisation lésionnelle, elle devient à la base du bilan de résécabilité des lésions et d’opérabilité des patients...

  4. The Role of Non-Destructive Testing in the Los Alamos Reactor Programme; Role des Essais Non Destructifs dans le Programme de Reacteurs de los Alamos; Rol' nedestruktivnykh ispytanij materialov v Los-Alamosskoj reaktornoj programme; Papel de los Metodos de Ensayo No Destructivo en el Programa de Reactores de Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Tenney, G. H. [University of California, Los Alamos Scientific Laboratory, Los Alamos, NM (United States)

    1965-10-15

    the work on this subject has not been previously published. (author) [French] Le Laboratoire scientifique de Los Alamos, exploite par l'Universite de Californie pour la Commission de l'energie atomique des Etats-Unis, s'occupe depuis plus de vingt ans de l'etude, de la mise au point et de la construction de quatre types de reacteurs nucleaires: reacteurs de recherche, reacteurs de puissance, reacteurs pour la propulsion des fusees et assemblages critiques. Le Groupe des essais non destructifs collabore a presque tous les projets et travaux du Laboratoire. Le memoire decrit quelques-unes des methodes inedites d'essais non destructifs qui y ont ete mises au point et sont appliquees dans le cadre du programme de reacteurs. Le reacteur de puissance experimental LAMPRE est fonde sur l'utilisation d'une solution de phosphate d'uranium a haute temperature. Cette solution est tres corrosive et toutes les parties en contact avec elle ont un revetement en or. On a eu recours a des techniques radiographiques speciales pour controler l'or pendant le processus de laminage d'un lingot coule. On a procede de la meme maniere a l'inspection des soudures. Une methode d'inspection fondee sur les variations de potentiel aux electrodes a ete mise au point, pour la detection d'impuretes sur les surfaces d'or. Le reacteur experimental au plutonium fondu LAPRE est fonde sur l'utilisation de plutonium metallique, sous forme liquide plutot que sous forme solide, comme combustible. Le combustible est contenu dans des capsules en tantale. On a eu recours a des methodes non destructives pour verifier le bon etat du metal de base et des soudures pendant la fabrication des capsules, ainsi que pour controler les capsules remplies de plutonium avant, pendant et apres les essais de fusion et solidification. L'essai d'une pompe a plutonium fondu a ete suivi par des methodes radiographiques, en utilisant notamment un circuit ferme de television a rayons gamma. Pour le reacteur experimental a tres haute

  5. “When I Grow Up, I Will be an Artist.” Japanese Avant-garde’s Experimental Sandpit

    Directory of Open Access Journals (Sweden)

    klara / HRVATIN

    2017-01-01

    Full Text Available Sōgetsu Art Center, one of the most important venues for the avant-garde in 1960s Japan, could be defined as an artistic “experimental sandpit”. Its activities brought new musical expressions to the world of Japanese art, and lead to the independent film production. Japanese artists could play in this sandpit with a group of interdisciplinary peers and thus search for their most suitable artistic styles. Good examples are film director Hiroshi Teshigahara (1927–2001, playwright Kōbō Abe (1924–1993 and musician Tōru Takemitsu (1930–1996. The article gives an insight into the artistic associations and events, which took place under the roof of the Sōgetsu Art Center in the period from September 1958 to March 1971. The emphasis will be put on the main associations; activities related to the fields of jazz music, contemporary music, experimental film and animation. We will look for the common ground among these, and note the innovations which were brought about by the main participants at the Center in the fields of music and film.

  6. ‘We the Avant-Garde’. A History from Below of Dutch Heroin Use in the 1970s

    Directory of Open Access Journals (Sweden)

    Gemma Blok

    2017-03-01

    Full Text Available In the 1970s the Netherlands (like many other western countries was shocked by a sudden wave of heroin use. The heroin ‘epidemic’ is  currently framed as a public health problem that has been solved in a commendably humane fashion. In the mean time heroin users have gained a ‘loser image’. Using memoirs written by and interviews with former heroin users, this article argues that heroin use was initially linked to cultural rebellion, self-development and social criticism. We need to take this forgotten aspect of the history of the Dutch heroin ‘epidemic’ into account when we try to explain this historical phenomenon. ‘Wij de avant-garde’. Een history from below van heroïnegebruik in Nederland in de jaren zeventigIn de jaren zeventig van de vorige eeuw werd Nederland (net als veel andere westerse landen opgeschrikt door een plotselinge golf van heroïnegebruik. Deze ‘heroïne-epidemie’ wordt momenteel beschouwd als volksgezondheidsprobleem dat succesvol is bedwongen, op een bewonderenswaardig humane wijze. Ondertussen hebben heroïnegebruikers een ‘loser’ imago gekregen. Op basis van memoires geschreven door en interviews met voormalige heroïnegebruikers, betoogt dit artikel dat het gebruik van heroïne oorspronkelijk verbonden was met culturele rebellie, zelfontplooiing en cultuurkritiek. Dit vergeten aspect van de ‘epidemie’ is onderdeel van de verklaring voor de populariteit van opiaten destijds.

  7. The British Avant Garde: A Joint Venture Between the New York Cultural Center and Studio International Magazine

    Directory of Open Access Journals (Sweden)

    Jo Melvin

    2016-07-01

    Full Text Available This essay considers the relevance of The British Avant Garde exhibition at the New York Cultural Center in 1971 to the reputation and discussion of British artists in the US, and its subsequent impact in Britain. It situates the exhibition with reference to Conceptual Art and Conceptual Aspects at the NYCC and Information at the Museum of Modern Art, both held in 1970, and within the background milieu of a lively transatlantic and multi-directional network of artists such as Terry Atkinson, Michael Baldwin, Ian Burn, Barry Flanagan, Dan Graham, Joseph Kosuth, Christine Kozlov, Richard Long, Mel Ramsden, Sol LeWitt and Lawrence Weiner, who were developing alternative ways to make and to distribute work by using text, photocopies, and self-publication as forms of production as well as becoming the site of exhibition. Devised by Charles Harrison, assistant editor of Studio International magazine, the exhibition was a collaboration between the magazine and the NYCC, directed by Donald Karshan. Despite the mixed press reviews in New York, the exhibition paved the way for establishing institutional support for the artists in the UK.

  8. From the Forgotten Russian Avant-Garde: An Unknown Acrostic by I.A.Aksenov Dedicated to K.A.Bol’shakov. (On IWL RAS Archival Materials

    Directory of Open Access Journals (Sweden)

    Alessandro Farsetti

    2016-09-01

    Full Text Available This is the first publication of a hitherto unknown acrostic by an avant-garde poet, I. A. Aksenov. The poem was found in the archive of the Russian Union of Soviet Writers (VSSP in the Manuscript Section of the Institute of World Literature (IWL. This poem dated 1918 is a complex example of Russian avant-garde poetry demonstrating subtle mechanisms of meaning-making. The essay places the poem within the context of Aksenov’s work and relates it to his biography (cf. his friendship with a poet, K.A. Bol’shakov, to whom the poem was dedicated and the participation of both in S.G.Kara-Murza’s literary circle “Tuesdays”. It outlines the basic structure of the acrostic, reveals its main linguistic devices and intertextual connections. The analysis shows that the acrostic was thematically connected with two poems Aksenov and Bol’shakov wrote later the same day at Kara-Murza’s house. All the three texts capture the incubus of the Civil war (more precisely, the so called «Red terror» in the Fall of 1918 but also express hope for the return of the normal life, relying on friendship of like-minded people. In addition to this, the essay reveals possible interrelation between poetic techniques of Bol’shakov and Aksenov; this will enable us to better understand the specificity of these two understudied representatives of Russian avant-garde.

  9. Mutual exchange between Polish and Belgian magazines: a case study in cultural mobility within the interwar network of the avant-garde

    Directory of Open Access Journals (Sweden)

    Michał Wenderski

    2015-07-01

    Full Text Available In January 1924, Flemish avant-garde magazine Het Overzicht published a list of its congenial modernist for­ma­tions named ‘Het Netwerk’. It named nineteen magazines from Europe, the United States and Brazil, including the Polish magazine Zwrotnica. It exemplified the close and direct relationships within the supranational network of the avant-garde. Various formations belonging to this network, both bigger and smaller nodes, were linked to each other, often directly through befriended artists and writers. It did not only concern places such as Paris or Berlin, but also less pivotal nodes of the avant-garde network. In this paper I will present a case study of two countries, namely Poland and Belgium, as an example of European interwar cultural mobility. Joined in their pursuit of modern art, and crossing national and linguistic frontiers, Polish, French and Dutch-language magazines exchanged and re-printed each other’s texts and artworks, a practice also discussed in the correspondence between their representatives. Based on such tangible traces I will describe the cultural mobility and mutual exchange between the Polish and Belgian modernist journals, and attempt to shed light on the features, dynamics, and key figures of the network.

  10. Neurological Impact of World War I on the Artistic Avant-Garde: The Examples of André Breton, Guillaume Apollinaire and Blaise Cendrars.

    Science.gov (United States)

    Bogousslavsky, Julien; Tatu, Laurent

    2016-01-01

    World War I erupted at a time when artistic avant-gardes were particularly thriving across Europe. Young poets, writers, painters and sculptors were called to arms or voluntary enrolled to fight, and several of them died during the conflict. Among others, it dramatically changed their creative output, either through specific wounds or through personal encounters and experiences. These individual events then significantly modified the course of the literary and artistic avant-garde movements. Three particularly illustrative examples of avant-garde French poets are presented here: André Breton (1896-1966), Guillaume Apollinaire (1880-1918) and Blaise Cendrars (1887-1961). The deep source of the surrealist movement can indeed be found in André Breton's involvement as an auxiliary physician with critical interest in neuropsychiatry, which caused him to discover automatic writing. Guillaume Apollinaire's right temporal subdural hematoma strongly modified his emotional state and subsequent artistic activities. Alternatively, after losing his right, writing hand, Blaise Cendrars not only substituted it with a phantom but also rapidly switched from poetry to novels after he learnt to write with his left hand. © 2016 S. Karger AG, Basel.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

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

  12. Containment for Heavy-Water Gas-Cooled Reactors; Le Confinement des Reacteurs a Eau Lourde Refroidis par Gaz

    Energy Technology Data Exchange (ETDEWEB)

    Verstraete, P.; Lehmann, D.; Lafitte, R. [Bonard et Gardel, Ingenieurs-Conseils, Lausanne (Switzerland)

    1967-09-15

    The safety principles applicable to heavy-water, gas-cooled reactors are outlined, with a view to establishing containment specifications adapted to the sites available in Switzerland for the construction of nuclear plants. These specifications are derived from dose rates considered acceptable, in the event of a serious reactor accident, for persons living near the plant, and are based on-meteorological and demographic conditions representative of the majority of the country's sites. The authors consider various designs for the containment shell, taking into account the conditions which would exist in the shell after the maximum credible accident. The following types of shell are studied: pre-stressed concrete; pre-stressed concrete with steel dome; pre-stressed concrete with inner, leakproof steel lining; steel with concrete side shield to protect against radiation; double shell. The degree of leak proofing of the shells studied is regarded as a feature of the particular design and not as a fixed constructional specification. The authors assess the leak proofing properties of each type of shell and establish building costs for each of them on the basis of precise plans, with the collaboration of various specialized firms. They estimate the effectiveness of the various shells from a safety standpoint, in relation to different emergency procedures, in particular release into the atmosphere through appropriate filters and decontamination of the air within the shell by recycling through batteries of filters. The paper contains a very detailed comparison of about 10 cases corresponding to various combinations of design and emergency procedure; the comparison was made using a computer programme specially established for the purpose. The results are compared with those for a reactor of the same type and power, but assembled together with the heat exchangers in a pre-stressed concrete shell. (author) [French] Les principes de securite des reacteurs a eau lourde refroidis

  13. L’évaluation du risque cardiaque avant l’utilisation de stimulants chez les enfants et les adolescents

    Science.gov (United States)

    Bélanger, SA; Warren, AE; Hamilton, RM; Gray, C; Gow, RM; Sanatani, S; Côté, J-M; Lougheed, J; LeBlanc, J; Martin, S; Miles, B; Mitchell, C; Gorman, DA; Weiss, M; Schachar, R

    2009-01-01

    Les décisions en matière de réglementation et les documents scientifiques au sujet de la prise en charge du trouble de déficit de l’attention avec hyperactivité (TDAH) soulèvent des questions quant à l’innocuité des médicaments et à l’évaluation convenable à effectuer avant le traitement afin de déterminer la pertinence d’une pharmacothérapie. Ce constat est particulièrement vrai en présence de cardiopathies structurelles ou fonctionnelles. Le présent article contient l’analyse des données disponibles, y compris les publications révisées par des pairs, des données tirées du site Web de la Food and Drug Administration des États-Unis au sujet des réactions indésirables déclarées chez des enfants qui prennent des stimulants, ainsi que des données de Santé Canada sur le même problème. Des lignes directrices consensuelles sur l’évaluation pertinente sont proposées d’après l’apport des membres de la Société canadienne de pédiatrie, de la Société canadienne de cardiologie et de l’Académie canadienne de psychiatrie de l’enfant et de l’adolescent, qui possèdent notamment des compétences et des connaissances précises tant dans le secteur du TDAH que de la cardiologie pédiatrique. Le présent document de principes prône une anamnèse et un examen physique détaillés avant la prescription de stimulants et s’attarde sur le dépistage des facteurs de risque de mort subite, mais il ne contient pas de recommandations systématiques de dépistage électrocardiographique ou de consultations avec un spécialiste en cardiologie, à moins que les antécédents ou que l’examen physique ne le justifient. Le document contient un questionnaire pour repérer les enfants potentiellement vulnérables à une mort subite (quel que soit le type de TDAH ou les médicaments utilisés pour le traiter). Même si les recommandations dépendent des meilleures données probantes disponibles, le comité s’entend pour affirmer que

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-03-15

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

  15. Developments in natural uranium - graphite reactors; Developpement des reacteurs a graphite et uranium naturel

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    in order to show the advantages resulting from such developments in gas-graphite natural metallic uranium reactor systems; these are: a doubling of the specific and volume powers, and a three-fold reduction in the number of channels. The research now under way will make it possible to calculate the reduction in capital costs which will result from these important technical advances. (authors) [French] Le programme francais de centrales a graphite et uranium naturel s'est developpe, d'EDF 1 a EDF 4 - dans la voie d'un accroissement de la puissance unitaire des installations, de la puissance specifique et de la puissance volumique, et d'une amelioration des conditions de securite de fonctionnement. La puissance elevee d'EDF 4 (500 MWe) et l'integration du circuit primaire dans le caisson, lui-meme en beton precontraint, permettent ainsi de tirer le meilleur parti des elements combustibles tubulaires utilises des EDF 1, et d'arriver ainsi a une solution tres satisfaisante. L'emploi d'un element combustible refroidi interieurement (element annulaire) permet de faire un nouveau pas en avant: il devient alors possible d'augmenter la pression du gaz de refroidissement sans craindre le fluage du tube d'uranium. L'emploi d'un caisson en beton precontraint permet une telle augmentation de pression, et l'integration du circuit primaire elimine les risques d'une depressurisation rapide qui aurait presente dans ce cas un risque majeur. On aborde dans ce rapport les principaux problemes poses par ce nouveau type de centrale et on indique les grandes lignes des recherches et etudes effectuees en France: - Les etudes de neutronique et thermique ont permis d'envisager l'emploi d'elements combustibles de grandes dimensions (diametre interne = 77 mm, diametre externe = 95 mm), tout en conservant l'uranium naturel. - Les problemes de fabrication de ces elements, et de leur comportement en pile, font l'objet d'un programme important, tant hors pile que dans les piles de puissance (EDF 2

  16. Developments in natural uranium - graphite reactors; Developpement des reacteurs a graphite et uranium naturel

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    in order to show the advantages resulting from such developments in gas-graphite natural metallic uranium reactor systems; these are: a doubling of the specific and volume powers, and a three-fold reduction in the number of channels. The research now under way will make it possible to calculate the reduction in capital costs which will result from these important technical advances. (authors) [French] Le programme francais de centrales a graphite et uranium naturel s'est developpe, d'EDF 1 a EDF 4 - dans la voie d'un accroissement de la puissance unitaire des installations, de la puissance specifique et de la puissance volumique, et d'une amelioration des conditions de securite de fonctionnement. La puissance elevee d'EDF 4 (500 MWe) et l'integration du circuit primaire dans le caisson, lui-meme en beton precontraint, permettent ainsi de tirer le meilleur parti des elements combustibles tubulaires utilises des EDF 1, et d'arriver ainsi a une solution tres satisfaisante. L'emploi d'un element combustible refroidi interieurement (element annulaire) permet de faire un nouveau pas en avant: il devient alors possible d'augmenter la pression du gaz de refroidissement sans craindre le fluage du tube d'uranium. L'emploi d'un caisson en beton precontraint permet une telle augmentation de pression, et l'integration du circuit primaire elimine les risques d'une depressurisation rapide qui aurait presente dans ce cas un risque majeur. On aborde dans ce rapport les principaux problemes poses par ce nouveau type de centrale et on indique les grandes lignes des recherches et etudes effectuees en France: - Les etudes de neutronique et thermique ont permis d'envisager l'emploi d'elements combustibles de grandes dimensions (diametre interne = 77 mm, diametre externe = 95 mm), tout en conservant l'uranium naturel. - Les problemes de fabrication de ces elements, et de leur comportement en pile

  17. Avant-propos

    Directory of Open Access Journals (Sweden)

    Mona Huerta

    2011-10-01

    Full Text Available En 2009 se cumplió el setenta aniversario del final oficial de la Guerra Civil, un enfrentamiento que tuvo repercusiones considerables en numerosos países europeos y americanos. Interpretada por algunos como el inicio de la Segunda Guerra mundial, la Guerra Civil fue un acontecimiento fundador para una parte significativa de la población de naciones como Francia, México y Argentina. Por sus consecuencias políticas, culturales y demográficas, este conflicto dejó una huella indeleble y se convi...

  18. Avant-propos

    Directory of Open Access Journals (Sweden)

    Severiano Rojo Hernandez

    2010-03-01

    Full Text Available Au cours de la première moitié du XXe siècle, l’Europe vit naître et se développer sur son territoire un nombre considérable de dictatures particulièrement sanglantes. Malgré leurs différences idéologiques, Hitler, Staline, Mussolini, Franco, Salazar pratiquèrent une même politique répressive, fondée sur la censure, la terreur, l’élimination des adversaires politiques et la mise sous surveillance de l’ensemble de la société. Comme le signale Giorgio Agamben (« L’Etat d’exception », Le Monde, ...

  19. Avant-propos

    Directory of Open Access Journals (Sweden)

    Naomi Wulf

    2010-02-01

    Full Text Available Depuis environ dix ans, les biographies des Pères fondateurs de la nation américaine connaissent un succès populaire sans doute inégalé dans le passé. Certaines sont l’œuvre de spécialistes universitaires de la jeune République américaine, tels Joseph J. Ellis avec Passionate Sage : The Character and Legacy of John Adams (1993, American Sphinx : The Character of Thomas Jefferson (1996, National Book Award, puis Founding Brothers : The Revolutionary Generation (2000, Prix Pulitzer et enfin ...

  20.  Avant-propos

    Directory of Open Access Journals (Sweden)

    Georges Martin

    2012-06-01

    Full Text Available Le numéro 13 de la revue e-Spania, désormais ouverte aux études modernes, réunit deux dossiers issus de rencontres scientifiques. Le dossier médiéval (« Convivencia de lenguas y conflictos de poder en la península ibérica durante la Edad Media » trouve son origine dans un colloque organisé à Madrid en novembre 2011 par GRHIDE, partenaire d’AILP à l’Universidad Autónoma de Madrid. Il s’agit d’une contribution à la thématique du GDRE (« approche interdisciplinaire des logiques de pouvoir dans ...

  1. Avant-propos

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    Monique DE MATTIA-VIVIES

    2010-09-01

    Full Text Available Le présent volume rassemble les textes des communications présentées lors de la Journée d’Étude intitulée La Production et l’Analyse des discours, qui s’est tenue à Aix-en-Provence (Aix-Marseille Université le 4 décembre 2009 sous l’égide du LERMA.L'énoncé de ce sujet d'étude met l’accent, par le pluriel de sa formulation, sur la variété des types de discours : discours verbal ou non verbal, discours oral ou discours écrit, discours littéraire ou spécialisé (l’on peut dans ce cas se poser la...

  2. Avant-propos

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    Masha Itzhaki

    2010-10-01

    Full Text Available La production littéraire israélienne, à l’aube du XXIe siècle, se caractérise par une extraordinaire diversité thématique et stylistique qui ouvre la voie et donne de la voix à des auteurs de toutes origines, religions et couches sociales. Ce numéro de YOD comporte les actes du colloque organisé en mai 2008 à l’INALCO (Paris et à l’Université de Lille 3, qui se donnait pour objectif de célébrer le soixantième anniversaire de la littérature israélienne, mais aussi et surtout de mettre en évi...

  3. Avant-propos

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    Masha Itzhaki

    2011-11-01

    Full Text Available Ce numéro de YOD présente un échantillon des études actuelles sur la langue et la littérature yiddish dans la sphère francophone. Nous avons voulu réunir des travaux d’auteurs de différents horizons, s’occupant du yiddish en permanence ou ponctuellement et ayant aussi en commun des liens avec la culture et l’université françaises. Si la plupart sont des universitaires travaillant en France, d’autres sont des chercheurs ayant étudié ou travaillé dans ce pays ou bien des Français travaillant à ...

  4. Avant-propos

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    Raymond Jamous

    2011-06-01

    Full Text Available Identités, nations, globalisation : ces trois termes concentrent un grand nombre d’interrogations sur les transformations que vit le monde actuel. Ce sont eux qui ont fourni matière à réflexion à la première manifestation internationale coorganisée par le Laboratoire d’ethnologie et de sociologie comparative (cnrs et université Paris X, Nanterre et le Centro de Investigaciones y Estudios Superiores en Antropología Social (ciesas, Mexico. Du 6 au 9 novembre 2000, un colloque franco-mexicain ...

  5. Avant-Propos

    OpenAIRE

    Ruppert, Helmut

    2013-01-01

    C’est à l’instigation de mon professeur, M. Eugen Wirth, que je me suis lancé dans ce travail. Lors d’un premier voyage au printemps 1966, il me fit ouvrir les yeux sur quelques-uns des importants problèmes de la géographie sociale et économique du Proche-Orient. Lors de voyages ultérieurs passés à parcourir et à arpenter avec moi d’autres villes orientales, le professeur Wirth m’a permis de comparer pour la ville de Beyrouth, grâce à une vue générale, les éléments proprement orientaux et ceu...

  6. Avant-Propos

    Science.gov (United States)

    Ollivier, J.; Farhi, E.; Ferrand, M.; Benoit, M.

    2005-11-01

    L'École Thématique “Neutrons et Biologie” s'est tenue du 22 au 26 Mai 2004 à Praz/Arly (Haute-Savoie, France), dans le cadre des 12 èmes Journees de la Diffusion Neutronique de la Societe Française de Neutronique. Cette école a ete organisee avec le concours financier du CNRS (formation permanente), du Laboratoire Léon Brillouin (CEA Saclay), de la region Rhône-Alpes, du conseil général de Haute-Savoie et de l'Université Joseph Fourier de Grenoble. Une cinquantaine de participants, dont une vingtaine d'intervenants, ont largement contribué à la réussite de l'École. D'un point de vue scientifique, l'École s'est déclinée en sept sessions thématiques majeures: - une première session introductive a été consacrée à une revue globale des méthodes biophysiques ayant un fort impact pour l'étude de la structure et de la dynamique des macromolécules biologiques (J. Parello). Un accent tout particulier à été apporté pour décrire les neutrons en tant que composante importante de la panoplie des techniques couramment utilisées en biophysique moléculaire (J. Schweitzer). - une session dédiée aux mesures dynamiques par diffusion incohérente de neutrons a été largement developpée. Qu'ils s'agissent de vibrations et de relaxations moléculaires dans les protéines (J.M. Zanotti), de dynamique globale des protéines (G. Zaccaï), ainsi que de dynamique de l'eau d'hydratation (F. Gabel), de nombreux exemples ont permis d'illustrer la pertinence des neutrons pour étudier la dynamique fonctionnelle des protéines sur l'échelle de temps picosecond nanoseconde. L'analyse des données de diffusion inélastique de neutrons ne peut se passer de modélisation théorique analytique des propriétés dynamique des biomolécules (D. Bicout). - une large place avait été réservée aux études structurales en biologie. Cette troisième session a rassemblé des contributions en diffusion aux petits angles de neutrons pour l'étude structurale en solution (D. Lairez), en réflectométrie de neutrons pour l'étude de systèmes des membranes ou de protéines en interaction avec des membranes (G. Fragneto), ainsi qu'en diffraction de fibres appliquée à l'étude de l'ADN (T. Forsyth). - les simulations de dynamique moléculaire constituent une méthode théorique unique pour étudier, au niveau atomique, les mouvements internes des macromolécules biologiques, que ce soit à l'équilibre (G. Kneller, S. Crouzy) ou hors équilibre (B. Gilquin). Les trajectoires de dynamique moléculaire s'étendent aujourd'hui à la centaine de nanosecondes, et peuvent être de ce fait utilisées par certains programmes pour calculer les observables expérimentales fournies par la diffusion de neutrons (G. Kneller, T. Hinsen). - l'ouverture des neutrons à des techniques instrumentales permettant d'approcher, d'une part, des états hors-équilibre par le biais d'études cinétiques couplées à des mélanges rapides pour des études de croissance de phases (I. Grillo) ou de repliement de protéines, d'autre part, des conditions expérimentales extrèmes (hautes-pressions, M. Plazanet), nous ont semblé constituer des émergences prometteuses. À ce titre, une revue sur le repliement des protéines (V. Forge) a précisé l'importance de nombreuses techniques (fluorescence intrinsèque, dichroïsme, infra-rouge, RMN) dans le domaine, tout en permettant d'entrevoir l'intérêt des études par neutrons. - en marge des sessions purement “neutrons”, il nous semblait important de pouvoir présenter des techniques et méthodes souvent reconnues comme très complémentaires des neutrons, en privilégiant un volet “études structurales” et un volet “études dynamiques”. Côté méthodes dynamiques, la RMN (M. Blackledge) a été positionnée comme une technique permettant d'étudier la flexibilité moléculaire sur des echelles de temps plus lentes (ms). Côté méthodes structurales, la bio-cristallographie des RX appliquée à l'études des structures virales (P. Gouet) a permis de mettre en évidence des aspects complémentaires entre RX et neutrons, et de souligner les avantages et inconvenients respectifs de ces techniques. - l'École Thématique s'est achevée par une session commune avec les Journées Rossat-Mignod, au cours de laquelle J. Helliwell a établi une revue comparative RX/neutrons sur les développements récents en bio-cristallographie des protéines, suivi de deux presentations portant sur la dynamique incohérente et cohérente de systèmes membranaires (F. Natali, M. Rheinstadter). Contrairement aux années précédentes, le contenu de cet ouvrage se veut davantage refléter les applications des neutrons en biologie et biophysique moléculaire, en se reportant à des travaux scientifiques précis, plutôt que d'être constitué d'un recueil de cours, certes trés pédagogiques, mais quelquefois trop éloignés de l'expérience. Nous espérons que ce choix saura satisfaire le lecteur et encourager de nouveaux biologistes à utiliser les neutrons dès que possible pour leurs systèmes d'intérêt. Bonne lecture et bonnes manips !!!!

  7. Avant-propos

    Directory of Open Access Journals (Sweden)

    Valérie AUDA-ANDRÉ

    2009-07-01

    Full Text Available La question de l’état de la démocratie britannique bénéficie à l’heure actuelle d’un haut degré de visibilité dans les médias ; elle fait l’objet d’une série de commentaires et d’initiatives émanant du gouvernement et plus largement de la classe politique mais aussi d’associations de la société civile et de groupes de pression. Cette préoccupation soudaine, teintée d’une inquiétude qui peut s’avérer éphémère tant elle est dictée par l’actualité, nous invite toutefois à tenter de remonter aux origines de la rupture de la « démocratie d’équilibre ». Nous suivrons les transformations du régime démocratique britannique de la démocratie de marché des années Thatcher et Major à la démocratie participative et aux nouveaux schémas de gouvernance mis en œuvre par New Labour. Ce panorama sera l’occasion d’une réflexion théorique sur les différentes stratégies d’adaptation du modèle démocratique aux mutations sociales, économiques et culturelles qui ont modifié en profondeur l’identité du peuple britannique, l’être collectif qui se réalise dans des institutions et une pratique démocratiques.

  8. Avant-propos

    OpenAIRE

    Forêt, Jean-Claude; Gardy, Philippe; Torreilles, Claire; Verny, Marie-Jeanne

    2014-01-01

    L’ouvrage que nous publions aujourd’hui constitue la première étape d’un programme de recherches pluriannuel sur le renouveau de la poésie occitane des années 1930 à 1960. La première partie du volume est consacrée à la figure de Max Rouquette dont le centenaire était célébré en cette année 2008. La deuxième partie élargit le cadre à d’autres poètes de la période (Robert Allan, Gumersind Gomila, Charles Camproux, Léon Cordes, Denis Saurat) ou à des cadres éditoriaux de l’expression poétique :...

  9. Avant-propos

    OpenAIRE

    Sohnle , Jochen

    2014-01-01

    Fait suite au colloque annuel de la Société française pour le droit de l'environnement, organisé les 29 et 30 novembre 2012 à Strasbourg en hommage à Alexandre-Charles Kiss; International audience

  10. Avant-propos

    Directory of Open Access Journals (Sweden)

    François Moureau

    2002-11-01

    Full Text Available Des grands cimetières sous la lune, les mieux entretenus sont encore les bibliothèques. Ce volume un peu fantomatique est une promenade sentimentale et savante au milieu de ces tombes de cuir et de papier qui ne peuvent revivre un instant que par notre regard et par notre attention passagère. Les bibliothèques sont remplies de livres qu'on ne lit plus, qu'on n'a jamais lu peut-être et de quelques ouvrages qui, par magie ou génie singulier, nous parlent encore une langue déchiffrable. Le livre...

  11. Avant-propos

    OpenAIRE

    Huerta, Mona; Hernández, Severiano Rojo; Compagnon, Olivier

    2011-01-01

    En 2009 se cumplió el setenta aniversario del final oficial de la Guerra Civil, un enfrentamiento que tuvo repercusiones considerables en numerosos países europeos y americanos. Interpretada por algunos como el inicio de la Segunda Guerra mundial, la Guerra Civil fue un acontecimiento fundador para una parte significativa de la población de naciones como Francia, México y Argentina. Por sus consecuencias políticas, culturales y demográficas, este conflicto dejó una huella indeleble y se convi...

  12. Avant-propos

    Directory of Open Access Journals (Sweden)

    Georges Martin

    2010-06-01

    Full Text Available Ce numéro 9 de la revue e-Spania réunit, sous l’égide d’AILP (GDRE 671 du CNRS et du SEMH-Sorbonne (CLEA, EA 4083, un ensemble d’études portant sur le Liber regum (ou Libro de las generaciones y linajes de los reyes. Ces articles constituent la version remaniée et expertisée de communications présentées lors d’un colloque qui s’est tenu en Sorbonne les 4 et 5 décembre 2009 sous le titre Historiographie royale léonaise, castillane et navarraise du XIIe siècle. 2 : le Liber regum. Coordonnée...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

  14. Experience gained in two years operation of G1; Experience acquise au cours de deux ans de fonctionnement du reacteur G1

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    Technical specifications in respect of the first plutonium generating graphite reactor, the G1 at Marcoule, were stated in a paper read at the first Geneva Conference in 1955. We shall not therefore deal further with the technical characteristics of G1 in the present note, but rather propose to define - in the characteristic fields we think will be of major interest to foreign specialists - the results obtained in two and a half years operation since G1 first became critical on january 7, 1956. (author)Fren. [French] Les caracteristiques techniques du premier reacteur plutonigene, au graphite, de Marcoule, G1, ont ete donnees dans une communication presentee a la premiere conference de Geneve, en 1955. Nous n'y reviendrons donc pas dans la presente note qui a pour objet de faire le point, dans quelques domaines caracteristiques, qui nous ont paru les plus susceptibles d'interesser les specialistes etrangers, des resultats obtenus et des experiences faites au cours des deux annees et demi de fonctionnement du reacteur qui ont suivi sa divergence, le 7 janvier 1956. (auteur)

  15. Preliminary handling studies in large size fast piles; Etudes preliminaires de manutention dans les reacteurs a neutrons rapides de grande taille

    Energy Technology Data Exchange (ETDEWEB)

    Leduc, J; Marmonier, P [Association Euratom-CEA Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    This report examines the various fuel handling systems which presently seem feasible for a fast power reactor. It tries to point out the advantages and / or the the disadvantages and the fabrication problems for each solution involved and makes, a tentative to evaluate the time required for a fuel loading and / or unloading operation. One has investigated the influence of the maximum allowable irradiation, the number of of shut-downs, the power distribution shape within the core on the storage capacity needed, the load factor expected and the average irradiation obtained. (authors) [French] On a examine dans ce rapport les differents systemes de manutention, qui semblent actuellement realisables pour un reacteur a neutrons rapides de puissance, en essayant de faire ressortir les avantages, les inconvenients et les difficultes de realisation de chaque systeme, et de chiffer les temps de manutention auxquels ils conduisent. On a aussi regarde l'influence des variations du taux d'irradiation maximal,de la cadence des arrets ou de la forme du flux dans le coeur du reacteur, sur la capacite du stockage, le taux de disponibilite et le taux d'irradiation moyen. (auteurs)

  16. Preliminary handling studies in large size fast piles; Etudes preliminaires de manutention dans les reacteurs a neutrons rapides de grande taille

    Energy Technology Data Exchange (ETDEWEB)

    Leduc, J.; Marmonier, P. [Association Euratom-CEA Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    This report examines the various fuel handling systems which presently seem feasible for a fast power reactor. It tries to point out the advantages and / or the the disadvantages and the fabrication problems for each solution involved and makes, a tentative to evaluate the time required for a fuel loading and / or unloading operation. One has investigated the influence of the maximum allowable irradiation, the number of of shut-downs, the power distribution shape within the core on the storage capacity needed, the load factor expected and the average irradiation obtained. (authors) [French] On a examine dans ce rapport les differents systemes de manutention, qui semblent actuellement realisables pour un reacteur a neutrons rapides de puissance, en essayant de faire ressortir les avantages, les inconvenients et les difficultes de realisation de chaque systeme, et de chiffer les temps de manutention auxquels ils conduisent. On a aussi regarde l'influence des variations du taux d'irradiation maximal,de la cadence des arrets ou de la forme du flux dans le coeur du reacteur, sur la capacite du stockage, le taux de disponibilite et le taux d'irradiation moyen. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

  18. Contribution to the study of the stability of water-cooled reactors; Contribution a l'etude de la stabilite des reacteurs refroidis par de l'eau

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-06-01

    This work is devoted to the study of the stability of reactors cooled by water subjected only to natural convection. It is made up of two parts, a theoretical study and experimental work, each of these parts being devoted to a consideration of linear and non-linear conditions: - calculation of the transfer function of the reactor using neutronic and hydrodynamic linear equations with the determination of the instability threshold; - demonstration of the existence of the limiting oscillation cycle in the case of a linear feedback using MALKIN'S method; - measurement and interpretation of the reactor's transfer functions and of the hydrodynamic transfer functions; and - analysis of the noise due to boiling. (author) [French] Dans ce travail on etudie la stabilite des piles refroidies par de l'eau circulant en convection naturelle. Cette etude se divise en deux parties: un travail theorique et un travail experimental, chacune de ces parties comportant une etude lineaire et une etude non-lineaire: - calcul de la fonction de transfert du reacteur a partir des equations lineaires de la neutronique et de l'hydrodynamique avec determination du seuil d'instabilite; - demonstration de l'existence du cycle limite des oscillations dans le cas d'une retroaction lineaire en utilisant la methode de MALKIN; - mesure et interpretation de la fonction de transfert du reacteur et des fonctions de transfert hydrodynamiques; et - analyse du bruit d'ebullition. (auteur)

  19. Preliminary studies of the kinetics of a reactor by the probability method; Etude preliminaire de la cinetique d'un reacteur par la methode des probabilites

    Energy Technology Data Exchange (ETDEWEB)

    Bruna, J G; Brunet, J P; Clouet D' Orval, Ch; Caizergues, R; Verriere, Ph [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The {alpha} decay constant of prompt neutrons has been studied in the homogeneous plutonium-fueled, light-water-moderated reactor Alecto, by the probability method. In this method, the probability to count one, two,.... neutrons during a given time is measured. The value of {alpha} can be deduced from this measurement, for various subcritical states of the reactor. The experimental results were then compared with values obtained, for the same reactivities, by the pulsed neutron technique. (authors) [French] On a etudie sur Alecto, reacteur homogene au plutonium, modere a l'eau legere, la constante de decroissance {alpha} des neutrons prompts par la methode des probabilites. Celle-ci consiste a mesurer la probabilite de compter un, deux, etc..., neutrons pendant un intervalle de temps donne. On a pu en deduire la valeur de {alpha}, dans divers etats sous-critiques du reacteur. On a compare les resultats experimentaux a d'autres valeurs obtenues, aux memes reactivites, par la methode des neutrons pulses. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

  2. General views about specimen irradiations in reactors; Considerations generales sur'les irradiations d'echantillons dans les reacteurs

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    Specimen irradiation of fissile or non-fissile materials, carried out under circumstances becoming more and more severe and in reactor of increasing flux bas led to an evolution of irradiation rigs. A survey of the problems arising from irradiating under these various circumstances leads to conclude that it is possible to devise one capsule type suitable to every particular case, and that in a wide temperature range. Consequently, once the various irradiation-parameters known, a general method of calculation can be followed so as to determine the various sizes of the parts constituting the capsule. These theoretical calculations might sometimes be corrected through benefits gained from previous irradiations. Similarly, practical experimentation might allow to foresee more handy assembling of the capsule, specimen loading-and unloading being easier at the same time. (author) [French] L'irradiation d'echantillons, fissiles ou non fissiles, dans des conditions imposees de plus en plus strictes et dans des reacteurs a flux de plus en plus eleve, a eu pour consequence une evolution dans la conception des dispositifs d'irradiation. Lorsqu'on examine les problemes souleves par ces differentes irradiations, on en conclut qu'il est possible de concevoir un type de capsule capable de donner satisfaction dans chaque cas particulier, et ce, dans une tres large gamme de temperature. Par consequent, les differents parametres de l'irradiation etant connus, une methode generale de calcul peut etre suivie pour determiner les differentes cotes des pieces constitutives de la capsule. Ces calculs theoriques devront quelquefois etre corriges grace aux enseignements tires d'irradiations precedentes. De meme, l'experience acquise permettra d'envisager un montage plus aise de la capsule, tout en facilitant l'enfournement et le defournement des echantillons.

  3. Niš music festival and avant-garde music: Case studies concert of the Radio Belgrade Electronic Studio and 'John Cage's Evening'

    Directory of Open Access Journals (Sweden)

    Cvetković Sonja S.

    2017-01-01

    Full Text Available In the period of domination of socialist realism and moderate modernism, which meant for the Serbian post-war musical creativity isolation from the European and world trends of musical avant-garde, during the sixties and seventies of the twentieth century music of the Serbian and Yugoslav composers of the younger generation becomes more open to a new sound concepts of serialism, aleatory, electronic media and minimalism. A radical break with tradition and changes in almost all aspects of the new music - aesthetics, notation, sound realization - made difficult to establish a clear criteria for its evaluation and therefore, the general reception of the most actual tendencies. Beside two institutional musical places where the contemporary world and national music was performed and promoted - International Music Biennale Zagreb, founded in 1961 and annual Review of Yugoslav Music in Opatija, founded in 1964 (since 1979 under the name Review of Musical Creativity of Yugoslavia, concert and festival stages in the leading musical centers in former Yugoslavia have shown considerable restraint to the contemporary music. In the case of the reception of electro-acoustic compositions created in the Radio Belgrade Electronic Studio and John Cage's sonatas for prepared piano that were performed at the Niš (October Music Festival during the eighties of the 20th century, the paper discusses about the representation of avant-garde music at this manifestation and openness of the local public towards the contemporary compositional streams. At the concert held in 1981 in the hall of the Niš Symphony Orchestra were presented the latest achievements of the composers Miloš Petrović (Anton with or without Webern, 1981, Paul Pignon (Cartoon, 1980, Janez Matičič (Fusions, 1979, Vladan Radovanović (Audiospacial, 1975-78 and Dragoslav Ortakov (Eleorp, 1976 realized in the Radio Belgrade Electronic Studio founded in 1971. Serbian pianist Nada Kolundžija performed in

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-09-15

    factors, inventory factors) from one cycle to another, with a comparative study of the use of {sup 235}U in thermal and fast reactors, variations in the discounted fuel cycle costs from one cycle to another, and weight and characteristics of the recycled fuel, of the additional fuel required and of excess fuel. (author) [French] Le memoire presente les premiers resultats d'une etude entreprise dans le cadre d'un contrat d'association Euratom-Belgique et destinee a evaluer l'interet de l'alimentation de reacteurs rapides en uranium-235. Plusieurs possibilites se presentent pour le demarrage d'un reacteur rapide a l'aide d'uranium-235. 1. Le reacteur peut etre alimente en permanence avec de l'uranium enrichi, le plutonium produit servant a demarrer et a alimenter d'autres reacteurs; dans ce cas, l'uranium est recycle dans le reacteur en y ajoutant de l'uranium enrichi. 2. Le plutonium produit dans le reacteur peut etre partiellement recycle dans celui-ci, ainsi que l'uranium; dans ce cas, le reacteur se transforme progressivement en un reacteur au plutonium. Ces deux cas peuvent etre combines pour un reacteur a plusieurs zones d'enrichissement, ou l'on peut appliquer simultanement les deux politiques a des zones differentes, c'est-a-dire: alimenter, par exemple, la zone interne en uranium enrichi et recycler le plutonium dans la zone externe. Le mode de traitement du combustible irradie rend egalement le probleme complexe, selon que l'on traite ensemble ou separement le coeur et les couvertures axiales; de meme, pour un reacteur a plusieurs zones d'enrichissement, celles-ci peuvent etre traitees ensemble ou separement. Les calculs sont effectues a l'aide d'un code de calcul utilisant, pour lavpartie relative aux caracteristiques des reacteurs successifs, les coefficients d'equivalence definis par Baker and Ross et, pour la partie economique, la methode du cout actualise du cycle du combustible. Dans la premiere phase des travaux, une analyse approcheedu phenomene a ete

  5. A study of switch circuits for use as safety devices in nuclear reactors; Etude de circuits de commutation destines a la securite des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-12-15

    The author reviews briefly a few basic assemblies using electromagnetic relays for safety circuits in nuclear reactors; he then studies the use of static relays with a shorter time of response, based on impedance changes in a self-inductance consisting of a coil with a magnetic core having a rectangular hysteresis cycle. The author examines in particular the way in which it functions and the method of determining the parameters. (author) [French] L'auteur apres avoir examine sommairement en revue quelques montages de base des circuits de securite des reacteurs nucleaires utilisant des relais electromecaniques, etudie l'emploi des relais statiques a plus grande vitesse de reponse bases sur la variation d'impedance que presente une self-inductance realisee a l'aide d'une bobine enroulee autour d'un noyau magnetique a cycle d'hysteresis rectangulaire. En particulier, il en examine le mode de fonctionnement et la determination des parametres. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

  7. Spatial flux instabilities, and their control in the graphite gas power reactors; Les instabilites spatiales du flux et leur controle dans les reacteurs de puissance graphite-gaz

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    Radial-azimuthal and axial spatial flux instabilities in graphite-gas reactors are studied by means of an analytical approach. Results are checked with those which are given by two dimensional (r, z and r, {theta}) kinetic models programmed for an IBM 7094 computer. At least, conclusions on the control of instabilities obtained from these models are reported. (author) [French] Les instabilites spatiales du flux dans les reacteurs graphite-gaz, radiales et azimutales d'une part, axiales d'autre part, sont etudiees au moyen d'une formulation analytique. Les resultats sont confrontes avec ceux que fournissent des modeles cinetiques a deux dimensions (r, z et r, {theta}) programmes sur IBM 7094. On donne enfin les conclusions relatives au controle de ces instabilites que ces modeles ont permis de degager. (auteur)

  8. Detection of burst cans in the reactors cooled by gaseous phase; Detection des ruptures de gaine dans les reacteurs refroidis par phase gazeuse

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    In a nuclear reactor including the bars or plates cooled by a gaseous fluid, burst risks to occur in the sheath assuring the tightness separation between the cooling gas and the fissile materials. It is necessary to be able to detect the formation of these cracks as possible in order to avoid all risk of fission products release or any reaction of uranium to the contact of the refrigerating gas. It is however the increase of the radioactivity in the cooling gas due to the scattering of the fission products that permits to signal the apparition of a crack or to follow its evolution. It is possible to detect cracks of the order of the square millimeter. In this report, we will detail the principle and the realization of a device used for the surveillance of a natural uranium reactor cooled by air circulation. (M.B.) [French] Dans un reacteur nucleaire comportant des barres ou des plaques refroidies par un fluide gazeux des fissures risquent de se produire dans les gaines assurant la separation etanche entre le gaz de refroidissement et les materiaux fissiles. II est necessaire de pouvoir detecter la formation de ces fissures des que possible afin d'eviter tout risque de liberation de produits de fission ou de reaction de l'uranium au contact du gaz refrigerant. C'est cependant l'augmentation de la radioactivite du gaz de refroidissement due a la dispersion des produits de fission qui permet de signaler l'apparition d'une fissure ou de suivre son evolution. On peut ainsi detecter des fissures de l'ordre du millimetre carre. Dans ce rapport, nous detaillerons le principe et la realisation d'un appareil utilise pour la surveillance d'un reacteur a uranium naturel refroidi par circulation d'air. (M.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  10. Presence of Tritium in the Cooling Circuits of the Reactors G2 and G3; Presence de tritium dans les circuits de refroidissement des reacteurs G2 et G3

    Energy Technology Data Exchange (ETDEWEB)

    Estournel, R [Commissariat a l' Energie Atomique. Centre de Production de Plutonium de Marcoule, 30 - Chusclan (France)

    1962-07-01

    In a reactor of the G 2-G 3 type, tritium can be formed by the neutronic bombardment of many elements present in the core. Tritium was found to be present in the cooling circuits of the reactors G 2 and G 3 in the water coming from the regeneration of the CO{sub 2} dehydrating columns. (author) [French] Dans un reacteur du type G 2 - G 3, le tritium peut etre forme par le bombardement. neutronique de nombreux elements existant dans le c r. La presence de tritium dans les circuits de refroidissement des reacteurs G 2 - G 3 a ete mis en evidence dans l'eau provenant de la regeneration des colonnes de deshydratation du CO{sub 2}. (auteur)

  11. Dissonant Echoes of the Great War: Avant-garde, Urban Space, and Immigrant Voices in Armando Discépolo’s Babilonia

    Directory of Open Access Journals (Sweden)

    Gorica Majstorovic

    2014-04-01

      The present essay proposes that the problem of WWI is central to the "dissemination" trope of the Argentine cultural production in the 1920’s. The trope is examined in relation to modernity and urban space, in Armando Discépolo’s Babilonia (1925 and Xul Solar’s "Puerto" paintings (1923-1925. Through a contextualized reading of Babilonia, the essay analyzes the disseminated nationalities and languages, at a time when post WWI European immigrants presented a "threat" to national purity. Babylonian trope is associated with images of distraction, dissemination, and destruction. This is of particular importance for the analysis, especially with regard to the presence of Babylonian "dissemination" trope alongside criollismo and the emergent avant-garde currents in Argentina (Duchamp in Buenos Aires 1918-19, Marinetti in 1926, Borges, Girondo.

  12. Phonemes, Graphemes, Dabs of Paint: Roman Jakobson, the Russian avant-garde and the search for the shared basic elements of painting and poetry

    Directory of Open Access Journals (Sweden)

    Hofstede, Bregje

    2012-03-01

    Full Text Available The subject of this paper is the supposed affinity between painting and poetry as theorised by the linguist Roman Jakobson who played a crucial role for the Russian avant-garde and its close association of painting and poetry. The paper focuses on Jakobson's relation to the two 1913 manifestos "The Word as Such" and "The Letter as Such", written by the poets Chlebnikov and Kruchenyck, and on Jakobson's own (lost reply. It calls into question the accuracy of Jakobson's claim of having influcenced the poets' manifestos, and describes what Jakobson considered to be the shared 'core elements' of the visual and literary arts. According to him, they share a visuality, not on the level of the written sign or grapheme, but on a deeper level, visible only to the mind's eye.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  14. Perméabilité et osmose des avant-gardes. Sur le Manifeste activiste adressé à la Jeunesse

    Directory of Open Access Journals (Sweden)

    Cristian-Robert Velescu

    2014-12-01

    Full Text Available Notre étude – centrée sur l’avantgarde historique – se propose d’analyser un phénomène complexe, résultat de la tension exercée entre deux termes, supposés être corrélatifs : la «perméabilité» et «l’osmose ». Comme en physique, le premier n’est que la condition nécessaire du second. Nous sommes persuadés que les trois mouvements de l’avant-garde historique, porteurs d’une valeur fondatrice – futurisme, dadaïsme, surréalisme –, loin de s’être isolés hermétiquement entre les limites infranchissables de leurs convictions, ont communiqué d’une manière plus ou moins discrète, au niveau même de leurs «actes d’identité», la «perméabilité» et l’«osmose» étant donc à découvrir à travers leurs manifestes. Notre analyse porte surtout sur le Manifeste activiste adressé à la jeunesse, paru en 1924, à Bucarest, dans les pages de la revue d’avant-garde Contimporanul. Nous tâchons de démontrer que l’origine de ce manifeste doit être cherchée dans les manifestes futuristes, étant le résultat palpable d’un échange direct d’idées, engendré par le processus «osmotique». Celui-ci peut se manifester également à la limite qui sépare l’avantgarde historique de la modernité, comme l’exposition internationale de 1924 organisée par la revue bucarestoise Contimporanul semble le démontrer.

  15. Detection and location of can rupture in reactors cooled by a flow of water; Detection et localisation des ruptures de gaines sur les reacteurs refroidis par circulation d'eau

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    This report brings together the principal methods of fission-product detection used for water reactors. The position, type and method of adjustment is given for each detector. The methods for localizing the defective elements are explained, in particular those using water sampling or decreases in the flux. A few installations are briefly described. They correspond to particular types of reactors using boiling, pressurized or cold water. Amongst the many methods used, it can be noted that when the fuel is resistant, the installations are fairly compact. In nuclear super-heated reactors on the other hand, the study of fuel behaviour calls for larger installations. An identification of defective elements exists when the reactor structure allows it. If this is not possible, a localization in a group of elements is obtained by a flux depression. (author) [French] Ce rapport rassemble les principales methodes de detection de produits de fission utilisees pour des reacteurs a eau. On indique pour les detecteurs leurs emplacements, leurs types, leurs reglages. On explique quelles sont les methodes de localisation des elements defectueux, en particulier celles utilisant des prelevements d'eau ou des depressions de flux. Quelques installations sont decrites sommairement. Elles correspondent a des types particuliers de reacteurs a eau bouillante, pressurisee ou froide. Parmi les nombreuses methodes utilisees, on constate que les installations sont peu importantes, lorsque le combustible est resistant. Par contre dans les reacteurs a surchauffe nucleaire l'etude du comportement du combustible necessite des installations plus importantes. Une identification d'elements defectueux existe lorsque la structure du reacteur le permet. A defaut une localisation dans un groupe d'elements est obtenue par depression de flux. (auteur)

  16. The behaviour of some polyatomic gases in nuclear reactors; Le comportement de quelques gaz polyatomiques dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The chemical effect of ionizing radiations on a certain number of gaseous systems is described. Under the influence of radiations from a reactor, NH{sub 3}, is decomposed to nitrogen and hydrogen in stoichiometric proportions. Formation of N{sub 2}H{sub 3}, particularly could not be detected. Under a slow neutron flux the reaction {sup 14}N (n, p) {sup 14}C constitutes the main source of decomposition energy. Direct recombination of H, and N, has been brought about under the influence of radiation. The radiolysis of NH{sub 3}, occurs by a complex mechanism; and the kinetics follow a law of the order of about 2.5 which increases with the decomposition rate. The decomposition of hydrogen sulphide is appreciably faster than that of NH{sub 3}. Hydrogen is the only gaseous product of the reaction. The sulphur, which is deposited on the walls of the ampoules, is clearly visible to the naked eye. Up to the present decompositions up to 84 per cent have been obtained. The influence of the reaction {sup 32}S (n, p) {sup 32}P is considered. Radiochemical decomposition of nitrous oxide N{sub 2}O takes place with high yields. The reaction is complicated from the beginning by the formation of higher oxides of nitrogen which we identify and measure. Radiochemical decomposition of methane gives quantities of higher hydrocarbons. Certain of these gaseous systems could find applications in the measurement of high doses of radiation. This problem is discussed in the conclusion. (author)Fren. [French] L'effet chimique des rayonnements ionisants sur un certain nombre de systemes gazeux est decrit. Sous l'influence des rayonnements d'un reacteur, NH{sub 3} se decompose en azote et hydrogene en proportions stoechiometriques. En particulier aucune formation de N{sub 2}H{sub 4}, n'a pu etre detectee. Sous flux de neutrons lents, la reaction {sup 14}N (n, p){sup 14}C constitue la principale source d'energie de decomposition. La recombinaison directe de H{sub 2} et N{sub 2} a ete realisous l

  17. Slow Neutron Spectrometers at the Swedish Reactors; Spectrometres a Neutrons Lents des Reacteurs Suedois; 0421 041f 0415 041a 0422 0420 041e 041c 0415 0422 0420 042b 041c 0415 0414 041b 0415 041d 041d 042b 0425 041d 0415 0419 0422 0420 041e 041d 041e 0412 041d 0410 0428 0412 0415 0414 0421 041a 0418 0425 0420 0415 0410 041a 0422 041e 0420 0410 0425 ; Espectrometros para Neutrones Lentos en los Reactores de Suecia

    Energy Technology Data Exchange (ETDEWEB)

    Dahlborg, U.; Skoeld, K. [AB Atomenergi, Stockholm (Sweden); Larsson, K. -E. [Royal Institute of Technology, Stockholm (Sweden)

    1965-06-15

    is briefly discussed for illustrational purposes. A comparison between the light- and heavy-water moderated reactors for beam tube work shows the distinct advantages of the heavy-water type. (author) [French] Aux centres crees autour des deux, reacteurs de recherche suedois, Rl a Stockholm et R2 a Studsvik, on a maintenant la possibilite d'utiliser quatre spectrometres differents pour les experiences de diffusion inelastique des neutrons. A Stockholm, le reacteur Rl de 600 kW, ralenti a l'eau lourde, est equipe de deux spectrometres mecaniques a neutrons lents qui fonctionnent simultanement, Avec l'un, on utilise toujours un monochromateur a filtre en Be; avec l'autre, on peut employer soit le meme genre de monochromateur, soit un monochromateur a cristal. On a constate que pour les mesures de distribution angulaire, on obtient d'excellents resultats en combinant un monochromateur a cristal et un spectrometre mecanique, meme si l'intensite et le pouvoir de resolution sont relativement faibles. Recemment on a fait l'essai d'un selecteur de vitesse mecanique ayant un pouvoir de separation des longueurs d'onde de 4,2%. Cependant, cet instrument n'est pas encore utilise pour les experiences. Le spectrometre mecanique de Studsvik, avec lequel le reacteur R2 de 30 MW ralenti a l'eau legere est equipe, utilise pour la monochromatisation l'action combinee d'un monochromateur a filtre de Be et d'un hacheur a courbe de transmission etroite. Dans ce spectrometre, de meme que dans celui de Stockholm, le hacheur est place avant l'echantillon, ce qui permet l'enregistrement simultane de donnees pour des angles d'observation differents. Un spectrometre a cristal triaxial est aussi en service pres du reacteur R2. Les auteurs donnent certaines caracteristiques de ces instruments, notamment l'intensite, le pouvoir de resolution, et indiquent dans quelle mesure ils conviennent pour certaines operations. Ainsi, il ressort des donnees numeriques mentionnees qu'une amelioration assez

  18. Les récits historiques du Futurisme, ou l'histoire sans passé de l'avant-garde

    Directory of Open Access Journals (Sweden)

    Serge Milan

    2008-12-01

    Full Text Available L’article examine le refus du genre historique en tant qu’expression artistique viable par le Futurisme italien, en revenant sur les manifestes et les essais qui établissent un rapport entre le projet avant-gardiste des années Dix et Vingt et ce genre littéraire et théâtral très populaire à l’époque. Le rapport à l'histoire et au passé constitue en effet un problème inhérent à la naissance de l'avant-garde futuriste : ainsi, nous examinons ici l’élaboration de la notion de « passéisme », mais également la métaphore de la guerre aux morts, toutes deux stratégiques dans la constitution idéologique du mouvement. Enfin, nous revenons sur les essais de F.T. Marinetti écrits entre 1915 et 1929 dans lesquels le genre narratif où domine la référence historique est paradoxalement prééminent, et en particulier sur Guerra sola igiene del mondo, publié en 1915.L’articolo si propone di esaminare il rifiuto del genere storico in quanto forma artistica praticabile da parte del Futurismo, tornando sui manifesti che stabiliscono un rapporto tra il progetto avanguardista degli anni dieci e venti e questo genere letterario e teatrale molto in voga all’epoca. In effetti, il rapporto alla storia e al passato costituisce un problema inerente alla nascita stessa del Futurismo. Si esamineranno dunque l’elaborazione della nozione di “passatismo” e della metafora della guerra contro i morti, ambedue strategiche nella costituzione ideologica del movimento marinettiano. Infine, si tornerà brevemente sui saggi pubblicati da Marinetti tra il 1915 e il 1929 (e in particolare sul volume Guerra sola igiene del mondo, del 1915 nei quali il genere narrativo preeminente è paradossalmente proprio quello storico.

  19. Space-time dependent impulse response of a subcritical cylindrical reactor; Reponse impulsionnelle spatio-temporelle d'un reacteur cylindrique en regime sous-critique

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    In this paper, a new formulation of the spatial dependent impulse response of a subcritical reactor in a cylindrical geometry is proposed. An expression of the transfer function between a point source at the center of coordinates and the flux at a given point (r,z) is obtained by solving: by means of Laplace transform, the one group diffusion equation. In this transfer function, variables r and p (p being the Laplace variable) remain linked within a modified Bessel function. Taking the inverse Laplace transform is done by two different ways: - using the Mellin-Fourier method which separates variables r and t. This method makes it possible to establish that there is identity between the classical formulation and the new one. - using an inverse Laplace transform which keeps variables r and t linked. This method requires to approximate the inverse Laplace transform of the end factor. It is then possible to replace the radial harmonics modes series of the classical expression by a single function. This new formulation seems to be of particular interest when dealing with reactors of large size and lifetime. It is also interesting each time the harmonics play an important role. (author) [French] Dans le present rapport, on propose une nouvelle formulation de la reponse impulsionnelle spatio-temporelle d'un reacteur sous-critique, en geometrie cylindrique. Une expression de la fonction de transfert entre une source ponctuelle placee au centre des coordonnees et le flux au point courant (r,z) est obtenue en resolvant, par transformation de Laplace, l'equation de la diffusion a un seul groupe d'energie. Dans cette fonction de transfert, les variables r et p (variable de Laplace) demeurent groupees dans une fonction de Bessel modifiee. Le retour a l'original est effectue de deux manieres: - la methode de Mellin-Fourier qui separe les variables r et t, permet d'etablir l'identite entre la nouvelle formulation et la formulation classique. - un original conservant les variables

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The economic advantage of electricity-generating nuclear stations decreases when their size decreases. However, when a counter-pressure turbine is joined on to a reactor and the residual heat can be properly used, it can be shown that fairly low capacity nuclear equipment may compete with conventional equipment under certain realistic enough conditions. The aim of this paper is to define these special conditions under which nuclear energy can be profitable. They are connected with the location and the general economic environment of the station, the pattern of the electricity and heat demands it must meet, the level of fuel and specific capital costs, nuclear and conventional. These conditions entail certain technical and economic specifications for the reactors used in this way otherwise they are unlikely to be competitive. In addition, these results are referred to the potential steam and electricity market, which leads us to examine certain uses for the heat generated by double purpose power stations; for example, to supply combined industrial plants, various types of town heating and for removal of salt from sea water. (authors) [French] L'interet economique de centrales nucleaires productrices d'electricite decroit lorsque la puissance decroit. Cependant, lorsqu'on associe une turbine a contrepression a un reacteur et qu'il est possible d'utiliser dans de bonnes conditions la chaleur residuelle, on peut montrer que dans certaines conditions assez realistes, des equipements nucleaires d'une puissance unitaire peu elevee peuvent etre competitifs avec des equipements conventionnels. Cette communication a donc pour but de mettre en evidence quelles sont ces conditions particulieres de rentabilite de l'energie nucleaire. Elles sont liees a la localisation de la centrale et a son contexte economique general, a la structure de la demande d'energie electrique et thermique a laquelle elle doit satisfaire, au niveau des couts des combustibles et des investissements

  1. Operating Experience with the BR-5 Reactor; Experience acquise aupres du reacteur BR-5; Opyt ehkspluatatsii reaktora BR-5; Experiencia practica con el reactor BR-5

    Energy Technology Data Exchange (ETDEWEB)

    Lejpunskij, A. I.; Kazachkovskij, O. D.; Pinkhasik, M. S.; Aristarkhov, N. N.; Karpov, A. V.; Larin, E. P.; Efimov, I. A.

    1963-10-15

    The paper discusses the carrying-out of repair and maintenance work on the radioactive liquid-metal circuit of the BR-5 fast neutron reactor. Attention is also given to problems of reactor operation after achievement of the planned 2% fuel burn-up with some disturbance of leak-tightness in individual fuel elements. An account is given of experience in discharging the active section, examining the condition and leak-tightness of the fuel elements, and decontaminating the equipment and piping of the first radioactive circuit after reaching 5% fuel burn-up. (author) [French] Dans ce memoire les auteurs decrivent l'execution des reparations et des travaux d'entretien dans le circuit radioactif liquide-metal du reacteur a neutrons rapides BR-5. Ils etudient egalement les problemes lies au fonctionnement du reacteur au taux de combustion de 2% prevu avec quelques defauts d'etancheite dans des elements combustibles particuliers. Ils decrivent le dechargementen zone active et examinent les conditions d'etancheite des elements combustibles. Ainsi que la decontamination de l'appareillage et des tuyauteries du premier circuit radioactif apres avoir atteint un taux de combustion de 5%. (author) [Spanish] En la memoria se examinan los problemas planteados por el mantenimiento del circuito radiactivo de metal liquido del reactor de neutrones rapidos BR-5. Se tratan cuestiones relacionadas con la explotacion del reactor una vez alcanzado el grado de combustion de 2%, previsto en el proyecto y luego de producirse ciertas alteraciones de la densidad de determinados elementos combustibles. Se describen la experiencia adquirida durante la descarga del cuerpo del reactor, las investigaciones del estado general y de la hermeticidad de los elementos combustibles y las operaciones de descontaminacion de la instalacion y de las tuberias del circuito radiactivo primario despues de alcanzado un grado de combustion de 5%. (author) [Russian] V doklade rassmatrivayutsya voprosy proizvodstva

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The economic advantage of electricity-generating nuclear stations decreases when their size decreases. However, when a counter-pressure turbine is joined on to a reactor and the residual heat can be properly used, it can be shown that fairly low capacity nuclear equipment may compete with conventional equipment under certain realistic enough conditions. The aim of this paper is to define these special conditions under which nuclear energy can be profitable. They are connected with the location and the general economic environment of the station, the pattern of the electricity and heat demands it must meet, the level of fuel and specific capital costs, nuclear and conventional. These conditions entail certain technical and economic specifications for the reactors used in this way otherwise they are unlikely to be competitive. In addition, these results are referred to the potential steam and electricity market, which leads us to examine certain uses for the heat generated by double purpose power stations; for example, to supply combined industrial plants, various types of town heating and for removal of salt from sea water. (authors) [French] L'interet economique de centrales nucleaires productrices d'electricite decroit lorsque la puissance decroit. Cependant, lorsqu'on associe une turbine a contrepression a un reacteur et qu'il est possible d'utiliser dans de bonnes conditions la chaleur residuelle, on peut montrer que dans certaines conditions assez realistes, des equipements nucleaires d'une puissance unitaire peu elevee peuvent etre competitifs avec des equipements conventionnels. Cette communication a donc pour but de mettre en evidence quelles sont ces conditions particulieres de rentabilite de l'energie nucleaire. Elles sont liees a la localisation de la centrale et a son contexte economique general, a la structure de la demande d'energie electrique et thermique a laquelle elle doit satisfaire, au niveau des couts des

  3. A DOCUMENTARY STUDY OF AVANTE, THE MAGAZINE OF THE SOCIEDAD GENERAL DE FOTÓGRAFOS DE ESPAÑA (1905-1906

    Directory of Open Access Journals (Sweden)

    Juan Miguel Miguel Sánchez Vigil

    2015-03-01

    Full Text Available The photography magazine Avante, of which there are no copies in the public documentation centers, with the exception of issue number 1 in the library of the Royal Palace, was the official publication of the Sociedad General de Fotógrafos of Spain, an institution which emerged from the first Professional Photographers Assembly held in Madrid in October of 1905. Created and directed by Manuel Compañy, one of the leading authors at the end of the 19th century and beginning of the 20th, only three issues were published, which have not been studied up until now. The object of this study has been to carry out a documentary analysis in order to furnish new data on the photography magazines in Spain and to obtain information to offer researchers on this subject. The results are of great interest in regard to the contents (texts, illustrations and advertising and to the purpose of the magazine in relation with the afore-cited Sociedad General de Fotógrafos.

  4. Mesure asymétrie avant-arriere des quarks lourds a LEP1 avec le détecteur OPAL

    CERN Document Server

    Lafoux, H

    A partir de l'ensemble des données accumulées par OPAL au cours de la première phase de fonctionnement du LEP, nous avons mesuré l'asymétrie avant-arrière des quarks b et c au voisinage du pic du Zo. Utilisant une méthode traditionnelle, basée sur la détection des leptons produits dans les désintégrations semi-leptoniques des hadrons lourds, nous avons cherché à optimiser chaque étape de la mesure, en mettant en œuvre les algorithmes les plus appropriés. Le recours aux réseaux de neurones artificiels s'est en particulier avéré d'une grande utilité lorsque le problème à résoudre impliquait la prise en compte simultanée de multiples sources d'informations, d'origine et de nature très variées. Nos résultats sont en bon accord avec ceux des autres mesures effectuées à LEP et compatibles avec les prédictions du Modèle Standard pour un quark top de 174 ± 31 GeV/c2 et un boson de Higgs de masse comprise entre 60 et 1000 GeV/c2

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  6. Recent progress in the detection of bursts in the canning in French reactors; Progres recents de la detection des ruptures de gaines dans les reacteurs francais G1, EL2, G3, EL3

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    method. A scintillator and an electronic system provide a specific signal of the fission products which is then marked on a recorder. In a case where the activity threshold is exceeded, the cell involved is isolated from the prospection system and taker, over by a 'follow-up' detector which follows the evolution of the crack. A year of working on the pile G{sub 1}, which is cooled by air at atmospheric pressure, has made it possible to obtain results on the operation of the canning-burst detection appliance, which has led us to perfect the original device by installing an 'evolution-meter' of the type described above for G{sub 3}. The reactor EL{sub 3}, cooled by heavy water, uses a detection system based on the measurement by GM counters of the activity of the fission gases carried by diluted helium into the heavy water, then extracted by hydro-cyclones. The selectivity of the system gives it a low sensitivity to parasite activities, and an excellent performance. (author) [French] Dans les piles refroidies par gaz carbonique sous pression, du type G{sub 3}, la radioactivite principale du gaz est celle de l'azote 16 creee par reaction {sup 16}O(n, p) {sup 16}N des neutrons rapides sur l'oxygene. Cette activite, de vie courte et de forte energie {beta}, masque l'activite des gaz de fission s'echappant par une fissure de gaine dans le gaz carbonique et oblige a utiliser une methode de separation materielle des produits de fission solides avant la detection proprement dite. Cette detection est faite par une chaine electronique speciale dont l'entree est un scintillateur associe a un photomultiplicateur. Un systeme de mesure d'evolution de fissure avec compensation des variations de puissance permet de suivre la vitesse d'evolution d'une fissure. Cet appareil, baptise evolumetre, est destine a ramener a une methode de zero la mesure de l'activite du gaz de refroidissement des canaux, il permet de s'affranchir: 1) de l'activite propre du gaz restant apres la discrimination

  7. Fluctuations in a system depending on several random parameters. Application to reactors (1962); Fluctuations d'un systeme dependant de plusieurs parametres aleatoires. Application aux reacteurs nucleaires (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Blaquiere, A [Faculte des Sciences de Paris, 75 (France); Pachowska, R [Universite Technique de Varsovie (Poland)

    1962-07-01

    We have previously developed a method for studying neutronic fluctuations in nuclear reactors using the analogy between the behaviour of a reactor and that of certain common radioelectric circuits. The fluctuations may then be calculated by introducing into the circuit a suitable noise source. By this method we have been able to consider the overall fluctuations in a particularly simple form and we have provided a physical significance for certain results obtained more laboriously by other methods. The object of the present report is to generalise this method and in particular to extend it to the case of a reactor having a cellular structure and to apply it to fluctuations within a cell. It is thus shown that the fluctuations in a cell are the resultant of two terms: - a rapidly evolving Poissonian noise, not related to the overall fluctuations; - a slowly evolving noise, when the reactor is not too far from criticality, which is related to the overall fluctuations. The first term arises from a rapid 'ordering' of the system, during which time the cells come mutually into equilibrium. The second term is due to the coordinated evolution of all the cells, after the end of the first transitory phase. The conclusions reached show that it would be useful to complete the study with an analysis of non-linear phenomena which can considerably influence the transitory behaviour of the cells during the initial pre-equilibrium phase. This report also Stresses the relationship of the new method to the old methods. It tends also to place pile fluctuation theory in a more general framework, that of the fluctuations of a system depending on several random parameters; from this point of view, the method could easily be transposed and adapted to the study of other physical problems of this type. (authors) [French] Nous avons precedemment developpe une methode d'etude des fluctuations neutroniques des reacteurs nucleaires mettant a profit l'analogie entre le comportement d

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Berger, F; Bertrand, J

    1958-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

  11. Measurement of the thermal utilisation factor of the reactor G1; Mesure du facteur d'utilisation thermique du reacteur G1

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-07-01

    The thermal utilisation factor of the lattice of the reactor G1 has been measured by applying the autoradiographic technique to thin detectors irradiated in the cell. The experimental apparatus is described, and the results compared with those obtained by calculation based on various formulae. The results of the study of the thermal flux distribution in a cell containing a thorium rod of the same diameter as the uranium rods in the lattice are also given. The precision of the measurements is discussed. Value found: f diameter 26 = 0.8949 {+-} 0,005. (author) [French] Le facteur d'utilisation thermique du reseau du reacteur G1 a ete mesure en appliquant la technique de l'autoradiographie a des detecteurs minces irradies dans la cellule. Les dispositifs experimentaux sont decrits et les resultats sont compares a ceux obtenus par le calcul a partir de diverses formules. Les resultats de l'etude de la distribution du flux thermique dans une cellule contenant une barre de thorium de meme diametre que les barres d'uranium du reseau sont egalement indiques. La precision des mesures est discutee. Valeur trouvee: f diametre 26 = 0,8949 {+-} 0,005. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-06-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-06-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

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

  19. Study of a Slightly Enriched R Reactor Fuel by Means of a Pulsed Neutron Source; Etude d'un reacteur a combustible legerement enrichi (rubeole) a l'aide de sources pulsees de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Sagot, M.; Tellier, H. [Commissariat a l' Energie Atomique. Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1962-04-01

    A Be O moderated reactor using slightly enriched uranium oxide as fuel was studied by the pulsed neutron source technique. The neutron lifetime was measured in two different cores without reflector, then attempts were made at the measurement of great negative reactivities introduced into the reactor under the following forms: decrease of the volume of the un reflected core, introduction of absorbing cadmium rods, removal of fuel at the periphery of the critical core while maintaining a constant height, and substitution of fuel elements by less reactive elements. In all cases, the results are compared with the data obtained by another type of experiment or by computation. (author) [French] Nous avons applique la methode des sources pulsees de neutrons a un reacteur utilisant de l'oxyde d'uranium legerement enrichi, modere a l'oxyde de beryllium et, apres avoir mesure le temps de vie des neutrons dans deux coeurs differents non reflechis, nous avons porte notre effort, sur la mesure de reactivites negatives importantes introduites dans le reacteur sous differentes formes: - diminution du volume du coeur non reflechi, - introduction de barres absorbantes en cadmium, - enlevement de combustible a la peripherie du coeur critique, tout en conservant une hauteur constante, - substitution d'elements de combustible par des elements moins reactifs. Dans tous les cas, les resultats sont compares aux valeurs obtenues par un autre type d'experience ou par le calcul. (auteur)

  20. Study of a Slightly Enriched R Reactor Fuel by Means of a Pulsed Neutron Source; Etude d'un reacteur a combustible legerement enrichi (rubeole) a l'aide de sources pulsees de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Sagot, M; Tellier, H [Commissariat a l' Energie Atomique. Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1962-04-01

    A Be O moderated reactor using slightly enriched uranium oxide as fuel was studied by the pulsed neutron source technique. The neutron lifetime was measured in two different cores without reflector, then attempts were made at the measurement of great negative reactivities introduced into the reactor under the following forms: decrease of the volume of the un reflected core, introduction of absorbing cadmium rods, removal of fuel at the periphery of the critical core while maintaining a constant height, and substitution of fuel elements by less reactive elements. In all cases, the results are compared with the data obtained by another type of experiment or by computation. (author) [French] Nous avons applique la methode des sources pulsees de neutrons a un reacteur utilisant de l'oxyde d'uranium legerement enrichi, modere a l'oxyde de beryllium et, apres avoir mesure le temps de vie des neutrons dans deux coeurs differents non reflechis, nous avons porte notre effort, sur la mesure de reactivites negatives importantes introduites dans le reacteur sous differentes formes: - diminution du volume du coeur non reflechi, - introduction de barres absorbantes en cadmium, - enlevement de combustible a la peripherie du coeur critique, tout en conservant une hauteur constante, - substitution d'elements de combustible par des elements moins reactifs. Dans tous les cas, les resultats sont compares aux valeurs obtenues par un autre type d'experience ou par le calcul. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

  4. Methods and experimental coefficients used in the computation of reactor shielding; Methodes et coefficients experimentaux pour le calcul des protections de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Bourgeois, J; Lafore, P; Millot, J P; Rastoin, J; Vathaire, F de [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    1) The concept of an effective removal cross section has been developed in order more easily to compute reactor shielding thicknesses. We have built an experimental facility for the purpose of measuring effective removal cross sections, the value of which had not been published at that time. The first part of this paper describes the device or facility used, the computation method applied, and the results obtained. 2) Starting from this concept, we endeavoured to define a removal cross section as a function of energy. This enabled us to use the method for computations bearing on the attenuation of fast neutrons of any spectrum. An experimental verification was carried out for the case of fission neutrons filtered by a substantial thickness of graphite. 3) Finally, we outline a computation method enabling us to determine the sources of captured gamma rays by the age theory and we give an example of the application in a composite shield. (author) [French] 1) La notion de section efficace effective de deplacement a ete introduite pour calculer commodement les epaisseurs de protection des reacteurs. Nous avons construit un dispositif experimental destine a mesurer les sections efficaces effectives de deplacement dont la valeur n'avait pas ete publiee a cette epoque. La premiere partie de cette communication decrit le dispositif utilise, la methode de calcul employee et les resultats obtenus. 2) A partir de cette notion, nous avons essaye de definir une section efficace de deplacement fonction de l'energie. Ceci permet d'utiliser la methode du deplacement pour des calculs d'attenuation de neutrons rapides dont le spectre est quelconque. Une verification experimentale a ete faite dans le cas de neutrons de fission filtres par une epaisseur notable de graphite. 3) Enfin une methode de calcul permettant de determiner les sources de gamma de capture par la theorie de l'age est exposee et un exemple d'application donne dans une protection composite. (auteur)

  5. Methods and experimental coefficients used in the computation of reactor shielding; Methodes et coefficients experimentaux pour le calcul des protections de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Bourgeois, J; Lafore, P; Millot, J P; Rastoin, J; Vathaire, F de [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    1. The concept of an effective removal cross section has been developed in order more easily to compute reactor shielding thicknesses. We have built an experimental facility for the purpose of measuring effective removal cross sections, the value of which had not been published at that time. The first part of this paper describes the device or facility used, the computation method applied, and the results obtained. 2. Starting from this concept, we endeavored to define a removal cross section as a function of energy. This enabled us to use the method for computations bearing on the attenuation of fast neutrons of any spectrum. An experimental verification was carried out for the case of fission neutrons filtered by a substantial thickness of graphite. 3. Finally, we outline a computation method enabling us to determine the sources of captured gamma rays by the age theory and we give an example of the application in a composite shield. (author)Fren. [French] 1. La notion de section efficace effective de deplacement a ete introduite pour calculer commodement les epaisseurs de protection des reacteurs. Nous avons construit un dispositif experimental destine a mesurer les sections efficaces effectives de deplacement dont la valeur n'avait pas ete publiee a cette epoque. La premiere partie de cette communication decrit le dispositif utilise, la methode de calcul employee et les resultats obtenus. 2. A partir de cette notion, nous avons essaye de definir une section efficace de deplacement fonction de l'energie. Ceci permet d'utiliser la methode du deplacement pour des calculs d'attenuation de neutrons rapides dont le spectre est quelconque. Une verification experimentale a ete faite dans le cas de neutrons de fission filtres par une epaisseur notable de graphite. 3. Enfin une mde de calcul permettant de determiner les sources de gamma de capture par la theorie de l'age est exposee et un exemple d'application donne dans une protection composite. (auteur)

  6. Partial combustion of a fuel cartridge in reactor G1; Combustion partielle d'une cartouche de combustible dans le reacteur G 1

    Energy Technology Data Exchange (ETDEWEB)

    De, Rouville; Leduc,; Segot, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    -devices, some null regulating tension systems, annealing the background due to continuous pollution. This event has been fruitful. A grid trap has been set right ahead the reactor. Stricter instructions have been given for rising power operations and automatic burst slug sy (already improved as said above) has been duplicated by a human control. At last, the fault has pointed out that the reactors with gap had the disadvantage of facilitating the contamination of channels from one to another. On the other hand, graphite stores the radioactive dusts and hinders an easy decontamination. (author) [French] Le 26 octobre 1956, le reacteur G1 etait remis en marche apres un arret de quelques jours. L'installation de detection de rupture de gaines donna un premier signal de prealerte a 19h07 cote chargement, un second a 19h13 cote dechargement, puis d'autres. Le chef de quart ordonna a 19h15 une baisse rapide de la puissance mais voulant reperer le canal fautif avec precision la fit remonter ensuite a 2 puis a 5 MW. Bientot, par crainte de contamination exterieure, on dut arreter l'exploration et c'est par detection {gamma} a l'exterieur des tuyaux de detection de rupture de gaine qu'on identifia la cartouche endommagee dans le canal 19-13. Les enregistrements des stations de sante montrerent que les pointes observees etaient restees notablement inferieures aux limites maxima admissibles. L'examen methodique et le degagement du canal accidente occuperent trois semaines. On put apercevoir cote chargement les billettes d'uranium nues sur un lit de poudre de magnesie; cote dechargement, la gaine etait intacte mais l'extremite de la cartouche 'pendait' a l'interieur de la fente d'arrivee d'air. Repoussee cote chargement d'environ 30 cm, la cartouche se bloqua. Apres des essais divers, toujours sous injection d'argon, et avec des protections severes du personnel, on mit en oeuvre un tube fraise, analogue a ceux utilises pour les forages. On nettoya le canal par aspiration, sans toutefois

  7. Testing of a reactimeter for a light water reactor in the range + 500 to - 5000 pcm; Essai d'un reactimetre pour reacteur a eau legere dans la gamme + 500, - 5000 pcm

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    This apparatus is designed to measure instantaneously the positive or negative reactivity of a uranium reactor moderated by light water, on condition that the point of departure is the critical state of the reactor, or an already known sub-critical state. Slight modifications only are required to adapt it to another type of reactor. It is an analogue computer which simply inverses the transfer function of the reactor; it is not therefore a model reactor of which the output voltage is connected by a servo-mechanism to the power of the reactor to give the reactivity; the principle of the calculation of the reactivity does not depend on a servomechanism. One of its disadvantages is that it cannot operate outside a power variation range of 2.5 decades. However the measurement of a negative reactivity value between 0 and 3000 pcm is immediate. It measures the reactivity without deducting it from the period; it therefore gives the reactivity very precisely both for divergence and convergence even through in this latter case the period does not in fact exist. The equipment makes it possible to calibrate very rapidly the control rods of a reactor (the rod-drop method), to measure the reactivity of an experiment in the core, and to measure certain temperature effects. It is also possible by introducing a control into the core at a measured rate, to deduce directly its efficiency curve. (author) [French] Cet appareil est destine a mesurer instantanement la reactivite positive ou negative d'un reacteur a uranium modere a l'eau legere, a condition de partir de l'etat critique du reacteur, ou eventuellement d'un etat sous-critique deja connu. De legeres modifications permettent de l'adapter a un autre type de moderateur. C'est un calculateur analogique, qui inverse purement et simplement la fonction de transfert du reacteur; ce n'est donc pas un simulateur de pile dont la tension de sortie est asservie a la puissance du reacteur pour elaborer la reactivite; le principe du

  8. Plantform: gebruikersgroep avant la lettre

    NARCIS (Netherlands)

    Hofstede, G.J.; Mos, de P.

    2007-01-01

    Vanwege de veranderde informatiebehoefte in de sector heeft een gebruikersgroep van sierteeltkwekers software laten ontwikkelen voor een ERP-systeem. De auteurs zetten uiteen hoe de gebruikersgroep tot stand gekomen is, wat er bereikt is en wat de betekenis daarvan is geweest. Naar aanleiding van

  9. Laid Back Avant-Garde

    DEFF Research Database (Denmark)

    Degn Johansson, Troels

    2010-01-01

    controversial. Whereas Laid Back has been one of the largest commercial successes of the Danish music industry due to the success of a handful of pop hits (in Germany, mainly), the duo has never been recognized for its artistic contribution. A few years after his public statement, von Trier directed...... the official music video for Laid Back’s Bakerman single, where the duo and a backing group dressed up as bakers is seen performing while skydiving. Rather than approaching this video as an illustration of the song, the paper suggests that the Bakerman video should be seen as the result of a curatorial act...... where Lars von Trier seeks to elaborate on his particular fondness of the values that this pop duo seems to represent for him; simplicity, popularity (in Danish “folkelighed”), and irony. In this sense, by promoting the Laid Back single by means of a music video, von Trier’s contribution leads us rather...

  10. Esporte e vanguardas artísticas: cubismo, Ashcan School e expressionismo Sport and avant-garde art: cubism, the Aschan School and expressionism

    Directory of Open Access Journals (Sweden)

    Victor Andrade de Melo

    2011-03-01

    Full Text Available Considerando que os movimentos artísticos possuem algum grau de coerência interna no que se refere a uma forma peculiar de estabelecer relação com o contexto histórico e com o próprio fazer artístico, esse estudo teve por objetivo discutir a presença do esporte em obras de arte ligadas ao cubismo, à Ashcan School e ao expressionismo. Para alcance do objetivo, trabalhando com a ideia de que é possível construir uma historia cultural/antropologia histórica da imagem (BURKE, 2004, adotou-se o modelo de análise e interpretação de Melo (2009. Cremos ser possível lançar olhares sobre o esporte a partir de sua inserção na construção do imaginário moderno, bem como o oposto: prospectar a modernidade desde a prática esportiva. Ao final concluiu-se que o quadro multifacetado de aproximação dessas vanguardas com o esporte nos ajuda a ter uma noção de como a manifestação estava se configurando e compondo seu quadro de popularização.Considering that the art movements have a certain degree of inner coherence regarding a peculiar form of establishing a connection between the historical context and the art making itself, this study aims at discussing the presence of sport in works of art related to cubism, the Aschan School and to expressionism. In order to reach that goal, working with the idea that it is possible to make a cultural/anthropological history of image (BURKE, 2004, we have adopted Melo's (2009 model of analysis and interpretation. We believe it is possible to cast new visions about sport from its insertion in the making of the modern imaginary, as well as the opposite: to prospect modernity itself from the sport practice. At the end we have concluded that the multifaceted picture of the approximation of those avant-gardes with sport might help us understand how the manifestation was being shaped, within their popularization set up.

  11. {sup 36}Cl and {sup 14}C behaviour in UNGG graphite during leaching experiments

    Energy Technology Data Exchange (ETDEWEB)

    Pichon, C.; Guy, C.; Comte, J. [Commissariat a l' Energie Atomique - C.E.A., Laboratoire d' Analyses Radiochimiques et Chimiques (L.A.R.C.) 13108 Saint Paul lez Durance (France)

    2008-07-01

    Graphite has been used as a moderator in Natural Uranium Graphite Gas reactors. Among the radionuclides, the long-lived activation product {sup 36}Cl and {sup 14}C, which are abundant in graphite after irradiation can be the main contributors to the dose during disposal. This paper deals with the first results obtained on irradiated graphite from French G2 reactor. Both leaching and diffusion experiments have been performed in order to understand and quantify the radionuclides behaviour. Chlorine leaching seems to be controlled by diffusion transport through graphite matrix. On the contrary {sup 14}C leaching is very low, probably because after irradiation, the remaining {sup 14}C was produced from {sup 13}C activation in the crystalline structure of graphite. (authors)

  12. L’aménagement du territoire avant la lettre : quelques exemples genevois (XVIIIe-XIXe siècles

    Directory of Open Access Journals (Sweden)

    Isabelle Roland

    2012-04-01

    Full Text Available Les facteurs historiques et géopolitiques ont eu, à Genève, une influence notable sur la structure du territoire et la morphologie de certaines localités. A Meyrin par exemple, la création d’un nouvel axe routier a transformé en quelques années un village-rue en village-carrefour. A Malagny, un hameau d’origine médiévale a été presque entièrement détruit au XVIIIe siècle pour faire place à un grand domaine. A Genthod, un modeste village s’est embourgeoisé suite à l’implantation de trois domaines patriciens et les paysans ont accepté de déplacer leur fumier dans une rue secondaire, créée à cet effet. A Chêne, un village a été scindé en deux entités politiques et confessionnelles bien distinctes, tandis qu’à Plan-les-Ouates, le contraste est frappant entre les deux côtés de la rue principale, colonisés à deux époques différentes. Ces quelques exemples relèvent de ce que l’on peut considérer comme de l’aménagement du territoire avant la lettre et démontrent qu’il est impossible de dissocier l’architecture rurale de son environnement et de son histoire.In Geneva, historic and geopolitical factors have significantly influenced the region’s overall structure and the form of particular locals within it. For example, in the course of just a few years, a new road transformed Meyrin from a one-street village into an important commercial crossroad. In Malagny, a medieval hamlet was almost entirely demolished in the 18th century to make way for a grand estate. In Genthod, a farming village was “gentrified” after 3 nobles estates were established around it. The village peasants agreed to move their dung-heaps to a more discreet secondary street, donated by one of the estates for the purpose. In Chêne, a village was divided into two distinct political and religious districts. Finally, at Plan-les-Ouates, there is a strong contrast between the two sides of the village’s main street, which were

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    organic liquids under irradiation. The equipments of Melusine are now being modernized. Siloe, another swimming-pool reactor, has been operating at 15 MW since the end of 1963. The performances achieved constitute a considerable progress in the field of swimming-pool reactors, since the fluxes obtained with Siloe are in the same order of magnitude than those which needed till now a tank type structure, whose numerous disadvantages in the fitting of experiments are well known. Siloe will be used mostly in the study of structural materials, graphites, refractory fissile materials, and for solid state physics. The reactor Pegase, in service in the Cadarache Nuclear Centre since 1963, is intended solely for testing full-scale fuel elements of EDF and EL 4 types. The current programme, for the eight loops of the reactor, covers the elements for the reactors EDF 2, EDF 3 and EL 4. New loops are in the course of being studied for the fuel elements of the EDF 4 and EDF 5 reactors. The general line of the CEA programmes has shown up the considerable need for fast neutron irradiations. The reactor Osiris which is in the course of being constructed will serve to complement the CEA's equipment in this field and at the same time fill the gap which will be left in the near future in the Centre de Saclay by the closing down of EL 2. Osiris is a light water reactor whose special structure will allow it to function at 50 MW without the disadvantages usually associated with the presence of a heavy waterproof tank. This reactor, which should be put into service in 1966, is mainly intended for the investigation of structural materials, graphite and refractory fuels; it will also serve to increase the production of high specific activity isotopes, and to develop activation analysis techniques. (authors) [French] Les auteurs examinent successivement les differents reacteurs de recherche en service dans les Centres du Commissariat a l'Energie Atomique. Ils retracent brievement l'histoire de ces

  15. A new detector for the measurement of neutron flux in nuclear reactors; Nouvelle methode de mesure des flux de neutrons dans les reacteurs atomiques

    Energy Technology Data Exchange (ETDEWEB)

    Koch, L; Labeyrie, J; Tarassenko, S [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The detector described is designed for the instantaneous measurement of thermal neutron fluxes, in the presence of high {gamma} ray activity; this detector can withstand temperatures as high as 500 deg. C. It is based on the following principle: radioactive atoms resulting from heavy-nucleus fission are carried by a gas flow to a detector recording their {beta} and {gamma} disintegration. Thermal neutron fluxes as low as few neutrons per cm{sup 2} per second can be measured. This detector may be used to control a nuclear reactor, to plot the thermal flux distribution with an excellent definition (1 mm{sup 2}) for fluxes higher than 10{sup 8} n/cm{sup 2}/s. The time response of the system to a sharp variation of flux is limited, in case of large fluxes, to the transit time of the gas flow between the fission product emitter and the detector; of the order of one tenth of a sec per meter of piping. The detector may also be applied for spectroscopy of fission products eider than 0,1 s. (author)Fren. [French] On decrit un appareil permettant la mesure instantanee des flux de neutrons thermiques accompagnes de flux intenses de rayons {gamma} et situes dans des enceintes pouvant etre portees a des temperatures superieures a 500 deg. C. On utilise la radioactivite des atomes resultant de la fission des noyaux lourds; ces atomes sont entraines par un courant gazeux vers un detecteur de radioactivite qui enregistre leurs desintegrations {beta} et {gamma}. On peut mesurer des flux partir de quelques neutrons thermiques par cm{sup 2} et par seconde. L'appareil permet de suivre la puissance d'un reacteur atomique, de tracer des cartes de densite de neutrons avec une tres bonne definition (1 mm{sup 2}) dans le cas de flux superieurs a 10{sup 8} cm{sup 2}/s. Le temps de reponse du systeme a une variation du flux de neutrons est limite, poes flux importants, par le temps de transit du gaz entre l'emetteur de produits de fission et le detecteur: soit quelques dizaines de

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-04-15

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

  17. Study of new structures adapted to gas-graphite and gas-heavy water reactors; Etude de structures nouvelles adaptees aux reacteurs graphite-gaz et eau lourde-gaz

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The experience acquired as a result of the operation of the Marcoule reactors and of the construction and start-up of the E.D.F. reactors on the one hand, and the conclusions of research and tests carried out out-of-pile on the other hand, lead to a considerable change in the general design of reactors of the gas-graphite type. The main modifications envisaged are analysed in the paper. The adoption of an annular fuel element and of a down-current cooling will make it possible to increase considerably the specific power and the power output of each channel; as a result there will be a considerable reduction in the number of the channels and a corresponding increase in the size of the unit cell. The graphite stack will have to be adapted to there new conditions. For security reasons, the use of prestressed concrete for the construction of the reactor vessel is becoming more widespread; they could lead to the exchangers and the fuel-handling apparatus becoming integrated inside the vessel (the so-called 'attic' device). A full-size mode) of this attic has been built at Saclay with the participation of EURATOM; the operational results obtained are presented as well as a new original design for the control rods. As for as the gas-heavy-water system is concerned, the research is carried out on two points of design; the first, which retains the use of horizontal pressure tubes, takes into account the experience acquired during the construction of the EL 4 reactor of which it will constitute an extrapolation; the second, arising from the research carried out on the gas-graphite system, will use a pre-stressed concrete vessel for holding the pressure, the moderator being almost at the same pressure as the cooling fluid and the fuel being placed in vertical channels. The relative merits of these two variants are analysed in the present paper. (authors) [French] L'experience acquise par l'exploitation des reacteurs de MARCOULE, la construction et le demarrage des reacteurs d

  18. The cryogenic installations for irradiation in the reactors Melusine and Siloe; Les installations cryogeniques pour irradiations des reacteurs Melusine et Siloe

    Energy Technology Data Exchange (ETDEWEB)

    Bochirol, L; Le Calvez, J; Doulat, J; Verdier, J; Lacaze, A; Weil, L [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    vaporized in the atmosphere and without any pollution of the refrigerating circuit. Lastly, a few words are said about the liquid helium loop, a prototype of which has worked, and which is being rebuilt with an increased power. (authors) [French] L'etude des defauts crees par l'irradiation dans les solides est d'un interet theorique et pratique, considerable. L'irradiation a basse temperature permet d'obtenir les defauts dans leur etat le plus simple, leur etat 'primaire' sans que l'agitation thermique permette leur annihilation ou leur rearrangement. L'irradiation en pile a basse temperature pose un certain nombre de problemes techniques provenant de la puissance de refrigeration necessaire, qui est quelquefois considerable, des reactions chimiques possibles sous rayonnement et du manque d'espace dans un reacteur. Enfin, la necessite de faire toute l'irradiation et les mesures ulterieures sans rechauffer les; echantillons impose que le dispositif fonctionne en continu sans defaillance et qu'il soit equipe de facon a permettre la recuperation des echantillons froids, ou bien leur mesure et leur rechauffage controle 'in situ'. On decrit la facon dont ces problemes ont ete resolus a Grenoble, pour des dispositifs d'irradiation a 78 deg. K, 28 deg. K et 4 deg. K dans les deux piles piscines Melusine et Siloe. Quelques resultats d'exploitation sont donnes sur la boucle a azote liquide, dite type A, qui fonctionne depuis plusieurs annees dans Melusine. En particulier certaines observations sont faites sur les reactions chimiques qui peuvent se produire sous irradiation dans l'azote liquide impur. On decrit assez en detail la boucle a azote liquide, dite type A, qui vient d'etre installee dans le reacteur Siloe. Les traits essentiels de cet appareil sont: qu'il permet l'irradiation dans des flux plus eleves que le precedent et que son exploitation est grandement facilitee grace a un mode de realisation qui permet l'acces aux echantillons sans demontage ni deconnexion de l

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-03-15

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

  20. Problems related with the power regulation of reactors by physico-chemical methods, and the behaviour of water and heavy water in nuclear reactors; Comportement de l'eau et de l'eau lourde dans les reacteurs nucleaires et problemes de la regulation de puissance par voie physico-chimique

    Energy Technology Data Exchange (ETDEWEB)

    Dolle, L; Conan, D; Dirian, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    Experience of the CEA heavy water reactors and a systematic study of the radiolytic decomposition of water in the core of swimming-pool reactors are described. Setting up of reactivity control by physico-chemical methods. Reactivity control by homogeneous poisoning of the reactor A comparison of the evolution of xenon poisoning with the residual anti reactivity of the poison in solution during its nuclear consumption establishes the programme which must govern the variation in its concentration if the exact compensation is to be produced The behaviour of the poison towards the reactor materials under the particular operational conditions must be taken into account. Radiolytic decomposition of water in the reactors in the presence of soluble poisons: A study of the effect of certain chemically inert salts, present in small concentrations in the water, on its radiolytic decomposition rate, has led to some new results which are discussed. The choice of a soluble poison is justified on the basis of the above results. Reactivity control by the use of a gaseous absorbent The use of a gas control rod circuit for compensation purposes, in place of solid control rods is described. The use of soluble poisons in the moderator to compensate the xenon effect, and of a gaseous absorbent in a circuit known as a gas control rod form original aspects of the reactivity control in the reactor EL 4. (authors) [French] L'observation du comportement de l'eau et de l'eau lourde dans les reacteurs en exploitation, contribue au fonctionnement sur de ceux-ci et oriente certaines etudes relatives aux techniques de controle de la reactivite par mise en oeuvre de poisons solubles. L'utilisation de poisons nucleaires dissous dans l'eau du reacteur entraine une pollution chimique de celle-ci. Les conditions d'emploi permettant d'eviter les effets indesirables de cette pollution sont etudiees. Les problemes analytiques - bien qu'importants - ne sont pas abordes dans le cadre de la communication

  1. The Role of Exponential and PCTR Experiments at Hanford in the Design of Large Power Reactors; Roles Respectifs des Experiences Exponentielles et du Reacteur d'Etude des Constantes Physiques de Hanford dans les Etudes de Grands Reacteurs de Puissance; Znachenie ehksponentsial'nykh opytov i opytov na reaktore PCTR pri proektirovanii bol'shikh ehnergeticheskikh reaktorov v khehnforde; Papel de los Experimentos Exponenciales y del Reactor PCTR de Hanford en el Proyecto de Grandes Reactores de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Heineman, R. E. [General Electric Company, Richland, WA (United States)

    1964-02-15

    use is described in the light of the trends which are observed. (author) [French] Des mesures exponentielles sont faites aux laboratoires de Hanford sur des reseaux uranium-graphite depuis pres de quinze ans. Les resultats de ces experiences ont ete utilises pour determiner les laplaciens de reacteurs de production que l'on se proposait de construire, mais ils ont servi egalement a ameliorer les connaissances dans le domaine de la physique de ces systemes. On s'est rendu compte tres rapidement qu'en raison des dimensions des assemblages et de leur manque de sensibilite aux petites perturbations localisees du systeme, l'experience exponentielle n'a qu'une utilite limitee. On a donc envisage de mettre au point des experiences integrales avec un reacteur de maniere a reduire au minimum la quantite de matieres necessaires pour se procurer des donnees valables. A cet effet, on a construit une installation critique perfectionnee a plusieurs regions, qu'on a appelee 'reacteur d'etude des constantes physiques' (RECP), dont on s'est servi pour determiner les constantes physiques de plusieurs reacteurs de puissance. On s'en est servi aussi couramment pour mesurer des sections efficaces et determiner des parametres differentiels et integraux de la physique des reacteurs pour divers types de milieux multiplicateurs. Apres la construction de RECP, on a encore employe les experiences exponentielles, bien que RECP ait largement comble les espoirs qui avaient ete places en lui. L'auteur indique quelques donnees caracteristiques obtenues a l'aide de ces deux genres d'installations et compare leurs roles respectifs pour l'etude de nouveaux reacteurs de puissance, pour la modification de reacteurs en fonctionnement, comme moyens de recherche sur la physique des reacteurs et comme moyen de formation. Il compare egalement les montants des capitaux investis dans ces installations et des frais de fonctionnement. Il indique comment ont ete mises au point de nouvelles methodes experimentales

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-10-01

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

  4. Operating Experience with the VERA Zero-Energy Fast Reactor; Fonctionnement du Reacteur VERA a Neutrons Rapides, de Puissance Zero; Opyt ehkspluatatsii reaktora VERA na bystrykh nejtronakh nulevoj moshchnosti; Experiencia Adquirida con el Reactor Rapido VERA de Potencia Nula

    Energy Technology Data Exchange (ETDEWEB)

    Weale, J. W.; McTaggart, M. H.; Goodfellow, H.; Paterson, W. J. [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

    1964-02-15

    The design of a two-halves zero-energy fast reactor is briefly described, particular emphasis being placed on those features which determine the practicability and precision of reactor physics measurements. The advantages and disadvantages of the design are discussed with reference to the two years' operating experience of the reactor. The following topics are dealt with: the experimental convenience of the lay-out and of the two halves design; the size and precision of the fuel pieces and the accuracy of location of the fuel elements; the effects of edge irregularities and heterogeneity of structure on the accuracy with which the critical mass of an 'ideal' equivalent assembly is determined; reproducibility of the critical condition after dismantling the assembly, or separating the two halves; variation of reactivity with separation of the halves, including effects of asymmetric loading; sensitivity of various counters, neutron source strength, use of an accelerator neutron source; speed of response of safety circuits and consequent restrictions on rate of assembly of the two halves; additional precautions necessary in using plutonium fuel; and notes on the accuracy of measurement of reactivity and on the practical limitations affecting various other reactor physics measurements. (author) [French] Les auteurs decrivent brievement ce modele de reacteur a neutrons rapides et de puissance zero construit en deux moities, en insistant particulierment sur les caracteristiques qui determinent la possibilites de faire des mesures relatives a la physique des reacteurs et la precision de ces mesures. Ils exposent les avantages et les inconvenients de ce modele compte tenu de l'experience acquise au cours des deux annees de fonctionnement du reacteur. Ils traitent les sujets suivants: interet pratique, au point de vue experimental, du plan de ce reacteur et de sa constitution en deux moities; dimension et precision des pieces de combustible et exactitude de l'emplacement des

  5. Contribution to the study and use of ionisation chambers for nuclear reactor control (1965); Contribution a l'etude et a l'utilisation des chambres d'ionisation pour le controle des reacteurs nucleaires (1965)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-02-15

    high-power reactors. (author) [French] Les chambres d'ionisation sont actuellement les detecteurs les mieux adaptes au controle des reacteurs nucleaires par des mesures neutroniques. Nous avons cru bon de rappeler quelques generalites concernant la dynamique des reacteurs, les differents procedes de detection des neutrons, le fonctionnement des chambres d'ionisation et les methodes de mesure utilisees. Notre contribution aux techniques de controle des reacteurs consiste d'une part en une tentative de synthese des facteurs intervenant dans le fonctionnement des chambres d'ionisation, l'etude de ces facteurs, et d'autre part l'elaboration de chambres d'ionisation a fission et a bore permettant de suivre la marche d'un reacteur du demarrage jusqu'a la puissance maximale. Dans le domaine des chambres a fission, nous avons en particulier ameliore les techniques de depot d'oxyde d'uranium sur l'aluminium et realise la mise au point de depots par electrolyse sur d'autres metaux: acier inoxydable, cuivre, molybdene, nickel, tantale, titane, kovar, tungstene et beryllium. Nous avons elabore plusieurs types de chambres a fission servant au demarrage des reacteurs: un type de performances moyennes actuellement utilise dans les piles francaises un type a haute sensibilite un type a haute temperature qui a fonctionne jusqu'a 600 deg. C. En ce qui concerne les chambres a bore, nous avons etudie les perturbations apportees dans les mesures par l'exposition des chambres a d'importants flux de neutrons et a un rayonnement {gamma} intense. Cette exposition produit une modification des proprietes des materiaux constitutifs et la production dans les chambres d'un bruit de fond qui peut gener considerablement les mesures neutroniques. Nous avons montre que la technique de compensation permettait de limiter l'importance de ce bruit de fond et d'augmenter ainsi la plage de fonctionnement des chambres d'ionisation classiques destinees aux mesures de puissance. Enfin, nous avons realise deux

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  7. General design and main problems of a gas-heavy-water power reactor contained in a pressure vessel; Conception generale et principaux problemes d'un reacteur de puissance eau lourde-gaz contenu dans un caisson resistant

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    In the framework of research carried out on a CO{sub 2}-cooled power reactor moderated by heavy water, the so-called 'pressure vessel' solution involves the total integration of the core, of the primary circuit (exchanges and blowers) and of the fuel handling machine inside a single, strong, sealed vessel made of pre-stressed concrete. A vertical design has been chosen: the handling 'attic' is placed above the core, the exchanges being underneath. This solution makes it possible to standardize the type of reactor which is moderated by heavy-water or graphite and cooled by a downward stream of carbon dioxide gas; it has certain advantages and disadvantages with respect to the pressure tube solution and these are considered in detail in this report. Extrapolation presents in particular.problems due specifically to the heavy water (for example its cooling,its purification, the balancing of the pressures of the heavy water and of the gas, the assembling of the internal structures, the height of the attic, etc. (authors) [French] Dans le cadre des etudes d'un reacteur de puissance modere a l'eau lourde et refroidi-au gaz carbonique, la solution dite 'en caisson' consiste en une integration totale du coeur, du circuit primaire (echangeurs et soufflantes) et du dispositif de manutention du combustible a l'interieur d'un meme caisson etanche et resistant en beton precontraint. La disposition envisagee est verticale; le grenier de manutention est dispose au-dessus du coeur, les echangeurs en dessous. Cette solution, qui permet d'uniformiser les types de reacteurs moderes a l'eau lourde ou au graphite et refroidis par une circulation descendante de gaz carbonique presente, par rapport a la solution a tube de force, des avantages et des inconvenients qui sont analyses dans cette etude. L'extrapolation pose, en particulier, des problemes specifiques a l'eau lourde (tels que son refroidissement, son epuration, l'equilibrage des pression entre l'eau lourde et le gaz, le montage

  8. General design and main problems of a gas-heavy-water power reactor contained in a pressure vessel; Conception generale et principaux problemes d'un reacteur de puissance eau lourde-gaz contenu dans un caisson resistant

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    In the framework of research carried out on a CO{sub 2}-cooled power reactor moderated by heavy water, the so-called 'pressure vessel' solution involves the total integration of the core, of the primary circuit (exchanges and blowers) and of the fuel handling machine inside a single, strong, sealed vessel made of pre-stressed concrete. A vertical design has been chosen: the handling 'attic' is placed above the core, the exchanges being underneath. This solution makes it possible to standardize the type of reactor which is moderated by heavy-water or graphite and cooled by a downward stream of carbon dioxide gas; it has certain advantages and disadvantages with respect to the pressure tube solution and these are considered in detail in this report. Extrapolation presents in particular.problems due specifically to the heavy water (for example its cooling,its purification, the balancing of the pressures of the heavy water and of the gas, the assembling of the internal structures, the height of the attic, etc. (authors) [French] Dans le cadre des etudes d'un reacteur de puissance modere a l'eau lourde et refroidi-au gaz carbonique, la solution dite 'en caisson' consiste en une integration totale du coeur, du circuit primaire (echangeurs et soufflantes) et du dispositif de manutention du combustible a l'interieur d'un meme caisson etanche et resistant en beton precontraint. La disposition envisagee est verticale; le grenier de manutention est dispose au-dessus du coeur, les echangeurs en dessous. Cette solution, qui permet d'uniformiser les types de reacteurs moderes a l'eau lourde ou au graphite et refroidis par une circulation descendante de gaz carbonique presente, par rapport a la solution a tube de force, des avantages et des inconvenients qui sont analyses dans cette etude. L'extrapolation pose, en particulier, des problemes specifiques a l'eau lourde (tels que son refroidissement, son epuration

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  11. Methods of Containment Adopted for the EL4 Reactor and Projected Heavy-Water, Gas-Cooled Plants; Mode de Confinement Adopte pour le Reacteur EL4 et les Projets de Centrales Eau Lourde-Gaz

    Energy Technology Data Exchange (ETDEWEB)

    Schulhof, P.; Justin, F. [Commissariat a l' Energie Atomique, Paris (France)

    1967-09-15

    After a brief description of the plant, the paper explains the principles adopted for preventing the release of waste gas, from the EL4 reactor and refers to some of the difficulties associated with this type of containment. From the economic standpoint, the authors present the results of a comparative civil engineering study of pre-stressed concrete and steel shells for a projected 60 MW(e) power station, giving various values for accidental pressures. They demonstrate the influence of the stress values adopted. (author) [French] Les auteurs rappellent les principes adoptes dans le reacteur EL4 pour le confinement des rejets gazeux, apres une description sommaire des installations. Suivent quelques aspects des difficultes introduites par ce type de confinement. Dans le domaine economique, ils presentent le resultat d'une etude comparative de genie civil d'enceintes en beton precontraint et en acier pour un projet de centrale de 600 MW(e), avec diverses valeurs de pression accidentelle. Dans cette etude, ils font ressortir l'influence des valeurs admises pour le taux de travail des materiaux. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

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

  13. General problems arising from the analogical resolution of the kinetic equations of nuclear reactors (1961); Problemes generaux poses par la resolution analogique des equations cinetiques des reacteurs nucleaires (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    The author reviews precisely the analogical techniques used for the resolution of the kinetic equations of nuclear reactors. Prior to this, he recalls the reasons which oblige physicians and engineers, even today, to use electronic machines in this domain. The author then considers the technological problems posed by the range of values which the various nuclear parameters adopt. In each case, he shows that a compromise is possible allowing an optimum precision. He compares the results to those obtained by arithmetic calculation and uses the examples chosen in a critical analysis of the present possibilities of the two methods of calculation. (author) [French] L'auteur cherche a faire un point aussi exact que possible des techniques analogiques utilisees pour resoudre les equations cinetiques des reacteurs nucleaires. Il rappelle auparavant les raisons pour lesquelles physiciens et ingenieurs sont obliges, encore aujourd'hui, de faire appel aux machines electroniques dans ce domaine. Puis il etudie les problemes technologiques que souleve le champ des valeurs prises par les differents parametres nucleaires. Dans chacun des cas, il montre l'existence d'un compromis qui permet d'atteindre une precision optimum. Il compare les resultats obtenus a ceux provenant de calculateurs arithmetiques et profite des exemples choisis pour faire une analyse critique des possibilites actuelles offertes par les deux modes de calcul. (auteur)

  14. La chronologie du royaume de Qatabân du Ier siècle avant J.-C. au Ier siècle après J.-C.

    Directory of Open Access Journals (Sweden)

    Mounir Arbach

    2002-04-01

    Full Text Available Les nouvelles découvertes archéologiques et épigraphiques de ces dernières années, effectuées au cours des fouilles franco-italiennes à Tamna`, l'ancienne capitale du royaume de Qatabân, permettent d'établir une nouvelle chronologie des souverains de Qatabân entre le Ier siècle avant J.-C. et le Ier siècle après J.- C.The chronology of the kingdom of Qatabân, from the 1st century BC to the 1st century AD. Archaeological and epigraphical discoveries made in recent years by the Franco-Italian excavations at Tamna`, the ancient capital of the kingdom of Qatabân, allows us to establish a new chronology for the kings of Qatabân during the 1st century BC and the 1st century AD.

  15. Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

    Energy Technology Data Exchange (ETDEWEB)

    Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    radioactivity exposure considerations. Recent full-scale inspection and overhaul of the Dresden turbine provided no maintenance problems, after over 12 000 h of operation on direct-cycle steam and after operation with known failed fuel elements in the reactor. (author) [French] On a maintenant acquis une experience appreciable dans l'exploitation des centrales equipees de reacteurs a eau bouillante. Vers la fin de 1962, on avait produit plus de 2,2.10{sup 9} kWh dans trois centrales nucleaires rattachees a des reseaux de distribution: la centrale de Dresden (Commonwealth Edison Company, Morris, Illinois), la centrale de Vallecitos (Pacific Gas and Electric Company and General Electric Company, Pleasanton, Californie) et la centrale de Kahl (Rheinish-Westfaiisches Elektrizitatswerk et Bayemwerk, a Kahl-sur-le-Main, Republique federale d'Allemagne). Le rendement de ces reacteurs a eau bouillante, exploites dans les conditions normales de production d'electricite, est excellent. On peut donc s'attendre que les centrales a eau bouillante continueront d'etre sures, etant donne le facteur de disponibilite et le facteur de puissance des reacteurs et des installations de ce type. Au cours de 1963, quatre nouvelles centrales equipees de reacteurs a eau bouillante entreront en service: la centrale de Big Rock Point (Consumers Power Company, Charlevoix, Michigan), la centrale de Humboldt Bay (Pacific Gas and Electric Company, Eureka, Californie), la centrale de Garigliano (Societa Elettronucleare Nazionale, Scauri, Italie) et la centrale de demonstration japonaise (Institut de recherches nucleaires du Japon, Tokai Mura, Japon). Les resultats obtenus lors du demarrage et pendant le fonctionnement initial de ces installations confirment les espoirs suscites par les centrales de Dresden, Kahl et Vallecitos. Les journaux de marche des centrales de Dresden, Kahl et Vallecitos mettent en evidence la stabilite et la securite des reacteurs a eau bouillante. De plus, les niveaux de rayonnements

  16. International Musicological Conference Young Musicology Prague: Czech and European Avant-garde Music of the Early 20th Century, Kabinet hudební historie Etnologického ústavu AV ČR, Praha 5.–8. září 2016

    Czech Academy of Sciences Publication Activity Database

    Pirner, Jan

    2017-01-01

    Roč. 54, č. 2 (2017), s. 236-237 ISSN 0018-7003. [International Music ological Conference Young Music ology Prague: Czech and European Avant-garde Music of the Early 20th Century. Prague, 05.10.2016-08.10.2016] Institutional support: RVO:68378076 Keywords : 20th Century * Young Music ology * Conference Subject RIV: AL - Art, Architecture, Cultural Heritage OBOR OECD: Performing arts studies ( Music ology, Theater science, Dramaturgy)

  17. À propos du lexique juridique en ancien français avant le 13e siècle : la Règle de saint Benoît et le Perceval de Chrétien de Troyes

    Directory of Open Access Journals (Sweden)

    Schauwecker Yela

    2012-07-01

    Full Text Available La plus ancienne traduction de la {em Règle} de saint Benoît en franc{c}ais, rédigée en dialecte picard-wallon, date de la première moitié ou du milieu du {sc xii}$^{m e}$~siècle. On veut montrer que son auteur, pour qui le changement de langue, n'est pas le premier objectif s'efforce de transférer le texte de son milieu originel de l'Antiquité tardive dans le monde chevaleresque-féodal du {sc xii}$^{m e}$~siècle. Même sans nécessité apparente, quand il a eu à sa disposition l'équivalent du mot employé dans la {em Regula}, il substitue aux mots latins des termes juridiques et féodaux franc{c}ais. par Son texte, en tant que document de droit pour les moines, devient ainsi une source de vocabulaire juridique franc{c}ais avant le {sc xiii}$^{m e}$~siècle, c'est-à-dire dans un temps où les documents juridiques en langue vulgaire sont extrêmement rares. Cela est dû au fait que la justice, dans le Nord, fondée sur des coutumes, utilisait la langue vernaculaire à l'oral. La terminologie juridique franc{c}aise est bien enracinée dans la langue courante de l'époque~: leur insertion dans les Lais et les Chansons de geste en fait preuve. Mais cette terminologie est souvent méconnue par la lexicographie traditionnelle de l'ancien franc{c}ais, en raison des contextes littéraires et figurés. par

  18. Development of a power-period calculation unit for nuclear reactor Control; Etude et realisation d'un ensemble de calcul puissance periode pour le controle d'un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-10-01

    The apparatus studied is a digital calculating assembly which makes it possible to prepare and to present numerically the period and power of a nuclear reactor during operation, from start-up to nominal power. The pulses from a fission chamber are analyzed continuously, using real time. A small number of elements is required because of the systematic use of a calculation technique comprising the determination of a base 2 logarithm by a linear approximation. The accuracy obtained for the period is of the order of 14%; the response time of the order of the calculated period value. An approximate value of the power (30%) is given at each calculation cycle together with the power thresholds required for the control. (author) [French] L'appareil etudie est un ensemble de calcul digital permettant d'elaborer et d'afficher numeriquement la periode et la puissance, d'un reacteur nucleaire lors de son fonctionnement depuis le demarrage jusqu'a la puissance nominale. Il traite en temps reel, de facon continue, les impulsions en provenance d'une chambre de fission. Grace a l'utilisation systematique d'une technique de calcul, la determination d'un logarithme a base 2 par approximation lineaire, un nombre reduit d'elements est utilise. La precision obtenue sur la periode est de l'ordre de 14 pour cent, le temps de reponse de l'ordre de la valeur de la periode calculee. Un ordre de grandeur de la puissance (30 pour cent) est donne a chaque cycle de calcul ainsi que des seuils de puissance necessaires au controle. (auteur)

  19. A review of calculation methods for fast and intermediate reactors; Expose des methodes pour le calcul de reacteurs a neutrons rapides et intermediaires; Obzor metodov rascheta reaktorov na promezhutochnykh i bystrykh nejtronakh; Estudio panoramico de los metodos de calculo de los reactores rapidos e intermedios

    Energy Technology Data Exchange (ETDEWEB)

    Marchuk, G I [Akademiya Nauk, Moskva, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    This paper discusses the development of methods for calculating intermediate and fast reactors. It deals with various approaches to the problems of physical calculation. The calculation of resonance effects is discussed. Consideration is given to multi-group systems of fundamental and conjugate equations, various applications of perturbation theory to the problems of physical reactor calculation, and numerical methods of solving fundamental and conjugate reactor equations, which approximate the method of spherical harmonics. The paper describes an application of the response method to the solution of critical-mass problems, and methods of calculating reactors with hydrogeneous moderators. The fundamental features of an effective one-group reactor model are described. (author) [French] L'auteur examine la mise au point de methodes pour le calcul de reacteurs a neutrons rapides et intermediaires . Il decrit diverses manieres d'aborder les problemes des calculs sur la physique des reacteurs, notamment le calcul des effets de resonance. Il s'attache particulierement aux points suivants: systemes d'equations fondamentales et conjuguees a plusieurs groupes; diverses applications de la theorie des perturbations aux problemes de calculs sur la physique des reacteurs; methodes numeriques pour resoudre les equations fondamentales et conjuguees, voisines de la methode des harmoniques spheriques. L'auteur decrit ensuite une maniere d'appliquer la methode de la reponse aux problemes de la masse critique ainsi que des methodes pour le calcul de reacteurs ralentis a l'hydrogene. Il decrit les caracteristique s fondamentale s d'un modele de reacteur a un groupe effectif. (author) [Spanish] El autor analiza el desarrollo de los metodos de calculo de los reactores nucleares que trabajan con neutrones rapidos y con neutrones intermedios. Examina diversos planteos de los problemas del calculo fisico. Indica la forma de tomar en cuenta los efectos de resonancia y menciona los sistemas

  20. Group cross-sections for fast reactors; Sections efficaces de groupes pour les reacteurs a neutrons rapides; Gruppovye secheniya reaktorov na bystrykh nejtronakh; Secciones eficaces de grupos para reactores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Zweifel, P P [University of Michigan, Ann Arbor, MI (United States); Ball, G L [Atomic Power Development Associates, Inc., Detroit, MI (United States)

    1962-03-15

    groupes. Ils montrent notamment que la section efficace moyenne de transport peut, avec une certaine approximation, s'exprimer en termes de libre parcours moyen. Le calcul de cette quantite prend beaucoup de temps, car elle ne peut se reduire en moyennes elementaires; neanmoins, on a demontre certaines inegalites, qui simplifient la methode de calcul des moyennes qui doit etre utilisee. Les auteurs analysent trois autres aspects des sections efficaces de groupes, que l'on neglige souvent, mais qu'il peut etre important de connaitre pour les etudes de reacteurs. a) Il est injustifie d'utiliser pour tous les reacteurs a neutrons rapides le meme ensemble de sections efficaces dont la moyenne par groupe a ete calculee si les spectres des differents reacteurs sont dissemblables et si les sections efficaces varient rapidement a l'interieur du groupe, comme c'est le cas le plus souvent. Les auteurs decrivent une methode d'iteration qui permet d'obtenir les valeurs moyennes correctes; ils determinent ensuite, a l'aide de cette methode, dans quelle mesure les calculs de reacteurs sont influences par les effets de spectre. b) Dans les calculs de transport (la methode S{sub n}, par exemple), les moyennes doivent etre calculees en tenant compte a la fois de tous les angles et de toutes les energies. Etant donne qu'on ne peut dissocier dans le flux une partie angulaire et une partie energetique, la plus grande attention est necessaire pour eviter les erreurs. Les auteurs etudient l'equation obtenue par la methode S{sub n} sous la forme d'un modele simple, et en tirent un critere qui pourrait aider a determiner l'importance de la non-separabilite angulaire dans les calculs de reacteurs. c) A partir de raisonnements fondes sur la conservation du nombre de neutrons, il est possible d'obtenir une relation consistant entre les coefficients de diffusion de groupe, le pouvoir de ralentissement et les sections efficaces d'absorption. Les auteurs montrent qu'il n'est pas exact de definir

  1. Avant-Garde Ultrafast Laser Writing

    Directory of Open Access Journals (Sweden)

    Kazansky P. G.

    2013-11-01

    Full Text Available Ultrafast laser processing of transparent materials reveals new phenomena. Reviewed, are recent demonstrations of 5D optical memory, vortex polarization and Airy beam converters employing self-assembled nanostructuring, ultrafast laser calligraphy and polarization writing control using pulses with tilted front.

  2. The Poverty of the Avant Garde

    Science.gov (United States)

    Levi, Albert William

    1974-01-01

    Article discussed the dialectic of past and present; the opposition between the Italian Renaissance and the Dutch seventeenth century on the one hand, and the rootless, random, and corruptly commercialized situation in which art finds itself today on the other. (Author/RK)

  3. Les blogs juridiques. AVANT-PROPOS

    OpenAIRE

    Chambost , Anne-Sophie

    2016-01-01

    International audience; Par le rapport spécifique que le droit entretient avec l’écrit, le juriste ressemble parfois à un documentaliste juridique, avide des documents qui nourriront son raisonnement. Davantage sans doute que les autres sciences, le droit nourrit (et se nourrit) en effet une relation étroite au texte, et une importante production d’écrits est à la base de la science juridique (lois, normes, décisions de justice, œuvres de la doctrine..). Or si la littérature scientifique se p...

  4. L'Univers avant le Big Bang

    CERN Document Server

    Rouat, Sylvie

    2003-01-01

    "Tout n'a pas commencé par une explosion. L'historie du cosmos avait débuté biena vant le Big Bang, si l'on suit la théorie défendue par les partisans d'une nouvelle cosmologie issue de la mystérieuse théorie des cordes. A l'heure où vacillent les scénarios classiques du XXe siècle, se prépare un grand chamboulement de nos idées sur la naissance de l'Univers et son devenir, sur l'existence possible d'univers parallèles. Des théories séduisantes qui seront mises à l'épreuve au cours de la prochaine décennie" (11 pages)

  5. Avant-garde femtosecond laser writing

    OpenAIRE

    Kazansky, Peter G.; Beresna, Martynas; Shimotsuma, Yasuhiko; Hirao, Kazuyuki; Svirko, Yuri P.; Aktürk, Selcuk

    2010-01-01

    Recently discovered phenomena of quill and non-reciprocal femtosecond laser writing in glasses and crystals are reviewed. Common beliefs that laser writing does not change when reversing beam scan or propagation direction are challenged.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-03-15

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

  7. Study of the strength of the internal can for internally and externally cooled fuel elements intended for gas graphite reactors; Etude de la tenue de la gaine interne pour-element combustible a refroidissement interne et externe d'un reacteur graphite-gaz

    Energy Technology Data Exchange (ETDEWEB)

    Boudouresque, B; Courcon, P; Lestiboubois, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The cartridge of an internally and externally cooled annular fuel element used in gas-graphite reactors is made up of an uranium fuel tube, an external can and an internal can made of magnesium alloy. For the thermal exchange between the internal can and the fuel to be satisfactory, it is necessary for the can to stay in contact with the uranium under all temperature conditions. This report, based on a theoretical study, shows how the internal can fuel gap varies during the processes of canning, charging into the reactor and thermal cycling. The following parameters are considered: tube diameter, pressure of the heat carrying gas, gas entry temperature, plasticity of the can alloy. It is shown that for all operating conditions the internal can of a 77 x 95 element, planned for a gas-graphite reactor with a 40 kg/cm{sup 2} gas pressure, should remain in contact with the fuel. (authors) [French] La cartouche d'un element combustible annulaire, a refroidissement interne et externe pour reacteur graphite-gaz, est composee d'un tube combustible en uranium, d'une gaine externe et d'une gaine interne en alliage de magnesium. Pour que l'echange thermique entre la gaine interne et le combustible soit bon, il faut que la gaine reste appliquee sur l'uranium quel que soit le regime de temperature. Cette note a pour but de montrer comment, d'apres une etude theorique, le jeu combustible-gaine interne varie au cours des operations de gainage, de chargement dans le reacteur, et des cyclages thermiques. Les parametres suivants sont etudies: diametres de tube, pression du gaz caloporteur, temperature d'entree du gaz, plasticite de l'alliage de gaine. Il est montre que, quel que soit le regime de fonctionnement, la gaine interne d'un element 77 x 95, en projet pour un reacteur graphite-gaz sous pression de 40 kg/cm{sup 2}, doit rester appliquee sur le combustible. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-06-15

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

  9. Initial Operating Experience with the ''NPD'' Reactor; Experience recueillie pendant les premiers mois de fonctionnement du reacteur NPD; Pervyj opyt po ehkspluatatsii reaktora NPD; Experiencia inicial de funcionamiento del reactor NPD

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, L. G. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

    1963-10-15

    Canada's first nuclear power station, the Nuclear Power Demonstration station (NPD), is intended to serve as a means of proof-testing the performance of the Canadian type of station using natural uranium as fuel and heavy water as moderator and coolant. It reached full power on 28 June 1962. Although designed for base-load operation it will, during the early stages, be operated part of the time on high-capacity.runs and part of the time on improvement periods. Progress has been favourable so far; the first high-capacity run of six weeks'duration yielded a capacity factor of 70%. Improvements already made have increased safety, improved performance and demonstrated potential methods of capital-cost reduction for future stations. For example, shaft seals on primary coolant pumps have been modified for better performance, freezer-type vapour recovery equipment has been replaced in favour of absorption columns to reduce heavy-water vapour loss, and flow limiters are being installed in sample lines to reduce losses of heavy water in the event of joint failures. During December 1962 two simultaneous leaks from the on-power refuelling machine led to an unusual sequence of events in which a considerable amount of hot high-pressure heavy water was spilled into the reactor vault where it suffered a slight downgrading in isotopic purity. It was upgraded and the reactor returned to operation by the end of the month. All safety devices operated correctly during the incident as did the provisions for containment of heavy water. (author) [French] La premiere centrale nucleaire du Canada, NPD, est une centrale de demonstration, qui doit servir a verifier les performances des reacteurs fonctionnant a l'uranium naturel et utilisant de l'eau lourde comme ralentisseur et comme fluide de refroidissement. Elle a atteint sa pleine puissance le 28 juin 1962 bien que concue pour etre exploitee comme centrale de base, elle fonctionnera au debut comme centrale d'appoint, ce qui permettra d

  10. Alize 3 - first critical experiment for the franco-german high flux reactor - calculations; Alize 3 - premiere experience critique pour le reacteur a haut flux franco-allemand. Calculs

    Energy Technology Data Exchange (ETDEWEB)

    Scharmer, K [Commissariat a l' Energie Atomique, Dir. des Piles Atomiques, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    The results of experiments in the light water cooled D{sub 2}O reflected critical assembly ALIZE III have been compared to calculations. A diffusion model was used with 3 fast and epithermal groups and two overlapping thermal groups, which leads to good agreement of calculated and measured power maps, even in the case of strong variations of the neutron spectrum in the core. The difference of calculated and measured k{sub eff} was smaller than 0.5 per cent {delta}k/k. Calculations of void and structure material coefficients of the reactivity of 'black' rods in the reflector, of spectrum variations (Cd-ratio, Pu-U-ratio) and to the delayed photoneutron fraction in the D{sub 2}O reflector were made. Measurements of the influence of beam tubes on reactivity and flux distribution in the reflector were interpreted with regard to an optimum beam tube arrangement for the Franco- German High Flux Reactor. (author) [French] Les resultats des experiences faites dans la maquette critique ALIZE III, refrigeree a l'eau legere et reflechie par l'eau lourde, ont ete compares aux calculs. On a utilise un modele de la theorie de diffusion a trois groupes rapides et epithermiques et deux groupes thermiques qui se recouvrent. Ce modele a permis de calculer la distribution de puissance dans le coeur en bon accord avec les mesures, meme dans le cas d'une forte variation du spectre des neutrons dans le coeur. L'erreur entre k{sub eff} calcule et mesure etait inferieure a 0,5 pour cent {delta}k/k. Le coefficient de vide et des materiaux de structure, la reactivite des barres 'noires', les variations du spectre (rapport Cd, rapport Pu/U) et la fraction des photo-neutrons retardes sont egalement calcules. Les mesures de reactivite et de perturbation de flux dans le reflecteur, dues aux canaux, ont ete interpretees du point de vue d'un arrangement optimum des canaux pour le Reacteur a Haut Flux Franco-Allemand. (auteur)

  11. 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

  12. Major accident analyses for experimental zero-power fast reactor assemblies; Analyse des accidents graves pouvant survenir dans les reacteurs experimentaux a neutrons rapides de puissance zero; Analiz krupnoj avarii dlya ehksperimental'ny kh reaktornykh ustanovok nulevoj moshchnosti na bystrykh nejtronakh; Analisis de los accidentes graves que pueden producirse en los reactores experimentales rapidos de potencia cero

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, G.; Barts, E. W.; Kapil, S.; Tomabechi, K. [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    systems with the very soft neutron-energy spectra characteristic of large oxide power breeders. (author) [French] Les auteurs ont etudie la possibilite, le mecanisme et les consequences de la fusion et autres accidents nucleaires graves dans les reacteurs experimentaux a neutrons rapides de puissance zero, du type ZPR-III, a coeur divise. Cette etude a ete completee par une evaluation de l'importance de l'effet Doppler sur un grand nombre de reacteurs de ce type. Les auteurs demontrent qu'il est fort peu probable qu'une fusion se produise, du fait que la conjonction des circonstances qui pourraient la provoquer est difficilement realisable. L'expose du mecanisme de fusion est suivi de l'analyse des resultats de calculs couples neutronique-hydrodynamiqu e relatifs a deux reacteurs de puissance zero. On a choisi pour cette etude un coeur de 1200 l, qui correspond a un reacteur relativement grand a coeur normal. L'etude a egalement porte sur un coeur plus petit ayant un coefficient cavitaire plus important, qui pourrait presenter un plus grand danger. Chaque systeme a eu un comportement en fonction du temps tout a fait different. Si un accident grave survient dans un reacteur de puissance zero, les atomes de {sup 235}U, isoles dans les plaques d'uranium enrichi, s'echauffen t tres rapidement tandis que le reste du coeur demeure pratiquement froid; il y a ainsi formation d'un gaz du {sup 235}U qui donne lieu a la pression de rupture. Les auteurs expliquent l'adaptation qu'ils ont faite du code AX-I de neutronique-hydrodynamiqu e pour l'appliquer a un gaz de Van der Waals. Une autre modification importante de l'equation d'etat utilisee dans ce code consiste a employer une equation du type Mie-Grueneisen, derivee de la theorie de l'etat solide. Cette modification permet d'evaluer de facon plus satis- faisante le terme de pression pour les coeurs de composition variable. Du fait que les plaques en uranium fortement enrichi d'un reacteur de puissance zero s'echauffent plus

  13. Comprender el cine: las vanguardias y la construcción del texto fílmico Understanding Cinema: the Avant-gardes and the Construction of Film Discourse

    Directory of Open Access Journals (Sweden)

    Mirian Estela Nogueira Tavares

    2010-10-01

    Full Text Available A través de este ensayo se pretende resaltar el papel que las vanguardias históricas han desempeñado en la construcción del discurso cinematográfico. Dicho papel es fundamental para el reconocimiento del cine como arte y para la constitución de un discurso visual y textual que se va a reflejar en el cine del denominado «Modo de representación institucional»: el cine hollywoodiense que va de las décadas de los años veinte a los cuarenta. Para comprender el papel de los movimientos artísticos que crearon nuevos paradigmas para el arte en general, es necesario conocer sus principios y el contexto del nacimiento de la nueva forma de ver y de representar/reflejar el mundo. La promoción de una auténtica «alfabetización fílmica» requiere centrarse en el nacimiento del cine y de su entorno, porque sólo a través de una mirada más profunda en el siglo XIX, es posible leer todo que está más allá de la creación de los hermanos Lumière. En suma, en este trabajo se pretende destacar que el cine no sólo se inscribe en su propio tiempo, sino que al mismo tiempo está lanzando un nuevo paradigma, aun por descubrir, para todas las artes en el siglo XX.This essay highlights the role of historical avant-gardes in shaping film discourse. This role was vital for the recognition of cinema as an art form, as well as for the constitution of a visual and textual discourse that came to be reflected in the Institutional Mode of Representation – Hollywood film from the 1920s to the 1940s. To realize the importance of artistic movements in the creation of new paradigms for art at large, it is necessary to understand their principles and the context in which a new way of looking and reflecting on the world came about. The promotion of authentic and efficient film literacy requires focusing on the era in which cinema began. Only by examining the 19th century more deeply can we perceive what lies beyond that invention of the Lumière brothers. The

  14. Some physics aspects of cermet and ceramic fast systems; Quelques aspects de la physique des reacteurs a neutrons rapides utilisant des cermets et des ceramiques comme combustibles; Nekotorye fizicheskie aspekty kermetnykh i keramicheskikh sistem na bystrykh nejtronakh; Algunos aspectos fisicos de los sistemas rapidos a base de combustibles cermet y ceramicos

    Energy Technology Data Exchange (ETDEWEB)

    Codd, J; James, M F; Mann, J E [United Kingdom Atomic Energy Authority, Reactor Group (United Kingdom)

    1962-03-15

    The characteristics of a system using an iron-based oxide cermet as fuel material are discussed. A transport theory investigation to develop methods of predicting the effect of core heterogeneity on reactivity and flux distribution is described. Some preliminary calculations are also given of resonance self-shielding and Doppler temperature effects in a cermet system. (author) [French] Les auteurs etudient les caracteristique s d'un reacteur utilisant comme combustible un cermet d'oxydes a armature de fer. Ils exposent une application de la theorie du transport a la mise au point des methodes permettant de prevoir l'effet de l'heterogeneite du coeur sur la reactivite et sur la distribution du flux. Ils donnent egalement quelques calculs preliminaires d'effets d'autoprotection due a la resonance et d'effet Doppler du a la chaleur dans un reacteur utilisant un cermet. (author) [Spanish] La memoria discute las caracteristicas de un sistema que emplea como combustible un oxido tipo cermet a base de hierro. Describe una investigacion de la teoria de transporte con miras a desarrollar metodos para evaluar el efecto de la heterogeneidad del cuerpo sobre la reactividad y la distribucion de flujo. Tambien da algunos calculos preliminares de los efectos del autoblindaje por resonancia y de la temperatura de Doppler en un sistema de tipo cermet. (author) [Russian] Obsuzhdayutsya kharakteristiki sistemy, ispol'zuyushchej v kachestve toplivnogo materiala oksidnye kermety, razrabotannye na osnove zheleza. Opisyvaetsya issledovanie teorii perenosa, chtoby razvit' metody predskazaniya vliyaniya geterogennosti aktivnoj zony na reaktivnost' i raspredelenie potoka. Dayutsya takzhe nekotorye predvaritel'nye raschety ehffektov rezonansnoj samozashchity i temperaturnogo ehffekta Dopplera v kermetnoj sisteme. (author)

  15. Construction of an apparatus for measuring the low-temperature thermal conductivity before and after neutron irradiation. Application to uranium dioxide (1963); Realisation d'un appareil pour la mesure de la conductibilite thermique a basse temperature avant et apres irradiation neutronique. Application au dioxyde d'uranium (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-09-15

    An apparatus has been studied and built which makes it possible to alternatively irradiate a sample at room temperature in the reactor 'Melusine' at the Grenoble Nuclear Research Centre, and to measure its thermal conductivity between 20 and 100 deg. K in perfect safety. The results obtained on UO{sub 2} have made it possible on the one hand to check experimentally that the spin-phonon diffusion leads to a thermal resistance independent of temperature above 30 deg. K, and on the other hand to propose a simple theory which takes into count the role played by the damage due to U-235 fission products in the decrease of thermal conductivity after irradiation. (author) [French] Un appareil permettant alternativement d'irradier un echantillon a temperature ambiante dans le reacteur ''Melusine'' du C.E.N.G., et de mesurer sa conductibilite thermique entre 20 et 100 deg. K en toute securite, a ete etudie et construit Les resultats obtenus sur UO{sub 2} ont permis, d'une part, de verifier experimentalement que la diffusion spin-phonon conduit a une resistance thermique independante de la temperature au-dessus de 30 deg. K, et, d'autre part, de proposer une theorie simple tenant compte du role joue par les degats dus aux produits de fission de l'uranium 235, dans la deterioration de la conductibilite thermique apres irradiation. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

  17. Preliminary studies of vanadium-base alloys intended for use in fabrication of cans for fast reactors; Etudes preliminaires sur les alliages a base de vanadium envisages pour la fabrication de gaines de reacteurs rapides

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-03-15

    Preliminary research has been carried out on a series of vanadium-based alloys: V, 0.5 per cent Si; V, 5 per cent Ca; V, 5 per cent Mo; V, 5 per cent Nb; V, 2 per cent Zr; V, 20 per cent Ti; V, 10 per cent Al; V, 10 per cent Sn and v, 10 per cent Ti liable to be used as canning material in fast reactors. The transformation by forging at about 1000 deg. C and rolling between 200 deg. C and room temperature is satisfactory for all types of alloys except V with 10 per cent Sn and V with 10 per cent Al. The mechanical properties deduced from tensile strength tests carried out on alloy samples annealed 1 hour at 1050 deg. C in a vacuum show that, generally speaking, the addition elements lead to an improvement in these properties as compared to those of pure vanadium. After undergoing corrosion tests in a liquid sodium loop purified by a cold trap, the alloys become brittle at room temperature. Only the vanadium containing 20 per cent Ti keeps its plastic properties. These alloys are covered by a layer of vanadium carbide VC. After undergoing treatment in a liquid sodium loop purified by a hot trap, all the alloys keep their good mechanical characteristics. The surface layer with which they are covered is composed of two vanadium carbides VC and {sub {gamma}}VC, and a vanadium sub-oxide VO{sub 0.9}. (author) [French] Des etudes preliminaires ont ete faites sur une serie d'alliages a base de vanadium: V-0,5 pour cent Si, V-5 pour cent Ca, V-5 pour cent Mo, V-5 pour cent Nb, V-2 pour cent Zr, V-20 pour cent Ti, V-10 pour cent Al, V-10 pour cent Sn et V-10 pour cent Ti susceptibles d'etre utilises comme materiau de gainage pour les reacteurs rapides. La transformation par forgeage a 1000 deg. C environ et laminage entre 200 deg. C et la temperature ambiante est satisfaisante pour toutes les nuances d'alliage sauf le V-10 pour cent Sn et le V-10 pour cent Al. Les proprietes mecaniques deduites des essais de traction realises sur des eprouvettes d'alliages recuits 1 heure a

  18. Training for Better Management: Avante Zambézia, PEPFAR and Improving the Quality of Administrative Services Comment on "Implementation of a Health Management Mentoring Program: Year-1 Evaluation of Its Impact on Health System Strengthening in Zambézia Province, Mozambique".

    Science.gov (United States)

    Schwarcz, Sandra K; Rutherford, George W; Horvath, Hacsi

    2015-07-23

    The United States President's Emergency Plan for AIDS Relief (PEPFAR) emphasizes health systems strengthening as a cornerstone of programmatic success. Health systems strengthening, among other things, includes effective capacity building for clinical care, administrative management and public health practice. Avante Zambézia is a district-level in-service training program for administrative staff. It is associated with improved accounting practices and human resources and transportation management but not monitoring and evaluation. We discuss other examples of successful administrative training programs that vary in the proportion of time that is spent learning on the job and the proportion of time spent in classrooms. We suggest that these programs be more rigorously evaluated so that lessons learned can be generalized to other countries and regions. © 2015 by Kerman University of Medical Sciences.

  19. Training for Better Management: Avante Zambézia, PEPFAR and Improving the Quality of Administrative Services; Comment on “Implementation of a Health Management Mentoring Program: Year-1 Evaluation of Its Impact on Health System Strengthening in Zambézia Province, Mozambique”

    Directory of Open Access Journals (Sweden)

    Sandra K. Schwarcz

    2015-11-01

    Full Text Available The United States President’s Emergency Plan for AIDS Relief (PEPFAR emphasizes health systems strengthening as a cornerstone of programmatic success. Health systems strengthening, among other things, includes effective capacity building for clinical care, administrative management and public health practice. Avante Zambéziais a district-level in-service training program for administrative staff. It is associated with improved accounting practices and human resources and transportation management but not monitoring and evaluation. We discuss other examples of successful administrative training programs that vary in the proportion of time that is spent learning on the job and the proportion of time spent in classrooms. We suggest that these programs be more rigorously evaluated so that lessons learned can be generalized to other countries and regions.

  20. Measurement of {pi}{sup {+-}} p forward elastic differential cross sections at 410 and 490 MeV; Mesures des sections efficaces differentielles {pi}{sup {+-}} p a 410 MeV et 490 MeV vers l'avant

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-01-01

    Measurements of the {pi}{sup {+-}} p forward elastic differential cross sections were performed with a missing mass spectrometer using spark chambers. Photographs were automatically scanned. Phase shift analysis of experimental results leads to three solutions. Experiments are indicated which ought to permit overcoming ambiguity. (author) [French] Des mesures de sections efficaces differentielles elastiques {pi}{sup {+-}} p vers l'avant ont ete effectuees a l'aide d'un spectrometre de masse manquante a chambres a etincelles. Les cliches ont ete depouilles par un appareillage automatique. Les resultats experimentaux sont analyses en dephasages et conduisent a trois solutions. Des experiences sont indiquees qui devraient permettre de lever l'ambiguite. (auteur)

  1. Effect of the plutonium isotopic composition on the performance of fast reactors; Effet de la composition isotopique du plutonium sur le rendement de reacteurs a neutrons rapides; Vliyanie izotopnogo sostava plutoniya na rabotu reaktorov na bystrykh nejtronakh; Efectos de la composicion isotopica del plutonio sobre el funcionamiento de los reactores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Yiftah, S [Israel Atomic Energy Commission (Israel)

    1962-03-15

    The isotopic composition of plutonium to be used as fuel for fast reactors will depend on the source of plutonium. In principle three different sources are possible: (a) production reactors; (6) thermal power reactors (using natural uranium or enriched uranium as fuel); (c) fast reactor blankets. In general, source (a) and to some extent source (c) will provide relatively 'clean' plutonium, that is mostly Pu{sup 239}, while plutonium from source (6) will be 'dirty' plutonium, that is plutonium rich in Pu{sup 240}, Pu{sup 241}, and Pu{sup 242}. The degree of 'dirtiness' will depend on the kind of reactor, amount of burn-up and in general on the irradiation history of the fuel. The question then arises, can one use as fuel for fast reactors any kind of plutonium? To investigate the effect of different isotopic composition of the plutonium fuel, in the metallic, oxide and carbide form, on the performance of fast reactors, a limited series of spherical geometry 16-group diffusion theory calculations were performed, using the 16-group cross-section set developed recently by Yiftah, Okrent and Moldauer and taking three different kinds of plutonium, starting with pure Pu{sup 239} and increasing the amount of higher isotopes. For the systems studied-800, 1500 and 2500-l core-volumes, which are typical for large fast power reactors-the result is, when one takes into account only the thermally fissionable isotopes Pu{sup 239} arid Pu{sup 241}, that the 'dirtier' the plutonium, the smaller the critical mass and the higher the breeding ratio. For the 1500-l reactor, taken as an example, it is further found that in the metallic, oxide and carbide plutonium fuels the reactivity change upon removal of 40% of the sodium initially present in the core is made more negative (or less positive) when the plutonium is richer in higher isotopes. (author) [French] La composition isotopique du plutonium qui doit etre utilise comme combustible dans des reacteurs a neutrons rapides depend de

  2. The Use of Prestressed Concrete Vessels in the French Power Reactor Programme; Les caissons en beton precontraint dans le programme francais des reacteurs de puissance; Korpusy iz predvaritel'no napryazhennogo betona vo frantsuzskoj programme ehnergeticheskikh reaktorov; Empleo de recipientes de presion de hormigon pretensado en el programa frances de reactores de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Conte, F. [Centre d' Etudes Nucleaires de Marcoule (France); Dambrine, C. [Centre d' Etudes Nucleaires de Fontenay-aux-Roses (France); Gaussot, D. [Electricite de France, Clamart (France)

    1963-10-15

    This paper deals with the use of pre-stressed concrete for the G2 and G3 reactors at Marcoule and for the EDF3 reactor now under construction at Chinon. The first two reactors have been operating at power since 1959 and 1960 respectively. Messrs. Conte and Dambrine discuss the problems that arose during construction of the vessels for G2 and G3 and also deal with the experience gained in operation - experience which suggests that they are extremely safe- Work on the EDF3 vessel, begun at Chinon in the second half of 1961, is still under way and should be finished towards the end of 1963. Mr. Gaussot discusses the reasons for choosing this type of vessel, the results of calculations and mock-up tests, and the problems presented by the construction itself. A number of studies have been devoted to the future prospects of prestressed concrete structures for reactors. It would seem that working pressures could be increased, if desired, and, in any case, that dimensions could be considerably enlarged, thus offering the chance of integral-type solutions. (author) [French] La communication traite de l'application du beton precontraint aux reacteurs G2 et G3 de Marcoule et au reacteur EDF 3, en construction a Chinon. Les reacteurs sont en puissance depuis respectivement 1959 et I960; le CEA indique les problemes qui se sont poses pendant la construction du caisson du reacteur, et la lecon tiree des observations faites en service, qui tend a demontrer la tres grande securite de ces appareils. La construction du caisson de EDF3 a commence a Chinon dans la deuxieme partie de 1961; elle est en cours actuellement et sera terminee vers la fin de 1963. L'EDF presente les raisons du choix de ce caisson, les resultats des calculs et des essais sur maquette ainsi que les problemes poses par la construction. Diverses etudes ont ete faites sur les perspectives futures des ouvrages en beton precontraint pour reacteurs. Il semble que l 'on puisse realiser, si on le desire, une elevation

  3. The Control of Fast Reactors: Current Methods and Future Prospects; Controle des Reacteurs a Neutrons Rapides. Methodes Actuelles et Perspectives d'Avenir; Upravlenie reaktorami na bystrykh nejtronakh. sushchestvuyushchie metody i dal'nejshie perspektivy; Control de Reactores Rapidos: Metodos Actuales y Perspectivas

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-06-15

    regarding the specification of this parameter. These considerations are discussed in terms of control reactivity in existing fast reactors as opposed to the amount that is really required for fast power-breeder reactor operation. Typical power- and temperature-dependent feedback parameters are cited for determination of their influence upon the control reactivity requirements. The methods used to predict the reactivity worth of control mechanisms have evolved from crude estimates to quite reliable calculations which can be confirmed by experimental data from critical assemblies. Experimental results and currently reliable analytical techniques are described. Critical experiments for the current generation of fast reactors included many investigations pertaining to the reactivity worth of their control mechanisms as well as peripheral experiments for larger-core-volume advanced systems. Exploratory analytical studies, which indicate that detailed experimental mockup investigations may not be required in the future, are cited. (author) [French] L'auteur examine dans ce memoire les aspects pratiques du probleme qui consiste a fournir une reactivite suffisante pour le controle des reacteurs a neutrons rapides; ce probleme differe dans une grande mesure de celui du controle des reacteurs a neutrons thenniques. Ces differences sont dues en premier lieu au fait que les sections efficaces d'absorption des neutrons rapides sont assez faibles. Il n'existe pas de poisons forts dans un reacteur a neutrons rapides. En consequence, les poisons forts que sont certains produits de fission dans un reacteur thermique (par exemple Xe et Sm) exigent un exces de reactivite beaucoup moins important que n'en exige la perte de reactivite due a la destruction de produit fissile par fission et capture. Comme les sections efficaces pour les neutrons rapides sont relativement petites comparees aux valeurs correspondantes pour les neutrons thermiques, la densite atomique du materiau joue un role

  4. The 'Reacteur Jules Horowitz': The preliminary design

    International Nuclear Information System (INIS)

    Ballagny, A.; Frachet, S.; Minguet, J.L.; Leydier, C.

    1999-01-01

    The 'Reactor Jules Horowitz' is a new research reactor project dedicated to materials and nuclear fuels testing, the location of which is foreseen at the CEA-Cadarache site, and the start-up in 2008. The launching of this project arises from a double finding: 1) the development of nuclear power plants aimed at satisfying the energy needs of the next century cannot be envisaged without the disposal of experimental reactors which are unrivalled for the validation of new concepts of nuclear fuels, materials, and components as well as for their qualification under irradiation. 2) the present park of experimental reactors is 30 to 40 years old and it is advisable to examine henceforth the necessity and the nature of a new reactor to take over and replace, at the beginning of next century, the reactors shut-down in the mean time or at the very end of their lives. Within this framework, the CEA has undertaken, in the last years, a reflection on the mid and long term irradiations needs, to determine the main features and performances of this new reactor. The concept of the reactor will have to fulfil the thermal neutron irradiation requirements as well as the fast neutron experimental needs, with a great potential versatility for any new irradiation programs. The selected reactor project, among several different concepts, is finally a light water open pool concept, with 100 MW thermal power. It could reach neutronic fluxes twice those of present French reactors, and allows many irradiations in the core and around the core, under high neutron fluxes. The reactor will satisfy the highest level of safety in full accordance with international safety recommendations and French safety approach for this kind of nuclear facility, thus giving an added safety margin keeping in mind the versatility of research reactors. The feasibility studies have been focused on the main items, and have permit to determine: the core and fuel designs, with added pressurisation; the different core surrounding structures in connection with the core studies; overall layout of the reactor/auxiliary pools and reactor building. (author)

  5. EURATOM's Programme of Participation in Power Reactor Construction; Le programme de participation d'Euratom aux reacteurs de puissance; Programma uchastiya v razrabotke ehnergeticheskikh reaktorov Evratoma; El programa de participacion de la Euratom en la construccion y explotacion de reactores de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Ramadier, R. C.; Parker, E. [Communaute Europoenne de l' Energie Atomique, Bruxelles (Belgium)

    1963-10-15

    -years during which operating problems will become decisive for the development of atomic power. (author) [French] L'un des moyens mis en oeuvre par la Commission de l'Euratom en vue d'assurer le developpement d'une industrie nucleaire europeenne est un programme dit de ''participation communautaire''. Ce programme permet a la Commission de participer a concurrence de 32 millions d'u.c. AME a des realisations dans le domaine des reacteurs de puissance. La contrepartie est l'acquisition des informations relatives a la conception, la construction, le demarrage et le fonctionnement de ces reacteurs. Jusqu'a present des propositions emanant de trois societes ont donne lieu a la signature de contrats. Il s'agit de: a) la Societa Elettronucleare Nazionale (SENN) qui fait construire en Italie une centrale de 150 MW(e) nets equipee d'un reacteur a eau bouillante a double cycle; b) la Societa Italiana Meridionale Energia Atomica (SIMEA) qui a entrepris en Italie la construction d'une centrale de 200 MW(e) nets equipee d'un reacteur du type uranium naturel-graphite-gaz carbonique; c) la Societe d'Energie Nucleaire Franco-Belge des Ardennes (SENA) qui a entrepris a la frontiere franco-belge la construction d'une centrale equipee d'un reacteur a eau pressurisee d'une puissance qui pourra atteindre et probablement depasser 242 MW(e) nets. En outre, la Commission a e te saisie de demandes de participation a deux autres reacteurs de puissance presentees respectivement par le Groupement Rheinisch-Westfalisches Elektiizitatswerk-Bayernwerke (RWE-BW), et par la N.V. Samenwerkende Electriciteits-Productiebedrijve; la premiere pour un reacteur de 237 MW(e) a eau bouillante a double cycle, la seconde pour un reacteur de 50 MW(e) a eau bouillante a simple cyc le et circulation naturelle. La participation communautaire peut prendre des formes diverses. Elle peut en particulier prendre celle d'une participation au deficit eventuel de la production d'electricite des centrales pendant les premieres

  6. Study of the consequences of the rupture of a pressure tube in the tank of a gas-cooled, heavy-water moderated reactor; Etude des consequences de la rupture d'un tube de force dans la cuve d'un reacteur modere a l'eau lourde et refroidi au gaz

    Energy Technology Data Exchange (ETDEWEB)

    Hareux, F; Roche, R; Vrillon, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    Bursting of a pressure tube in the tank of a heavy water moderated-gas cooled reactor is an accident which has been studied experimentally about EL-4. A first test (scale 1) having shown that the burst of a tube does not cause the rupture of adjacent tubes, tests on the tank resistance have been undertaken with a very reduced scale model (1 to 10). It has been found that the tank can endure many bursts of tube without any important deformation. Transient pressure in the tank is an oscillatory weakened wave, the maximum of which (pressure peak) has been the object of a particular experimental study. It appears that the most important parameters which affect the pressure peak are; the pressure of the gas included in the bursting pressure tube, the volume of this gas, the mass of air included in the tank and the nature of the gas. A general method to calculate the pressure peak value in reactor tanks has been elaborated by direct application of experimental data. (authors) [French] L'eclatement d'un tube de force dans la cuve d'un reacteur de puissance modere a l'eau lourde et refroidi par un gaz sous pression est un accident qui a ete etudie experimentalement a propos d'EL-4. Un premier essai a l'echelle 1 ayant montre que l'eclatement d'un tube ne provoque pas celui des tubes voisins, des essais relatifs a la tenue de la cuve ont ete effectues sur maquettes a echelle tres reduite (l/lO). Il a ete trouve que la cuve peut supporter plusieurs eclatements de tubes sans deformations notables. La pression transitoire dans la cuve a une allure oscillatoire amortie dont le maximum (pression de pic) a fait l'objet d'une etude experimentale detaillee. Il apparait que les parametres essentiels influant sur cette pression sont: la pression du gaz contenu dans le tube de force, le volume du gaz qui participe a l'eclatement, la flexibilite de la cuve, la masse d'air empoisonnee dans la cuve, la nature du gaz explosant. Une methode generale d'estimation des pics de pression dans

  7. Neutron Tests at the Start-Up of EDF1; Les essais neutroniques au demarrage du reacteur EDF1; Nejtronnye izmereniya pri puske reaktora EDF1; Ensayos neutronicos efectuados durante la puesta en marcha del reactor EDF1

    Energy Technology Data Exchange (ETDEWEB)

    Teste du Bailler, A. [Centre d' Etudes Nucleaires de Saclay (France); Janin, R. [Electricite de France, Paris (France)

    1963-10-15

    A series of neutron measurements, for which the principal experimental methods perfected at the Marcoule reactors were used, was carried out at the start-up of EDF1. The measurements were designed mainly to determine the efficiency of the control rods at different depths of insertion. From them a rod-withdrawal configuration was derived which allowed full-power operation without infringing certain limitations on cladding and gas temperatures. At the same time flux measurements were made for different shim-rod positions and different absorber loadings in certain channels. These measurements based on preliminary two-dimensional calculations, were obtained by activation of point detectors,using the standard technique of air poisoning. At certain temperature plateaus (up to 140{sup o}C), measurements of temperature coefficients and control-rod efficiency were made. Spectrum index measurements were carried out at the same time by activation of appropriate detectors (U, Pu, Lu, Mn, In, Au). The oscillation technique was used to measure the efficiency of certain shim rods. Finally, fast-neutron measurements were made in connection with studies of shielding and graphite damage. (author) [French] Une serie de mesures neutroniques utilisant les principales methodes experimentales mises au point sur les reacteurs de Marcoule a ete effectuee au cours du demarrage d'EDF1. Les mesures portent essentiellement sur l 'efficacite des barres de controle a differents enfoncements. On en deduit une configuration de montee des barres permettant d'obtenir la pleine puissance en respectant certaines limitations sur les temperatures de gaines et de gaz. Parallelement des mesures de flux ont ete faites pour differentes positions des barres de compensation et pour divers chargements d'absorbants dans certains canaux, suivant des calculs previsionnels a deux dimensions. Ces mesures sont obtenues par activation de detecteurs ponctuels, au moyen de la technique classique par empoisonnement a l

  8. Advanced epithermal thorium reactor (AETR) physics; Physique d'un reacteur au thorium, a neutrons epithermiques, de type perfectionne (AETR); Fizika usovershenstvovannog o nadteplovogo torievogo reaktora; Fisica del reactor epitermico de tipo avanzado, alimentado con torio (AETR)

    Energy Technology Data Exchange (ETDEWEB)

    Campise, A. V. [Atomics International, Canoga Park, CA (United States)

    1962-03-15

    'etude de cet ensemble a mis en relief l'importance des donnees relatives aux sections efficaces et de l'interpretation theorique des resultats experimentaux pour l'etude d'un reacteur au thorium de type perfectionne. La precision des methodes analytiques employees a ete demontree lors de l'analyse des resultats experimentaux obtenus avec le ZPR-III. L'auteur compare trois configurations pour le transfert de chaleur, en utilisant le temps de doublement comme parametre d'optimisation. Les effets de la production de {sup 233}Pa et d'isotopes de l'uranium sur le bilan neutronique, les taux possibles de surgeneration et les caracteristiques de la combustion sont evalues en tenant compte de l'imprecision des sections efficaces nucleaires. (author) [Spanish] El autor estudia la concepcion del reactor AETR desde el punto de vista de la teoria actual de los parametros nucleares y del balance neutronico. En los sistemas moderados por grafito examina el efecto de la captura por resonancia en el torio para energias medias de absorcion del orden de 0,10 a 100 keV. Aplica formulas de resonancia angosta y de resonancia ancha para obtener la integral de resonancia efectiva en funcion de la temperatura, correspondiente a las barras de torio, y dicho parametro se expresa como secciones eficaces equivalentes de varios grupos. Se ha disenado y construido un conjunto critico para obtener datos nucleares indispensables en la gama de energias intermedias. En el diseno nuclear de dicho conjunto, se ha tenido particularmente en cuenta la importancia de los datos relativos a secciones eficaces y la interpretacion teorica de estos resultados experimentales, cosas ambas relacionadas con el diseno del reactor AETR. La precision de los metodos analiticos ha quedado demostrada por el estudio de los resultados experimentales obtenidos con el reactor ZPR-III. Se comparan tres sistemas de transmision de calor utilizando el tiempo de duplicacion como parametro optimo. Se estudia el efecto de la formacion

  9. Indium-Gallium Radiation Contour of the IRT Nuclear Reactor; Circuit d'activation d'indium-gallium dans le reacteur nucleaire IRT; Indij-gallievyj radiatsionnyj kontur yadernogo reaktora IRT; Circuito de radiaciones de indio-galio del reactor IRT

    Energy Technology Data Exchange (ETDEWEB)

    Breger, A K; Ryabukin, Y S; Tulkes, S G; Volkov, E N

    1960-07-15

    Following on theoretical work already published, an indium-gallium radiation contour of the IRT nuclear reactor has been prepared, and represents a powerful new source of gamma-radiation. The first contour of this type ''RK-1'' was prepared on the IRT reactor at the Physics Institute of the Academy of Sciences of the Georgian SSR. The paper gives the activation calculations for indium-gallium alloy; the structural components of RK-1 and their arrangement in the reactor tank and the hot cell; the devise for feeding liquid and gaseous substances into the irradiation zone; and the conveyor for solid substances to be irradiated. When the IRT reactor is at a power of 2000 kW, the radiation strength of the contour is equivalent to that of a gamma-emitter having an activity of 20,000 g. Ra equivalent. The prospects for the use of the indium-gallium radiation contour for research and semi-industrial purposes are discussed. (author) [French] A la suite de la publication d'un ouvrage theorique, on a etabli autour du reacteur nucleaire IRT un circuit d'activation d'indium-gallium qui represente une nouvelle source de rayonnements gamma de grande intensite. Le premier circuit de ce type ''RK-1'' a ete etabli sur le reacteur IRT a l'Institut de physique de l'Academie des sciences de la RSS de Georgie. Les auteurs donnent les calculs de l'activation pour l'alliage indium-gallium; ils indiquent les elements structurels du RK-1 et leur disposition dans le reservoir et dans la cellule de haute activite du reacteur; ils decrivent le dispositif permettant d'introduire des substances liquides et gazeuses dans la zone d'irradiation et le systeme qui transporte les substances solides a irradier. Lorsque le reacteur IRT fonctionne a 2 000 kW, la puissance de rayonnement du circuit equivaut a celle d'un emetteur gamma ayant une activite equivalente a 20 000 grammes de radium. Les auteurs examinent les perspectives d'emploi de ce processus pour la recherche et a des fins semi

  10. Study of the formation and of the distribution of dissolved gases and hydrogen peroxide in water from a swimming-pool reactor (triton) (1961); Etude de la formation et de la repartition des gaz dissous et de l'eau oxygenee dans l'eau d'un reacteur piscine (triton) (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J; Rozenberg, J; Dolle, L; Dirian, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    In order to determine experimentally the amount of radiolysis in the swimming-pool reactor Triton, direct measurements have been made of the quantity of radiolysis gas and hydrogen peroxide in the water, at the entry and exit of the core. The concentration distribution of these gases in the reactor was also determined. An explanation is given as to why no gases evolution is seen in the swimming-pool reactors of the C.E.A. The overall amount of radiolysis is zero, and a simple interpretation of this result is possible. The real amount of radiolysis occurring in the reactor core can be calculated. This is in satisfactory agreement with certain measurement mad elsewhere. (authors) [French] Pour determiner experimentalement le taux de radiolyse dans la pile piscine Triton, des mesures directes de la quantite de gaz de radiolyse et d'eau oxygenee dans l'eau a l'entree et a la sortie du coeur ont ete faites. La repartition de la concentration de ces gaz dans la piscine a egalement ete determinee. On explique pourquoi aucun degagement gazeux n'est observe dans les piles piscines du CE.A. Le taux de radiolyse global est nul, et une interpretation simple de ce resultat est possible. Un taux de radiolyse reel dans le coeur du reacteur peut etre calcule. Celui-ci est en accord satisfaisant avec certaines determinations faites ailleurs. (auteurs)

  11. Practical guide to dosimetry as applied in the research reactors of the Saclay and Grenoble nuclear research centers; Guide pratique de la dosimetrie mise en oeuvre dans les reacteurs de recherche du C.E.N./G et du C.E.N./S

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1968-07-01

    Since the problems concerning neutron and gamma flux measurements which arise during irradiation experiments in the reactors in the Grenoble and Saclay Centres are of the same type, and since the solutions found are very often adopted in common, we have attempted to describe the methods we use at the present time. A brief description is given of the production of the detectors, the electronic apparatus; the formulae usually used for the interpretation of the measurements are given. A series of technical data cards give the most commonly used detector characteristics. These cards give the physical characteristics of the detectors, their nuclear constants, if any, the most suitable counting methods and the field of application. (authors) [French] Les problemes de mesures de flux de neutrons et de flux gamma qui se posent pour les experiences irradiees dans les reacteurs des Centres de Grenoble et de Saclay etant du meme type et les solutions trouvees, tres souvent adoptees en commun, nous avons cherche a decrire les methodes que nous pratiquons actuellement. On decrit tres brievement la fabrication des detecteurs, l'appareillage electronique; on rappelle les formules usuelles qui servent dans l'interpretation des mesures. Une serie de fiches techniques rassemble les caracteristiques des detecteurs les plus couramment utilises. Ces fiches indiquent les caracteristiques physiques des detecteurs, leurs constantes nucleaires s'il y a lieu, les methodes de comptage les mieux adaptees et le domaine d'utilisation. (auteurs)

  12. Reactor Radiation Loops as Large Gamma Sources; Boucles d'irradiation des reacteurs nucleaires utilisees comme sources gamma intenses; Radiatsionnye kontury yadernykh reaktorov kak moshchnye gamma-istochniki; Empleo de circuitos de irradiacion de los reactores como fuentes gamma de gran intensidad

    Energy Technology Data Exchange (ETDEWEB)

    Ryabukhina, Yu. S.

    1963-11-15

    . On a etudie le comportement de deux alliages eutectiques de l'indium en presence de certains materiaux de construction; la premiere installation a ndium-gallium est entree en service au debut de 1960. Des travaux ulterieurs ont permis d'equiper le reacteur IRT de l'Academie des sciences de Georgie d'une boucle modele permettant d'obtenir dans le.canal d'irradiation une activite maximum equivalent a environ 100 g de radium, et d'installer une boucle d'essai a indium-gallium-etain dans le canal du reacteur IRT appartenant a l'Institut de l'energie atomique de l'Academie des sciences de l'URSS. Enfin, en 1962, une boucle a indium - gallium - etain a ete mise en service dans le reacteur IRT de l'Academie des sciences de Lituanie, en vue d'executer des irradiations a une echelle semi-industrielle. Son activite maximum atteignait, dans le dispositif d'irradiation, un niveau equivalent a 30 000 g de radium. Le memoire se compose des quatre parties suivantes: 1. ''Calcul des boucles d'irradiation''; les auteurs generalisent les resultats des travaux sur les methodes de calcul des boucles d'irradiation. 2. ''Modele d'une boucle d'irradiation a indium-gallium pour le reacteur IRT-2000 de Tbilisi''; les auteurs decrivent le fonctionnement de la boucle. 3. ''Boucle d'irradiation a indium-gallium-etain du reacteur nucleaire IRT de l'Academie des sciences de Lituanie''; les auteurs decrivent le fonctionnement de la boucle. 4.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

  14. Contribution to the study of the effect of a low dose of gamma irradiation on seeds and tubers before planting; Contribution a l'etude de l'effet d'une irradiation gamma a faible dose sur les graines et tubercules avant plantation

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    From 1962 to 1965, 25 tests have been made with carrots (1 variety), radish (3 varieties), spinach (2 var.), tomatoes (2 var.), potatoes (2 var.), barley (2 var.), rice (3 var.) and corn (1 var.), with the object of studying the interest for agriculture of seed and tuber gamma irradiation at low dose before planting. These tests were made in the laboratory, in greenhouses and in the open field, all necessary care being taken for a valuable statistical analysis of- the results. Special attention was paid to the homogeneity of plant material by controlling more particularly moisture content of seeds and the storage conditions of tubers. The observations concerned germination, growth at early stages, development phases and yield of leaves, roots and fruit. Some stimulation cases are observed. For tomatoes, it is found that stimulation cases occur at extreme moisture content and not in the range of mean moisture content which corresponds to maximum radioresistance. The demonstration of these effects is related to varieties, complementary treatments, conditions of cultivation and observation criteria. In most cases, they are short-lived and suitable modifications of seed conditioning produce, upon controls, an effect equivalent to that of irradiation. In conclusion, it seems very unlikely - considering our cultivation methods - that seed and tuber irradiation before planting could be of interest for agriculture. (authors) [French] Dans le but d'etudier l'interet agricole d'une irradiation gamma a faible dose des graines et tubercules avant plantation, 25 essais ont ete mis en place de 1962 a 1965 sur carotte (1 var.), radis (3 var.), epinard (2 var.), tomate (2 var.), pomme de terse (2 var.), orge (2 var.), riz (3 var.) et mais (1 var. ). Les essais ont ete faits au laboratoire, dans les serres et en plein champ avec toutes les precautions requises pour une analyse statistique valable des resultats. On a prete une attention particuliere a l

  15. Contribution to the study of the effect of a low dose of gamma irradiation on seeds and tubers before planting; Contribution a l'etude de l'effet d'une irradiation gamma a faible dose sur les graines et tubercules avant plantation

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    From 1962 to 1965, 25 tests have been made with carrots (1 variety), radish (3 varieties), spinach (2 var.), tomatoes (2 var.), potatoes (2 var.), barley (2 var.), rice (3 var.) and corn (1 var.), with the object of studying the interest for agriculture of seed and tuber gamma irradiation at low dose before planting. These tests were made in the laboratory, in greenhouses and in the open field, all necessary care being taken for a valuable statistical analysis of- the results. Special attention was paid to the homogeneity of plant material by controlling more particularly moisture content of seeds and the storage conditions of tubers. The observations concerned germination, growth at early stages, development phases and yield of leaves, roots and fruit. Some stimulation cases are observed. For tomatoes, it is found that stimulation cases occur at extreme moisture content and not in the range of mean moisture content which corresponds to maximum radioresistance. The demonstration of these effects is related to varieties, complementary treatments, conditions of cultivation and observation criteria. In most cases, they are short-lived and suitable modifications of seed conditioning produce, upon controls, an effect equivalent to that of irradiation. In conclusion, it seems very unlikely - considering our cultivation methods - that seed and tuber irradiation before planting could be of interest for agriculture. (authors) [French] Dans le but d'etudier l'interet agricole d'une irradiation gamma a faible dose des graines et tubercules avant plantation, 25 essais ont ete mis en place de 1962 a 1965 sur carotte (1 var.), radis (3 var.), epinard (2 var.), tomate (2 var.), pomme de terse (2 var.), orge (2 var.), riz (3 var.) et mais (1 var. ). Les essais ont ete faits au laboratoire, dans les serres et en plein champ avec toutes les precautions requises pour une analyse statistique valable des resultats. On a prete une attention particuliere a l'homogeneite du materiel

  16. New Instruments and Principles for the Dimensional Measurement and Measurement of Spacing of Reactor Components; Nouveaux Instruments et Procedes de Mesure des Dimensions et de l'Espacement des Elements d'un Reacteur; Novye pribory i printsipy izmereniya razmerov i raspolozheniya komponentov reaktora; Nuevos Instrumentos y Principios para Medir las Dimensiones y la Separacion Entre Componentes de Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

    1965-09-15

    instrument for reactor components are discussed. Special attention is given to the possibility of using a small and versatile pick-up by means of manipulators in the ''hot'' zones and on ''hot'' materials. The increase of surface roughness with increasing irradiation dose is discussed. (author) [French] Full text: L'auteur presente les problemes de mesure de l'epaisseur de feuilles et des parois de tubes et recipients en aciers austenitiques ou en metaux non ferreux. Deux methodes de mesure des epaisseurs sans contact sont discutees: la mesure, par courants de Foucault, de l'epaisseur de feuilles et des parois de recipients en metaux non ferreux ou en aciers austenitiques, au moyen de bobines se deplacant le long des pieces a examiner: la mesure, par courants de Foucault, de l'epaisseur des parois de tubes, au moyen de bobines dans lesquelles se deplacent les pieces a examiner. L'auteur decrit des instruments appropries et le mode d'utilisation. Il discute egalement la mesure de l'epaisseur des parois de parties constitutives de reacteurs, en metaux non ferreux, par la 'methode de la bille magnetique' et explique le principe de ce nouveau type de mesure et son domaine d'utilisation - notamment pour les mesures par points; il decrit un instrument approprie. L'auteur examine la mesure des revetements non magnetiques de materiaux magnetiques; il explique les principes de mesure (methodes fondees sur les champs magnetiques des courants continus et des courants alternatifs) et decrit des instruments de mesure de revetements non magnetiques dont l'epaisseur varie entre 3 {mu}m et 20 mm. Il expose le probleme special de la mesure des depots de stellite sur les parois en aciers ferritiques des cuves de reacteurs. La mesure des revetements non conducteurs de metaux non ferreux est etudiee. Le memoire explique le principe de mesure (courants de Foucault). Il decrit un instrument approprie et donne des exemples de mesures typiques. L'auteur examine egalement la mesure sans contact, en

  17. Change of I-V characteristics of SiC diodes upon reactor irradiation; Modification des caracteristiques I-V de jonctions p-n au SiC du fait d'une irradiation dans un reacteur; Izmeneniya kharakteristik I-V vyrashchennogo v SiC perekhoda tipa p-n posle oblucheniya ego v reaktore; Modificaciones que sufren por irradiacion en un reactor las caracteristicas I-V de uniones p-n en SiC

    Energy Technology Data Exchange (ETDEWEB)

    Heerschap, M; De Coninck, R [Solid State Physics Dept., SCK-CEN, Mol (Belgium)

    1962-04-15

    In search for semiconductors, which can be used in high-flux reactors in order to measure flux distributions, we irradiated SiC p-n junctions in the Belgium BR-1 reactor. Two types of SiC-diodes of different origin have been irradiated. These junctions are grown in the Lely-furnace. The change in forward and reverse characteristics have been measured during and after irradiation up to temperatures of 150{sup o}C, while measurements up to a temperature of 500{sup o}C are in progress. It has been found that one type resists BR-1 neutrons up to an integrated flux of 10{sup 15} n/cm{sup 2}, while the other resists irradiation up to a flux of 10{sup 17} n/cm{sup 2}. The changes in characteristics are given as well as the result of some annealing experiments. (author) [French] En recherchant des semi-conducteurs pouvant servir a mesurer les distributions de flux dans les reacteurs a haut flux de neutrons, les auteurs ont irradie des jonctions p-n au SiC dans le reacteur belge BR-1. Deux types de diodes a SiC d'origines differentes ont ete ainsi irradies. Les jonctions en question sont preparees par etirage dans le four Lely. Les auteurs ont mesure les modifications subies par les caracteristiques I-V apres et pendant l'irradiation a des temperatures allant jusqu'a 150{sup o}C; ils poursuivent leurs mesures dans la gamme des temperatures allant de 150{sup o}C a 500{sup o}C. Us ont constate que l'un des types de diode a SiC resiste aux neutrons du reacteur BR-1 jusqu'a 10{sup 15} n/cm{sup 2}, tandis que l'autre type resiste a l'irradiation jusqu'a 10{sup 17} n/cm{sup 2}. Les auteurs indiquent les modifications subies par les caracteristiques, ainsi que le resultat de certaines experiences de recuit. (author) [Spanish] Los autores estan tratando de encontrar semiconductores con los que sea posible medir distribuciones de flujo en reactores de flujo elevado, y con este fin irradiaron uniones p-n del SiC en el reactor BR-1 de Belgica. Irradiaron dos tipos de diodos de SiC de

  18. The Materiality of a Contemporary Avant-Garde?

    DEFF Research Database (Denmark)

    Paldam, Camilla Skovbjerg

    2013-01-01

    of the elements rather than on material ones. The surrealists of the 1920s had an extended and metaphorical use of the word collage, which depended less on technique than on structure: Elements that were at the wrong place, in the wrong context, in surprising constellations. Max Ernst thus writes about...... collage quality by means of disturbing clashes of elements from different contexts, as for instance the grotesque, chimerical china figurines (2007-2009) of Danish artist Louise Hindsgavl. Another that clings to the reality fragment, but uses it in a new digitized way. Here the Danish artist Peter Holst...... of graffiti, tags and torn posters. The latter is set free as paste-ups where the original photos were taken, thus making small poetic changes in the city (2009-2011). And finally “mock collages” that confronts the concept of collage through a play with materials by making objects that look like collages made...

  19. Teenagerlove - en populær avant-garde musical

    DEFF Research Database (Denmark)

    Eigtved, Michael

    2012-01-01

    Artiklen forfølger den brudflade mellem populærkultur og avantgarde, som Ernst Bruun Olsens musikforestilling Teenagerlove fra 1962 er en repræsentant for. Fokus er især på hvorledes teatrale strategier fra hhv Bertolt Brecht og broadway musicals mødes i denne forestilling.......Artiklen forfølger den brudflade mellem populærkultur og avantgarde, som Ernst Bruun Olsens musikforestilling Teenagerlove fra 1962 er en repræsentant for. Fokus er især på hvorledes teatrale strategier fra hhv Bertolt Brecht og broadway musicals mødes i denne forestilling....

  20. Therapeutic communication in nursing students: A Walker & Avant concept analysis

    Science.gov (United States)

    Abdolrahimi, Mahbobeh; Ghiyasvandian, Shahrzad; Zakerimoghadam, Masoumeh; Ebadi, Abbas

    2017-01-01

    Background and aim Therapeutic communication, the fundamental component of nursing, is a complex concept. Furthermore, the poor encounters between nursing student and patient demonstrate the necessity of instruction regarding therapeutic communication. The aim of this study was to define and clarify this important concept for including this subject in the nursing curriculum with more emphasis. Methods A literature search was conducted using keywords such as “nursing student”, “patient” and “therapeutic communication” and Persian-equivalent words in Persian databases (including Magiran and Medlib) and English databases (including PubMed, ScienceDirect, Scopus and ProQuest) without time limitation. After extracting concept definitions and determining characteristic features, therapeutic communication in nursing students was defined. Then, sample cases, antecedents, consequences and empirical referents of concept were determined. Results After assessing 30 articles, therapeutic communication defining attributes were as follows: “an important means in building interpersonal relationships”, “a process of information transmission”, “an important clinical competency”, “a structure with two different sections” and “a significant tool in patient centered care”. Furthermore, theoretical and clinical education and receiving educators’ feedback regarding therapeutic communication were considered as antecedents of the concept. Improving physical and psychological health status of patient as well as professional development of nursing students were identified as consequences of the concept. Conclusion Nursing instructors can use these results in order to teach and evaluate therapeutic communication in nursing students and train qualified nurses. Also, nursing students may apply the results to improve the quality of their interactions with patients, perform their various duties and meet patients’ diverse needs. PMID:28979730

  1. L'avant-projet : définition et enjeux

    OpenAIRE

    Gautier , Frédéric; Lenfle , Sylvain

    2004-01-01

    This paper explores the strategic role of front-end activities in project performance. More precisely it focuses on what is called pre-project. Using case studies from auto aeronautics we propose a definition of this phase and we discuss the question it raises.; Depuis la fin des années 80, la place prise par les stratégies de différenciation dans les économies occidentales est à l'origine de mutations importantes de l'organisation de la conception de produits nouveaux dans les entreprises. C...

  2. Danish Sixties Avant-Garde and American Minimal Art

    Directory of Open Access Journals (Sweden)

    Max Ipsen

    2007-05-01

    Full Text Available Denmark is peripheral in the history of minimalism in the arts. In an international perspective Danish artists made almost no contributions to minimalism, according to art historians. But the fact is that Danish artists made minimalist works of art, and they did it very early. Art historians tend to describe minimal art as an entirely American phenomenon. America is the centre, Europe the periphery that lagged behind the centre, imitating American art. I will try to query this view with examples from Danish minimalism. I will discuss minimalist tendencies in Danish art and literature in the 1960s, and I will examine whether one can claim that Danish artists were influenced by American minimal art.

  3. Avant projet de programme du colloque UEMOA/CRDI

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

    Unicornis

    nationaux. Il est pour cela nécessaire que les chercheurs soient particulièrement connectés sur les évolutions et les besoins de la société, qu'ils assument cette responsabilité sociale à nos yeux particulièrement importante pour les chercheurs ...

  4. Et rien ne fut plus comme avant... - French version only

    CERN Multimedia

    2005-01-01

    Dans le cadre de l'Année internationale de la physique, la section de physique de l'Université de Genève ouvre ses portes aux non initiés et organise une série de conférences de vulgarisation scientifique. Chacune des conférences débute par une démonstration de détection de rayons cosmiques dans l'auditoire et l'utilisation de ces signaux venus du fond de l'Univers pour créer une « musique cosmique », en collaboration avec le Professeur Ellberger du Conservatoire de musique de Genève. La seconde conférence, intitulée « symétrie brisée », aura lieu le 1er février 2005 et sera donnée par le Professeur Chris Quigg de Fermilab à Chicago. Selon les cosmologistes, l'Univers a jailli d'un Big Bang d'énergie extrême mais d'une grande uniformité. Le Professeur Q...

  5. The Avant-Garde and the Art Market in Denmark

    DEFF Research Database (Denmark)

    Gether, Vibeke Petersen

    2012-01-01

    At the end of the nineteenth century, artists acknowledged, once and for all, that they were dependent on market mechanisms to distribute their work.This involved several parameters. how could the understanding of art be propagated? How would their art be received by the public? And last but not ...... and cultural conditions of the first decade of the twentieth century. Let us first consider how an artistic career emerged at this time by turning our attention to the academy of fine arts and its policies....

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  7. Experimental studies of some of the physical features of beryllium-moderated intermediate reactors; Etude experimentale de quelques particularites physiques des reacteurs a neutrons intermediaires, ralentis au beryllium; Ehksperimental'ny e issledovaniya nekotorykh fizicheskikh osobennostej promezhutochnykh reaktorov s berillievym zamedlitelem; Estudios experimentales de algunas caracteristicas fisicas de los reactores intermedios moderados con berilio

    Energy Technology Data Exchange (ETDEWEB)

    Lejpunskij, A I; Kuznetsov, V A; Artyukhov, G Ya; Mogil' ner, A I; Prokhorov, Yu A; Steklovski, V M; Chernov, L A [Akademiya Nauk, Moskva, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    of neutrons absorbed by the uranium. The paper provides data, derived from the same assembly, on the efficiency of rods made of various absorbing materials. It gives the experimentally measured distribution of neutron density for neutrons of various energies in the neighbourhood of a boron-carbide rod, and the density of neutron captures by a 1/v detector within the rod. The paper also discusses methods used and the results obtained from experiments designed to assess the efficiency of recompensation, cylinders placed on the boundary between core and reflector. (author) [French] Le memoire analyse les resultats de plusieurs experiences effectuees sur l'ensemble critique PF-4, qui est destine a l'etude detaillee des particularites physiques des reacteurs a neutrons intermediaires. Les coeurs et les reflecteurs des differents esembles critiques etaient constitues par un assemblage compact de tubes en acier ou en aluminium dans lesquels etaient inseres des diques de diverses matieres. En combinant selon differentes proportions les disques d'uranium enrichi a 90% et les matieres de ralentissement et en introduisant dans le reflecteur des couches de ralentisseur de diverses epaisseurs, on a pu obtenir de grandes modifications du spectre des neutrons provoquant la fission. Le memoire decrit l'ensemble critique PF-4 et les differents assemblages qui le composent. Les auteurs analysent l'efficacite relative du ralentissement interieur et exterieur pour des reacteurs dans lesquels le rapport noyaux du ralentisseur noyaux d'uranium dans le coeur est tres peu eleve. Il ressort des experiences que, meme lorsqu'on emploie des reflecteurs tres epais, la faible dilution de l'uranium par le ralentisseur (le rap- port entre les noyaux du beryllium et de l'uranium-235 etant: {partial_derivative}Be/{partial_derivative}{sup 235}U{approx_equal}1) entraine un accroissement de la masse critique. Une partie importante du memoire est consacree a une analyse des effets hetero- genes produits

  8. Heat exchanges during the re-flooding of a water reactor core - within the framework of the 'reference accident'; Echanges thermiques lors du renoyage d'un coeur de reacteur a eau - dans le cadre de 'l'accident de reference'

    Energy Technology Data Exchange (ETDEWEB)

    Andreoni, Daniel

    1975-11-28

    After a brief presentation of reported studies made in different countries and regarding the so-called 'reference accident', this research thesis reports the study of reactor re-flooding when the reactor is completely dried and heating elements have reached a temperature between 300 and 900 C, with a constant water flow rate entering the test section, with a constant dissipated electrical power, and by using very simple geometries. After a first part addressing the experimental study, the author reports the development of conduction calculation codes used to compute the flow extracted by the two-phase flow, present the thermal-hydraulic code used to compute local values and to study the correlation of the upstream area exchange coefficient. The author finally reports an analysis of the different existing models and the study of a re-flooding model [French] La presente etude est consacree a l'un des aspects de la surete des reacteurs a eau sous pression, et plus precisement a l'accident tres important qui consiste en une perte de fluide caloporteur (Loss of Coolant Accident - 'LOCA'). Le but de l'etude est de fournir des renseignements necessaires a l'interpretation des experiences effectuees sur des grappes, de donner une correlation de coefficient d'echange dans la zone aval, et de donner aussi un modele de progression du front de trempe pour les analyses de surete. Une etude bibliographique preliminaire nous a permis de faire le point sur les experiences entreprises concernant le refroidissement de secours. Ensuite, les chapitres suivants seront decrits: 1) Le chapitre II, consacre a l'etude experimentale (boucle, sections d'essais, resultats globaux). 2) Le chapitre III ou seront presentes les codes de calcul de conduction, necessaires au calcul du flux extrait par le melange diphasique, le code de thermohydraulique necessaire au calcul des grandeurs locales et l'etude de la correlation du coefficient d'echange de la zone aval. 3) Enfin le chapitre IV ou, apres

  9. Void Reactivity Effects in the Second Charge of the Halden Boiling Water Reactor; Effets Cavitaires dans la Deuxieme Charge du Reacteur a Eau Lourde Bouillante de Halden (HBWR); Ehffekty pustotnoj reaktivnosti vo vtoroj zag HBWR; Effectos de Cavitacion en la Segunda Carga del Reactor de Agua Pesada Hirviente de Halden (HBWR)

    Energy Technology Data Exchange (ETDEWEB)

    Lunde, J. E. [OECD Halden Reactor Project (Norway)

    1964-02-15

    calculation of void effects. Preliminary theoretical comparisons are made for these experiments. Two-group diffusion theory is applied, and the conclusion can be drawn that fair agreement is obtained between theory and experiment for the perturbations in the lattice parameters for a void fraction equal to one, both at low and high temperatures. For intermediate void fractions, however, somewhat less satisfactory agreement is found. (author) [French] L'auteur a mesure, aussi bien lors d'experiences avec vide simule a puissance nulle que dans les conditions normales de puissance, l'effet cavitaire, provoque par l'ebullition qui se produit a l'interieur des canaux du refroidisseur, dans la deuxieme charge de HBWR. Les experiences avec vide simule ont consiste a mesurer les effets que produit sur la reactivite le fait d'enfoncer a des profondeurs differentes des tubes plus ou moins vides a paroi mince. Les tubes ont ete places en plusieurs endroits entre les barres, dans une seule cartouche formee de sept barres en grappe et pratiquement identique aux cartouches de combustible de la deuxieme charge. Cette experience permet de determiner comment la reactivite varie en fonction du volume cavitaire relatif et de l'emplacement des bulles dans le canal du refroidisseur. L'experience a ete effectuee dans le reacteur NORA de puissance zero, avec un coeur compose de 36 cartouches de la deuxieme charge de HBWR et dans une geometrie de reseau identique a celle de ce reacteur. L'auteur a observe comment l'effet cavitaire variait avec la temperature dans un ensemble de puissance zero avec le cceur a 100 cartouches de HBWR. Dans une seule cartouche, il a abaisse le niveau de l'eau a l'interieur du canal de refroidissement a des niveaux differents et mesure l'effet de cette perturbation sur la reactivite a differentes temperatures comprises entre 50 et 220 Degree-Sign C. L'auteur a mesure l'effet cavitaire, a l'interieur de HBWR et dans les conditions de puissance, en fonction de la puissance

  10. Comparison Of The Worth Of Critical And Exponential Measurements For Heavy-Water-Moderated Reactors; Valeur Relative des Mesures Critiques et Exponentielles pour l'Etude des Reacteurs Ralentis a l'Eau Lourde; Sravnenie tsennosti kriticheskikh i ehksponentsial'nykh izmerenij dlya reaktorov s tyazhelovodnym zamedlitelem; Valor Relativo de las Mediciones Criticas y Exponenciales para los Reactores Moderados por Agua Pesada

    Energy Technology Data Exchange (ETDEWEB)

    Graves, W. E.; Hennelly, E. J. [Savannah River Laboratory, E.I. Du Pont De Nemours and Co., Aiken, SC (United States)

    1964-02-15

    direct effects in mock-ups and as a test for heterogeneous and two-dimensional diffusion calculations. (6) Criticality studies of heavy-water lattice fuel in light water The SRL exponentials have proved particularly valuable for criticality studies to determine safe methods of handling enriched fuel in light water. High accuracy is not required in this case, and the generalized exponential buckling studies are definitely preferable to the more particularized critical studies. (author) [French] En regle generale, les experiences critiques et exponentielles sur des reseaux de reacteurs fournissent des renseignements qui font double emploi. Durant les dix dernieres annees, le Savannah River Laboratory (SRL) a fait fonctionner simultanement un ensemble critique a eau lourde (PDP) et un ensemble exponentiel (SE). Les auteurs exposent brievement l'experience acquise au SRL, indiquent les resultats obtenus et font des recommandations au sujet de la possibilite d'appliquer ces deux genres d'installations dans differentes experiences. Les auteurs examinent les six types d'experiences ci-apres: 1. Mesures du laplacien dans les reseaux isotropiques uniformes Le SRL a procede a de nombreuses comparaisons entre les mesures faites a l'aide d'ensembles critiques a une seule region, d'ensembles exponentiels, d'ensembles critiques a substitution et du reacteur d'essai des constantes physiques (PCTR). El semble que les seules difficultes que presentent les experiences exponentielles, resident dans les determinations du laplacien dans le sens radial. Si l'on reussit a faire ces determinations, les experiences exponentielles peuvent etre comparees favorablement aux experiences critiques. Les ensembles critiques a une seule region necessitent le plus de matieres; viennent ensuite les ensembles critiques a substitution et les ensembles exponentiels dont les besoins sont en gros comparables; enfin le PCTR ou les mesures en exigent le moins. 2. Effets anisotropiques et effets cavitaires Des

  11. Measurements with a Pulsed and Modulated Source in a Reactor; Mesures au Moyen d'une Source Pulsee et Modulee dans un Reacteur; Izmereniya v reaktore s pomoshch'yu impul'snogo i moduliruemogo is tochnika; Mediciones Efectuadas en Reactor con una Fuente Pulsada y Modulada

    Energy Technology Data Exchange (ETDEWEB)

    Rotter, W. [Centre d' Etude de l' Energie Nucleaire, Mol (Belgium)

    1965-10-15

    a digital computer [French] Un generateur dont le debit neutronique est variable selon une fonction du temps quelconque a ete mis au point par les Laboratoires de recherches Philips. Son utilite pratique dans le domaine de la physique des reacteurs a ete demontree par une serie de mesures effectuees dans le reacteur BRO2 a fotat sous-critique. Sa bonne stabilite, la possibilite de faire varier brusquement l'intensite neutronique, de puiser le debit ou de le moduler sinusoldalement, rend ce generateur tres souple. Il permet de determiner la reactivite ({rho} = {Delta}k/{beta}) et le temps de vie des neutrons ( Script-Small-L /{beta}) d'apres differentes methodes independantes. Une comparaison exacte de ces methodes est possible puisqu'elles peuvent etre employees sans modifier les conditions de mesure. On a determine: a) {rho} sur la base des neutrons retardes, par une reduction instantanee du debit de neutrons; b) {rho} sur la base des neutrons instantanes par des bouffees de neutrons; c) Script-Small-L /{beta} par combinaison de a) et b) pour 0,5 $ < {rho} <2 $; d) Script-Small-L /{beta} sur la base de la fonction de transfert du reacteur pour une source modulee. Les fonctions de transfert pour un oscillateur de reactivite et pour une source modulee sinusoldalement sont discutees. Il est montre que la mesure de Script-Small-L /{beta} est possible pour 0,1 $ < {rho} < 10 $ en utilisant une source modulee. La meme methode fournit aussi la reactivite a l'aide du rapport des neutrons instantanes aux neutrons retardes pour une frequence optimale, pratiquement independamment des donnees relatives aux neutrons retardes et de la valeur de f Script-Small-L /{beta}. Par accumulation d'un grand nombre de cycles dans l'analyseur multicanal, la statistique peut etre amelioree pour chaque methode. Le debit du generateur etant bien sinusoiedal, la reponse du reacteur peut etre integree sur chaque quart d'une periode, etant donne que la chafhe de mesure est pilotee par le

  12. Study of the thermal drop at the uranium-can interface for fuel elements in gas-graphite reactors; Etude de la chute thermique au contact uranium-gaine pour des elements combustibles de reacteur de la filiere graphite-gaz

    Energy Technology Data Exchange (ETDEWEB)

    Faussat, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Levenes, G; Michel, M [Societe Industrielle de Combustible Nucleaire (France)

    1964-07-01

    The report reviews the tests now under way at the CEA, for determining the thermal contact resistance at the uranium-can interface for fuel elements used in gas-graphite type reactors. These are laboratory tests carried out with equipment based on the principle of a heat flow across a stack of test pieces having planar contact surfaces. The following points emerge from this work: - for a metallic uranium element canned in magnesium, of the type G-2 or EDF-2, a value of 0.2 deg C/W/cm{sup 2} seems reasonable for can temperatures of 400 deg C and above. - this value is independent of the micro-geometric state of the uranium surface in a range of roughness which easily includes those observed on tubes and rods produced industrially. - for the internal cans of elements cooled internally and externally, the value of the contact resistance for temperatures of under 400 deg C as a function of the stresses in the can has not yet been measured exactly. (authors) [French] Le rapport fait le point des essais actuellement en cours au CEA pour determiner la resistance thermique de contact uranium-gaine pour des reacteurs de la filiere graphite-gaz. Ces essais sont effectues en laboratoire sur des appareils bases sur le principe d'une circulation de flux de chaleur a travers un empilement d'eprouvettes dont les faces en contact sont planes. De l'etude, il ressort essentiellement que: - pour un element a uranium metallique et gaine de magnesium type G-2 ou EdF-2, on peut admettre la valeur de 0,2 deg C/W/cm{sup 2} pour des temperatures de gaines de 400 deg C et plus. - cette valeur ne depend pas de l'etat de surface microgeometrique de l'uranium pour un domaine de rugosites couvrant largement celles que l'on observe sur des tubes et barreaux fabriques en serie. - pour les gaines internes d'elements a refroidissement interne et externe la valeur de la resistance de contact reste a preciser pour les temperatures inferieures a 400 deg C, en fonction des contraintes existant dans les

  13. 4D Joint Stratigraphic Inversion of Prestack Seismic Data: Application to the CO2 Storage Reservoir (Utsira Sand Formation at Sleipner Site Inversion stratigraphique jointe 4D de données sismiques avant sommation : application au réservoir de stockage de CO2 (Formation Utsira du site de Sleipner

    Directory of Open Access Journals (Sweden)

    Labat K.

    2012-04-01

    éservoirs au cours de leur production. Nous présentons ici une méthodologie d'inversion stratigraphique 4D qui fournit une estimation des variations d'impédances des ondes P et S dans le réservoir, par inversion de données de sismiques répétées avant-sommation. L'inversion 4D est implémentée dans le domaine temps et nécessite une loi de mise à l'échelle des temps de trajets pour chaque jeu de données de sismique répétée (aussi appelé "millésime" afin de mettre en correspondance les temps d'arrivée d'événements homologues observés sur les jeux de données appelés référence et monitors. Cette opération est souvent appelée "warping". L'inversion 4D est une méthodologie qui comporte trois étapes : la première étape consiste à inverser chaque millésime sismique séparément, pour produire autant de distributions en impédances P et S que de jeux de données considérés. La seconde étape utilise l'information des impédances P disponibles pour résoudre le problème du warping, qui est un point clé pour la troisième et dernière étape : l'inversion jointe de tous les millésimes sismiques disponibles. Cette séquence d'inversion 4D a été appliquée aux jeux de données enregistrés sur le réservoir de stockage de CO2 du site norvégien de Sleipner (Mer du Nord. Ce dernier est devenu un site industriel de référence pour le stockage à long terme du dioxyde de carbone (CO2 dans un aquifère salin, la formation des sables de l'Utsira. Nous avons focalisé notre étude sur l'inversion 4D des millésimes 1994 et 2006, acquise respectivement avant et dix ans après le début de l'injection de CO2. Le warping a fourni une loi de mise à l'échelle des temps de propagation avec un retard maximum d'environ 45 ms à la base de l'aquifère Utsira. L'inversion 4D jointe a donné des résultats plus cohérents que les inversions 3D : l'inversion 4D fournit en particulier des impédances P pour les grès saturés en CO2 qui sont très proches des

  14. Fission gas pressure build-up and fast-breeder economy; Accumulation de la pression des gaz de fission et economie des reacteurs surgenerateurs a neutrons rapides; Nakoplenie davleniya gazov produktov deleniya i ehkonomika reaktorov-razmnozhitelej na bystrykh nejtronakh; Aumento de la presion de los gases de fision y economia de los reactores reproductores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Engelmann, P [Kernforschungszentrum, Karlsruhe (Germany)

    1962-03-15

    Fuel-cycle costs and doubling time of fast-breeder reactors are strongly affected by the fuel-burn-up obtainable. Use of oxide or carbide fuel offers the possibility of reaching a burn-up of 100 000 MWd/t. In fuel-clad elements, a limiting factor is the fission-gas-pressure build-up. At the high burn-up considered, an appreciable fraction of the fission gases gets into the pores and thus contributes to the pressure on the can. Starting from the known fission-product yields and decay chains, gas production and pressure build-up have been calculated. Three physical models have been employed in calculating the pressure acting upon the can : the gas is contained either in interconnected pores, in separate pores, or in a central hole. The pressure-dependence upon free volume (fuel density) and temperature will be discussed. Cans made of high-strength materials as Ineonel-X and molybdenum could stand the fission-gas pressure at operating temperatures. Unfortunately, these materials have higher absorption cross-sections than stainless steel. Results of a multi-group calculation are given, showing the effect of using these can materials and of decreasing the fuel density on critical mass and breeding ratio in small and medium-size breeders. (author) [French] Le cout du cycle de combustible et la periode de doublement des reacteurs surgenerateurs a neutrons rapides dependent etroitement du taux de combustion. En utilisant pour combustible un oxyde ou un carbure, on peut atteindre un taux de combustion de 100 000 MW j/t. Avec des combustibles gaines, l'accumulation de la pression des gaz de fission est un facteur limitatif. Pour le fort taux de combustion envisage, une fraction non negligeable des gaz de fission penetre dans les interstices et contribue ainsi a la pression sur la gaine. A partir des rendements en produits de fission et des chaines de desintegration connus, l'auteur a calcule la production de gaz et l'accumulation de pression. Pour calculer la pression

  15. The effective lifetime and temperature coefficient in a coupled fast-thermal reactor; Temps de vie effectif et coefficient de temperature dans un reacteur a couplage neutrons rapides-neutrons thermiques; Ehffektivnyj srok zhizni i temperaturnyj koehffitsient nejtronov v dvoyakom reaktore na bystrykh i teplovykh nejtronakh; Vida efectiva y coeficiente de temperatura en un reactor con acoplamiento rapido-termico

    Energy Technology Data Exchange (ETDEWEB)

    Haefele, W. [Kernforschungszentrum, Karlsruhe (Germany)

    1962-03-15

    The theory of coupled systems was extensively developed by Avery and co-workers at the Argonne National Laboratory. One of the main points of interest in a coupled system is the larger effective lifetime of neutrons. The effect of the thermal component acts as a sort of neutron-delayer. As in the theory of delayed neutrons the delaying effect disappears if the reactivity worth is high enough to make the fast component critical by itself. In the study a coupled reactor is considered where the fast component suffers a sudden reactivity step {alpha}{sub 0}. Because of the increasing power-level the temperature rises and two temperature coefficients start to work: the temperature coefficient of the fast component and the temperature coefficient of the thermal component. The problem is considered with one group of delayed neutrons (in the ordinary meaning). A formalism is given to express the effective lifetime and temperature coefficient during the different stages of the excursion. Excursions for different {alpha}{sub 0} are given so that the limit of fast-reactor kinetics is reached. (author) [French] La theorie des systemes a couplage a ete mise au point par Avery et ses collaborateurs au Laboratoire national d'Argonne. L'une des caracteristique les plus interessantes d'un systeme a couplage est que le temps de vie effectif des neutrons est plus long. L'effet de la partie thermique contribue en quelque sorte a retarder les neutrons. Comme dans la theorie des neutrons retardes, l'effet de retardement disparait lorsque la reactivite a une valeur suffisamment elevee pour rendre la partie rapide critique par elle-meme. L'auteur du memoire considere un reacteur a couplage dont la partie rapide subit un saut instantane de reactivite, {alpha}{sub 0}. La temperature s'eleve a cause de l'augmentation de puissance et deux coefficients de temperature commencent a s'appliquer: le coefficient de temperature de la partie rapide et le coefficient de temperature de la partie

  16. Aspects of Reactor Physics Research at the Victoria University of Manchester; Quelques Aspects des Experiences de Physique des Reacteurs a l'Universite Victoria de Manchester; Aspekty ehksperimental'nykh issledovanij po fizike reaktorov v universitete viktorii v manchestere; Trabajos de Fisica Experimental con Reactores Efectuados en la Universidad Victoria de Manchester

    Energy Technology Data Exchange (ETDEWEB)

    Harris, M. J.; Walton, D. G. [Victoria University of Manchester (United Kingdom)

    1964-02-15

    constructed. Its mechanical design gives considerable flexibility so that, for instance, measurements parallel and perpendicular to the fuel rods are greatly facilitated. A programme of steady-state measurements is under way. Future work is outlined, and includes fine structure measurements, voidage effects and pulsed neutron studies. (author) [French] Le Departement du genie nucleaire de l'Universite de Manchester a ete cree en 1959. Depuis lors, les etudes post-universitaires de physique des reacteurs se sont progressivement developpees et elargies en partant virtuellement de zero; les travaux ont porte sur les reseaux a eau ordinaire et notamment sur les experiences exponentielles a uranium naturel et a eau ordinaire alimentees par un accelerateur de particules. Les auteurs passent en revue les travaux effectues, etudient les resultats obtenus, donnent des apercus sur les recherches futures et illustrent leur expose par la description de diverses techniques experimentales adoptees a Manchester, qui sont peu onereuses et ne necessitent qu'un personnel reduit. Les principaux sujets de recherches sont decrits ci-apres. Les auteurs ont etudie la diffusion des neutrons dans l'eau ordinaire en employant successivement la methode de la source puisee et celle de la source stationnaire. Avec la premiere methode, ils se sont astreints a faire une analyse harmonique complete, au point d'etudier effectivement les modes superieurs alors que, par le passe, ont cherchait seulement a les eliminer. Au moyen de la methode de la source stationnaire, ils ont cherche surtout a eliminer tous les effets dus a la dimension de la source finie et du detecteur, al'activation par resonance, a la perturbation du flux, etc. Ils discutent et comparent les resultats de ces deux etudes. Le memoire decrit ensuite une mesure tres precise des sections efficaces d'absorption, egalement en cours, par la methode des neutrons puises, en prenant soin d'eliminer les effets harmoniques et autres, generateurs d

  17. Ultrasonic Water-Gap Measurements in MTR Fuel Elements; Mesure par Ultrasons des Espaces Intercalaires dans les Elements Combustibles des Reacteurs d'Essai de Materiaux; Izmereniya vodyanogo zazora v teplovydelyayushchikh ehlementakh dlya materialovedcheskogo reaktora s pomoshch'yu ul'trazvuka; Medicion Ultrasonica de la Capa de Agua en Elementos Combustibles para Reactores de Ensayo de Materiales

    Energy Technology Data Exchange (ETDEWEB)

    Deknock, R. [Metallurgy Department, S.C.K./C.E.N., Mol (Belgium)

    1965-10-15

    The high thermal fluxes, which are usual in the latest materials testing reactors, impose suitable paths for uniform heat transfer and a reliable heat removal avoiding bulk-vapour formation. Furthermore, to control the over-all swelling and reactor fuel behaviour, water-gap measurements will also be performed in post-irradiation experiments on spent fuel elements. For that purpose, a probe for measuring the 3-mm water-gap of the BR-2 fuel element over a 1-m length, based on the principle of ultrasonics, has been developed. In the case of post-irradiation experiments, the measuring probe should operate in a fuel element by being immersed in a water pool at a depth of at least 6 m. The probe can withstand prolonged immersion in water and is not affected by normal gamma-irradiation doses. Although operating on the usual pulse-reflection method, the system allows emitted and reflected pulses to be separated by a 10-MHz ferro-electric crystal with high inherent energy dissipation. Oscilloscope read-out can be used, whereby the time is displayed on the horizontal axis, the scanning speed being adjusted to bear a direct relation to the velocity of wave propagation, i.e. the gap distance. This type of read-out Is satisfactory where the number of measurements is restricted, but chart recorder read-out is obviously desirable. In this case, emitted and reflected pulses are shaped and fed to a time-voltage converter using transistor logic techniques. The instrument allows continuous adjustment of output zero for any arbitrary gap distance between 2 and 4 mm thereby permitting zero-centre recording. Furthermore, any desired 100-{mu}m gap distance variation can give a stable 1-V output voltage to a recorder. An accuracy of 5-{mu}m gap-distance variation is easily obtained. Several fuel elements have been measured. The results and reproducibility were very satisfactory. (author) [French] Etant donne que dans les plus recents reacteurs d'essai de materiaux les flux thermiques sont

  18. Non-Destructive Testing in Reactor Pressure-Vessel Fabrication; Essais non Destructifs dans la Fabrication des Caissons Etanches de Reacteurs; Nedestruktivnoe ispytanie pri izgotovlenii reaktornykh bakov vysokogo davleniya; Ensayo no Destructivo Durante la Fabricacion de Recipientes de Presion para Reactores

    Energy Technology Data Exchange (ETDEWEB)

    McGonnagle, W. J. [Fluids Dynamics Research, Iit Research Institute, Chicago, IL (United States)

    1965-09-15

    of the pressure vessel are discussed. (author) [French] Le memoire a pour objet d'exposer les grandes lignes d'un programme de controle de la qualite dans la fabrication d'un caisson etanche de reacteur qui satisfera a toutes les specifications du point de vue nucleaire et de la securite, et de mettre en evidence le role et l'importance des essais non destructifs dans ce programme. Les defauts constates dans les materiaux, les elements et leur assemblage montrent que les methodes actuelles de fabrication ne permettent pas en elles-memes d'assurer le maintien de la qualite des elements critiques. 11 se produit des pailles et des heterogeneites memes lorsque l'on utilise les meilleurs procedes de fabrication et que l'on applique des methodes et techniques dument controlees. C'est pourquoi, afin d'obtenir la qualite requise pour un caisson de reacteur, il faut executer un programme approprie et coherent d'essais non destructifs. Les principales methodes d'essais non destructifs appliquees par les fabricants de caissons de reacteurs sont les suivantes: inspection visuelle, radiographie par les rayons X ou gamma, ultrasons, particules magnetiques et penetration de liquides. Le programme d'essais non destructifs comporte le controle des materiau', du forgeage, du moulage, du gainage et des soudures. L'auteur etudie les problemes particuliers que posent les essais non destructifs des caissons etanches. Il decrit et discute les techniques speciales propres aux essais non destructifs des caissons et de leurs elements. Le memoire donne un apercu des reglements et specifications applicables, notamment du reglement de fabrication des bouilleurs et caissons etanches publie par la Societe americaine des ingenieurs mecaniciens. L'auteur etudie la mesure dans laquelle les essais non destructifs peuvent contribuer a repondre aux specifications imposees par les institutions de normalisation, ainsi que la mesure dans laquelle les normes admises pour ces essais sont appropriees et

  19. The Development of Materials for Application to Control Rod Systems in Graphite moderated Reactors; Mise au Point de Materiaux pour les Dispositifs de Controle a Barres, Utilbes dans les Reacteurs Ralentis au Graphite; Razrabotka materialov , primenyaemykh v sistemakh upravlyayushchikh sterzhnej v reaktorakh s grafitovym zamedlitelem; Perfeccionamiento de Materiales Aplicables a las Barras de Control en los Reactores Moderados por Grafito

    Energy Technology Data Exchange (ETDEWEB)

    Wade, G. E.; Kempf, F. J. [Hanford Atomic Products Operation, General Electric Company, Richland, WA (United States)

    1964-06-15

    Material problems associated with the control- and safety-rod systems for graphite moderated, tube-type reactors can be divided into two categories: control materials and operating-channel liner materials. The control materials, such as boron or gadolinium, can be integral with the rod sheath, as in the boron stainless steel used for safety rods. Another approach is the enclosure of a boron-containing sintered compact, such as B{sub 4}C-graphite or B{sub 4}C-aluminium, in a metallic sheath. Rods of the latter type are adaptable for control purposes because of the increased percentages of boron that can be included. Test and fabrication experience indicate that a wide range of satisfactory rod designs is possible with any of these materials. The rod operating channels in the reactor often require liners to protect the surrounding graphite moderator from rod-insertion impact loads and wear and to help maintain channel alignment. Abrasion- and impact resistant, high-strength, low cross-section materials that will operate uncooled are required for these liners. Pyrolytic graphite, pyrolytic graphite composites, aluminium oxide and silicon carbide have been tested for such applications. Physical and irradiation damage data indicate that some of these materials are suitable for lining rod-operating channels. (author) [French] Les problemes de materiaux lies aux dispositifs de controle a barres de reglage et de securite pour les reacteurs tubulaires ralentis au graphite sont doubles et concernent les materiaux absorbants d'une part et les materiaux de garnissage des canaux d'autre part. Les materiaux absorbants tels que le bore ou le gadolinium peuvent former un tout avec le materiau de gainage comme dans le cas ou les barres de securite sont en acier inoxydable au bore. Une autre technique consiste a enfermer un melange presse et fritte contenant du bore, tel que B4C-graphite ou B4C-aluminium, dans une gaine metallique. Les barres de ce dernier type peuvent etre adaptees

  20. Industrial Ultrasonic Inspection of Stainless-Steel Claddings for the EL4 Reactor; Controle Industriel par Ultrasons des Gaines en Acier Inoxydable du Reacteur EL4; Promyshlennyj kontrol' obolochechnykh trub iz nerzhaveyushchej stali reaktora dlya EL4 s pomoshch'yu ul'trazvukovogo metoda; Metodos Ultrasonicos para Control Industrial de las Vainas de Acero Inoxidable del Reactor EL4

    Energy Technology Data Exchange (ETDEWEB)

    Prot, A. C.; Foulquoer, H. E.; Peyrot, J. P. [Centre d' Etudes Nucleaires de Saclay (France)

    1965-09-15

    Improved reactor performance requires the use of accurately fabricated and carefully inspected components. One inspection relates to the quality of the cladding tubes, whose mechanical reliability is essential for economic reactor operation. The choice and development of a method is a difficult matter and the authors explain the main factors involved. Once the choice has been made and the method has been developed in the laboratory, two new problems arise: Adaptation to meet industrial requirements; and The need to reconcile the quality standards attainable with the manufacturing process at any given stage and the somewhat arbitrarily defined specifications for the finished product. In practice, this involves a statistical study of batches of tubes from various sources and their classification in relation to more or less strict thresholds. The number of tubes which have to be inspected is much larger than originally expected. This has led to the design of an automatic inspection device geared both to the output rates involved and to the requirements of the type of inspection adopted; the latter are generally mechanical and impose particularly careful product fabrication. These various characteristics are now embodied in a device whose capacity can already easily meet the requirements of a fuel-element production line. The potentialities of the device are closely dependent on the characteristics of the inspection equipment used, especially the performances of the electronic part of ultrasonic inspection instruments and of the transducers. This study shows that standard equipment is not very suitable and that immediate thought should be given to special instruments for this type of inspection. (author) [French] L'accroissement des performances des reacteurs necessite l'utilisation de materiaux finement elabores et soigneusement controles. L'un des aspects de ce controle est celui de la qualite des tubes de gainage utilises, dont la tenue mecanique est un facteur

  1. A critical summary of microscopic fast-neutron interactions with reactor structural, fissile and fertile materials; Apercu critique des interactions microscopiques des neutrons rapides avec les materiaux de construction et les matieres fissiles et fertiles utilisees dans les reacteurs; Kriticheskij obzor mikroskopicheskog o vzaimodejstviya bystrykh nejtronov s konstruktsionnymi, rasshcheplyayushchimis ya i vosproizvodyashchim i reaktornymi materialami; Resumen critico de las interacciones microscopicas de los neutrones rapidos con los materiales estructurales fisionables y fertiles utilizados en los reactores

    Energy Technology Data Exchange (ETDEWEB)

    Smith, A B [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    Prevailing knowledge of fast-neutron-induced reactions utilized in the nuclear design of reactor systems is reviewed. Principal emphasis is placed upon microscopic experimental methods, results and precisions. Fast-neutron scattering is considered in detail, including the results of experimental determinations of scattering from oxygen, iron, zirconium, niobium, tungsten, thorium and uranium. Representative results of experimental studies of fast-neutron capture and fast-neutron-induced fission are given. The measurements discussed not only provide results of considerable applied usefulness but axe also examples of the application of advanced experimental nuclear techniques. Areas of limited, conflicting or non-existent experimental information are outlined. A prognosis of future knowledge of fast-neutron reactions is made, with emphasis on the fulfillment of reactor requirements for basic nuclear data. (author) [French] L'auteur fait le point des connaissances sur les reactions provoquees par les neutrons rapides sur lesquelles on tend a fonder les projets de reacteurs. Il met en relief les methodes, les resultats et la precision de mesures experimentales a l'echelle microscopique. Il etudie en detail la diffusion des neutrons rapides, et donne les resultats de mesures experimentales de diffusion dans l'oxygene, le fer, le zirconium, le niobium, le tungstene, le thorium et l'uranium. Il donne les resultats les plus significatifs d'etudes experimentales sur la capture des neutrons rapides et sur la fission provoquee par des neutrons rapides. Les mesures etudiees, non seulement fournissent des renseignements d'une utilite pratique considerable, mais aussi constituent des exemples de l'application de techniques experimentales nucleaires a la pointe du progres. L'auteur indique les domaines ou les donnees experimentales sont limitees, contradictoires ou inexistantes. Il se livre a des pronostics sur le developpement des connaissances experimentales en matiere de

  2. The Economical Application of Non-Destructive Testing to Reactor Components, Especially Jacket Tubing; Avantages Economiques du Controle Non Destructif des Pieces de Reacteurs, Notamment des Tubes de Gainage; Ehkonomicheskoe primenenie nedestruktivnykh ispytanij dlya reaktornykh komponentov, v chastnosti obolochechnykh trub; Aplicacion en Condiciones Economicas de Ensayos No Destructivos a las Piezas de los Reactores, en Especial a los Tubos de Revestimiento

    Energy Technology Data Exchange (ETDEWEB)

    Renken, C. J. [Metallurgy Division Argonne National Laboratory Argonne, IL (United States)

    1965-10-15

    electro-magnetic method for technical as well as economic reasons. The optimum area of application of these two methods is explained as well as the large area of overlap where results produced by well- designed and properly operated equipment of both types are essentially equivalent. Spurious defect indications contribute directly to increased component costs, so an evaluation of these effects for both the ultrasonic and the electromagnetic test methods is included for several commonly encountered sources of spurious defect signals. The experience in the application of these methods at Argonne National Laboratory on relatively large quantities of tubing from various sources are recounted from the standpoint of the lowest possible inspection cost per unit length of tubing. This section also summarizes experience gained at Argonne with the newer pulsed electromagnetic test methods. The critical but generally unappreciated role of tube diameter and wall thickness on tube inspection cost is discussed. Since the question of economical inspection is closely related to allowable defect levels, defect levels and standards in use at Argonne are covered. Finally, the practical and theoretical barriers to reduced component inspection costs are enumerated and a projection of what possible reductions in cost might be attainable in the future with the ultrasonic and electromagnetic test methods is attempted. (author) [French] Le reacteur ideal aurait entre autres caracteristiques celle de ne pas exiger de controles non destructifs. Cet ideal, comme tant d'autres, ne sera probablement jamais atteint. Dans l'etude de tout reacteur pour lequel le prix de revient constitue un facteur important, il faudrait envisager la question de savoir si les pieces de ce reacteur pourront etre essayees de facon economique en meme temps que l'on examine les possibilites de fabrication. Cette partie du memoire contient quelques considerations a ce propos ainsi qu'un expose de l'importance des essais non

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-11-01

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

  4. The 'Reacteur Jules Horowitz': a new experimental reactor project

    International Nuclear Information System (INIS)

    Frachet, S.; Ballagny, A.

    1999-01-01

    The Jules Horowitz Reactor (RJH) is a new research reactor project dedicated to materials and nuclear fuel testing, the location of which is foreseen at the CEA-CADARACHE site, and the start-up in 2006. The launching of this project originated from a double finding: The development of nuclear power plants aimed at satisfying the energy needs of the next century, cannot be envisaged without experimental reactors which are unrivaled for the validation of new concepts of nuclear fuels, materials, and components as well as for their qualification under irradiation. The existing experimental reactors are 30 to 40 years old and it is advisable to examine henceforth the necessity for and the nature of a new reactor to take over and replace, at the beginning of next century, the reactors shut-down in the mean time or at the very end of their lives. Within this framework, the CEA has undertaken, in the last years, a study on the mid and long term irradiation needs, to determine the main features and performances of this new reactor. The concept of the reactor will have to fulfill the thermal neutron irradiation requirements as well as the fast neutron experimental needs, with a great potential versatility for any new irradiation programs. The reactor project selected among several different concepts, is finally a light water pool concept, with 100 MW thermal power. It could reach neutronic fluxes twice those of present French reactors, and allows for many irradiations in and around the core, under high neutron fluxes. The reactor will satisfy the highest level of safety in full accordance with international safety recommendations and the French safety approach for this kind of nuclear facility, thus giving an added safety margin keeping in mind the versatility of research reactors. The feasibility studies have been focused on the following most important items: neutronic and thermalhydraulic studies on alternative core designs, with or without added pressurization, assessment of different core surrounding structures in connection with the core studies, overall layout of the reactor/auxiliary pools and reactor building. (author)

  5. The Flamanville 3 EPR reactor; Le reacteur EPR Flamanville 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    On April 10. 2007, the french government authorized EDF to create on the site of Flamanville ( La Manche) a nuclear base installation containing a pressurized water EPR type reactor. This nuclear reactor, conceived by AREVA NP and EDF, is the first copy of a generation susceptible to replace later, at least partly, the French nuclear reactors at present in operation.Within the framework of its mission of technical support of the Authority of Nuclear Safety ( A.S.N.), the I.R.S.N. widely contributed successively: to define the general objectives of safety assigned to this new generation of pressurized water nuclear reactors; to analyze the options of safety proposed by EDF for the EPR project; To deepen, upstream to the authorization of creation, the evaluation of the step of safety and the measures of conception retained by EDF that have to allow to respect the objectives of safety which were notified to it. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-15

    'oxydation directe de l'azote sous irradiation, entreprises depuis plusieurs annees par le Rensselaer Polytechnic Institute et le Brookhaven National Laboratory, utilisent directement les particules de recul de fission comme rayonnements ionisants, au moyen de la dispersion d'uranium-235 dans des fibres de verre de cinq microns de diametre environ. Les auteurs ont determine les effets de la temperature, de la pression et du rapport azote/oxygene sur la valeur de G pour l'oxydation de l'azote et ont publie le compte rendu de leurs travaux. Ils en donnent un bref apercu. Les recherches en question ont ete effectuees avec des systemes statiques; plus recemment des systemes statiques et des systemes a circulation ont ete utilises a la fois. Avec les systemes statiques, les auteurs se sont surtout attaches a etudier l'effet de l'intensite des rayonnements, notamment sur la cinetique d'equilibre sous irradiation. Ils ont constate que dans des melanges ou le rapport azote/oxygene est de 4 a 1 et de 2 a 1 N0{sub 2} et N{sub 2}0 se forment jusqu'a epuisement de tout l'oxygene present. Un systeme a circulation continue (cycling) fonctionne maintenant dans une boucle a l'interieur du reacteur de Brookhaven. Les auteurs fournissent sur les effets de la temperature, de la pression, du rapport azote/oxygene et de l'intensite des rayonnements des donnees que l'on pourra utiliser pour etablir un projet de reacteur de chimie nucleaire. Le systeme actuel fonctionne sous 10 atmospheres et a 150{sup o}C. La temperature est fonction de l'energie de fission liberee dans les fibres de verre et de la resistance thermique du circuit. Une autre boucle, qui doit fonctionner sous 50 - 75 atmospheres et a 600{sup o} C, est en construction. Il est possible, grace a ces boucles, d'etudier les caracteristiques d'un systeme continu, y compris le comportement des produits de fission liberes dans le courant, gazeux. Les auteurs distinguent trois stades dans la cinetique complexe de l'oxydation de l'azote: reactions

  7. New Methods and Facilities for the Measurement of Physical Properties of Reactor Components and Irradiated Materials; Nouveaux Procedes et Instruments de Mesure des Proprietes Physiques des Elements de Reacteur et des Matieres Irradiees; Novye metody i sredstva izmereniya fizicheskikh s vojstv komponentov reaktora i obluchennykh materialov; Nuevos Metodos y Equipos para Medir Propiedades Fisicas de Componentes de Reactor y de Materiales Irradiados

    Energy Technology Data Exchange (ETDEWEB)

    Foerster, F.; Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

    1965-09-15

    zone 'chaude ' du reacteur. Ils discutent la relation entre la conductivite electrique et la dose d'irradiation. Les auteurs decrivent un instrument de mesure de la permeabilite, de la remanence et de la force co- ercitive en fonction des contraintes mecaniques, de la deformation elastique et inelastique et de la dose d'irradiation. Ils donnent des mesures de la variation des proprietes magnetiques en fonction des contraintes elastiques et de la deformation inelastique. Ils etudient les effets de l'irradiation sur la permeabilite et sur la force coercitive. Les auteurs decrivent un instrument permettant la mesure rapide et la lecture directe de la permeabilite des elements en acier inoxydable. Ils expliquent la correlation entre la permeabilite et la teneur en ferrite {Delta}. Us discutent certaines mesures du pourcentage de ferrite {Delta} dans les soudures de tubes en acier inoxydable ainsi que certaines mesures de precipitation de ferrite {Delta} en fonction de la deformation inelastique (forgeage a la main d'elements combustibles pour reacteurs). (author) [Spanish] Se describe un intrumento para medir y registrar en forma totalmente automatica el modulo de Young, el modulodecorte y la capacidad de amortiguamiento, en funcion de la temperatura y el tiempo. El modulo de Young se determina excitando muestras de diversos tamanos con sus frecuencias naturales, mientras que la capacidad de amortiguamiento se mide en funcion de la libre atenuacion de la vibracion, o bien por la anchura media de la curva de resonancia. Se presentan ejemplos de medidas de la recuperacion despues de provocar danos por irradiaciones y deformaciones plasticas asf como grado de grafitacion. Se describe la deteccion de fallas y variaciones de densidad en barras de grafito. Se explica, ademas, un metodo para investigar la retencion de pastillas de UO{sub 2} en tubos austenfticos de pared delgada. Se describe un horno especial para estudiar el comportamiento elastico e inelastico de muestras

  8. 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.)

  9. Handling and Separation of Short-Lived Radioisotopes from Research Reactors; Manipulation et Separation des Radioisotopes a Courte Periode Produits dans des Reacteurs de Recherche; ПОЛУЧЕНИЕ И ОТДЕЛЕНИЕ КОРОТКОЖИВУЩИХ ИЗОТОПОВ В ИССЛЕДОВАТЕЛЬСКИХ РЕАКТОРАХ; Manipulacion y Separacion de Radioisotopos de Periodo Corto Obtenidos en Reactores de Investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Meinke, W. W. [University of Michigan, Ann Arbor, MI (United States)

    1963-03-15

    distillation, selective reduction, etc., also add to the variety of separation possibilities to be explored. The local research reactor, whether it is in a university in the United States, or in a developing country, thus opens a whole new era of tracer possibilities. (author) [French] L'emploi des radioisotopes a souvent ete limite aux radioisotopes dont la periode est superieure a un jour, etant donne l'eloignement du reacteur qui les produit. Ceci explique un certain manque d'interet a l'egard du traitement et de l'utilisation de ces radioisotopes, et par suite une certaine reticence de la part du consommateur a envisager meme les possibilites d'emploi de nombreux radioisotopes a courte periode. Comme il existe maintenant de nombreux reacteurs de recherche dans le monde, les laboratoires ne dependent plus de producteurs de radioisotopes eloignes; en outre, les radioisotopes a courte periode couvrent de nombreux champs d'experimentation nouveaux. Il importe, cependant, a cette fin de considerer la production des radioindicateurs sous un angle nouveau. Depuis pres de cinq annees, le programme execute au moyen du reacteur de recherche de l'Universite du Michigan comporte la manipulation, le traitement et la mesure de radioisotopes a courte periode. Les chercheurs de l'Universite emploient couramment des radioisotopes dont les periodes ne depassent pas plusieurs heures, voire quelques minutes. Les traveaux entrepris jusqu'a present avaient trait principalement a l'analyse par activation, mais le material, les methodes et les techniques utilises.peuvent s'appliquer a de nombreux autres domaines. Pour utiliser les radioisotopes a courte periode, il n'est pas necessaire de prevoir un roulement de trois equipes pour le reacteur; il n'est pas lion plus indispensable de disposer de stocks importants de radioisotopes, ni d'installations de traitement perfectionnees.En fait, de simples pinces, utilisees de la maniere courante, donnent generalement de meilleurs resultats que de

  10. Dispersions of Oxides in Oxide Matrices as High-Temperature Reactor Fuels; Dispersions d'oxyde dans des matrices d'oxyde, utilisees comme combustibles dans des reacteurs a haute temperature; Dispersiya okisej v okislovykh matritsakh v kachestve topliva dlya vysokotemperaturnogo reaktora; Empleo de dispersiones de oxidos en matrices de oxidos, como combustibles para reactores de elevada temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Williams, J. [Atomic Energy Research Establishment, Harwell (United Kingdom)

    1963-11-15

    The potential usefulness of dispersions of PuO{sub 2}, UO{sub 2} and ThO{sub 2} in matrices of BeO, Al{sub 2}O{sub 3}, MgO and SiO{sub 2} is reviewed in terms of fuel integrity and fabrication. Dimensional stability and fission-product retentivity are the two features most important to fuel integrity. Compatibility of the constituents of the fuels with one another and with the coolant will influence dimensional stability, but oxide fuels are well favoured in these respects. Dimensional changes under irradiation will contain contributions from neutron and fission fragment damage to the matrix, from radiation damage to the fissile-fertile phase and from agglomerated fission-product gases. Thermal stresses are also capable of effecting changes in shape. However, information on mechanisms for stress relaxation is too limited to enable any reasonable theoretical assessment of behaviour to be made. Both light irradiation and high burn-up studies of fission-product release from the fissile-fertile oxides have concerned themselves mainly with the gaseous products, chiefly xenon. Data on the release of other fission products is very limited as is also information on the movement of fission products in general through the potential matrix materials. Studies of the permeability of sintered pure oxides indicate that densities of at least 95% theoretical density (maybe even 98%) will be needed to eliminate open porosity in such matrices. A variety of techniques are available for the preparation of fissile-fertile particles, for their coating and for their incorporation into high-density matrices. Work on laboratory-scale fabrication processes is well advanced. (author) [French] L'auteur examine la possibilite d'utiliser des combustibles disperses - PuO{sub 2}, UO{sub 2} et ThO{sub 2} et matrices de BeO, Al{sub 2}O{sub 3}, MgO et SiO{sub 2} - dans des reacteurs a haute temperature, au point de vue de l'integrite du combustible et de sa transformation. La stabilite dimensionnelle

  11. Development of Non-Metallic Fuel Elements for a High-Temperature Gas-Cooled Reactor; Mise au point d'elements combustibles non metalliques pour un reacteur a haute temperature, refroidi par un gaz; Razrabotka nemetallicheskikh teplovydelyashchikh ehlementov dlya vysokotemperaturnogo reaktora s gazovym okhlazhdeniem; Elementos combustibles no metalicos para un reactor de temperatura elevada refrigerado por gas

    Energy Technology Data Exchange (ETDEWEB)

    Liebmann, B.; Schafer, L.; Spener, G. [NUKEM, Nuklear-Chemie und -Metallurgie G.m.b.H., Wolfgang bei Hanau, Federal Republic of Germany (Germany)

    1963-11-15

    In connection with fuel element development work for the high-temperature gas-coolcd reactor of the Brown-Boveri/Krupp Reaktorbau G.m.b.H., two different fuel element concepts were considered and developed. In both cases the fuel element consists of a graphite ball of 6 cm in diam. which contains the fuel insert, a cylindrical pellet of about 20 mm in diam. and 16 mm in height. The two concepts differ in the type of the.fuel insert as well as in the preparation of the graphite ball. In the first concept the fuel insert consists of a mixture of UC{sub 2} and graphite which is prepared by blending U{sub 3}O{sub 8} and graphite, pressing them into pellets and reacting the two components in a vacuum furnace at 1800{sup o}C. The atomic ratio of U : C is 1:45. Since this type of fuel pellet does not retain the fission products completely the surrounding graphite sphere had to be made impervious to fission products by impregnation in order to obtain a fission-product retaining element. Permeabilities of the order of 10{sup -6}cm{sup 2}/s could be achieved. In the second concept the fuel insert consists of a solid solution of UC in ZrC and is coated with a layer of ZrC. The molar ratio of UC to ZrC is 1 : 20. The fuel pellet preparation was accomplished by the following procedure: UO{sub 2}, ZrO{sub 2}, and graphite were mixed and pressed into pellets. The pellets were reacted to the carbides. Ball milling of the carbides was followed by hot pressing at temperatures o f 2000{sup o}C. Densities of more than 95% of the theoretical density could be achieved. A full description of the preparation and of some physical properties of the fuel pellets is given in the paper. A sufficient fission gas retention behaviour of this type of fuel insert which allows it to be put into unimpregnated graphite balls is expected. Other advantages of this kind of fuel are discussed. (author) [French] Dans le cadre des etudes de combustibles destines au reacteur a haute temperature, refroidi par

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

    Energy Technology Data Exchange (ETDEWEB)

    Girardin, G.

    2009-07-09

    modeles neutroniques 2D et 3D du coeur du reacteur ont ete crees, bases sur le schema de calculs de reference ERANOS-2.0/ERALIB1. Pour l'analyse thermo-hydraulique, le code COPERNIC du CEA a ete utilise. Le travail de design a ete poursuivi par l'etude d'un schema de l'implantation des assemblages de controle (nombre et position dans le coeur). Des etudes detaillees de neutronique ont reveles l'existence de grands effets d'interaction entre les AC, appeles effets d'ombre/d'anti-ombre, conduisant a une amplification/reduction de l'antireactivite des AC. Les interactions entre les barreaux absorbants a l'interieur d'un AC, ainsi qu'entre les AC eux-memes, ont ete investiguees dans le detail, dans le but d'optimiser l'efficacite des AC (en terme de la fraction d'absorbant et la minimisation des effets d'heterogeneite associes). Resultant d'investigations detaillees, le diametre des pastilles absorbantes a ete choisi de maniere a minimiser l'influence 'barreau-a-barreau' a l'interieur de l'assemblage. En particulier, une partie centrale de l'assemblage a ete concue sans aucun barreau absorbant (zone remplie d'helium statique). Par ce biais, une reduction, a 13%, des effets d'heterogeneite, a ete obtenue. Les investigations neutroniques effectuees pour le coeur RNR-G de reference ('2004-Coeur'), specialement, celles liees a l'Etude des interactions entre les AC, ont directement contribue au nouveau design du coeur ('2007-Coeur'). Le rapport hauteur sur diametre a ete augmente a 0.6, compare a la valeur de 0.3 pour le coeur de reference. Pendant la troisieme phase, des modeles couples et detailles, cinetiques 3D et thermohydrauliques 1D, ont ete developpes pour le coeur RNR-G; le but etait d'arriver a une comprehension, en profondeur, du comportement 3D du coeur pendant des transitoires induits par le mouvement d

  13. Stoïcisme et jugement littéraire au Ier siècle avant J.-C. : le témoignage de Denys d’Halicarnasse Stoicism and Literary Judgment in the First Century BC : the Testimony of Dionysius of Halicarnassus Stoicismo e critica letteraria del I sec. a.C.:  la testimonianza di Dionigi di Alicarnasso

    Directory of Open Access Journals (Sweden)

    Mélina Lévy-Makinson

    2011-07-01

    Full Text Available Intégré au cercle des Aelii Tuberones, famille romaine d’obédience stoïcienne, l’historien et rhéteur Denys d’Halicarnasse était familier des théories du Portique : de fait, les théories stoïciennes sur le langage constituaient un intérêt certain pour les recherches stylistiques de Denys, comme en témoignent ses Opuscules Rhétoriques. D’autre part, sa réflexion reflète des enjeux importants du débat littéraire du Ier siècle avant J.-C. à Rome. Atticiste convaincu, Denys rédige ainsi deux traités (Sur Thucydide et la Seconde lettre à Ammée en réaction contre les admirateurs stoïciens de l’auteur de la Guerre du Péloponnèse. Notre auteur développe pour sa part un « atticisme stoïcisant » qui s’adosse à une conception de l’Empire réconciliant Grecs et Romains.Integrated into the circle of the Aelii Tuberones, a Roman family of Stoic inclinations, the historian and rhetorician Dionysius of Halicarnassus was very familiar with theories of Stoicism : in fact, the Stoic theories about language were of high interest for Dionysus’ stylistic research, as his Rhetorical Works demonstrate. Moreover, his thinking reflects important issues of literary debate of first century BC in Rome. As an earnest atticist writer, Dionysius wrote two treatises (On Thucydides and the Second Letter to Ammeus in reaction to the Stoic admirers of the author of the Peloponnesian War. Our author develops for his part a “directed to Stoicism atticism” that leans on a conception of reconciling Greeks and Romans in the Empire.Membro del circolo degli Aelii Tuberones, famiglia romana d’obbedienza stoica, lo storico e retore Dionigi di Alicarnasso aveva dimestichezza con le teorie della Stoa: le teorie stoiche sul linguaggio costituivano, infatti, un sicuro interesse per le indagini sullo stile di Dionigi, come testimoniato dai suoi Opuscoli retorici. D’altro canto, la sua riflessione riflette importanti sfide del

  14. Suitability of Cadmium Tantalate and Indium Tantalate as Control Materials for High-Temperature Reactors; Le Tantalate de Cadmium et le Tantalate d'Indium Comme Absorbants pour les Reacteurs a Haute Temperature; Vozmozhnosti ispol'zovaniya tantalatov kadmiya i indiya v kachestve kontrol'nogo materiala dlya vysokotemperaturnykh reaktorov; Empleo del Tantalato de Cadmio y del Tantalato de Indio Como Materiales de Control Para Reactores de Alta Temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Preisler, E.; Haessner, F.; Petzow, G. [Max-Planck-Institut fuer Metallforschung, Stuttgart, Federal Republic of Germany (Germany)

    1964-06-15

    oxygen in their most stable valency states than the parent elements can. Therefore, the reduction of Cd{sup ++}to metal can be expected while indium tantalate should.be stable. This has been confirmed by experiments with SnO- and WO{sub 2}-additions to cadmium tantalate. Addition of copper oxide to the compounds suppresses this effect. (author) [French] Quelles que soient les conditions particulieres requises dans chaque cas d'espece, les absorbants utilises dans la pratique pour des reacteurs a haute temperature devraient avoir les proprietes suivantes: a) section efficace d'absorption elevee pour les neutrons d'une gamme etendue d'energies; b) forte capacite d 'absorption des neutrons; c) faible sensibilite au point de vue des dommages radioinduits; d) bonne resistance thermique; e) reactivite faible avec le milieu environnant; f) cout eleve et approvisionnemeent facile. Si l 'on tient compte de ces considerations et que l 'on veuille eviter les inconvenients des reactions (n, {alpha}), on s'interessera surtout aux elements suivants: cadmium, tungstene, indium et tantale. Il faut combiner un absorbant de neutrons thermiques efficace avec un absorbant de neutrons epi thermiques; le materiau ainsi obtenu est stable a des temperatures elevees ( Greater-Than-Or-Equivalent-To 700 Degree-Sign C). Les oxydes doubles CdWO{sub 4}, Cd {sub 2}Ta{sub 2}O{sub 7} et CdIn{sub 2}O{sub 2} conviennent bien a cette fin. En outre, c'est le tantalate de cadmium qui a la plus forte resistance thermique. Le tantalate d'indium est un autre oxyde double qui, en combinaison avec le tantalate de cadmium, possede un spectre d'absorption des neutrons interessant. Il a egalement une bonne resistance thermique. Etant donne qu'il faut souvent faconner les materiaux ceramiques absorbants par deformation plastique, on les utilise habituellement sous forme de cermets. C'est la raison pour laquelle ils doivent etre compatibles avec des metaux. Le tantalate de cadmium est compatible avec l'argent et le

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  16. Participation des hommes aux soins aux enfants avant la mise en ...

    African Journals Online (AJOL)

    Journal de la Recherche Scientifique de l'Université de Lomé ... before the implementation of the family and community component of the IMCI strategy in Togo. ... Despite the cultural diversity that characterizes African societies, it is necessary ...

  17. De l'avant au Zimbabwe : dialogue sur les politiques fondé sur des ...

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

    Avec la formation d'un gouvernement inclusif en mars 2009, le Zimbabwe émerge de dix ans de déclin socioéconomique marqués par des taux de pauvreté, de chômage et d'inflation élevés, de même que par la prestation de services ... New website will help record vital life events to improve access to services for all.

  18. Play and the Avant-Garde: Aren't We All a Little Dada?

    DEFF Research Database (Denmark)

    Prager, Phillip

    2013-01-01

    Dada, an art movement that became well known in the late 1910s and early 1920s, challengeded traditional notions of art and aesthetics. Dada artists, for example, tossed colored scraps of paper into the air to compose chance-based collages, performed sound poems devoid of semantic value, and mode......Dada, an art movement that became well known in the late 1910s and early 1920s, challengeded traditional notions of art and aesthetics. Dada artists, for example, tossed colored scraps of paper into the air to compose chance-based collages, performed sound poems devoid of semantic value...... originates from art history’s methodological blindness to the importance of play, not only to creative and artistic endeavors, but to human identity itself. Dada is characterized by an effervescent love of improvisation, curiosity, novelty and an unselfconscious exploration of the phenomenal world...

  19. “Experiência N.2” – uma deriva avant lettre?

    Directory of Open Access Journals (Sweden)

    Giorgio Zimann Gislon

    2012-02-01

    Full Text Available http://dx.doi.org/10.5007/2176-8552.2012n13p51 Flávio de Carvalho realizou a Experiência N.2, que depois relatou em livro dividido em dois capítulos chamados: “A experiência” e “Análise”, em 1931. Ela consistiu em sair às ruas de São Paulo, no meio de uma procissão de Corpus Christi, de chapéu na cabeça. Anos mais tarde, em Paris, um grupo de jovens pensadores e revolucionários de inspiração marxista participou de algumas atividades que lembram a experiência de Flávio de Carvalho. Uma delas era sair de casa e seguir a primeira pessoa que usasse determinado adereço, ou, uma peça de roupa de tal cor. Esse grupo francês, chamado de Situacionista, teve uma revista em que Guy Debord, um dos seus principais integrantes, escreveu, inclusive, a teoria desse tipo de atividade, a teoria da deriva. Aqui se busca demonstrar os pontos de contatos entre a deriva situacionista e a Experiência N.2 de Flávio de Carvalho: psicologia da rua, experiência, acaso e jogo.

  20. Siegried Kracauer, L’Histoire – Des avant-dernières choses

    Directory of Open Access Journals (Sweden)

    Jean Chesneaux

    2006-01-01

    Full Text Available Comment caractériser le savoir historien ? Et la structure même de l’évolution historique ? Voici qu’à l’immense cohorte des professionnels affrontant inlassablement ces questions, se joint un essayiste « extraterritorial » (ainsi définit-il l’historien, dont l’itinéraire intellectuel était passé d’Offenbach au cinéma allemand préhitlérien et de la philosophie du roman policier à la sociologie des petits employés berlinois. Proche de l’Ecole de Francfort et de l’intelligentsia weimarienne de...

  1. Constitutional Adjudication in Colombia: Avant-Garde or Case law Transplant? A Literature Review

    Directory of Open Access Journals (Sweden)

    Liliana Lizarazo-Rodríguez

    2011-03-01

    Full Text Available Colombia is mentioned, together with the US, Uruguay, Argentina and Mexico, as one of the first countries worldwide to adopt the judicial review as a means for adjudicating on the constitutionality of legislation. In recent years, and particularly since the enactment of the Political Constitution of 1991, the Colombian Constitutional Court is also mentioned as a notorious example of judicial activism in terms of legislating through the constitutional adjudication process. This article presents a literature review on the globalization of judicial review and the contemporary methods of constitutional adjudication (including the balancing method, in order to assess the uniqueness and avantgarde nature of constitutional adjudication in Colombia in the global context. Brief reference is also made to the literature on the institutional limitations faced by less developed countries, inasmuch as they affect the way constitutional adjudication is applied and perceived.

  2. The chaos avant-garde memories of the early days of chaos theory

    CERN Document Server

    Abraham, Ralph H

    2001-01-01

    This book is an authoritative and unique reference for the history of chaos theory, told by the pioneers themselves. It also provides an excellent historical introduction to the concepts. There are eleven contributions, and six of them are published here for the first time - two by Steve Smale, three by Yoshisuke Ueda, and one each by Ralph Abraham, Edward Lorenz, Christian Mira, Floris Takens, T Y Li and James A Yorke, and Otto E Rossler. Contents: On How I Got Started in Dynamical Systems 1959-1962 (S Smale); Finding a Horseshoe on the Beaches of Rio (S Smale); Strange Attractors and the Ori

  3. "Particle Fever": avant-premiere at CERN Main auditorium on 10 December, at 19:30

    CERN Multimedia

    Neal David Hartman

    2013-01-01

    CERN people will have the chance to see a preview of the film "Particle Fever" in CERN's main auditorium on Tuesday 10 December at 19:30. The director, Mark Levinson, will be in attendance to speak with the audience about the film after the screening.   CERN and its experiments have been the focus of innumerable television documentaries, news reports, and other media productions.  However, until now, no film about the search for the Higgs Boson has been made for theatrical release in the classic documentary tradition.  "Particle Fever" has received numerous awards and travelled to festivals around the world, where it has consistently played to sell-out audiences.  The film will begin a commercial theatrical run in the United States in early 2014, but CERN people have the chance to see a preview in the CERN main auditorium on Tuesday, 10 December at 19:30.   The director, Mark Levinson, has wor...

  4. Georges Perec and the avant-garde in the visual arts

    DEFF Research Database (Denmark)

    Ørum, Tania

    2006-01-01

    Den franske forfatter Georges Perec tilhører 1960ernes avantgarde, og hans værker deler træk med samtidens billedkunst. Perec deler tresseravantgardens interesse for massekultur, dens kritik af den traditionelle kunstnerrolle og dens ønske om at bevæge sig på tværs af grænserne mellem kunst og li...

  5. La situation politique du Jawf au Ier millénaire avant J.-C.

    Directory of Open Access Journals (Sweden)

    Mounir Arbach

    2003-09-01

    Full Text Available La région du Jawf, située à une centaine de kilomètres au nord-est de Sanaa, possède un nombre important de sites archéologiques sudarabiques. Les plus importants sont, du sud-est au nord-ouest : Barâqish, l’antique Yathill, dont l’enceinte est l’ouvrage défensif le mieux conservé parmi les sites préislamiques ; Ma‘în, l’antique Qarnaw, capitale du royaume de Ma‘în ; Kharibat Hamdân, l’antique Haram ; Kamna, l’antique Kaminahû ; al-Sawdâ’, l’antique Nashshân ; et al-Baydâ’, l’antique Nashq. L...

  6. Freedom of Expression and Rhetorical Art: The Problems of Avant-Garde Jazz.

    Science.gov (United States)

    Francesconi, Robert

    Although the success of black jazz has been limited by its lack of recognition in the white-controlled music industry, its rhetorical development as an expression of black consciousness can be traced from the bebop of the 1940s and early 1950s, through the hard bop and free jazz of the 1960s, to the jazz orientation of the disco circuit in the…

  7. The avant-garde is not dead / René Block ; intervjueerinud Eero Epner

    Index Scriptorium Estoniae

    Block, René, 1942-

    2010-01-01

    Intervjuu saksa galeristi ja kuraatori René Blockiga, kes 1964. a. avas Berliinis galerii, kus eksponeeris J. Beuysi, S. Polke, G. Richteri jt. töid. Töötamisest kuraatorina alates 1970. aastatest, biennaalide tulevikust, avangardist. René Blocki galeriis 1966. a. toimunud Joseph Beuys'i performance'ist "Kuidas seletada kunsti surnud jänesele", millest inspireerituna teater NO99 lõi samanimelise lavastuse

  8. Self-Organisation in the Avant-Garde of the 1960s

    DEFF Research Database (Denmark)

    Ørum, Tania

    2016-01-01

    A spirit of self-organised, autonomous action was a hallmark of the political, youth cultural and artistic movements of the 1960s. One example is The Experimental School of Art in Copenhagen......A spirit of self-organised, autonomous action was a hallmark of the political, youth cultural and artistic movements of the 1960s. One example is The Experimental School of Art in Copenhagen...

  9. Avant le deluge: An investigation of some neglected dimensions of electricity restructuring in California

    Science.gov (United States)

    Golove, William Harry

    Chapter One of this dissertation focuses on describing the key participant groups and their principle interests in the restructuring process. The process of reaching agreement on the restructuring plan turned on each major interest group receiving satisfaction of all of its key objectives. Chapter Two explores the effective use of rhetoric in the electricity restructuring debate. Despite a lack of public involvement, the use of rhetoric appears to have been a prominent feature of the public policy process. A series of rhetorical concepts and mechanisms defined. Of these, the notions of rhetorical salience and rhetorical efficacy are most significant. The results of a field test on the impact of the particular examples of these tropes prominent in the restructuring debate on opinions regarding some of the key restructuring issues are presented. Chapter Three describes the sea change in the nature of demand side management (DSM) policy in the state, brought about by the restructuring of the electricity market. Whereas the primary goal of DSM had been resource acquisition, the new policy goal was to be market transformation. This chapter reviews the economic, and other social science theory that led to the development of demand side management programs based on a resource acquisition goal prior to restructuring and, subsequently, to a market transformation objective. Chapter Four examines the performance of the market during the period beginning in early 1998 through the first few months of 2000 at which time both the wholesale and retail markets in California were apparently functioning relatively well. The findings presented in this chapter are the result of a series of semi-structured interviews conducted with non-residential electricity customers that had chosen to receive electric service and, in some cases, value-added services from a competitive retail electricity service provider One of the key conclusions is that market rules appear to be critical to customer experiences with retail competition, yet the relationship between market rules and market development is inadequately understood. The over-arching theme, that the "free market" was inadequate to manage the complexities of the electricity market, is articulated throughout this work.

  10. D. P. M. Botes, Marcel Duchamp, die Europese avant-garde en 'n ...

    African Journals Online (AJOL)

    D. P. M. Botes, Marcel Duchamp, the avantgarde and a literary definition of plagiarism. This article attempts to widen the literary critical perspective on plagiarism by focussing on an early example of plagiarism in Afrikaans literature associated with the name of D.P.M. Botes and the little magazine Wurm. Botes's supposed ...

  11. Mainstreaming the Avant-Garde: Modernism in Life Magazine (New York, 1883–1936

    Directory of Open Access Journals (Sweden)

    Céline Mansanti

    2016-12-01

    Full Text Available This paper explores the relationship between literary modernism and mainstream culture within a little-studied American magazine, Life (New York, 1884-1936. It does so by looking at three ways in which Life presented modernism to its readers: by quoting modernist writing, and, above all, by satirizing modernist art, and by offering didactic explanations of modernist art and literature. By reconsidering some of the long-established divisions between high and low culture, and between ‘little’ and ‘bigger’ magazines, this paper contributes to a better understanding of what modernism was and meant. It also suggests that the double agenda observed in Life – both satirical and didactic – might be a way of defining middlebrow magazines.

  12. From Realist to “Avant-garde”: Henry James in France

    Directory of Open Access Journals (Sweden)

    Micéala SYMINGTON

    2005-10-01

    Full Text Available “Je crois que l’apparence des choses est toujours trompeuse mais qu’à la longue cette tromperie de l’apparence devient l’équivalent de leur vérité, leur vérité même, et que sans doute il n’y a que ce faux-semblant qui au jour le jour puisse supporter d’être vécu.”Catherine Bertram, in La Bête dans la jungle by Marguerite Duras, states from the beginning of the play the essential truth which John Marcher only understands after her death: that appearances are deceptive, but that this deception ...

  13. Avant-propos. Ce que la bioéthique veut dire Foreword: What bioethics mean

    Directory of Open Access Journals (Sweden)

    Jean-Pierre Baud

    2009-06-01

    Full Text Available Lorsque Mary Shelley publie en 1818 son célèbre Frankenstein, le mot bioéthique n’existe pas. Pourtant c’est de l’éthique propre à la recherche biologique qu’il y est question. Quelle faute a commise l’étudiant en médecine Victor Frankenstein ? L’immense majorité de ceux qu’on interrogerait sur ce point répondrait qu’il s’agit du fait d’avoir fabriqué un être humain. Mais cette immense majorité n’a jamais lu l’œuvre de Mary Shelley et bien peu savent qu’elle était sous-titrée Le Prométhée mod...

  14. Antibiothérapie : les questions qu'il faut se poser avant toute prescription

    OpenAIRE

    2011-01-01

    La prescription d’un antibiotique doit être individualisée. Après s’être demandé si la prescription est réellement utile, il faut évaluer la capacité de l’antibiotique à aider les défenses de l’organisme à éradiquer la bactérie dans le site infectieux. Le choix de la dose et de la durée de traitement doit être ensuite optimisé pour favoriser la guérison et éviter la sélection de résistances tout en garantissant l’observance du propriétaire...

  15. Stratigraphic inversion of pre-stack multicomponent data; Inversion stratigraphique multicomposante avant sommation

    Energy Technology Data Exchange (ETDEWEB)

    Agullo, Y.

    2005-09-15

    This thesis present the extension of mono-component seismic pre-stack data stratigraphical inversion method to multicomponent data, with the objective of improving the determination of reservoir elastic parameters. In addiction to the PP pressure waves, the PS converted waves proved their interest for imaging under gas clouds; and their potential is highly significant for the characterization of lithologies, fluids, fractures... Nevertheless the simultaneous use ol PP and PS data remains problematic because of their different the time scales. To jointly use the information contained in PP and PS data, we propose a method in three steps first, mono-component stratigraphic inversions of PP then PS data; second, estimation of the PP to PS time conversion law; third, multicomponent stratigraphic inversion. For the second point, the estimation of the PP to PS conversion law is based on minimizing the difference between the S impedances obtained from PP and PS mono-component stratigraphic inversion. The pre-stack mono-component stratigraphic inversions was adapted to the case of multicomponent data by leaving each type of data in its own time scale in order to avoid the distortion of the seismic wavelet. The results obtained on a realistic synthetic PP-PS case show on one hand that determining PP to PS conversion law (from the mono-component inversion results) is feasible, and on the other hand that the joint inversion of PP and PS data with this conversion law improves the results compared to the mono-component inversion ones. Although this is presented within the framework of the PP and PS multi-component data, the developed methodology adapts directly to PP and SS data for example. (author)

  16. Marcel Fournier, Charles Kraemer (dir.), Durkheim avant Durkheim. Une jeunesse vosgienne

    OpenAIRE

    Béra, Matthieu

    2016-01-01

    Cet ouvrage restitue un grand nombre de recherches, souvent pointues, communiquées au public il y a maintenant sept ans (en mai 2008) à Épinal, à l’occasion des 150 ans de la naissance de Durkheim dans cette ville en 1858. La biographie d’Émile Durkheim par Marcel Fournier venait alors de paraître (Durkheim, 2007, Fayard) ; le projet de Fournier, co-organisateur des trois journées, était de reconstituer le cadre social de la « prime jeunesse » de Durkheim, de remonter aux sources, d’immerger ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-10-15

    and the ends closed. In addition, the integrity of end closures is established, by radiography. Multiple exposures are commonly made to examine the whole of circumferential weld adequately. The disposition of the fuel can also be recorded accurately by using a panoramic technique. The use of colour radiography is also discussed. Pins are normally tested for leakage after filling with helium, using a mass-spectrometer leak detector. Pins not filled with helium may be tested using a ''back-pressurizing'' technique. Conventional ''probing'' and ''sniffing'' methods are used when it is desirable to locate the sites of leaks. The bubble test in liquids is also used, as a cheap and simple test. The use of krypton-85 as a tracer gas is discussed. (author) [French] Les auteurs decrivent les methodes d'essai que les laboratoires charges des elements combustibles ont elaborees dans le cadre du programme etabli par le reacteurs> en vue de mettre au point des aiguilles de combustible pour diverses filieres de reacteurs. Ces aiguilles sont contenues dans des gaines de 5 a 15 mm de diametre, les materiaux utilises etant des aciers inoxydables et des alliages de zirconium, a) Detection de defauts dans les gaines. Examen par ultrasons a l'aide de deux traducteurs immerges. Les tubes sont animes d'un mouvement helicoidal rapide dans un reservoir fixe. Chaque signal de defaut est verifie et enregistre. Pour regler le dispositif et verifier sa stabilite, on utilise comme temoins des fentes'pratiquees a l'arc a la surface des tubes. Dans certains cas, on a egalement recours au controle par courants de Foucault. Les auteurs decrivent deux procedes: l'un, a debit rapide, est fonde sur un systeme de bobines encerclant le tube; l'autre, a exploration heliccfldale, utilise une bobine se deplacant le long du tube. Les signaux fournis par un circuit a pont sont selectionnes selon la phase et filtres, pour des frequences de 30 a 60 kHz. b) Controle des dimensions de tubes et de

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-03-15

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

  19. Improved Techniques for Low-Flux Measurement of Prompt Neutron Lifetime, Conversion Ratio and Fast Spectra; Methodes Perfectionnees de Mesure de la Duree de Vie des Neutrons Instantanes, du Rapport de Conversion et des Spectres de Neutrons Rapides, dans un Reacteur a Bas Flux; Usovershenstvovannye metody izmereniya vremeni zhizni mgnovennykh nejtronov, koehffitsienta konversii i spektra bystrykh nejtronov pri slabykh potokakh nejtronov; Tecnicas Perfeccionadas para la Determinacion del Periodo de los Neutrones Inmediatos, la Razon de Conversion y los Espectros de Neutrones Rapidos, con Flujos Reducidos

    Energy Technology Data Exchange (ETDEWEB)

    Armani, R. J.; Bennett, E. F.; Brenner, M. W.; Bretscher, M. M.; Cohn, C. E.; Huber, R. J.; Kaufmann, S. G.; Redman, W. C. [Argonne National Laboratory, Argonne, IL (United States)

    1964-02-15

    been concentrated on the use of pulse shape analysis to reject gamma-ray initiated events in hydrogen recoil proportional counters and the introduction of collimation in Li{sup 6}F solid-state detector ''sandwiches'' to improve the resolution obtained. A number of such instruments have been built and their response to mono-kinetic and reactor neutrons has been investigated. Use of the gamma-ray rejection technique was equivalent to a several hundred-fold effective reduction in gamma-ray sensitivity of the recoil counter and extends the usable range down to at least 30 keV. For the Li{sup 6} solid-state devices, resolutions as low as 70 keV full-width at half maximum (1.5%) have been observed for the sum pulse in thermal neutron irradiation. (author) [French] Dans le programme des reacteurs de puissance zero, on a utilise diverses methodes statistiques pour mesurer le rapport duree de vie des neutrons instantanes/duree de vie des neutrons differes. Les auteurs ont mis au point une methode nouvelle, qui consiste a analyser le bruit du reacteur a l'aide d'un filtre passe-bande, et ont perfectionne d'autres methodes telles que la mesure, a l'aide d'un compteur a impulsions, de la frequence des coincidences retardees en fonction du temps de retard et celle de la variance relative des flux de neutrons integres en fonction du temps d'integration. Ils ont etudie les domaines dans lesquels les differentes methodes peuvent etre utilisees avec le plus d'interet. II se sont aussi preoccupes de l'interpretation des resultats de ces mesures, et montrent que l'interpretation fondee sur un modele cinetique simple peut s'appliquer dans la pratique a une grande diversite de cas. Les auteurs decrivent plusieurs perfectionnements de leur methode d'activation pour la determination du rapport de conversion: application de techniques chimiques tres sensibles pour confirmer les resultats obtenus; correction pour les coups parasites en utilisant, dans la determination de la capture, des

  20. Techniques d'inspection par ondes guidees ultrasonores d'assemblages brases dans des reacteurs aeronautiques =

    Science.gov (United States)

    Comot, Pierre

    L'industrie aeronautique, cherche a etudier la possibilite d'utiliser de maniere structurelle des joints brases, dans une optique de reduction de poids et de cout. Le developpement d'une methode d'evaluation rapide, fiable et peu couteuse pour evaluer l'integrite structurelle des joints apparait donc indispensable. La resistance mecanique d'un joint brase dependant principalement de la quantite de phase fragile dans sa microstructure. Les ondes guidees ultrasonores permettent de detecter ce type de phase lorsqu'elles sont couplees a une mesure spatio-temporelle. De plus la nature de ce type d'ondes permet l'inspection de joints ayant des formes complexes. Ce memoire se concentre donc sur le developpement d'une technique basee sur l'utilisation d'ondes guidees ultrasonores pour l'inspection de joints brases a recouvrement d'Inconel 625 avec comme metal d'apport du BNi-2. Dans un premiers temps un modele elements finis du joint a ete utilise pour simuler la propagation des ultrasons et optimiser les parametres d'inspection, la simulation a permis egalement de demontrer la faisabilite de la technique pour la detection de la quantite de phase fragile dans ce type de joints. Les parametres optimises sont la forme de signal d'excitation, sa frequence centrale et la direction d'excitation. Les simulations ont montre que l'energie de l'onde ultrasonore transmise a travers le joint aussi bien que celle reflechie, toutes deux extraites des courbes de dispersion, etaient proportionnelles a la quantite de phase fragile presente dans le joint et donc cette methode permet d'identifier la presence ou non d'une phase fragile dans ce type de joint. Ensuite des experimentations ont ete menees sur trois echantillons typiques presentant differentes quantites de phase fragile dans le joint, pour obtenir ce type d'echantillons differents temps de brasage ont ete utilises (1, 60 et 180 min). Pour cela un banc d'essai automatise a ete developpe permettant d'effectuer une analyse similaire a celle utilisee en simulation. Les parametres experimentaux ayant ete choisis en accord avec l'optimisation effectuee lors des simulations et apres une premiere optimisation du procede experimental. Finalement les resultats experimentaux confirment les resultats obtenus en simulation, et demontrent le potentiel de la methode developpee.

  1. Modelisation et simulation de pyrolyse de pneus usages dans des reacteurs de laboratoire et industriel

    Science.gov (United States)

    Lanteigne, Jean-Remi

    The present thesis covers an applied study on tire pyrolysis. The main objective is to develop tools to allow predicting the production and the quality of oil from tire pyrolysis. The first research objective consisted in modelling the kinetics of tires pyrolysis in a reactor, namely an industrial rotary drum operating in batch mode. A literature review performed later demonstrated that almost all kinetics models developed to represent tire pyrolysis could not represent the actual industrial process with enough accuracy. Among the families of kinetics models for pyrolysis, three have been identified: models with one single global reaction, models with multiple combined parallel reactions, and models with multiple parallel and series reactions. It was observed that these models show limitations. In the models with one single global reaction and with multiple parallels reactions, the production of each individual pyrolytic product cannot be predicted, but only for combined volatiles. Morevoer, the mass term in the kinetics refers to the final char weight (Winfinity) that varies with pyrolysis conditions, which yields less robust models. Also, despite the fact that models with multiple parallels and series reactions can predict the rate of production for each pyrolysis product, the selectivities are determined for operating temperatures instead of real mass temperatures, giving models for which parameters tuning is not adequate when used at the industrial scale. A new kinetics model has been developed, allowing predicting the rate of production of noncondensable gas, oil, and char from tire pyrolysis. The novelty of this model is the consideration of intrinsic selectivities for each product as a function of temperature. This hypothesis has been assumed valid considering that in the industrial pyrolysis process, pyrolysis kinetics is limiting. The developed model considers individual kinetics for each of the three pyrolytic products proportional to the global decomposition kinetics of pyrolysables. The simulation with data obtained in industrial operation showed the robustness of the model to predict with accuracy in transient regime, tires pyrolysis, with the help of model parameters obtained at laboratory scale, namely in regards of the trigger of production, the residence time of tires (dynamic production) and the amount of oil produced (cumulative yield). It is a novel way to model pyrolysis that could be extrapolated to new waste materials. The second objective of this doctoral research was to determine the evolution of specific tires specific heat during pyrolysis and the enthalpy of pyrolysis. The origin of this objective comes from a primary contradiction. With few exceptions, it is acknowledged that organic materials pyrolysis is globally an endothermic phenomenon. At the opposite, all experiments led with laboratory apparatuses such as DSC (Differential Scanning Calorimetry) showed exothermic peaks during dynamic experiments (constant heating rate). It has been confirmed by results obtained at the industrial scale, where no sign of exothermicity has been observed. The Hess Law has also confirmed these results, that globally, pyrolysis is indeed a completely endothermic process. An accurate energy balance is required to predict mass temperature during pyrolysis, this parameter being unbindable from kinetics. An advanced investigation of char first allowed demonstrating that specific heat of solids during pyrolysis decreases with increasing temperature until the weight loss peak is reached, around 400°C, and then starts increasing again. This observation, combined with the fact that the sample loses weight during pyrolysis is considered as the major cause of the apparition of an exothermic peak in laboratory scale experiments. That is, the control system of these apparatuses generates a bias and an unavoidable overheat of the samples producing this exothermic behavior. It would thus be an artifact. On the base of new data on the evolution of global specific heat during pyrolysis, a model of the energy balance has been developed at the industrial scale to determine the enthalpy of pyrolysis. The simulation has shown that a major part of the heat transferred to the pyrolized mass would make its temperature increase. Next, an enthalpy of pyrolysis dependent of weight loss was obtained. Finally, two other terms of enthalpy have been found, namely an enthalpy for the breakage of sulfur bridges and an enthalpy for the stabilization of char when conversion approaches completion. This research will have allowed establishing a novel general methodology to determine the enthalpy of pyrolysis. More particularly, new clarifications hasve been obtained in regards to the evolution of specific heat of solids during pyrolysis and new enthalpies of pyrolysis, all endothermic, could be obtained, in agreement with the theoretical expectations. The third research objective concerned the behavior of sulfur during tires pyrolysis. With as a premise that sulfur is an intrinsic contaminant of many types of waste, it is critical to clarify its fate during pyrolysis, in the present case for waste tires. It has been observed in the literature that some quantitative analyses had been presented, but generally, the mechanisms for the distribution of sulfur within the pyrolytic products remain unclear. Thus, it was then not possible to predict the transfer of sulfur to each of the tire pyrolysis products. The results taken form literature have been complemented with a series of TGA experiments followed by complete elemental analyses of the residual solids. Mass balances have been performed in order to characterize the distribution of elements within the three products (noncondensable gas, oil, and char). A novel parameter has been created during this research: the sulfur loss selectivity. This intrinsic selectivity is a prediction of the distribution of sulfur within the pyrolysis products as a function of temperature. Three phenomena has been identified that could affect the sulfur loss selectivity. First, the natural devolatilization of sulfur due to pyrolysis. Next, the sulfur devolatilization due to the desulfurization of the solid matrix by hydrogen and finally, the clustering of sulfur in the solid state due to metal sulfidation (zinc and iron). The results have shown that this selectivity reach a limit value of 1 when pyrolysis is limited by the kinetics and in the absence of metal. When the mass transfer is limiting at low temperature (<500°C) the selectivity will be greater than 1. At a temperature over 350°C with the presence of metals, the selectivity will be lower than 1. It is a useful tool for industrial pyrolysis processes, being a novel indicator for the distribution of contaminants during the pyrolysis of waste. A better comprehension of these mechanisms allows elaborating a better strategy when designing these industrial processes. For example, in light of this research, it could be preferable to pre-treat the tires at lower temperature to eliminate a significant part of sulfur before pyrolyzing them at high temperature. The resulting pyrolytic products would then necessitate a lighter purification post-treatment, being more efficient and more economical.

  2. Complete automation of nuclear reactors control; Automatisation complete de la conduite des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The use of nuclear reactor for energy production induces the installation of automatic control systems which need to be safe enough and can adapt to the industrial scale of energy production. These automatic control systems have to insure the constancy of power level and adjust the power produced to the energy demand. Two functioning modes are considered: nuclear plant connected up to other electric production systems as hydraulic or thermic plants or nuclear plants functioning on an independent network. For nuclear plants connected up with other production plants, xenon poisoning and operating cost lead to keep working at maximum power the nuclear reactors. Thus, the power modulation control system will not be considered and only start-up control, safety control, and control systems will be automated. For nuclear power plants working on an independent network, the power modulation control system is needed to economize fuel. It described the automated control system for reactors functioning with constant power: a power measurement system constituted of an ionization chamber and a direct-current amplifier will control the steadfastness of the power produced. For reactors functioning with variable power, the automated power control system will allow to change the power and maintain it steady with all the necessary safety and will control that working conditions under P{sub max} and R{sub max} (maximum power and maximum reactivity). The effects of temperature and xenon poisoning will also be discussed. Safety systems will be added to stop completely the functioning of the reactor if P{sub max} is reached. (M.P.)

  3. Liquid distribution in trickle-bed reactor; Distribution du liquide en reacteur a lit ruisselant

    Energy Technology Data Exchange (ETDEWEB)

    Marcandelli, C.; Wild, G. [Centre National de la Recherche Scientifique (CNRS-ENSIC), Lab. des Sciences du Genie Chimique, 54 - Nancy (France); Lamine, A.S. [CNRS-Universite de Paris-Nord, Lab. d' Ingenierie des Materiaux et des Hautes Pressions, 93 - Villetaneuse (France); Bernard, J.R. [Elf Antar France, Centre de Recherche Elf de Solaize, 69 - Solaize (France)

    2000-07-01

    The aim of this study is to develop techniques to qualify the efficiency of liquid distribution in trickle-bed reactors, using cold mockups. The experimental setup consists mainly in a 0.3-m-ID packed-bed column with three different plates used to vary the quality of inlet liquid distribution. Liquid distribution has been qualified using several techniques: global pressure drop measurements, global RTD (Residence-Time Distribution) of the liquid, local heat transfer probes, capacitance tomography, collector at the bottom of the reactor with nine equal zones. The bed pressure drop and the overall external liquid saturation decrease when the maldistribution increases; quantitative information is however difficult to obtain this way. Global RTD of the liquid allows quantifying of the average liquid distribution in the bed. The local thermal sensors give an indication of local liquid velocity and indicate possible local maldistribution of the liquid (scale mm) even when global distribution is good. Concerning the results obtained with the collector, a maldistribution index is defined ranging from 0 (ideal distribution) to 1 (worst possible distribution), and the influence of the different operating parameters (gas and liquid velocities, particle shape) is discussed. (authors)

  4. The hydraulics of the pressurized water reactors; L'hydraulique des reacteurs a eau pressurisee

    Energy Technology Data Exchange (ETDEWEB)

    Bouchter, J.C. [CEA Cadarache, SMET, 13 - Saint-Paul-lez-Durance (France); Barbier, D. [CEA/Grenoble, Dept. de Thermohydraulique et de Physique, DTP/SH2C, 38 (France); Caruso, A. [Electricite de France, Service Etudes et Projets Thermiques et Nucleaires, 75 - Paris (France)] [and others

    1999-07-02

    The SFEN organized, the 10 june 1999 at Paris, a meeting in the domain of the PWR hydraulics and in particular the hydraulic phenomena concerning the vessel and the vapor generators. The papers presented showed the importance of the industrial stakes with their associated phenomena: cores performance and safety with the more homogenous cooling system, the rods and the control rods wear, the temperature control, the fluid-structure interactions. A great part was also devoted to the progresses in the domain of the numerical simulation and the models and algorithms qualification. (A.L.B.)

  5. Fast neutron dosimetry in research reactors; Dosimetrie en neutrons rapides dans les reacteurs de recherche

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    This work chiefly concerns the measurement of fast neutron fluxes by means of threshold detectors. It is shown first that the cross sections to use for measurements by threshold detectors depend largely on the neutron spectrum, that is the position in which the measurement is performed. The spectrum is determined by calculation for several positions in the piles EL2 and EL3; from this can be deduced the cross-sections to be used for the measurements carried out in these positions. In the last part of the report, possible methods for the experimental determination of the spectrum are indicated. (author) [French] On etudie principalement la mesure des flux de neutrons rapides a l'aide de detecteurs a seuil. On montre d'abord que les sections efficaces a utiliser pour les mesures par detecteurs a seuil, dependent grandement du spectre des neutrons, c'est-a-dire de l'emplacement ou s'effectue la mesure. La determination du spectre est effectuee par le calcul pour plusieurs emplacements des piles EL2 et EL3; on en deduit les sections efficaces a utiliser pour les mesures effectuees a ces emplacements. Dans la derniere partie du rapport, on indique quelles methodes sont possibles pour la determination experimentale du spectre. (auteur)

  6. Validation d'un nouveau calcul de reference en evolution pour les reacteurs thermiques

    Science.gov (United States)

    Canbakan, Axel

    Resonance self-shielding calculations are an essential component of a deterministic lattice code calculation. Even if their aim is to correct the cross sections deviation, they introduce a non negligible error in evaluated parameters such as the flux. Until now, French studies for light water reactors are based on effective reaction rates obtained using an equivalence in dilution technique. With the increase of computing capacities, this method starts to show its limits in precision and can be replaced by a subgroup method. Originally used for fast neutron reactor calculations, the subgroup method has many advantages such as using an exact slowing down equation. The aim of this thesis is to suggest a validation as precise as possible without burnup, and then with an isotopic depletion study for the subgroup method. In the end, users interested in implementing a subgroup method in their scheme for Pressurized Water Reactors can rely on this thesis to justify their modelization choices. Moreover, other parameters are validated to suggest a new reference scheme for fast execution and precise results. These new techniques are implemented in the French lattice scheme SHEM-MOC, composed of a Method Of Characteristics flux calculation and a SHEM-like 281-energy group mesh. First, the libraries processed by the CEA are compared. Then, this thesis suggests the most suitable energetic discretization for a subgroup method. Finally, other techniques such as the representation of the anisotropy of the scattering sources and the spatial representation of the source in the MOC calculation are studied. A DRAGON5 scheme is also validated as it shows interesting elements: the DRAGON5 subgroup method is run with a 295-eenergy group mesh (compared to 361 groups for APOLLO2). There are two reasons to use this code. The first involves offering a new reference lattice scheme for Pressurized Water Reactors to DRAGON5 users. The second is to study parameters that are not available in APOLLO2 such as self-shielding in a temperature gradient and using a flux calculation based on MOC in the self-shielding part of the simulation. This thesis concludes that: (1) The subgroup method is at least more precise than a technique based on effective reaction rates, only if we use a 361-energy group mesh; (2) MOC with a linear source in a geometrical region gives better results than a MOC with a constant model. A moderator discretization is compulsory; (3) A P3 choc law is satisfactory, ensuring a coherence with 2D full core calculations; (4) SHEM295 is viable with a Subgroup Projection Method for DRAGON5.

  7. Hybrid reactors: recent progress of a demonstration pilot; Reacteurs hybrides: avancees recentes pour un demonstrateur

    Energy Technology Data Exchange (ETDEWEB)

    Billebaud, Annick [Laboratoire de Physique Subatomique et de Cosmologie IN2P3-CNRS/UJF/INPG, 53 av. des Martyrs, 38026 Grenoble Cedex (France)

    2006-12-15

    Accelerator driven sub-critical reactors are subject of many research programmes since more than ten years, with the aim of testing the feasibility of the concept as well as their efficiency as a transmutation tool. Several key points like the accelerator, the spallation target, or neutronics in a subcritical medium were investigated extensively these last years, allowing for technological choices and the design of a low power European demonstration ADS (a few tens of MWth). Programmes dedicated to subcritical reactor piloting proposed a monitoring procedure to be validated in forthcoming experiments. Accelerator R and D provided the design of a LINAC for an ADS and research work on accelerator reliability is going on. A spallation target was operated at PSI and the design of a windowless target is in progress. All this research work converges to the design of a European demonstration ADS, the ETD/XT-ADS, which could be the Belgian MYRRHA project. (author)

  8. Calculus of a reactor VVER-1000 benchmark; Calcul d'un benchmark de reacteur VVER-1000

    Energy Technology Data Exchange (ETDEWEB)

    Dourougie, C

    1998-07-01

    In the framework of the FMDP (Fissile Materials Disposition Program between the US and Russian, a benchmark was tested. The pin cells contain low enriched uranium (LEU) and mixed oxide fuels (MOX). The calculations are done for a wide range of temperatures and solute boron concentrations, in accidental conditions. (A.L.B.)

  9. Investigations of the chemical states of carrier-free phosphorus-32 as extracted into water from pile-irradiated sulphur; Recherches sur les etats chimiques du phosphore-32 sans entraineur obtenu par extraction aqueuse a partir de soufre irradie dans un reacteur; Issledovanie khimicheskogo sostoyaniya svobodnogo ot nositelya fosfora-32 pri izvlechenii ego v vodu iz obluchennoj v yadernom reaktore sery; Estudio de los estados quimicos del fosforo-32 libre de portador que se obtiene por extraccion acuosa del azufre irradiado en un reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dahl, J B; Birkelund, O R [Institutt for Atomenergi, Kjeller, Lillestrom (Norway)

    1962-01-15

    One of the methods of producing carrier free phosphorus-32 today is by extraction into water from pile-irradiated sulphur. The present work gives information concerning the chemical states of P{sup 32} in aqueous solutions at different steps of the routine production-process. The variation in the chemical state of P{sup 32} compounds in the final product has also been examined as a function of storage time. P{sup 32} bound as orthophosphate was found to be the main component. During the chemical processing, the amount of orthophosphate increased from about 70% at the beginning of the extraction to about 98 % in the final carrier-free P{sup 32} product. The residual amount consisted of a mixture of pyro-, tri-, tetra-, and other long-chain polyphosphates (number of P {>=} 5). No metaphosphates (ring-formed) were found in the solutions during production and storage. The results indicate that the polyphosphorus compounds were formed in the target material during irradiation. Special attention was paid to the adsorption of carrier-free P{sup 32} compounds to glassware under the existing experimental conditions. (author) [French] L'une des methodes employee a l'heure actuelle pour obtenir du phosphore-32 sans entraineur consiste a l'extraire dans l'eau a partir de soufre irradie dans un reacteur. Les auteurs donnent des indications sur l'etat chimique du phosphore-32 dans des solutions aqueuses, a differentes etapes du processus de preparation courant. Us examinent aussi les changements de l'etat chimique des composes du phosphore-32 dans le produit final en fonction de la duree de stockage. On a constate que le {sup 32}P combine sous forme d'orthophosphate etait le principal composant. Au cours du traitement chimique, la teneur en orthophosphate est passee d'environ 70% au debut de l'extraction a environ 98% lors de l'obtention du produit final sans entraineur. Le reste etait constitue d'un melange de pyro-, tri-, tetra- et autres polyphosphates a chaine longue (P

  10. African arts between curios, antiquities, and avant-garde at the Maison Brummer, Paris (1908-1914

    Directory of Open Access Journals (Sweden)

    Yaëlle Biro

    2015-06-01

    Full Text Available Before World War I, Hungarian-born art dealer Joseph Brummer (1883-1947 developed in Paris an extensive trade network through talented salesmanship and brilliant art selections. Helped by his brothers Imre (1889-1928 and Ernest (1891-1964, he promoted original art-forms that were not previously integral to the Western art canon. Juxtaposing works from Africa with art of Medieval Europe, Ancient Greece and Rome, as well as creations by living artists, the Maison Brummer blurred the boundaries that existed between these fields of collecting and was instrumental in awakening the interest of many collectors and museum professionals. Despite the Brummer brothers’ extensive international dealership and the fame of the collections they helped build, only recently has in depth scholarship begun to explore their activities. Using an array of unpublished archival documents and little-examined written accounts, this paper focuses on the early history of the Maison Brummer before its expansion to New York in 1914.

  11. La rondelle au bison d'enlène (Montesquieu-Avantès, Ariège

    Directory of Open Access Journals (Sweden)

    R. BÉGOUËN

    2009-10-01

    Full Text Available Une rondelle perforée en os, hors du commun par son décor, a été mise au jour dans une couche du Magdalénien moyen de la grotte d'Enléne. Sur la moitié d'une face un bison entier a été gravé. L'autre face présente un décor beaucoup plus fruste et n'était vraisemblablement pas destinée a étre vue. Cette rondelle, caractéristique du Magdalénien moyen, est replacée par les auteurs dans le contexte des objets de méme nature connus en France et dans les Asturies.

  12. Recherche et ingénierie au service des acteurs de l'assainissement - Avant-propos

    Directory of Open Access Journals (Sweden)

    HEDUIT, Alain

    2012-12-01

    Full Text Available L'épuration des eaux usées domestiques est un point clé de la protection des milieux aquatiques. L’Union européenne, à travers la directive relative au traitement des eaux résiduaires urbaines (DERU, 1991 et la directive cadre sur l’eau (DCE, 2000, a imposé aux États membres des obligations en termes de traitement des eaux usées et de qualité des milieux aquatiques. Ces exigences ont nécessité des efforts financiers considérables dans le domaine de l’assainissement. Lire la suite

  13. A Fascination with Folk Art. Modernism and the Avant-Garde in Munich, Prague and Moscow around 1913

    Czech Academy of Sciences Publication Activity Database

    Winter, Tomáš

    2016-01-01

    Roč. 64, 3/4 (2016), s. 240-253 ISSN 0049-5123 R&D Projects: GA ČR GA15-07456S Institutional support: RVO:68378033 Keywords : primitivism * cosmopolitanism * 20th-century art Subject RIV: AL - Art, Architecture, Cultural Heritage

  14. Reflection tomography from pre-stack migrated images; Tomographie de reflexion a partir des images migrees avant addition

    Energy Technology Data Exchange (ETDEWEB)

    Adler, F

    1996-10-29

    The application of reflection tomography to data from complex geological structures is very interesting in the hydrocarbons exploration. Indeed, it contributes to localize the hydrocarbons potential traps. The used reflection tomography method is faced with two major difficulties. Travel time picking is difficult or impossible in seismic time sections. The processing of multiple arrival travel times needs an adequate formulation of reflection tomography. In order to solve the first problem, we adopt the approach of the SMART (Sequential Migration Aided Reflection Tomography) method which is an original method for the implementation of migration velocity analysis. The velocity model is automatically calculated by reflection tomography. The kinematic data set for reflection tomography is constructed from pre-stack depth-migrated images that are interpreted in the chosen migration configuration. For the implementation of the SMART method in the common-offset domain, we propose an original formulation of reflection tomography that takes multiple arrival travel times, which are calculated from common-offset migrated images, into account. In this new formulation, we look for a model such that a modelling, which consists in shooting in this model from the source locations with some ray parameters at the source, matches some emergence conditions: for each offset, the rays emerge at the receiver locations (given by the offset) with the same travel times and the same travel time slopes as observed in the associated common-offset section. These conditions constitute the kinematic data set for tomographic inversion. The common-offset travel time slope is the difference between the ray parameter at the receiver and the ray parameter at the source. Therefore, the ray parameter at the source is an unknown and has to be determined together with the model parameters during inversion. (author)

  15. Les peintures murales de l’église de Mălâncrav. Notes avant la restauration

    Directory of Open Access Journals (Sweden)

    Dana Jenei

    2015-12-01

    Full Text Available The two distinct ensembles of mural paintings of the church, from the nave and sanctuary have permanently been in the attention of the researchers, but their study cannot be considered completed, because thorough parament studies and archaeological investigations, indispensable to clarify the phases of the monument, have not yet been achieved. However, the research works in the years 2001-2002 and 2013 brought to light new data that substantially enrich the information and contribute to a better understanding of the evolution of the monument. In 2001, the investigations showed, among others, that except the frescoes on the north, there are no other painted zones inside the nave, while in 2013 the restorers have revealed the existence of the register VI of paintings on the pillars, which mostly are under the lime. The art historian’s research contributes with the identification of several scenes and details unknown so far, such as the figures of Saints James, Sebastian, Anthony and Peter, or the jesters next to Herod and Pilate in the Christological Cycle. There was also detected the contribution of three distinct teams who have worked, “soon after 1350”. The paintings in the nave illustrate, along with the ensemble in the sanctuary, the various artistic trends subsumed to the Gothic painting from the fourteenth century and due to the munificence of successive generations of the noble family Apa, lords at Mălâncrav since 1258. The graffiti on the painted surface of the apse, transcribed by Victor Roth in several versions, contains the year 1404/1405, considered as a terminus ante quem for the achievement of the painting, and the name Nicolaus, the most important representative of the family and the presumptive donor of the paintings. Gernot Nussbächer “shows” that the inscription is not of “Hic fuit” type and the script is a few decades later, presumably recording an event that took place that year. The obvious difference of the architectonic and spatial expression between the basilica and the Gothic choir decorated in the elaborated forms of “international style” was highlighted by the researchers and Vasile Drăguț’s theory concerning the rebuilding of the sanctuary in the late fourteenth century remains relevant, being sustained by our observation on the different heights of the dados, lower in the choir than in the church, as well as the compaction of masonry on the north, hidden by the first buttress. The scientific investigations from 2001–2002 also showed that a “Baroque restoration” or other repaintings in the choir ensemble didn’t exist, while the most important information after removing the lime in 2013 is related to the identification of certain figures, such as “Johel Propheta” and, in the newly stripped area, St. Elizabeth of Thuringia. Near the right margin of the Crucifixion appeared the damaged fragments of the Laying into the Tomb and, hypothetically, the figure of the donor. The style of the Master of the Mălâncrav sanctuary and of his team, derived from the illuminated manuscripts from the Court in Prague, can also be found in the newly discovered representations from Ighișu Nou and in the fragments of the Dârjiu Crucifixion, extracted and preserved at Budapest Szépművészeti Múzeum.

  16. Trois observations de néphrome mésoblastique avant l'âge de 6 mois

    African Journals Online (AJOL)

    L. Sahnoun

    2005;12:561–3. [12] Malone PS, Ransley RA, Cook T. Congenital mesoblastic nephroma, renin production and hypertension. Journal of pediatric surgery Juin. 1989;24:599–600. [13] Oren F M ET Thomas F K. Hypperreninemia and congenital mesoblas- tic nephroma: case report and review of the literature. Urology (2000).

  17. Divine Horsemen de Maya Deren: una visión avant-garde del vudú haitiano

    Directory of Open Access Journals (Sweden)

    Isabel De León Olivares

    2017-01-01

    Full Text Available Maya Deren (1917-1961 fue una cineasta de mediados del siglo XX que llegó a ser considerada la “madre” del cine experimental y de vanguardia de los Estados Unidos, gracias a filmes como Meshes of the Afternoon (1943, At Land (1944, Ritual in Transfigured Time (1946. Entre 1947 y 1954, esta artista realizó cuatro viajes a Haití que le permitieron adentrarse en el conocimiento de la religión vudú, lo cual dio como resultado diversos trabajos. En primer lugar, un libro sobre la religión haitiana titulado Divine Horsemen: The Living Gods of Haiti, publicado en 1953, y, en segundo lugar, un material fílmico de casi 9 horas que, si bien Deren nunca dio a conocer en vida, salió a la luz pública en 1981 a manera de documental. En este trabajo se examinan algunas de las representaciones e interpretaciones que sobre el vudú construyó y legó esta cineasta pionera , en función de las cua- les se inscribió dentro de una corriente más amplia de revalorización del vudú que tuvo en el libro Ansi parla l’Oncle (1928, del escritor haitiano Jean Price-Mars, un momento fundacional.

  18. La bande dessinée, nouveau continent des études américaines ? Avant-propos

    Directory of Open Access Journals (Sweden)

    Jean-Paul Gabilliet

    2010-09-01

    Full Text Available Lors d’une table ronde qui s’est tenue en juillet 2009 pendant la San Diego Comic-Con (équivalent américain du Festival international de la bande dessinée d’Angoulême, Henry Jenkins, professeur de sciences de la communication à University of Southern California, a salué le processus actuel de construction des Comic Studies comme domaine de recherche et d’enseignement inter-disciplinaire et souligné la pluralité des devenirs qui pouvaient s’ouvrir devant lui (http://henryjenkins.org/2009/07/t...

  19. Gabriele Veneziano : "La physique moderne doit dépasser Einstein et explorer l'avant-Big Bang"

    CERN Multimedia

    Deschamps, Pascale-Marie

    2004-01-01

    Interview with Gabriele Veneziana: in search of the infinitesimally small and infinitesimally large, the Standard Model of elementary particles and Einstein's general relativity are not enough to explain the universe. The "visible" matter predicted by the Standard Model represents only 5% of the energy of the Universe, the dark "invisible" matter constitutes 25 to 30%. Therefore 65 to 70 % of something else is missing. String theory calls into question all that one knows of the primordial universe formulated by the Standard Model (4 pages)

  20. High-Temperature Gas-Cooled Reactor Critical Experiment and its Application to Thorium Absorption Rates; Experience Critique pour l'Etude d'un Reacteur a Haute Temperature, Refroidi par un Gaz et son Application a la Determination des Taux d'Absorption du Thorium; Kriticheskij opyt, postavlennyj na vysokotemperaturnom reaktore s gazovym okhlazhdeniem, i primenenie ego dlya opredeleniya stepeni pogloshcheniya toriya; Experimento Critico Efectuado en un Reactor de Elevada Temperatura Refrigerado por Gas y su Aplicacion para Calcular los Indices de Absorcion del Torio

    Energy Technology Data Exchange (ETDEWEB)

    Bardes, R. G.; Brown, J. R.; Drake, M. K.; Fischer, P. U.; Pound, D. C.; Sampson, J. B.; Stewart, H. B. [General Dynamics Corporation,San Diego, CA (United States)

    1964-04-15

    the fact that the thorium is dispersed in graphite and the usual cadmium-ratio technique is difficult to apply. Comparison of experimental and theoretical results shows excellent agreement over a range of variables. In addition, the results of both activation and reactivity measurements of Doppler coefficient are in agreement, a fact which is felt to be significant in view of the disparity between results from these two techniques in the literature. (author) [French] Lors de l'etude du reacteur HTGR a haute temperature refroidi par un gaz, et de son premier prototype a Peach Bottom, la General Atomic Division de la societe General Dynamics a decide qu'il fallait proceder a une experience critique pour obtenir certaines donnees d'entree necessaires pour l'analyse nucleaire. Aux fins de l'etude nucleaire theorique, les besoins particuliers en donnees d'entree relatives aux absorptions par le thorium ont amene les ingenieurs a concevoir un assemblage experimental critique compose d'un reseau central entoure d*une region tampon et d'une region de commande. Ce type.d'assemblage, dans lequel on peut creer le spectre a mesurer dans le reseau central relativement petit ayant la geometrie voulue, permet d'obtenir des donnees d'entree tres diverses pour les etudes de projets nouveaux, au point de vue de l'analyse nucleaire. Le memoire indique les avantages particuliers que presente cette methode par rapport a celle qiu consiste a construire une maquette, ainsi que le role de la theorie pour determiner quelles experiences sont le plus utiles et comment utiliser ensuite ces experiences dans la verification des procedes d'etude. Les auteurs ont mis au point deux methodes relativement nouvelles qui peuvent etre utilisees avec l'assemblage decrit ci-dessus: une methode d'oscillation de la reactivite pour determiner le coefficient Doppler pour le thorium; une methode d'activation pour determiner a la fois l'integrale de resonance pour le thorium disperse dans le graphite et ses

  1. Reactive turbulent flow CFD study in supercritical water oxidation process: application to a stirred double shell reactor; Etude par simulation numerique des ecoulements turbulents reactifs dans les reacteurs d'oxydation hydrothermale: application a un reacteur agite double enveloppe

    Energy Technology Data Exchange (ETDEWEB)

    Moussiere, S

    2006-12-15

    Supercritical water oxidation is an innovative process to treat organic liquid waste which uses supercritical water properties to mix efficiency the oxidant and the organic compounds. The reactor is a stirred double shell reactor. In the step of adaptation to nuclear constraints, the computational fluid dynamic modeling is a good tool to know required temperature field in the reactor for safety analysis. Firstly, the CFD modeling of tubular reactor confirms the hypothesis of an incompressible fluid and the use of k-w turbulence model to represent the hydrodynamic. Moreover, the EDC model is as efficiency as the kinetic to compute the reaction rate in this reactor. Secondly, the study of turbulent flow in the double shell reactor confirms the use of 2D axisymmetric geometry instead of 3D geometry to compute heat transfer. Moreover, this study reports that water-air mixing is not in single phase. The reactive turbulent flow is well represented by EDC model after adaptation of initial conditions. The reaction rate in supercritical water oxidation reactor is mainly controlled by the mixing. (author)

  2. Compression-absorption (resorption) refrigerating machinery. Modeling of reactors; Machine frigorifique a compression-absorption (resorption). Modelisation des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Lottin, O; Feidt, M; Benelmir, R [LEMTA-UHP Nancy-1, 54 - Vandoeuvre-les-Nancy (France)

    1998-12-31

    This paper is a series of transparencies presenting a comparative study of the thermal performances of different types of refrigerating machineries: di-thermal with vapor compression, tri-thermal with moto-compressor, with ejector, with free piston, adsorption-type, resorption-type, absorption-type, compression-absorption-type. A prototype of ammonia-water compression-absorption heat pump is presented and modeled. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  4. Compression-absorption (resorption) refrigerating machinery. Modeling of reactors; Machine frigorifique a compression-absorption (resorption). Modelisation des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Lottin, O.; Feidt, M.; Benelmir, R. [LEMTA-UHP Nancy-1, 54 - Vandoeuvre-les-Nancy (France)

    1997-12-31

    This paper is a series of transparencies presenting a comparative study of the thermal performances of different types of refrigerating machineries: di-thermal with vapor compression, tri-thermal with moto-compressor, with ejector, with free piston, adsorption-type, resorption-type, absorption-type, compression-absorption-type. A prototype of ammonia-water compression-absorption heat pump is presented and modeled. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Wohleber, X

    1997-11-17

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-06-01

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

  7. The under-critical reactors physics for the hybrid systems; La physique des reacteurs sous-critiques des systemes hybrides

    Energy Technology Data Exchange (ETDEWEB)

    Schapira, J P [Institut de Physique Nucleaire, IN2P3/CNRS 91 - Orsay (France); Vergnes, J [Electricite de France, EDF, Direction des Etudes et Recherches, 75 - Paris (France); Zaetta, A [CEA/Saclay, Direction des Reacteurs Nucleaires, DRN, 91 - Gif-sur-Yvette (France); and others

    1998-03-12

    This day, organized by the SFEN, took place at Paris the 12 march 1998. Nine papers were presented. They take stock on the hybrid systems and more specifically the under-critical reactors. One of the major current preoccupation of nuclear industry is the problems of the increase of radioactive wastes produced in the plants and the destruction of the present stocks. To solve these problems a solution is the utilisation of hybrid systems: the coupling of a particle acceleration to an under-critical reactor. Historical aspects, advantages and performances of such hybrid reactors are presented in general papers. More technical papers are devoted to the spallation, the MUSE and the TARC experiments. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Lelievre, F

    1998-12-11

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

  9. Presence de Carbone-13 dans les elements combustibles de type (U,Pu)O 2 irradies en reacteur rapide

    Science.gov (United States)

    Kryger, Bernard; Hagemann, Robert

    1982-06-01

    Du carbone-13 produit par la réaction de capture neutronique 168O + 10n → 136C + 42He se forme dans les combustibles de type oxyde irradiés en neutrons rapides. Cette réaction, dont le seuil d'énergie se situe à 2.35 MeV, conduit à la formation d'une quantité de carbone-13 qui peut varier notablement suivant le spectre neutronique du réacteur (entre 20 et 40 × 10 -6g 13C/g (U,Pu)O 2 pour une fluence de 2 × 10 23 n/cm 2). DES mesures effectuées sur le combustible et la gaine par spectrométrie de masse après irradiation montrent qu'une fraction égale ou supérieure à la moitié du carbone-13 produit dans l'oxyde peut être transférée dans la gaine. Un tel comportement nous fait considérer le carbone-13 comme un véritable marqueur du carbone plus généralement contenu dans l'oxyde et, à ce titre, la détection de cet isotope devrait contribuer à élucider tout particulièrement les mécanismes de carburation de la gaine par les combustibles (U,Pu)O 2 des réacteurs surgénérateurs.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  11. Experiments prior to construction of the Rapsodie reactor (1962); Experiences preliminaires a la construction de la pile rapsodie (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Before proceeding to the construction of the various reactor components described in the paper 'Fast Breeder Reactor Rapsodie', many experimental studies of a hydraulic, thermal and mechanical character have been carried out, or are under consideration, to test the validity of the principles adopted in the Preliminary Project. This paper deals with the most important of these: 1. Studies of coolant circuit components: sodium pumps (mechanical or electromagnetic), Na-NaK and NaK ir heat exchangers, measuring instruments (flow rates, temperatures), sodium purification circuits, etc. 2. Studies in cooling of fuel and fertile assemblies: a) study of the sodium cooling carried out by means of hydraulic mockups (scale of 1: 1 or over) reproducing the flow of the coolant fluid in the piping, upstream from and inside the fuel and fertile elements. b) study of the cooling by gas and by immersion in lead, employed during handling and storage operations. 3. Studies of special reactor devices: fusible rotating linkage, parts of the control rod mechanisms. 4. Study of the reactor block and coolant circuits as a whole. This study is to begin at the end of the year. The mock-up, now nearing completion, reproduces on a scale of 1: 1 the installation provided in the Preliminary Project and includes: the reactor block, to which is connected a high flow ate sodium circuit, permitting of long-term tests and thermal shocks, and also, a control rod testing circuit; complete installation of the 1 MW and 10 MW coolant circuits, the performances of which it will be possible to check under various operational conditions. 5. A safety study carried out on a 3: 10 scale mock p comprising the whole of the reactor block and shielding, with the object of limiting the effects of any accidental liberation of energy of an explosive character. (authors) [French] Avant d'entreprendre la realisation des divers elements du reacteur decrit dans le rapport 'Reacteur rapide surregenerateur RAPSODIE

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-15

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

  13. An avant-garde professorship of neurobiology in education: Christofredo Jakob (1866-1956) and the 1920s lead of the National University of La Plata, Argentina.

    Science.gov (United States)

    Théodoridou, Zoe D; Koutsoklenis, Athanasios; del Cerro, Manuel; Triarhou, Lazaros C

    2013-01-01

    The interdisciplinary trend in "Mind, Brain, and Education" has witnessed dynamic international growth in recent years. Yet, it remains little known that the National University of La Plata in Argentina probably holds the historical precedent as the world's first institution of higher education that formally included neurobiology in the curriculum of an educational department, having done so as early as 1922. The responsibility of teaching neurobiology to educators was assigned to Professor Christofredo Jakob (1866-1956). In the present article, we highlight Jakob's emphasis on interdisciplinarity and, in particular, on the neuroscientific foundations of education, including special education.

  14. L’agriculture en Arabie du Sud avant l’Islam South Arabian Pre-Islamic Agriculture: Piecing Together Ancient Landscapes & Agricultural Systems

    Directory of Open Access Journals (Sweden)

    Julien Charbonnier

    2008-04-01

    Full Text Available Le présent article vise à reconstituer les différents systèmes de culture d’Arabie du sud antique. Pour ce faire, les études archéobotaniques sont mises en perspective avec les recherches sur les paysages et les techniques de culture anciennes. Il apparaît ainsi, qu’entre l’âge du Bronze et la période sudarabique, le Yémen n’a cessé de s’enrichir de l’arrivée de nouvelles plantes, en provenance de Proche-Orient, de l’Afrique et du Monde indien. Leurs capacités propres et les nouvelles combinaisons dont elles offraient l’opportunité ont permis à l’homme de diversifier les systèmes de culture afin de tirer au maximum parti des terres et d’être plus flexible face aux altérations du climat et de l’environnement.This paper aims at recognizing and understanding the various agro-systems of the ancient South Arabia. Archaeobotanical data are confronted with studies concerning pre-Islamic landscapes and agricultural techniques. It appears that, during the Bronze Age and the South Arabian period, new cultivars, coming from the Near-East, Africa and India, have regularly reached the region. Because of their own specificities and of the new associations they permitted, these plants have allowed Man to enrich agro-systems and to be more flexible in order to cope with climatic and environmental changes.

  15. La poésie de Danielle Collobert et Sophie Podolski. Entre lucidité et folie, les ultimes soubresauts de la modernité avant son suicide

    Directory of Open Access Journals (Sweden)

    Martine Renouprez

    2017-11-01

    Full Text Available The end of the twentieth century has been marked y the failure of a critical reasoning usher d in by Enlightenment. The condemning of all ideologies has given way to widespread and generalized cynicism within a society imbued with deception. We shall first of all analyze what has caused this twilight of Modernity to later on evidence that the progressive depersonalization and un-reality, inscribed with poetry of Danielle Collobert, are the reflection of a schizoid society. As a buffer against this cynical power, Sophie Podolski adopts the insolent laugh of the fool appropriated from a Kunica tradition initiated by Diogenes and which extends to Thyl Ulenspiegel. La fin du XXe siècle accuse un échec de la raison critique issue de l’esprit des Lumières : la dénonciation des idéologies a fait place à un cynisme diffus et généralisé au sein d’une société marquée par l’imposture. Nous analysons d’abord ce qui a conduit au crépuscule de la Modernité pour démontrer ensuite que la déréalisation et la dépersonnalisation progressive, inscrites dans la poésie de Danielle Collobert, sont le reflet de la schize sociétale. Face au pouvoir cynique, Sophie Podolski adopte, quant à elle, le rire frondeur du « fou » de la tradition kunique, de Diogène à Thyl Ulenspiegel.

  16. Line 400000 volts Marlenheim-Vigy: step of summary draft; Liaison 400000 volts marlenheim-vigy: etape d'avant projet sommaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The rebuilding of the line 225000 volts by a 400000 volts line, between Marlenheim and Vigy, will allow to reinforce energy exchanges between Alsace and Lorraine, to reassure the city of Strasbourg and at long dated, assure the european train TGV-east alimentation. (A.L.B.)

  17. Using hydro power at the Chiblins Mill - Feasibility study; Etude d'avant-projet PCH Moulin de Chiblins - Rapport final

    Energy Technology Data Exchange (ETDEWEB)

    Ramseyer, P.

    2008-06-15

    Today, the Chiblins Mill in Gingins, Switzerland is the location of an agricultural machinery museum and is also used for meetings and festivals. The old water wheel from the 19{sup th} century has no mechanical function any longer. The idea of the current project is to use the 6 m high water fall on the joined rivers Asse and Bam to generate electricity. A 10 kW turbine could be installed and produce about 75,000 kWh/y. The technical and economical feasibility of the project is demonstrated. The recommended next step is the request of a water use license.

  18. Les armes du dépôt du Cailar (Gard, France IIIe siècle avant notre ère

    Directory of Open Access Journals (Sweden)

    Cantuel, Jean

    2010-12-01

    Full Text Available A great amount of different types of weapons has been found in the archaeological site of Le Cailar (Gard, France. This proto-historic settlement is located in the lower Rhône valley and was founded in the middle, or maybe at the beginnings, of the 6th century BC. Le Cailar was an important port of trade dealing with different Mediterranean products, mainly wine and pottery. The relation with the Phocean city of Massalia was certainly strong. During the 3rd century BC, a vast sacred area was created along the city walls. In this space, numerous weapons, other metallic objects and fragments of human skull bones (cut-off heads, but also coins and fragments of animal bones and pottery have been found. These elements shed light on ritual practices related to war during the 3rd century BC.Un gran número de distintos tipos de armas ha sido hallado en el yacimiento arqueológico de Le Cailar (Gard, Francia. Este asentamiento protohistórico está ubicado en el valle bajo del Ródano y fue fundado a mediados, o quizás a inicios, del siglo VI a.C. Le Cailar fue un importante puerto de comercio donde están atestiguadas distintas producciones mediterráneas, en especial vino y cerámica. La relación con la ciudad focense de Massalia fue seguramente intensa. Durante el siglo III a.C., un vasto espacio sagrado fue creado a lo largo de las murallas. En este espacio han sido halladas numerosas armas, otros objetos metálicos y fragmentos de calaveras humanas (cabezas cortadas, así como monedas y fragmentos de huesos animales y de cerámica. Estos elementos arrojan luz sobre las prácticas rituales relacionadas con la guerra durante el siglo III a.C. [fr] Différents types d’armes ont été retrouvés en grand nombre sur le site du Cailar (Gard, France. Cet établissement protohistorique est situé dans la basse vallée du Rhône et fut fondé au milieu, ou peut-être au début, du VIe s. a.C. Le Cailar fut un important port de commerce où sont attestés différentes productions d’origine méditerranéennes, comme le vin et la céramique. Les relations avec la cité phocéenne de Massalia furent probablement importantes. Au cours du IIIe s. a.C., une vaste aire sacrée fut créée le long des murailles. A l’intérieur de cet espace ont été retrouvés des armes et divers objets métalliques, ainsi que des fragments de crânes humains (têtes coupées, des monnaies et des fragments de céramiques et d’os animaux. Ces éléments permettent d’éclairer les pratiques rituelles liées à la guerre au IIIe s. a.C.

  19. The 'Pontareuse' small hydropower station in Boudry, Switzerland; Avant-projet. Petite centrale hydroelectrique de Boudry 'Pontareuse'

    Energy Technology Data Exchange (ETDEWEB)

    Hausmann, M.

    2007-05-15

    This illustrated report for the Swiss Federal Office of Energy (SFOE) describes work done in 2007 on the preliminary project for a small hydropower project to be realised in Boudry, Switzerland. The goal of this project is to take advantage of the hydro power of the river Areuse using an existing artificial weir which has been built and renovated as part of several river corrections in the past. Three variants for the construction of the proposed hydropower installation with a maximum projected power rating of 391 kilowatts are presented in detail. Options for the realisation of a fish pass to enable fish to pass the weir are also discussed. Figures are presented on the financial viability of the project which, although low, could however become interesting when the expected tariff changes in connection with the new Swiss legislation on electrical energy supply are considered.

  20. Retrofitting of the small hydro electric scheme 'Moulin de Bavois' - Feasibility study; Rehabilitation du Moulin de Bavois. Etude d'avant-projet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-15

    This illustrated final report for the Swiss Federal Office of Energy (SFOE) is a feasibility study of the retrofitting of the small hydro electric scheme 'Moulin de Bavois' located in Bavois on the Talent river, Switzerland. The existing scheme uses a 12 m water fall and its power amounts to about 10 kW. After retrofitting, based on a future new water-use concession, the maximum electric power produced should be 172 kW, generating 531 MWh/y, 65% of which in the wintertime. New weir and penstock are foreseen as is an axial Kaplan turbine and a reliable water cleaning device. The Talent river flows in the woods. Electricity production cost is estimated to be 0.214 CHF/kWh.

  1. Retrofitting of the hydro-power installation of Vicques, Switzerland; Rehabilitation de la centrale de Vicques, Emile Aebin SA. Etude d'avant-projet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-04-15

    This technical report for the Swiss Federal Office of Energy (SFOE) reports on work involved in obtaining a new concession for the use of the water in the mill canal in Vicques, Switzerland on the Scheulte river. The author states that the existing concession for use is not optimal and should be optimised. A window of opportunity exists as a new river protection law requires a higher residual water flow rate and the creation of a fish passage facility. The paper discusses how the production of electrical energy could be doubled. The existing installation is described. Details of existing conduits and the installed power generator are presented. The measures proposed for the renewal of the hydro-power plant are described. An annex includes a copy of the construction plans.

  2. Etude du comportement sous charges laterales des ossatures de beton arme avec murs de remplissage de maconnerie, construites avant les annees 1960

    Science.gov (United States)

    Lefebvre, Karine

    Reinforced concrete structures with unreinforced masonry infills (BMR) are considered vulnerable to earthquakes. Under seismic actions, infills could fail (causing injuries or death) and cause damages to columns. In Quebec and Canada, most of BMR structures have been constructed prior to the introduction of modern seismic design codes raising question on the contribution of the infill to the structure lateral resistance. The aim of this thesis is to improve modelling technique of BMR structures built in Quebec between 1915 and 1960. This type of structures is found in hospitals or schools buildings, which must comply with some post-earthquake functionality requirements. They could also be residential or office buildings. Actually, practicing engineers usually calculate seismic capacity of BMR structures without considering the infill's structural contribution to the lateral resistance. Yet, this contribution should not be omitted. The first part of the thesis investigates the construction techniques and material properties of the old BMR structures in the Province. The results are the material properties (concrete, reinforcing steel, brick, terra cotta tile, and mortar) and the characteristics of the assemblies (wall section, reinforcement details…). The second part of the thesis presents the results of series of parametric analyses to identify among modelling and geometric parameters, which ones are the most influent on the lateral load response (rigidity, fundamental period, normal modes). Linear and modal analyses were performed. The most influent parameters identified are: number of storeys, number of bays, bay's width, soft storey, openings, upper storeys modelized (instead of being replaced by punctual loads) and the modelization technique of infills panels (strut or shell). Nonlinear static analyses have been performed to identify the most influent parameters to be considered for evaluating the lateral resistance, the capacity (load / displacement) and the yielding sequence (beam versus columns versus infills). The identified parameters are the presence of the infills, the openings and the geometric characteristics of the models (number of storeys and number of bays). One important contribution of this work is the development of an equivalent strut model to represent the action of the infill. The model could be easily implemented in standard analysis software. A central axial hinge reproducing the nonlinear behaviour of the masonry is added to the strut element. This model is a hybridization of existing proposals (FEMA and others) with added innovations by the author. It has been validated with experimental and numerical analyses results from literature. An important conclusion of this thesis is that the contribution of infills to lateral load resisting capacities of BMR structures should be considered for structure of more than one storey. Infills can add up to 51 % to bare frame capacity. The National building code requires that the lateral resistance of existing buildings must be at least 60 % of the equivalent static seismic force (V2005). It is concluded that one storey BMR buildings have a sufficient resistance, while three-storeys structures exhibit plastic deformations for loads under 0,6* V2005.

  3. Mission Planning Systems for Tactical Aircraft (Pre-Flight and In- Flight) (Systemes de Planification des Missions pour Avions Tactiques (Avant Vol et en Vol)

    Science.gov (United States)

    1991-05-01

    NIilitary,%ircsTai R ite P I tti71gSI ’ --- -’I Uttotmmand. Conttrol. Cumin ITtcatituns anti IBegye Intelligence ACS Manetiver Control Ssisrnm (’A~IAL...has either been introduced recently or is high workload and stress on the unaided operator, and it is imminent. These are reviewed elsewhere in this

  4. „Mais Paris demeure un phare...“ Influences de la France dans la vie d’Edvard et Hana Beneš avant 1919

    Czech Academy of Sciences Publication Activity Database

    Hájková, Dagmara; Hajdinová, Eva

    2015-01-01

    Roč. 86, č. 4 (2015), s. 449-472 ISSN 0080-2557 R&D Projects: GA ČR GAP410/10/1273 Institutional support: RVO:67985921 Keywords : Beneš, Edvard * Benešová, Hana * First World War Subject RIV: AB - History

  5. Les déterminants du statut “perdu de vue” chez les patients pris en charge pour cancer au Maroc: situation avant le Plan Cancer

    Science.gov (United States)

    Najdi, Adil; Berraho, Mohamed; Bendahhou, Karima; Obtel, Majdouline; Zidouh, Ahmed; Errihani, Hassan; Nejjari, Chakib

    2014-01-01

    Introduction Le cancer au Maroc représente un problème majeur de santé publique, sa prise en charge doit être globale, active et complète pour tous les patients. L'objectif de ce travail était d'estimer la fréquence des perdus de vue « PDV » en oncologie au Maroc durant la première année de suivi et de déterminer les facteurs associés à ce problème. Méthodes Par une étude rétrospective portant sur 2854 dossiers de malades hospitalisés dans les trois principaux centres d'oncologie au Maroc depuis janvier 2003 jusqu’à juin 2007 et concernant les cinq principales localisations de cancer au Maroc, nous avons cherché la date des dernières nouvelles des patients ayant un recul de 18 mois minimum afin de déterminer le statut de ces malades après un an de suivi. Résultats La moyenne d’âge était de 52±14 ans, une proportion féminine de 63%, les sujets actifs constituaient 28%, les mariés 71%, les analphabètes 51%, 70% des patients habitaient en milieu urbain et seulement 11% des malades disposaient d'une couverture sociale. La localisation cancéreuse la plus fréquente était le poumon (23,8%) suivie du colon-rectum (23,5%) puis le col (21,9%), le sein (20,4%) et les lymphomes (10,4%). Le taux des «PDV» à un an de suivi était de 48%, ce statut était significativement lié au sexe, à l’âge, au NSE et au statut matrimonial. Sur le plan médical, le statut «PDV» était lié à la localisation du cancer, au stade de diagnostic et au type de traitement reçu. Conclusion Notre étude a mis en évidence la grande ampleur du problème des PDV en cancérologie au Maroc ainsi que ces déterminants. Ces résultats incitent tous les acteurs dans le domaine de la cancérologie à collaborer ensemble pour prendre les mesures qui s'imposent pour y pallier PMID:25400850

  6. Hydro electric scheme on the Forestay river. Communes of Chexbres and Rivaz. Feasibility study; Turbinage du Forestay. Communes de Chexbres et Rivaz. Etude d'avant-projet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-06-15

    This illustrated final report for the Swiss Federal Office of Energy (SFOE) is a feasibility study of the retrofitting of the small hydro electric scheme located in Rivaz, Switzerland on the shore of the lake of Geneva. Water of the Forestay river, which crosses a steep wine region, is used in a 89 kW Pelton turbine with a water head of 63 m and a maximum flow rate of 180 litre/s, producing about 350,000 kWh/year for now more than 50 years. After retrofitting the maximum electric power produced should be 707 kW, generating 2,500,000 kWh/y by using a water head of 184 m and a maximum flow rate of 500 litre/s. Part of the new equipment would be mounted underground in order to respect the aesthetics of the beautiful site. Electricity production cost is estimated to be 0.109 CHF/kWh.

  7. ′An avant-garde indirect bonding technique for lingual orthodontics using the first complete digital "tad" (torque angulation device, & "BPD" (bracket positioning device′

    Directory of Open Access Journals (Sweden)

    Tushar Hegde

    2010-01-01

    This article covers an Indirect Bonding Technique using the Torque Angulation Device (TAD and the Bracket Positioning Device (BPD which ensure great accuracy while minimizing the poten- tial for error as compared to most methods available to the orthodontist today. This technique has been developed by taking into account the advantages and pitfalls of indirect bonding.

  8. Apport de matières fertilisantes avant plantation de vigne. Résultats d'un essai en sol de Graves du Bordelais

    Directory of Open Access Journals (Sweden)

    Jacques Delas

    1983-03-01

    A complete basic fertilizer with joined organic, calcary and phospho-potassic elements enhances plant development and gives a normal crop yield four years after planting. No or incomplete basic fertilizer leads to very low crop yields and is followed by a replacement of a large number of vinestocks.

  9. Une méthode pour estimer l’interception du rayonnement par un couvert bas : application au colza avant montaison

    Directory of Open Access Journals (Sweden)

    Denoroy Pascal

    2002-01-01

    Full Text Available Dans les modèles de simulation du fonctionnement des cultures, l’interception du rayonnement est une variable cruciale pour la prévision de la productivité en biomasse. D’autre part, la connaissance de l’interception du rayonnement par une culture permet de mieux analyser la réponse à un traitement en autorisant la distinction entre les effets morphogénétique et physiologique du traitement. Par exemple, dans l’étude de la fertilisation azotée du colza [1] on a pu faire la part de l’effet morphogénétique (accroissement de l’indice foliaire, donc de l’interception et de l’amélioration de la conversion photosynthétique du rayonnement absorbé. Dans un cas comme dans l’autre, une estimation correcte de l’interception du rayonnement est essentielle. Très souvent, un formalisme dérivé de la loi de Beer-Lambert est utilisé pour quantifier la part interceptée du rayonnement : PARi = epsiloni PAR (1 et epsiloni = 1 - e- k.IF (2, PAR représentant le rayonnement photosynthétiquement actif incident (exprimé en Joules ou en moles de photons, PARi la part de ce dernier interceptée par le couvert, epsiloni le coefficient (sans dimension d’interception, IF l’indice foliaire et k le coefficient d’extinction du rayonnement. Un formalisme un peu plus complexe doit être utilisé si on veut considérer le rayonnement absorbé [1, 2]. Pour des cultures couvrantes, la sensibilité de ces modèles à la valeur de k est faible pour les IF élevés, c’est pourquoi ces modèles sont souvent utilisés avec succès. Mais aux faibles IF, les modèles sont sensibles à k, d’où l’importance de l’estimation de ce paramètre pour les cultures présentant une longue période de faible couverture du sol, tel le colza peu fertilisé en phase hivernale. De plus, pour les cultures discontinues, c’est-à-dire présentant des zones où le sol n’est pas du tout couvert par la végétation, comme les inter-rangs, on doit introduire dans l’équation 2 un paramètre représentant le taux de couverture du sol. Si l’estimation par mesure directe de epsiloni et donc l’estimation de k sont assez simples, au moins dans le principe pour un couvert développé en hauteur (colza après montaison [3], une telle mesure devient beaucoup plus complexe dans le cas d’un couvert discontinu et bas. Dans ce milieu hétérogène (et souvent dans des conditions hivernales sévères, une distribution représentative des capteurs de rayonnement est difficile, les risques de perturbation de la mesure (salissure des capteurs, déréglages sont élevés. Plusieurs études ont déjà traité de epsiloni et k dans le cas du colza [3-7]. Elles sont fondées sur des mesures d’interception du rayonnement et concernent des couverts fermés, après montaison. Une autre approche consiste à effectuer un calcul précis de PARi avec des modèles détaillés utilisant une description complète des paramètres (géométriques et radiatifs du feuillage, et du rayonnement incident [8]. Mais les données nécessaires sont alors nombreuses, complexes à obtenir et donc généralement non disponibles en expérimentation. Pour répondre aux besoins de calcul de l’interception du rayonnement dans les phases d’installation du colza, cet article présente une méthode permettant de calculer epsiloni en tenant compte des principales caractéristiques de la morphologie du couvert et du régime radiatif auquel ce dernier est soumis. Les données nécessaires sont limitées : l’indice foliaire, les taux de couverture du sol (deux définitions, la latitude du lieu considéré, la date et le rayonnement incident quotidien. Ce calcul permet une estimation du coefficient moyen d’extinction k (équation 2. On verra que k peut être corrélé à l’IF, la période de l’année et la latitude du lieu, ce qui permet de proposer une estimation simple de k et donc un calcul simplifié de epsiloni, adapté au cas des faibles IF(colza entre levée et montaison.

  10. Politique et stratégie énergétiques de l’Inde avant et après Copenhague 2009

    Directory of Open Access Journals (Sweden)

    Megha Shenoy

    2011-05-01

    Full Text Available L’Inde est un pays démocratique d’une extraordinaire diversité. Sa croissance économique est l’une des plus rapides au monde. C’est le sixième plus grand consommateur mondial d’énergie. Ses politiques et ses stratégies énergétiques suscitent un intérêt de plus en plus important en raison de leur impact considérable sur les relations géopolitiques, sur les prix mondiaux de l’énergie et sur les changements climatiques. Actuellement, sa consommation d’énergie per capita et ses valeurs d’émissions de gaz à effet de serre sont faibles. Cependant, elles sont vouées à augmenter si le pays emprunte la même trajectoire de développement que l’Occident. Pour que l’Inde saute par-dessus ces sentiers déjà souvent battus pour en atteindre un qui garantisse un développement durable, le pays doit impérativement redéfinir son paradigme de développement de sorte à assurer une croissance inclusive. Des subventions inviables, une mise en œuvre des réformes laissant à désirer, des prix énergétiques faussés et des investissements inadaptés dans des énergies renouvelables sont quelques-unes des principales entraves que le gouvernement indien doit réexaminer afin d’améliorer la sécurité énergétique et de fournir un cadre de transition vers une économie à faible intensité de carbone. Outre des politiques énergétiques innovatrices telles que la Mission solaire nationale (National Solar Mission, la Mission nationale pour l’amélioration de l’efficacité énergétique (National Mission on Enhanced Energy Efficiency et la Mission nationale pour l’habitat durable (National Mission on Sustainable Habitat, l’Inde a besoin d’adopter un cadre de croissance découplée, que nous considérons comme une amélioration de la qualité de vie des citoyens sans pour autant intensifier les dommages à l’environnement. Depuis 2008, l’Inde démontre qu’elle prend au sérieux le changement de son modèle de croissance et le passage à des énergies propres. Néanmoins, ces perspectives ne se réaliseront pas pleinement si l’hémisphère Nord n’apporte pas une aide technique et financière pour atténuer collectivement les effets nuisibles du réchauffement de la planète et des changements climatiques qu’il provoque.

  11. Integrated evolution of the medium power CANDU{sup MD} reactors; Evolution integree des reacteurs CANDU{sup MD} de moyenne puissance

    Energy Technology Data Exchange (ETDEWEB)

    Nuzzo, F. [AECL Accelerators, Kanata, ON (Canada)

    2002-07-01

    The aim of this document is the main improvements of the CANDU reactors in the economic, safety and performance domains. The presentation proposes also other applications as the hydrogen production, the freshening of water sea and the bituminous sands exploitation. (A.L.B.)

  12. Very high temperature measurements: Applications to nuclear reactor safety tests; Mesures des tres hautes temperatures: Applications a des essais de surete des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Parga, Clemente-Jose

    2013-09-27

    This PhD dissertation focuses on the improvement of very high temperature thermometry (1100 deg. C to 2480 deg. C), with special emphasis on the application to the field of nuclear reactor safety and severe accident research. Two main projects were undertaken to achieve this objective: - The development, testing and transposition of high-temperature fixed point (HTFP) metal-carbon eutectic cells, from metrology laboratory precision (±0.001 deg. C) to applied research with a reasonable degradation of uncertainties (±3-5 deg. C). - The corrosion study and metallurgical characterization of Type-C thermocouple (service temp. 2300 deg. C) prospective sheath material was undertaken to extend the survivability of TCs used for molten metallic/oxide corium thermometry (below 2000 deg. C)

  13. Fe Al40, a new canning material for reactors using refractory fuels; Le Fe Al40, un nouveau materiau de gainage pour les reacteurs a combustibles refractaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    Fe Al40, owing to its high aluminium content, is more suitable than stainless steels for nuclear applications; it has two advantages: its nuclear cross section is half that of 18-10 stainless steels, and its compatibility with fuel elements and heat extracting fluids is exceptionally good. Ferrous alloys with more than 16 per cent by weight of aluminium are reputed to be brittle because of their ordered lattice. But actually, most of the brittleness of these alloys is due to the presence of intergranular precipitates. The vacuum casting of pure iron and aluminium, together with additions of scavenging elements, gives a very clean alloy with sufficiently reduced brittleness at high temperatures as to allow transformation with a very good yield. Studies of smelting and transformation have enabled the optimum composition and the best industrial fabrication conditions to be established. The mechanical properties of extruded or rolled products are dependent, on the ferritic ordered structure of the alloys prepared as follows: Extension at room temperature between 8 and 11 p.100, continuous increase of the elongation at rupture with increase of temperature so that at 800 C it exceeds 100 p.100; yield strength stable at 30 kg/mm{sup 2} from 20 to 550 C; progressive decrease of impact strength as the temperature increases Creep strength at 650-700 C in the region of 10 kg/mm{sup 2} with a very high elongation because of the appearance of a fine grain recrystallization during the test. Welding of Fe Al40 is facilitated by the fact that this alloy remains ferritic up to its melting point (1350 C); however it. is sensitive to hot short cracking and grain swelling. Several welding processes have been successfully applied to this alloy, under conditions where the superficial alumina layer was removed. This very impervious oxide skin gives Fe Al 40 a unique resistance to corrosion: in carbon dioxide at 700 C, 60 atm, the weight gain after 3000 h is about one third of that of a 18-10 niobium - stabilized stainless steel, in water, either de oxygenated or saturated with oxygen at 25 C, the weight gain is one hundred time smaller than that of mild steel, after a 3 month test, in water vapour at 500 C, also after 3 months, only the growth of impervious and very adherent oxide skins is observed, in sodium up to 1000 h at 700 C, the behaviour is at least as good as that of stainless steel. No diffusion reaction has been detected either with uranium dioxide up to 800 C, or with uranium carbide up to 700 C. Extension specimens and thin walled cans are subjected to high flux irradiations between 20 and 700 C; preliminary results will be given. (authors) [French] Le Fe Al40, grace a sa haute teneur en aluminium, presente de grands avantages sur les aciers inoxydables, pour les applications nucleaires; en particulier, sa section efficace est moitie de celle de l'acier a 18 p.100 Cr et 10 p.100 Ni, et sa compatibilite avec les elements combustibles et avec les fluides caloporteurs est exceptionnellement bonne. Les alliages ferreux, contenant plus de 16 p.100 en poids d'aluminium, sont reputes fragiles en raison de leur structure ordonnee. En fait, la plus grande partie de la fragilite de ces alliages est due a la presence de precipites intergranulaires. L'emploi de fer et d'aluminium purs, ainsi que des additions destinees a pieger les traces d'impuretes residuelles, permet d'obtenir, par coulee sous vide, un alliage tres propre dont la fragilite a chaud est suffisamment reduite pour permettre une transformation. avec un excellent rendement. Les etudes de fonderie et de transformation, qui ont defini la composition de l'alliage et les meilleures conditions industrielles de preparation, seront decrites. Les proprietes mecaniques des produits files ou lamines sont conditionnees par la structure ferritique ordonnee des alliages ainsi prepares: allongement par traction a temperature ambiante compris entre 8 et 11 p.100, augmentation progressive de l'allongement de rupture quand la temperature croit de sorte qu'a 800 C il depasse 100 p.100, limite elastique de 30 kg/mm{sup 2} de 20 jusqu'a 550 C, baisse progressive de la resilience quand la temperature croit, resistance au fluage a 650-700 C de l'ordre de 10 kg/mm{sup 2} avec un allongement tres important par suite de l'apparition d'une recristallisation, en grains tres fins en cours d'essai. La soudure du Fe Al 40 est facilitee par le fait que cet alliage reste ferritique jusqu'a son point de fusion (1350 C); toutefois, il est assez sensible aux contraintes thermiques et au grossissement du grain. Plusieurs procedes de soudure ont pu etre appliques, avec succes, a cet alliage, dans les conditions ou la couche d'alumine superficielle a pu etre enlevee. Cette couche d'oxyde, tres impermeable, confere au Fe Al40 une remarquable resistance a la corrosion: dans le gaz carbonique, a 700 C sous 60 atmospheres, gain de poids au bout de 3000 h environ, 1/3 de celui d'un acier inoxydable 18-10 stabilise au niobium; dans l'eau a 25 C, desoxygenee ou saturee en oxygene gain de poids 100 fois plus faible que celui d'un acier doux au bout de 3 mois; dans la vapeur d'eau a 500 C, en 3 mois aussi, formation de couches d'oxyde tres adherentes et impermeables; dans le sodium jusqu'a 1000 h a 700 C, comportement au moins aussi bon que celui de l'acier inoxydable. Aucune reaction de diffusion n'a ete decelee ni avec l'oxyde d'uranium jusqu'a 800 C, ni avec le carbure d'uranium jusqu'a 700 C. Des eprouvettes et des gaines a parois minces sont soumises a l'irradiation dans des flux neutroniques intenses entre 20 et 700 C; les resultats preliminaires seront communiques. (auteurs)

  14. Contribution to the study of the temperature reactivity coefficient for light water reactors; Contribution a l`etude du coefficient de temperature des reacteurs a eau legere

    Energy Technology Data Exchange (ETDEWEB)

    Mounier, C.

    1994-05-01

    In this work, we looked for the error sources in the calculation of the isothermal temperature coefficient for light water lattices. We studied three fields implied: the nuclear data, the calculation methods and the temperature coefficient measurement. About the measurement, we pointed out the difficulties of he interpretation. So we used an indirect approach by the mean of critical states at various temperatures. In that way, we can say that if the errors in the effective multiplication factor are constants with temperature then the temperature coefficient is correctly calculated. We studied the neutronic influence of light water models which are used in the thermal scattering cross-section computation. This cross-section determines the thermalization process of neutrons. We showed that the actual model (JEF2) is satisfactory of the needs of the reactors physics. Concerning the majors isotopes ({sup 235}U, {sup 238}U, {sup 239}Pu), the uncertainties on the nuclear data do not seem as a preponderant cause of errors, without to be totally negligible. We also studied, with the neutron transport code Apollo-2, the influence of difference approximations for cell calculation . The new possibilities of the code has been used to represent the critical experiments, particularly the improvement of the resonance self-shielding formalism. The calculation scheme adopted permits to remove partially the fundamental mode approximation by the mean of a two-dimensional transport calculation with the SN method, the axial leakage being treated as an absorption in DB{sup 2}{sub Z}. The agreement between theory and experiment is good both for the reactivity and the temperature coefficient. (author). 114 refs., 40 figs., 163 tabs., 1 append.

  15. Behaviour of BF{sub 3} counters after in-pile irradiation; Comportement de compteurs a BF{sub 3} apres irradiation dans un reacteur

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    The behaviour of a proportional BF{sub 3}LCT 14 NE 31 counter with aluminium cathode has been studied after irradiation from 10{sup 5} to 10{sup 6} n.cm{sup -2} in the swimming-pool reactor Triton. The pulse spectrum was only slightly modified by two successive irradiations at 10{sup 15} n.cm{sup -2}, and 1 hour after the end of the irradiation the decrease in sensitivity reached 10 to 20 per cent. One hour after irradiation at 10{sup 16} n.cm{sup -2} this decrease was 20 per cent but the pulse spectrum was affected. The advantages of an aluminium cathode with respect to a standard counter using a copper cathode and irradiated under the same conditions are given. Beforehand, it had been established that the limit for use of an aluminium-cathode counter in the presence of {gamma} radiation is about 200 R.h{sup -1}. (author) [French] Le comportement d'un compteur proportionnel a BF-3LCT 14 NE 31, a cathode d'aluminium, a ete etudie apres des irradiations de 10{sup 5} a 10{sup 6} n.cm{sup -2} dans la pile-piscine TRITON. Deux irradiations successives de 10{sup 15} n.cm{sup -2} ont peu modifie le spectre des impulsions et 1 heure apres la fin de l'exposition la perte de sensibilite etait de 10 a 20 pour cent. Une heure apres une irradiation de 10{sup 16} n.cm{sup -2}, cette perte etait de 20 pour cent mais le spectre d'impulsions etait perturbe. L'avantage d'une cathode en aluminium est mis en evidence par comparaison avec un compteur standard a cathode de cuivre irradie dans les memes conditions. En preliminaire, on avait etabli que la limite d'utilisation d'un compteur a cathode d'aluminium en presence de rayonnements {gamma} etait de l'ordre de 200 R.h{sup -1}. (auteur)

  16. Fuel and target programs for the transmutation at Phenix and other reactors; Programmes combustibles et cibles pour la transmutation dans Phenix et autres reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Gaillard-Groleas, G

    2002-07-01

    The fuels and targets program for transmutation, performed in the framework of the axis 1 of the December 1991 law about the researches on the management of long-lived radioactive wastes, is in perfect consistency with the transmutation scenario studies carried out in the same framework. These studies put forward the advantage of fast breeder reactors (FBR) in the incineration of minor actinides and long-lived fission products. The program includes exploratory and technological demonstration studies covering the different design options. It aims at enhancing our knowledge of the behaviour of materials under irradiation and at ensuring the mastery of processes. The goals of the different experiments foreseen at Phenix reactor are presented. The main goal is to supply a set of results allowing to precise the conditions of the technical feasibility of minor actinides and long-lived fission products incineration in FBRs. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Verdier, A

    2005-04-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Perdu, F

    2003-12-01

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

  19. Synthesis of a catalytic reactor membrane for synthesis gas production; Elaboration d'une membrane de reacteur catalytique pour la production de gaz de synthese

    Energy Technology Data Exchange (ETDEWEB)

    Juste, E.; Julian, A.; Chartier, T. [Limoges Univ., Lab. Science des Procedes Ceramiques et de Traitements de Surface (SPCTS, UMR 6638 CNRS), 87 (France); Juste, E.; Julian, A.; Del Gallo, P.; Richet, N. [Centre de Recherche Claude-Delorme, Air Liquide, 78 - Jouy en Josas (France)

    2007-07-01

    The conversion of natural gas to synthesis gas (mixture of H{sub 2} and CO) is a main challenge for the hydrogen and clean fuels production. Mixed (ionic O{sup 2-} and electronic) conducing ceramics membrane reactors seem particularly promising. The design considered for the membrane is a tri-layer system integrating a reforming catalyst and a dense membrane laying on a porous support. Among the materials considered for the dense membrane, perovskites La{sub 1-x}Sr{sub x}Fe{sub 1-y}Ga{sub y}O{sub 3-{delta}} seem to be interesting for their performances and stability. The oxygen flux through the membrane is measured in terms of temperature under different oxygen partial pressure gradients. In the industrial experimental conditions, the membrane is submitted to a strong oxygen (air/methane) partial pressure gradient of about 900 C which induces mechanical stresses, on account of the material expansion difference, in terms of p{sub O2}. In this framework, the evolutions of the performances and of the expansion coefficient have been followed in terms of the substitutions rates in La{sub (1-x)}Sr{sub x}Fe{sub (1-y)}Ga{sub y}O{sub 3-{delta}} with x{<=}0.5 and y{<=}0.5. (O.M.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Dadoun, O

    2003-06-01

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

  1. Study of trans-uranian incineration in molten salt reactor; Etude de l'incineration des transuraniens en reacteur a sel fondu

    Energy Technology Data Exchange (ETDEWEB)

    Valade, M

    2000-10-27

    With the emergence of new options for nuclear power, molten salt reactors are envisaged for waste management. The aim of this thesis is to show how molten salt reactors can help to solve the transuranics issue. Their high versatility regarding to isotopic vector allows to accommodate large fractions of minor actinides as compared to solid fuel system. In this thesis, a neutronics study of molten salt reactors, MSR, has been conducted. For this purpose, two reference systems were considered, TIER1 and AMSTER. In the case of TIER1, an optimisation was made to reach an equilibrium. The analysis of both systems showed the main characteristics of MSR: their link to chemistry and on line reprocessing. In this work, several methods to drive the system to a state of equilibrium have been implemented and compared. During this process the isotopic composition and neutron spectrum, thus the nuclear reaction cross sections, vary tremendously. It is essential to take these evolutions into account in order to accurately estimate the equilibrium state. This has been accomplished inside the multi-recycling procedure we set with ERANOS. A dedicated calculation schema has been realized to simulate superthermal systems with this computation code. These results were checked through a benchmark against other computer codes. Then, with multi-recycling method, several molten salt systems have been compared in order to define the optimal reactor for transuranics incineration. Nevertheless, a final choice can not only be done using only neutronics characteristics since chemistry and thermal-hydraulics constraints are really important for MSR. Moreover, a complete safety study would be required. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  3. Accident at the zero power reactor which happened on October 15 1958; Sur l'accident avec le reacteur de puissance zero du 15 octobre 1958

    Energy Technology Data Exchange (ETDEWEB)

    Savic, P [Boris Kidric Institute of Nuclear Sciences, Vinca, Beograd (Yugoslavia)

    1959-03-15

    During an experiment on the zero power heavy water reactor with natural uranium fuel in the Boris Kidric Institute of Nuclear Sciences, the reactor escaped control. Six staff members in the immediate surrounding of the bare assembly were exposed to high neutron and ionising irradiation. Other two employees who were at some bigger distance were exposed to doses higher than permitted. This paper deals with the circumstances that caused the accident, status of the dosimetry, control and alarm systems. Individual exposure doses were estimated according to the calculated neutron flux values obtained from measuring the activities of personal belongings made of gold and copper as well as radioactive phosphorous from urine.

  4. Fast ultrasonic visualisation under sodium. Application to the fast neutron reactors; Visualisation ultrasonore rapide sous sodium. application aux reacteurs a neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Imbert, Ch

    1997-05-30

    The fast ultrasonic visualization under sodium is in the programme of research and development on the inspection inside the fast neutron reactors. This work is about the development of a such system of fast ultrasonic imaging under sodium, in order to improve the existing visualization systems. This system is based on the principle of orthogonal imaging, it uses two linear antennas with an important dephasing having 128 piezo-composite elements of central frequency equal to 1.6 MHz. (N.C.)

  5. Turbulent precipitation of uranium oxalate in a vortex reactor - experimental study and modelling; Precipitation turbulente d'oxalate d'uranium en reacteur vortex - etude experimentale et modelisation

    Energy Technology Data Exchange (ETDEWEB)

    Sommer de Gelicourt, Y

    2004-03-15

    Industrial oxalic precipitation processed in an un-baffled magnetically stirred tank, the Vortex Reactor, has been studied with uranium simulating plutonium. Modelling precipitation requires a mixing model for the continuous liquid phase and the solution of population balance for the dispersed solid phase. Being chemical reaction influenced by the degree of mixing at molecular scale, that commercial CFD code does not resolve, a sub-grid scale model has been introduced: the finite mode probability density functions, and coupled with a model for the liquid energy spectrum. Evolution of the dispersed phase has been resolved by the quadrature method of moments, first used here with experimental nucleation and growth kinetics, and an aggregation kernel based on local shear rate. The promising abilities of this local approach, without any fitting constant, are strengthened by the similarity between experimental results and simulations. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-12-31

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

  7. Simulation des fuites neutroniques a l'aide d'un modele B1 heterogene pour des reacteurs a neutrons rapides et a eau legere

    Science.gov (United States)

    Faure, Bastien

    The neutronic calculation of a reactor's core is usually done in two steps. After solving the neutron transport equation over an elementary domain of the core, a set of parameters, namely macroscopic cross sections and potentially diffusion coefficients, are defined in order to perform a full core calculation. In the first step, the cell or assembly is calculated using the "fundamental mode theory", the pattern being inserted in an infinite lattice of periodic structures. This simple representation allows a precise modeling for the geometry and the energy variable and can be treated within transport theory with minimalist approximations. However, it supposes that the reactor's core can be treated as a periodic lattice of elementary domains, which is already a big hypothesis, and cannot, at first sight, take into account neutron leakage between two different zones and out of the core. The leakage models propose to correct the transport equation with an additional leakage term in order to represent this phenomenon. For historical reasons, numerical methods for solving the transport equation being limited by computer's features (processor speeds and memory sizes), the leakage term is, in most cases, modeled by a homogeneous and isotropic probability within a "homogeneous leakage model". Driven by technological innovation in the computer science field, "heterogeneous leakage models" have been developed and implemented in several neutron transport calculation codes. This work focuses on a study of some of those models, including the TIBERE model from the DRAGON-3 code developed at Ecole Polytechnique de Montreal, as well as the heterogeneous model from the APOLLO-3 code developed at Commissariat a l'Energie Atomique et aux energies alternatives. The research based on sodium cooled fast reactors and light water reactors has allowed us to demonstrate the interest of those models compared to a homogeneous leakage model. In particular, it has been shown that a heterogeneous model has a significant impact on the calculation of the out of core leakage rate that permits a better estimation of the transport equation eigenvalue Keff . The neutron streaming between two zones of different compositions was also proven to be better calculated.

  8. Relative measurement of the fluxes of thermal, resonant and rapid neutrons in reactor G1; Mesures relatives des flux thermique, resonnant et rapide dans le reacteur G1

    Energy Technology Data Exchange (ETDEWEB)

    Carle, R.; Mazancourt, T. de [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    We sought to determine the behavior of the thermal, resonant and rapid neutron fluxes in the multiplier-reflector transition region, in the two principal directions of the system. We have also measured the variation of these different fluxes in the body of the multiplier medium in a canal filled with graphite and in an empty canal. The results are given in the form of curves representing: - the variation of the ratio of the thermal flux to the rapid flux in axial and radial transitions - the behavior of the thermal and resonant fluxes and the variation of their ratio in the same regions. (author) [French] Nous avons cherche a determiner le comportement des differents flux, thermique, resonnant et rapide a la transition milieu multiplicateur-reflecteur dans les deux directions principales du reseau. Nous avons egalement mesure la variation de ces differents flux au sein du milieu multiplicateur dans un canal rempli de graphite et dans un canal vide. Les resultats sont donnes sous forme de courbe representant: - La variation du rapport du flux thermique au flux rapide aux transitions axiale et radiale - L'allure des flux thermique et resonnant et la variation de leur rapport dans les memes regions. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-01

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

  10. Concrete benchmark experiment: ex-vessel LWR surveillance dosimetry; Experience ``Benchmark beton`` pour la dosimetrie hors cuve dans les reacteurs a eau legere

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, H.; D`Hondt, P.; Oeyen, J.; Risch, P.; Bioux, P.

    1993-09-01

    The analysis of DOEL-1 in-vessel and ex-vessel neutron dosimetry, using the DOT 3.5 Sn code coupled with the VITAMIN-C cross-section library, showed the same C/E values for different detectors at the surveillance capsule and the ex-vessel cavity positions. These results seem to be in contradiction with those obtained in several Benchmark experiments (PCA, PSF, VENUS...) when using the same computational tools. Indeed a strong decreasing radial trend of the C/E was observed, partly explained by the overestimation of the iron inelastic scattering. The flat trend seen in DOEL-1 could be explained by compensating errors in the calculation such as the backscattering due to the concrete walls outside the cavity. The `Concrete Benchmark` experiment has been designed to judge the ability of this calculation methods to treat the backscattering. This paper describes the `Concrete Benchmark` experiment, the measured and computed neutron dosimetry results and their comparison. This preliminary analysis seems to indicate an overestimation of the backscattering effect in the calculations. (authors). 5 figs., 1 tab., 7 refs.

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

    Energy Technology Data Exchange (ETDEWEB)

    Dehaut, Ph

    2000-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Lelievre, F

    1998-12-11

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

  13. Calculation of control rods in rectangular reactor, and applications (1960); Calcul des barres de conteole dans un reacteur rectangulaire et applications (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Goshen, S; Pazy, A [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The aim of this report is to find a method for estimating the anti-reactivity of control rods perpendicular to the axis in a cylindrical pile. The paper is divided into two parts. In the first is given a method of calculating control rods in a rectangular pile, similar to the Nordheim-Scalettar method for cylindrical piles. As an example the formulas are given for the theories of one and two neutron groups, the generalisation for several groups being evident. In the second part we find by a variation method a formula for estimating the Laplacian of a pile, which may be divided into parallelepipeds for which the Laplacian are given. Finally, this formula is used to calculate the anti-reactivity of rods perpendicular to the axis in a cylindrical pile. (author) [French] Le but de ce rapport est de trouver une methode pour estimer l'antireactivite des barres de controle perpendiculaires a l'axe dans pile cylindrique. Le rapport se divise en deux parties. Dans la premiere nous donnons une methode de calcul des barres de controle dans une pile rectangulaire, analogue a la methode de Nordheim-Scalettar pour les piles cylindriques. A titre d'exemple, nous donnons les formules de theories a un et deux groupes de neutrons, la generalisation pour plusieurs groupes est evidente. Dans la deuxieme partie, nous trouvons, par une methode de variation, une formule qui permet d'estimer le laplacien d'une pile, qui peut etre divisee en parallelepipedes dont les laplaciens sont donnes. Nous utilisons enfin, cette formule pour calculer l'antireactivite des barres perpendiculaires a l'axe dans une pile cylindrique. (auteur)

  14. Detailed study of transmutation scenarios involving present day reactor technologies; Etude detaillee des scenarios de transmutation faisant appel aux technologies actuelles pour les reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    This document makes a detailed technical evaluation of three families of separation-transmutation scenarios for the management of radioactive wastes. These scenarios are based on 2 parks of reactors which recycle plutonium and minor actinides in an homogeneous way. A first scenario considers the multi-recycling of Pu and Np and the mono-recycling of Am and Cm using both PWRs and FBRs. A second scenario is based on PWRs only, while a third one considers FBRs only. The mixed PWR+FBR scenario requires innovative options and gathers more technical difficulties due to the americium and curium management in a minimum flux of materials. A particular attention has been given to the different steps of the fuel cycle (fuels and targets fabrication, burnup, spent fuel processing, targets management). The feasibility of scenarios of homogeneous actinides recycling in PWRs-only and in FBRs-only has been evaluated according to the results of the first scenario: fluxes of materials, spent fuel reprocessing by advanced separation, impact of the presence of actinides on PWRs and FBRs operation. The efficiency of the different scenarios on the abatement of wastes radio-toxicity is presented in conclusion. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Cognet, G

    1998-07-07

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

  16. Contribution to the modelling of gas-solid reactions and reactors; Contribution a la modelisation des reactions et des reacteurs gaz-solide

    Energy Technology Data Exchange (ETDEWEB)

    Patisson, F

    2005-09-15

    Gas-solid reactions control a great number of major industrial processes involving matter transformation. This dissertation aims at showing that mathematical modelling is a useful tool for both understanding phenomena and optimising processes. First, the physical processes associated with a gas-solid reaction are presented in detail for a single particle, together with the corresponding available kinetic grain models. A second part is devoted to the modelling of multiparticle reactors. Different approaches, notably for coupling grain models and reactor models, are illustrated through various case studies: coal pyrolysis in a rotary kiln, production of uranium tetrafluoride in a moving bed furnace, on-grate incineration of municipal solid wastes, thermogravimetric apparatus, nuclear fuel making, steel-making electric arc furnace. (author)

  17. Multi-physic simulations of irradiation experiments in a technological irradiation reactor; Modelisation pluridisciplinaire d'experiences d'irradiation dans un reacteur d'irradiation technologique

    Energy Technology Data Exchange (ETDEWEB)

    Bonaccorsi, Th

    2007-09-15

    A Material Testing Reactor (MTR) makes it possible to irradiate material samples under intense neutron and photonic fluxes. These experiments are carried out in experimental devices localised in the reactor core or in periphery (reflector). Available physics simulation tools only treat, most of the time, one physics field in a very precise way. Multi-physic simulations of irradiation experiments therefore require a sequential use of several calculation codes and data exchanges between these codes: this corresponds to problems coupling. In order to facilitate multi-physic simulations, this thesis sets up a data model based on data-processing objects, called Technological Entities. This data model is common to all of the physics fields. It permits defining the geometry of an irradiation device in a parametric way and to associate information about materials to it. Numerical simulations are encapsulated into interfaces providing the ability to call specific functionalities with the same command (to initialize data, to launch calculations, to post-treat, to get results,... ). Thus, once encapsulated, numerical simulations can be re-used for various studies. This data model is developed in a SALOME platform component. The first application case made it possible to perform neutronic simulations (OSIRIS reactor and RJH) coupled with fuel behavior simulations. In a next step, thermal hydraulics could also be taken into account. In addition to the improvement of the calculation accuracy due to the physical phenomena coupling, the time spent in the development phase of the simulation is largely reduced and the possibilities of uncertainty treatment are under consideration. (author)

  18. Methods for determining thermal stresses values. Some examples relating to nuclear reactors; Methodes de determination des contraintes thermiques. Quelques exemples d'application aux reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, J; Gautier, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Peres, A [Israel Institute of Technology, Dept. of Nuclear Science Technion (Israel)

    1958-07-01

    As modern techniques develop more elaborate machines, and make their way towards higher and higher temperatures and pressures, the thermal stresses become a matter of major importance in the design of mechanical structures. In the first part of this paper, the authors examine the problem from a theoretical standpoint, and try to evaluate the aptitude and limitation of mathematical techniques to attain the quantitative values of thermal stresses. This paper deals mainly with the experimental methods to measure thermal stresses. The authors show some examples relating to nuclear reactors. (author)Fren. [French] Au fur et a mesure que la technique moderne developpe des machines plus poussees et s'oriente vers des temperatures et des pressions toujours plus elevees, les contraintes thermiques deviennent un facteur d'importance capitale dans le calcul des structures mecaniques. Les auteurs examinent d'abord l'aspect theorique du probleme, ainsi que l'aptitude et les limites du calcul pour exprimer quantitativement la valeur des contraintes thermiques. Les auteurs exposent principalement, ensuite, les methodes experimentales qui permettent de mesurer ces contraintes, et illustrent cet expose de quelques exemples relatifs aux installations nucleaires. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-07-01

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

  20. Relative measurement of the fluxes of thermal, resonant and rapid neutrons in reactor G1; Mesures relatives des flux thermique, resonnant et rapide dans le reacteur G1

    Energy Technology Data Exchange (ETDEWEB)

    Carle, R; Mazancourt, T de [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    We sought to determine the behavior of the thermal, resonant and rapid neutron fluxes in the multiplier-reflector transition region, in the two principal directions of the system. We have also measured the variation of these different fluxes in the body of the multiplier medium in a canal filled with graphite and in an empty canal. The results are given in the form of curves representing: - the variation of the ratio of the thermal flux to the rapid flux in axial and radial transitions - the behavior of the thermal and resonant fluxes and the variation of their ratio in the same regions. (author) [French] Nous avons cherche a determiner le comportement des differents flux, thermique, resonnant et rapide a la transition milieu multiplicateur-reflecteur dans les deux directions principales du reseau. Nous avons egalement mesure la variation de ces differents flux au sein du milieu multiplicateur dans un canal rempli de graphite et dans un canal vide. Les resultats sont donnes sous forme de courbe representant: - La variation du rapport du flux thermique au flux rapide aux transitions axiale et radiale - L'allure des flux thermique et resonnant et la variation de leur rapport dans les memes regions. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

    Hennion, A

    1999-03-15

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

  2. Calculation system for physical analysis of boiling water reactors; Modelisation des phenomenes physiques specifiques aux reacteurs a eau bouillante, notamment le couplage neutronique-thermohydraulique

    Energy Technology Data Exchange (ETDEWEB)

    Bouveret, F

    2001-07-01

    Although Boiling Water Reactors generate a quarter of worldwide nuclear electricity, they have been only little studied in France. A certain interest now shows up for these reactors. So, the aim of the work presented here is to contribute to determine a core calculation methodology with CEA (Commissariat a l'Energie Atomique) codes. Vapour production in the reactor core involves great differences in technological options from pressurised water reactor. We analyse main physical phenomena for BWR and offer solutions taking them into account. BWR fuel assembly heterogeneity causes steep thermal flux gradients. The two dimensional collision probability method with exact boundary conditions makes possible to calculate accurately the flux in BWR fuel assemblies using the APOLLO-2 lattice code but induces a very long calculation time. So, we determine a new methodology based on a two-level flux calculation. Void fraction variations in assemblies involve big spectrum changes that we have to consider in core calculation. We suggest to use a void history parameter to generate cross-sections libraries for core calculation. The core calculation code has also to calculate the depletion of main isotopes concentrations. A core calculation associating neutronics and thermal-hydraulic codes lays stress on points we still have to study out. The most important of them is to take into account the control blade in the different calculation stages. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  4. Tables of formulae for calculating the mechanics of stacks in gas-graphite reactors; Formulaire pour le calcul de la mecanique des empilements des reacteurs graphite-gaz

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1968-07-01

    This collection of formulae only gives, for nuclear graphite stacks. The mechanical effects due to the strains, thermal or not, of steel structures supporting or surrounding graphite blocks. Equations have been established by mean of experiments made at Chinon with large pile models. Thus, it is possible to calculate displacement, strain and stress in the EDF type stacks of horizontal triangular block lattice. (authors) [French] Le domaine de ce formulaire est strictement limite aux effets mecaniques, pour les empilements, des deformations, thermiques ou autres, des structures metalliques de soutien (aire - support et corset). On propose un ensemble de relations qui ont ete etablies a la suite des essais de CHINON sur des maquettes de grande taille. Ces relations permettent le calcul des mouvements, des deformations et des contraintes dans les empilements du type EDF, a reseau horizontal triangulaire regulier. (auteurs)

  5. The development of fast reactors in France from March 1980 to March 1981; Le developpement des reacteurs a neutrons rapides en France de mars 1980 a mars 1981

    Energy Technology Data Exchange (ETDEWEB)

    Vautrey, L. [Commissariat a l' Energie Atomique, CEN de Saclay, Gif-sur-Yvette (France)

    1981-05-15

    This paper describes general features concerning development in the field of fast reactors in France from March 1980 to March 1981. It concentrates mainly on: Rapsodie, Phenix NPP, prototype reactor Super Phenix 1, future fast reactor NPPs and current research and development programs in the field. The present situation is as follows. Rapsodie has restarted operation but at reduced power in July 1980 because of the problems in the primary circuit which have not yet been solved. Phenic operates in a very satisfactory manner. Construction of Super Phenix is continuing normally. Research activities are performed sometimes for the needs of Super Phenix and sometimes for the needs of future fast rector projects like Super Phenix 2. International cooperation is being continued.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Dardour, S

    2007-04-15

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

  8. Calculation scheme for boiling water reactors cores; Methode de calcul des coeurs de reacteurs a eau bouillante par le systeme saphyr

    Energy Technology Data Exchange (ETDEWEB)

    Marsault, Ph [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SERSI), 13 - Saint-Paul-lez-Durance (France); Nicolas, A; Lenain, R; Richebois, E; Royer, E; Caruge, D [CEA Saclay, Dept. de Mecanique et de Technologie (DMT/SERMA), 91 - Gif-sur-Yvette (France); Blaise, P [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SPEX), 13 - Saint-Paul-lez-Durance (France); Gastaldi, B; Delpech, M [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SPRC), 13 - Saint-Paul-lez-Durance (France)

    1999-07-01

    Boiling Water Reactors represent one third of the world's reactors. They are presently evolving towards greater simplification, allowing a reduction in the costs of operation, improved safety and a relative flexibility in their capacity to accommodate 100% MOX cores. The CEA, in a combined effort with its partners, the COGEMA and the EDF, would like to assess the interest of this reactor type, especially on this last point. A definition program and subsequent qualification of the calculation scheme have been undertaken. We are presenting here the specific features inherent in the calculation of these reactors, in comparison to PWRs, as well as the first results of the program. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

    Zammit-Averlant, V

    1998-11-19

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

  10. Cronos 2: a neutronic simulation software for reactor core calculations; Cronos 2: un logiciel de simulation neutronique des coeurs de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Lautard, J J; Magnaud, C; Moreau, F; Baudron, A M [CEA Saclay, Dept. de Mecanique et de Technologie (DMT/SERMA), 91 - Gif-sur-Yvette (France)

    1999-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-07-01

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

  12. Calculation system for physical analysis of boiling water reactors; Modelisation des phenomenes physiques specifiques aux reacteurs a eau bouillante, notamment le couplage neutronique-thermohydraulique

    Energy Technology Data Exchange (ETDEWEB)

    Bouveret, F

    2001-07-01

    Although Boiling Water Reactors generate a quarter of worldwide nuclear electricity, they have been only little studied in France. A certain interest now shows up for these reactors. So, the aim of the work presented here is to contribute to determine a core calculation methodology with CEA (Commissariat a l'Energie Atomique) codes. Vapour production in the reactor core involves great differences in technological options from pressurised water reactor. We analyse main physical phenomena for BWR and offer solutions taking them into account. BWR fuel assembly heterogeneity causes steep thermal flux gradients. The two dimensional collision probability method with exact boundary conditions makes possible to calculate accurately the flux in BWR fuel assemblies using the APOLLO-2 lattice code but induces a very long calculation time. So, we determine a new methodology based on a two-level flux calculation. Void fraction variations in assemblies involve big spectrum changes that we have to consider in core calculation. We suggest to use a void history parameter to generate cross-sections libraries for core calculation. The core calculation code has also to calculate the depletion of main isotopes concentrations. A core calculation associating neutronics and thermal-hydraulic codes lays stress on points we still have to study out. The most important of them is to take into account the control blade in the different calculation stages. (author)

  13. Study of trans-uranian incineration in molten salt reactor; Etude de l'incineration des transuraniens en reacteur a sel fondu

    Energy Technology Data Exchange (ETDEWEB)

    Valade, M

    2000-10-27

    With the emergence of new options for nuclear power, molten salt reactors are envisaged for waste management. The aim of this thesis is to show how molten salt reactors can help to solve the transuranics issue. Their high versatility regarding to isotopic vector allows to accommodate large fractions of minor actinides as compared to solid fuel system. In this thesis, a neutronics study of molten salt reactors, MSR, has been conducted. For this purpose, two reference systems were considered, TIER1 and AMSTER. In the case of TIER1, an optimisation was made to reach an equilibrium. The analysis of both systems showed the main characteristics of MSR: their link to chemistry and on line reprocessing. In this work, several methods to drive the system to a state of equilibrium have been implemented and compared. During this process the isotopic composition and neutron spectrum, thus the nuclear reaction cross sections, vary tremendously. It is essential to take these evolutions into account in order to accurately estimate the equilibrium state. This has been accomplished inside the multi-recycling procedure we set with ERANOS. A dedicated calculation schema has been realized to simulate superthermal systems with this computation code. These results were checked through a benchmark against other computer codes. Then, with multi-recycling method, several molten salt systems have been compared in order to define the optimal reactor for transuranics incineration. Nevertheless, a final choice can not only be done using only neutronics characteristics since chemistry and thermal-hydraulics constraints are really important for MSR. Moreover, a complete safety study would be required. (author)

  14. Analog study of the power control, temperature and flow of the reactor EL4; Etude analogique de la regulation de puissance, temperature et debit du reacteur EL4

    Energy Technology Data Exchange (ETDEWEB)

    Boulven, J; Chazal, G

    1966-07-01

    This study concerns the implementing and the exact determination of the gains of the plant control loops and the knowledge of the system response during possible solicitations under normal conditions. (A.L.B.)

  15. Cells for the examination of irradiated plutonium fuel elements - two years operation - may 1961/may 1963 (1963); Cellules pour examen d'elements combustibles au plutonium irradies - deux ans d'exploitation - mai 1961/mai 1963 (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    Within the framework of the 'Rapsodie' fast reactor program, prototype plutonium fuel elements are irradiated and then examined in an {alpha} {beta} {gamma} laboratory at Saclay. This laboratory consists of five in line cells and a lead enclosure microscope. Each cell contains an {alpha} sealed removable box 4 ft 3 in. high, 4 ft 11 in. wide and 5 ft 1 in. deep, fitted with one or two magnetic transmission indirect manipulators. The boxes are contained in an {beta} {gamma} shielded enclosure whose front face is constructed of cast iron panels 21-2/3 in. thick. Nitrogen circulating in a closed loop forms the atmosphere of the boxes. This laboratory is essentially intended for metallurgical research. The functions of the various cells are as follows: transferring and packing, cutting, density measurement and cathodic etching, storage and metallography. Work on radioactive materials began in April 1961. Operational incidents have always been of a material nature only. (author) [French] Dans le cadre du projet de reacteur rapide Rapsodie, des elements combustibles prototypes au plutonium sont, apres irradiation, examines a Saclay dans un laboratoire {alpha} {beta} {gamma}. Celui-ci comprend cinq cellules en ligne et une enceinte en plomb contenant un microscope telecommande. Chaque cellule est constituee d'un caisson etanche (1, 3 m x 1, 5 m x 1, 56m) equipee d'un ou deux manipulateurs indirects a transmissions magnetiques. Les caissons sont places, dans une enceinte {beta} {gamma} dont la face avant est formee de blocs en fonte ayant 55 cm d'epaisseur. L'atmosphere des caissons est de l'azote, circulant en circuit ferme. Ce laboratoire est destine essentiellement a des recherches metallurgiques. Les fonctions des differentes cellules sont: conditionnement et transferts, tronconnage, mesure de densite et polissage ionique, stockage, metallographie. Le travail sur materiaux radioactifs a commence en avril 1961. Les incidents d'exploitation ont toujours ete d

  16. Cells for the examination of irradiated plutonium fuel elements - two years operation - may 1961/may 1963 (1963); Cellules pour examen d'elements combustibles au plutonium irradies - deux ans d'exploitation - mai 1961/mai 1963 (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    Within the framework of the 'Rapsodie' fast reactor program, prototype plutonium fuel elements are irradiated and then examined in an {alpha} {beta} {gamma} laboratory at Saclay. This laboratory consists of five in line cells and a lead enclosure microscope. Each cell contains an {alpha} sealed removable box 4 ft 3 in. high, 4 ft 11 in. wide and 5 ft 1 in. deep, fitted with one or two magnetic transmission indirect manipulators. The boxes are contained in an {beta} {gamma} shielded enclosure whose front face is constructed of cast iron panels 21-2/3 in. thick. Nitrogen circulating in a closed loop forms the atmosphere of the boxes. This laboratory is essentially intended for metallurgical research. The functions of the various cells are as follows: transferring and packing, cutting, density measurement and cathodic etching, storage and metallography. Work on radioactive materials began in April 1961. Operational incidents have always been of a material nature only. (author) [French] Dans le cadre du projet de reacteur rapide Rapsodie, des elements combustibles prototypes au plutonium sont, apres irradiation, examines a Saclay dans un laboratoire {alpha} {beta} {gamma}. Celui-ci comprend cinq cellules en ligne et une enceinte en plomb contenant un microscope telecommande. Chaque cellule est constituee d'un caisson etanche (1, 3 m x 1, 5 m x 1, 56m) equipee d'un ou deux manipulateurs indirects a transmissions magnetiques. Les caissons sont places, dans une enceinte {beta} {gamma} dont la face avant est formee de blocs en fonte ayant 55 cm d'epaisseur. L'atmosphere des caissons est de l'azote, circulant en circuit ferme. Ce laboratoire est destine essentiellement a des recherches metallurgiques. Les fonctions des differentes cellules sont: conditionnement et transferts, tronconnage, mesure de densite et polissage ionique, stockage, metallographie. Le travail sur materiaux radioactifs a commence en avril 1961. Les incidents d

  17. RPV-1: a first virtual reactor to simulate irradiation effects in light water reactor pressure vessel steels; RPV-1: un premier reacteur virtuel pour simuler les effets d'irradiation dans les aciers de cuve des reacteurs a eau legere

    Energy Technology Data Exchange (ETDEWEB)

    Jumel, St

    2005-01-15

    The presented work was aimed at building a first VTR (virtual test reactor) to simulate irradiation effects in pressure vessel steels of nuclear reactor. It mainly consisted in: - modeling the formation of the irradiation induced damage in such steels, as well as their plasticity behavior - selecting codes and models to carry out the simulations of the involved mechanisms. Since the main focus was to build a first tool (rather than a perfect tool), it was decided to use, as much as possible, existing codes and models in spite of their imperfections. - developing and parameterizing two missing codes: INCAS and DUPAIR. - proposing an architecture to link the selected codes and models. - constructing and validating the tool. RPV-1 is made of five codes and two databases which are linked up so as to receive, treat and/or transmit data. A user friendly Python interface facilitates the running of the simulations and the visualization of the results. RPV-1 relies on many simplifications and approximations and has to be considered as a prototype aimed at clearing the way. According to the functionalities targeted for RPV-1, the main weakness is a bad Ni and Mn sensitivity. However, the tool can already be used for many applications (understanding of experimental results, assessment of effects of material and irradiation conditions,....). (O.M.)

  18. Characteristics and construction problems of EL 4; Caracteristiques et problemes de construction d'EL4

    Energy Technology Data Exchange (ETDEWEB)

    Carle, R; Schulhof, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Sevin, Ph [Electricite de France (EDF), 75 - Paris (France); Buttin, J [Societe INDATOM (France)

    1964-07-01

    detail and the connections to be employed were tested. The whole circuit is made in fairly classical materials (slightly alloyed steels) whose behaviour in the carbon dioxyde at 500 deg. C was proved. The CO{sub 2}, and heavy water circuits construction will begin in October 1964. Aerodynamic tests were carried out for the helico-centrifugal blowers (of unit power 9 MW). The choice of a pressure as high as 60 kg/cm{sup 2} does not seem to induce new problems in connection with leaks on the machine shafts. Finally, the choice of a type of CO{sub 2} - steam heat exchanger with forced circulation led Electricite de France to test the operation and stability of a prototype exchanger in its test plant The reactor will be equipped with a de-pressurizing and de-superheating system which will allow the reactor to operate at 20 p. 100 of its nominal power whether the turbo-alternator is available or not. (authors) [French] EL 4 est le prototype d'une filiere originale de reacteurs moderes a l'eau lourde et refroidis au gaz carbonique. Son etude a ete menee dans la double optique de: - realiser un reacteur suffisamment important et complet pour y tester l'ensemble des problemes de construction et d'exploitation de la filiere; - menager dans l'installation les possibilites de tenir compte des ameliorations (materiaux nouveaux, elements combustibles ameliores) qui sont etudiees par ailleurs. Le premier objectif n'etait envisageable que sous reserve d'un volume d'etudes preliminaires important. A ce titre, ont ete realises et essayes de 1962 a 1964 plusieurs canaux prototypes, hors pile, mais dans les conditions reelles de temperature et de pression. Ces essais ont montre la bonne tenue des materiaux aux difficiles conditions mecaniques et chimiques du projet. Ces installations seront d'ailleurs disponibles pour eprouver, avant mise en pile, les modifications ulterieures. D'importants essais touchant la securite du reacteur en cas d'explosion du circuit de CO{sub 2}, ont ete realises

  19. Performance Characteristics of the Experimental Boiling Water Reactor from 0 to 100 MW(t); Performances de l'EBWR de 0 a 100 MW; Rabochaya kharakteristika ehksperimental'nogo kipyashchego reaktora EBWR pri moshchnosti 0 - 100 mgvt.; Rendimiento del reactor experimental de agua hirviente (EBWR) entre 0 y 100 MW

    Energy Technology Data Exchange (ETDEWEB)

    Iskenderian, A.; Lipinski, W. C.; Petrick, M.; Wimunc, E. A. [Argonne National Laboratory, Argonne, IL (United States)

    1963-10-15

    's performance characteristics changed radically. The steam disengaging velocity reached 1 ft/s and the steam dome height decreased to 3 ft. Under these conditions liquid carryover occurred and increased rapidly with increasing power. The reactor no longer behaved as a direct-cycle boiling-water reactor; in a sense it functioned as a natnral-circulation dual-cycle reactor. (author) [French] Le 25 mai 1962, le Laboratoire national d'Argonne a recu l'autorisation de la Commission de l'energie atomique des Etats-Unis (CEA-EU) d'exploiter le reacteur experimental a eau bouillante (EBWR) jusqu'a une puissance de 100 MW. Dans le cadre de l'administration du systeme de garanties, l'Agence internationale de l'energie atomique a autorise a aller de l'avant le 11 juillet 1962. Le 5 novembre 1962, on a atteint la puissance de 100 MW. Le programme experimental, realise avec le reacteur EBWR de 100 MW, a ete acheve le 6decembre 1962. L'un des principaux objectifs du projet etait de pourvoir le reacteur de tous les instruments de mesures necessaires pour obtenir des donnees et des renseignements sur les performances de cette filiere. C'est le premier programme de ce genre qui ait ete entrepris. On a mis au point plusieurs techniques d'instrumentation nouvelles pour obtenir les donnees voulues. Cet objectif a ete atteint avec le plus grand succes, et on a pu recueillir beaucoup de donnees nouvelles sur les performances d'un reacteur a eau bouillante a circulation naturelle. Ce programme a permis d'obtenir des indications sur les points suivants: debit de recirculation; limite de separation de la vapeur et du liquide (entrainement de vapeur dans le tube d'eau et de liquide par la vapeur); sous-refroidissement; localisation de l'interface vraie dans le reacteur et son influence sur le niveau de la colonne d'eau; taux de condensation de la vapeur dans le tube d'eau; coefficients cavitaires; antireactivite de l'acide borique; coefficients de temperature; emploi de bandes de bore a des fins de

  20. Seeking new paths by attempting avant-garde teaching methods through translation and creative writing for classes of English for Academic Purposes (EAP) . The cases of the Schools of Engineering, Departments of Mechanical Engineering, Informatics and Tele

    OpenAIRE

    CHRISTIDOU, SOFIA; KAMAROUDIS, STAVROS E.

    2016-01-01

    The aim of our paper is to discuss how the courses of English Language of the Department of Applied and Visual Arts of the School of Fine Arts and of the Departments of Mechanical Engineering, Informatics and Telecommunications Engineering of the School of Engineering of the University of Western Macedonia were taught during the academic year 2014-5 and how students reacted towards the teaching approaches that were adopted. For reasons of economy of space we present here only the experiment t...

  1. Élites musulmanes et processus d’acculturation par les activités physiques modernes dans les années vingt : de la Médersienne à l’Avant-garde Musulmane de Cirta

    OpenAIRE

    Boulebier, Djamel

    2013-01-01

    Dans l’Algérie coloniale, l’après guerre a eu pour première conséquence sur le plan sportif l’enclenchement d’un processus d’autonomisation des pratiques sportives vis-à-vis de l’Union des Sociétés Françaises des Sports Athlétiques devenue de plus en plus obsolète au vu de l’importance grandissante de ce qu’il était convenu d’identifier de plus en plus comme un phénomène social. Ces changements n’affectèrent en rien les sportsmen musulmans, bien au contraire. Nous assistons à leur redéploieme...

  2. Les autres Irakiens : émigrés et exilés d’avant 2003 en Jordanie et leurs récits d’appartenance (Une recherche en cours

    Directory of Open Access Journals (Sweden)

    Hala Fattah

    2007-07-01

    Full Text Available Cet article s’intéresse à une importante minorité de la communauté irakienne exilée à Amman (Jordanie, à savoir la génération des années 1950. Après une brève présentation de l’histoire de l’émigration irakienne en Jordanie, l’auteur évoque les quelques travaux sociologiques sur les Irakiens à Amman et dans les autres villes jordaniennes. La seconde section de l’article est consacrée à l’analyse de la manière dont cette génération formule l’identité ou les identités irakiennes, la question communautaire, celle des droits des femmes et la notion de gouvernance. Bien qu’il s’agisse d’une étude à ses débuts, l’exploration par l’auteur de cette histoire orale introduit des nuances passionnantes à notre connaissance de l’histoire irakienne, qu’elle s’efforce de relier (de façon encore impressionniste au récit plus large de la mémoire irakienne.

  3. The small-scale hydroelectric power plant project 'Les Esserts' in Boudry, Switzerland - Feasibility study and preliminary planning; Centrale des Esserts a Boudry. Etude de faisabilite et avant-projet detaille

    Energy Technology Data Exchange (ETDEWEB)

    Roelli, P.; Croci, S.; Ernst, J.-R.

    2004-07-01

    This report describes in details the project of the installation of a small-scale hydroelectric power plant on the river Areuse in Switzerland. Located on a 4 m high waterfall the plant includes a 10-13 m{sup 3}/s Kaplan turbine, which should deliver roughly 1.6 GWh/year for an installed power of about 500 kVA. The authors insist on the ecological aspect of the project. The plant will be built underground; the river track will be practically unchanged and the existing fish ladder maintained. The report includes maps and pictures of the site as well as technical drawings of the installation. An economic analysis of the project is presented and its viability is discussed. Finally, the authors state that the energy produced by this plant will certainly be certified under one of the Swiss labels 'naturemade star' or 'naturemade basic', in the framework of the federal government's promotion of renewable energy sources.

  4. Tracer des limites, les franchir. Essai sur la notion de frontière, en Syrie, à la fin du deuxième millénaire avant Jésus-Christ

    OpenAIRE

    Racine-Dognin, Elisabeth

    2015-01-01

    If, as we would define it, the word “border” indicates a place of contact and exchanges between two spaces rather than a well-drawn line of separation, numerous borders exist: political, social, cultural, linguistic in an Ancient Near East often characterized as “a world without borders” since it shares the same cuneiform culture. From the fourteenth century BC to the beginning of the twelfth, the Syrian States have belonged to successive spheres of influence of powerful empires, Mitanni, Egy...

  5. Un’avanguardia in provincia. La “Mostra degli Archivi” all’Esposizione regionale marchigiana di Macerata del 1905 / A provincial avant-garde. The “Archives exhibition” to the Marche Regional Exhibition in Macerata in 1905

    Directory of Open Access Journals (Sweden)

    Francesco Pirani

    2013-05-01

    Full Text Available Il saggio indaga, sotto il profilo storiografico, i tratti culturali della “Mostra degli Archivi”, organizzata a Macerata nel 1905 nell’ambito della “Esposizione regionale marchigiana”. La mostra fu un evento innovativo, teso a comunicare il ricco patrimonio documentario custodito nei numerosi e dispersi archivi storici comunali. L’obiettivo della mostra fu di valorizzare un patrimonio ancora in gran parte sconosciuto e negletto, dando un impulso al riordinamento delle carte e all’accessibilità degli archivi. Al tempo stesso, si volle ridefinire l’identità culturale delle Marche: non più terra di municipalismi, non più area defilata nella geografia dell’Italia unita, ma una regione orgogliosa della sua storia e del proprio patrimonio. Animatore della mostra fu uno studioso boemo, Lodovico Zdekauer, il cui profilo culturale è indagato per comprendere appieno le ragioni e gli obiettivi del progetto. La mostra fu apprezzata fuori delle Marche e fu proposta a modello per l’intera nazione.   This essay inquires, from an historiographical point of view, into the cultural features of  the “Archives Exibition”, held in Macerata in 1905, as part of  the “ Marche Regional exhibition”. The exhibition - a truly innovative event – was designed to make known the wealth of records heritage kept in the many but dispersed municipal historical archives. The exhibition aimed at valuing a still largely unknown and neglected heritage, boosting documents reorganization and assuring accessibility to archives. At the same time, the exhibition redefined the cultural identity of Marche: no longer a land of parochialism, no longer a low-profile land in a unified Italy, but a region proud of its past and its heritage. The exhibition was fostered by a Bohemian scholar, Lodovico Zdekauer, whose cultural profile is searched to fully understand the exhibition aims. The cultural event was highly appreciated outside the Marche region and proposed as a model to the whole country.

  6. Energy balance of a cheese factory and preliminary project for biogas production; Bilan energetique de la fromagerie et avant-projet d'installation de biogaz. Richard Bettex - 1487 Champtauroz (VD)

    Energy Technology Data Exchange (ETDEWEB)

    Membrez, Y. [Erep SA, Aclens (Switzerland); Wellinger, A. [Nova Energie GmbH, Aadorf (Switzerland); Bonjour, B. [Sorane SA, Lausanne (Switzerland)

    2002-07-01

    This report is a feasibility study for a biogas production unit adapted to a farm in Champtauroz in Switzerland, and a dual purpose power plant generating thermal and electric energy from the biogas according to the energy demand of the cheese factory attached to the farm. Typically 5*10{sup 5} m{sup 3} per year of biogas should be extracted from the manure of around 1,500 farm animals. The methane would be produced by a continuously operated digestor. The energy demand of the cheese factory, mainly thermal energy for the goat milk transformation process and electric power for the milk refrigeration, is measured in details and its annual profile is estimated. This demand is practically independent from the outdoor temperature as long as this temperature is higher than 10 {sup o}C. The report also includes a cost estimate for the whole project, functional schematics of the biogas production unit and of the power plant, and several diagrams displaying the heat and electric power demands of the cheese factory as a function of parameters like the cheese production and the quantity of refrigerated milk.

  7. LEP1 measurement of heavy quark forward-backward asymmetries with Opal detector; Mesure de l`asymetrie avant-arriere des quarks lourds a LEP1 avec le detecteur Opal

    Energy Technology Data Exchange (ETDEWEB)

    Lafoux, H

    1996-04-30

    Using all data collected by OPAL during the first phase of LEP operation, called LEP1, we have measured the b and c quark forward-backward asymmetries on and around the Z{sup 0} peak. The measurement, which is based on prompt leptons produced in semileptonic decays of heavy quarks, has been optimized using artificial neural networks whenever necessary, that is whenever the problem to solve implied taking into account simultaneously a large number of parameters. Our results are compatible with other LEP measurements and with the Standard Model predictions for a top quark of 174{+-}31 GeV/c{open_square} and a Higgs boson mass between 60 and 1000 GeV/c{open_square}. (author). 159 refs., 88 figs., 37 tabs.

  8. Esteetiline autonoomia ja ideoloogiline opositsioon Eesti NSV-s, ehk kuidas avangard minetas poliitilise otstarbe = Aesthetic autonomy and ideological opposition in Estonia in the 1960s and 1970s, or how the avant-garde lost its political edge / Tõn

    Index Scriptorium Estoniae

    Tatar, Tõnis, 1980-

    2013-01-01

    Kunstis ja ühiskonnas aset leidnud muudatustest 1960. aastate lõpust alates. Kunsti vabanemisest normatiivsetest süsteemidest ja kunstnikele avanenud võimalusest kujundada endale sobiv kunstimaailm.

  9. L’auto-référencement en physiothérapie : la mise de l’avant d’une culture éthique pour encadrer la pratique organisationnelle

    Directory of Open Access Journals (Sweden)

    Hudon, Anne

    2014-10-01

    Full Text Available Self-referral in physiotherapy, that is, a healthcare professional referring a patient to a private physiotherapy clinic in which the same professional has a financial interest, presents significant organizational ethical implications. This article offers potential solutions to this ethically reprehensible practice. In addition to focusing on legislative and ethical strategies, private clinics should adopt guidelines and formal activities to improve the ethical culture of their company, by involving owners, shareholders and employees.

  10. Statistical process control applied to intensity modulated radiotherapy pretreatment controls with portal dosimetry;Maitrise statistique des processus appliquee aux controles avant traitement par dosimetrie portale en radiotherapie conformationnelle avec modulation d'intensite

    Energy Technology Data Exchange (ETDEWEB)

    Villani, N.; Noel, A. [Laboratoire de recherche en radiophysique, CRAN UMR 7039, Nancy universite-CNRS, 54 - Vandoeuvre-les-Nancy (France); Villani, N.; Gerard, K.; Marchesi, V.; Huger, S.; Noel, A. [Departement de radiophysique, centre Alexis-Vautrin, 54 - Vandoeuvre-les-Nancy (France); Francois, P. [Institut Curie, 75 - Paris (France)

    2010-06-15

    Purpose The first purpose of this study was to illustrate the contribution of statistical process control for a better security in intensity modulated radiotherapy (I.M.R.T.) treatments. This improvement is possible by controlling the dose delivery process, characterized by pretreatment quality control results. So, it is necessary to put under control portal dosimetry measurements (currently, the ionisation chamber measurements were already monitored by statistical process control thanks to statistical process control tools). The second objective was to state whether it is possible to substitute ionisation chamber with portal dosimetry in order to optimize time devoted to pretreatment quality control. Patients and methods At Alexis-Vautrin center, pretreatment quality controls in I.M.R.T. for prostate and head and neck treatments were performed for each beam of each patient. These controls were made with an ionisation chamber, which is the reference detector for the absolute dose measurement, and with portal dosimetry for the verification of dose distribution. Statistical process control is a statistical analysis method, coming from industry, used to control and improve the studied process quality. It uses graphic tools as control maps to follow-up process, warning the operator in case of failure, and quantitative tools to evaluate the process toward its ability to respect guidelines: this is the capability study. The study was performed on 450 head and neck beams and on 100 prostate beams. Results Control charts, showing drifts, both slow and weak, and also both strong and fast, of mean and standard deviation have been established and have shown special cause introduced (manual shift of the leaf gap of the multi-leaf collimator). Correlation between dose measured at one point, given with the E.P.I.D. and the ionisation chamber has been evaluated at more than 97% and disagreement cases between the two measurements were identified. Conclusion The study allowed to demonstrate the feasibility to reduce the time devoted to pretreatment controls, by substituting the ionisation chamber's measurements with those performed with E.P.I.D., and also that a statistical process control monitoring of data brought security guarantee

  11. Gated blood-pool SPECT assessment of Wolff-Parkinson-White syndromes before and after radiofrequency ablation of accessory pathways; Evaluation fonctionnelle par tomographie cavitaire du syndrome de Wolff-Parkinson-White, avant et apres traitement par radiofrequence

    Energy Technology Data Exchange (ETDEWEB)

    Bontemps, L.; Ben Brahim, H.; Kraiem, T.; Chevalier, P.; Kirkorian, G.; Touboul, P.; Itti, R. [Hopital Cardiologique de Lyon, 69 (France)

    1997-08-01

    Radiofrequency (RF) ablation of accessory pathways in Wolff-Parkinson-White (WPW) syndrome is supposed to be less aggressive than fulguration while providing excellent results. The aims of our study were therefore the evaluation of the functional results of this therapy in terms of left or right ejection fractions and its effects on the contraction synchronism between both ventricular chambers, derived from bi-ventricular Fourier phase histograms. A consecutive series of 44 patients has been investigated within 48 hours before and after RF therapy: 14 patients had right sided WPW and 30 patients left sided WPW. Only patients for whom RF treatment was considered as a success have been included in the study. Gated blood pool tomography has been performed in order to localize the site of pre-excitation and to build-up the phase histograms for both ventricles, and planar gated imaging has been used for right and left ejection fraction determination. Functional results demonstrate the absence of deleterious effect of RF on ventricular contraction and rather a slight increase of ejection fractions, with a more statistically significant difference for left WPW (LVEF = 62.2 % before RF vs 64.4 % after RF; p = 0.02) than for right WPW (RVEF = 36.3 % before RF vs 39.7 after RF; p = 0.16). Phase analysis, on the contrary, show only significant differences for right WPW, with a noticeable decrease of the pre-excitation (left-to-right phase difference 14.4 deg before RF vs 7.5 deg after RF; p = 0.03) and a significant reduction of the right ventricular phase dispersion (right phase standard deviation 26.5 deg before RF vs 19.0 deg after RF; p = 0.03). For left WPW no measurable differences can be demonstrated in the basal state and it is suggested to use stimulation techniques in order to enhance the competition between the normal and accessory conduction pathways. (authors). 17 refs.

  12. Retrofitting of the small hydro electric scheme 'Moulin d'en Bas' in Cronay, Switzerland - Preliminary project; Rehabilitation du Moulin d'en Bas, commune de Cronay. Etude d'avant-projet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-09-15

    This illustrated final report for the Swiss Federal Office of Energy (SFOE) is a feasibility study for the retrofitting of the small hydro electric scheme 'Moulin d'en Bas' located in Cronay on the Mentue river, Switzerland. Two variants are considered. In the first one the existing scheme uses a 4.72 m water fall and its power amounts to about 25 kW. A 4-blades Kaplan turbine is foreseen to generate 160,000 kWh/y. In the second variant, weir and penstock have to be adapted in order to take advantage of the full 6.74 m water fall indicated in the water-use concession granted in 1952. A new fish pass has to be built as well. The resulting electric power is in this case 80 kW and the power generation by the turbo group 353,000 kWh/y, about 60% of which in the wintertime. Electricity production cost is estimated to be 0.282 CHF/kWh in the second variant.

  13. Comments made by the Syndicate of renewable energies on the draft of orientation law about energies; Observations du Syndicat des energies renouvelables a l'avant-projet de loi d'orientation sur les energies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-12-01

    This document presents the proposals of modifications and the comments made by the French syndicate of renewable energies (SER) about the draft of energy law proposed by the government in November 2003. The document is presented as 3 columns with the original text of the law, the modifications proposed by the SER and their observations. The comments of the SER concern only the promotion of development and use of renewable energy sources, the energy saving certificates and the development of bio-fuels. (J.S.)

  14. Une fibule ornithomorphe du début du Ve siècle avant J.-C. au musée de Slaný (Bohême)

    Czech Academy of Sciences Publication Activity Database

    Kruta, V.; Moucha, Václav

    2018-01-01

    Roč. 70, č. 1 (2018), s. 67-90 ISSN 0323-1267 Institutional support: RVO:67985912 Keywords : bird's head brooch * Late Hallstatt period * north-south relations * symbolism of coral and water fowl Subject RIV: AC - Archeology, Anthropology, Ethnology OBOR OECD: Archaeology

  15. Pavel Haas Study Day a IMR Study Day: Inter-War Avant-Garde across National and Disciplinary Borders, 30. a 31. ledna 2016, Cardiff University School of Music, Cardiff, Velká Británie

    Czech Academy of Sciences Publication Activity Database

    Kratochvílová, Markéta; Zapletal, Miloš

    2016-01-01

    Roč. 53, č. 1 (2016), s. 101-102 ISSN 0018-7003. [Pavel Haas Study Day. Cardiff, 30.01.2016] R&D Projects: GA ČR(CZ) GP14-35842P Institutional support: RVO:68378076 Keywords : Pavel Haas * conference * music * inter-war * avantgarde Subject RIV: AL - Art, Architecture, Cultural Heritage

  16. Les Bruits en lettres brute. Variations onomatopéiques dans trois mouvements d’avant-garde au XXe siècle: Futurisme, Dadaïsme, Lettrisme

    Directory of Open Access Journals (Sweden)

    Noemie Fargier

    2017-07-01

    Full Text Available Standing between an original expression and a universal language, a poetic game and a linguistic system, onomatopoeia occupied a cen­tral spot in three avan­t-gardes of the twen­tieth-cen­tury: futurism, dadaism, lettrism, regarding their own artistic research and the competition between them. Audible, graphic and linguistic material composing works halfway between poetry, music and graphic arts, onomatopoeia seems to converge in the three avan­t-gardes’ artistic and historic goals because of their intermedial, interdisciplinary and transnational dimension. They assert themselves by shaping this ambiguous material in a new approach, and each of them pretends to be the inven­tor of the onomatopoeic creation. Questioning origin, onomatopoeia looks however toward novelty, and wish to appear as a modern medium, with which the so-called fossilized arts could be revolutionized.

  17. Introduction of a priori information in the elastic linearized inversion of seismic data before stacking; Introduction d'informations a priori dans l'inversion linearisee elastique de donnees sismiques de surface avant sommation

    Energy Technology Data Exchange (ETDEWEB)

    Tonellot, Th.L.

    2000-03-24

    In this thesis, we propose a method which takes into account a priori information (geological, diagraphic and stratigraphic knowledge) in linearized pre-stack seismic data inversion. The approach is based on a formalism in which the a priori information is incorporated in an a priori model of elastic parameters - density, P and S impedances - and a model covariance operator which describes the uncertainties in the model. The first part of the thesis is dedicated to the study of this covariance operator and to the norm associated to its inverse. We have generalized the exponential covariance operator in order to describe the uncertainties in the a priori model elastic parameters and their correlations at each location. We give the analytical expression of the covariance operator inverse in 1-D, 2-D, and 3-D, and we discretized the associated norm with a finite element method. The second part is dedicated to synthetic and real examples. In a preliminary step, we have developed a pre-stack data well calibration method which allows the estimation of the source signal. The impact of different a priori information is then demonstrated on synthetic and real data. (author)

  18. Prise en charge des RCIU d'origine placentaire avant 32 semaines d'aménorrhée. Enquête nationale sur les pratiques françaises

    OpenAIRE

    Patte , Charlotte

    2013-01-01

    Non disponible / Not available; Introduction : Bien qu'étant la première cause de morbidité et de mortalité périnatale, leRetard de Croissance Intra Utérin (RCIU) reste une pathologie obstétricale complexe dans son diagnostic et sa prise en charge. Le RCIU d'origine placentaire est un processus pathologique consistant en une altération de la croissance due à un dysfonctionnement placentaire, avec défaut chronique d'apports au foetus. Il n'existe actuellement pas de possibilité de prise en cha...

  19. The climate regime before and after Copenhagen: science, policy, and the two-degrees target; Le regime climatique avant et apres Copenhague: sciences, politiques et l'objectif des deux degres

    Energy Technology Data Exchange (ETDEWEB)

    Aykut, S.C. [EHESS, Centre Alexandre Koyre, Paris (France); Dahan, A. [CNRS, Centre Alexandre Koyre, Paris (France)

    2011-04-15

    The article discusses the political results of the Copenhagen Conference and evolutions in the international climate arena including geopolitical shifts, new issues on the agenda and a changing cartography of the main actors. As recent attacks on the climate regime concern both its political governance and the peculiar relationship between science and politics that developed through its main institutions (IPCC and the Conference of the Parties), we retrace in a first part the construction of the climate arena and in a second part the framing of the problem between climate science, expertise, and politics. Drawing on this historical sketch, we suggest the years 2000 were characterized by a convergence of top-down approaches in climate expertise and policies, structuring action and discourse around quantified reduction targets, temperature and concentration thresholds, and carbon budgets. The bottom-up character of the voluntary reduction commitments in the Copenhagen Accord is a serious setback to this approach. A central figure in this context is the threshold of 'dangerous warming' of two degrees. The Copenhagen Accord - endorsed in the Cancun compromise - elevates this figure to an official target of the U.N. negotiation process, thereby accentuating the tension between a newly assumed 'Real politic' and an alarming expertise. The article analyzes the construction of the two-degrees target and the role it plays in the climate regime. We conclude by discussing several contributions to the Post-Copenhagen debate. (authors)

  20. Small-scale hydro power in the Anniviers Valley. Project Chippis-Ricard. Variants and preliminary project; Forces Motrices de la Gougra SA. Mini-hydraulique en Anniviers. Projet Chippis-Ricard. Etude de variantes et avant-projet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-04-15

    This report for the Swiss Federal Office of Energy (SFOE) reports on the preliminary project for a small hydropower plant in Chippis, Switzerland. The project takes advantage of an existing irrigation scheme that deviates water from the Navisence River into two successive tunnels (total 1.8 km) and a following channel built on steep mountain sides. The basic idea of the project is to increase the flow rate entering the tunnels from 265 l/s to 1265 l/s and to lead the additional 1000 l/s to a new penstock connected to the second tunnel's outlet. In this way, a hydraulic head of 130 m could be used for power generation for over 600 households (mechanical power: 0.8 to 1.1 MW, annual electrical energy production: 2.5 to 3.6 GWh, depending on the variant considered). The report reviews the history of water use at this location and its present use as well as a feasibility study previously made. The project is described, including water collection points, conduits, the power station and the particular aspects of the joint use of water for power generation and irrigation from mid April to mid September. Technical details on water quantities and energy production are presented. Financial aspects including construction and operating costs are presented and the economic viability of the project is discussed. Environmental aspects are reviewed. Further steps to be taken in the realisation of this hydropower installation are listed.

  1. Small-scale hydro power in the Anniviers Valley. Project Ayer-Nava. Variants and preliminary project; Forces Motrices de la Gougra SA. Mini-hydraulique en Anniviers. Projet Ayer-Nava. Etude de variantes et avant-projet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-04-15

    This report for the Swiss Federal Office of Energy (SFOE) reports on the preliminary project for a small hydropower plant near Ayer, a village in the Anniviers Valley (Swiss Alps). Water from the Nava, a steep mountain river, should be lead into a hydraulic scheme for power generation. A hydraulic head of 400 to 550 m is available, depending on the variant considered. The corresponding expected mechanical power is 0.9 to 1.1 MW. For the most promising variant a preliminary project is described (peak electric power: 0.91 MW, annual electrical energy production: 3.1 GWh). The local geology and hydrogeology are presented. The water collection points, conduits and the power station are described. Technical details on water quantities and energy production are presented. Financial aspects including construction and operating costs are presented and the economic viability of the project is discussed. Environmental aspects are reviewed. Further steps to be taken in the realisation of this hydropower installation are listed.

  2. L’apologie de la politique coloniale française dans la littérature pour la jeunesse avant 1914 : un soutien sans limites ?

    Directory of Open Access Journals (Sweden)

    Bernard Jahier

    2012-01-01

    Full Text Available Si la littérature pour la jeunesse se charge, à partir de 1871, de diffuser et d’exalter les thèmes patriotiques activés par le souvenir traumatisant de la guerre de 1870, elle ne manque pas non plus de faire l’apologie de la politique d’expansion coloniale qui se met en place dans les années 1880. Approuvant largement ces conquêtes territoriales qui viennent compenser la perte de l’Alsace-Lorraine, la littérature pour la jeunesse privilégie principalement la mission « civilisatrice » de la France, sans négliger pour autant l’intérêt économique et financier de la colonisation. Ces romans de jeunesse présentent peu de restrictions, sinon limitées voire ambiguës, à l’approbation très majoritaire qu’ils apportent à la politique coloniale de la troisième République. En cela, ils ont contribué, pendant plusieurs générations, à conditionner les jeunes esprits et participé à l’adhésion de l’opinion publique à la politique impérialiste de la France.

  3. Draft of law relating to revamping of natural gas supply public service and to development of gas enterprises; Avant projet de loi relatif a la modernisation du service public du gaz naturel et au developpement des entreprises gazieres

    Energy Technology Data Exchange (ETDEWEB)

    Bricq [ed.] [Deputee de Seine-et-Marne, Assemblee Nationale, Paris (France)

    2000-02-07

    The state secretariat for industry has launched a large public debate between June and October 1999 based on a white book titled 'Towards the future organization of the gas sector'. The suggestions obtained were substantial. A brief presentation is added to the draft of the law devoted to revamping of natural gas supply public service and to development of gas enterprises. The presentation addresses the following points: 1. A public gas supply service modern and thought to reconcile the dynamism, equity and solidarity. 2. A controlled opening of the natural gas market towards competition: participating to the struggle for employment. 3. Tools ensuring the quality of gas supply and security of resources. 4. A transparent and efficient regulation: creating the conditions of a nondiscriminatory competition. 5. Requirements for developing the transport of natural gas regime. 6. Storage. 7. Social questions. The draft of the law relating to revamping of natural gas supply public service and to development of gas enterprises is a working document, not engaging the government. It is based on six titles. Title 1 and Title 2 treat the points 1 and 2 mentioned above. Title 3 contains two chapters devoted to transparency and accounting dissociation and to regulation in the natural gas sector, respectively. The Title 4 contains three chapters devoted to: 1. authorization of the works of natural gas transport; 2. gas distribution and 3. exploitation of the transport and natural gas distribution network. The fifth Title is dedicated to underground storage. The sixth Title presents diverse directives.

  4. Les «États point-champ» phéniciens et l’empire carthaginois dans l’espace méditerranéen (IXe-IIe siècles avant J.-C.

    Directory of Open Access Journals (Sweden)

    Philippe Moyen

    2006-03-01

    Full Text Available De la prospérité des cités-États phéniciennes à la disparition de l’empire carthaginois, la Méditerranée, entre le IXe et le IIe siècle, constitue un champ d’analyse privilégié pour étudier, dans la longue durée, l’évolution des «États point-champ» et mettre en évidence la diversité des modalités de territorialisation dans la production des aires géopolitiques supports de la trame évènementielle de l’Histoire.

  5. Baldwin, l’homotextualité et les identités plurielles : une rencontre à l’avant-garde Encounter in the Vanguard. Baldwin, Homotextuality, and Multiple Identities

    Directory of Open Access Journals (Sweden)

    Jean-Paul Rocchi

    2004-01-01

    Full Text Available Fifty years after Baldwin’s works were first published, they still disclose the essence of our dawning 21st century—the century of identity. Baldwin’s writing goes beyond the bare representation of racial and sexual categorisation. It launches a fierce attack upon the building-up of identities. Resisting self-erasure and self-negation, the author’s Black and gay consciousness frees itself from the traditional Western conceptions of spatio-temporality and distorts the conventional representation of masculinity-now seen through the lens of the sensuous trinity of the father, the son and the lover. Finally, it sheds a new light on Black identity, not only to be transmitted but also to be translated and transformed. Using psychoanalytical, sociological and semiological frames, this essay aims at showing how the process of writing in Baldwin’s fictional and non-fictional works inverts binarisms and dislocates the origin so as to oppose every attempt at defining identity. On the one hand, focusing more particularly on the interplay of identifications between the individual and the American community in Giovanni’s Room and on the other hand between the reader and the writer in “Notes of a Native Son”, this essay explores Baldwin’s major themes such as memory, homotextuality, the writer’s political philosophy, his ethics of inclusion and his position as an outsider. It also examines the Black and gay speech out of which springs his art of writing-in-beyond identity, in the political and literary vanguard.

  6. Small hydro schemes in Turtmanntal, Switzerland; Forces Motrices de la Gougra SA. Mini-hydraulique dans le val de Tourtemagne. Projet Tourtemagne. Etude de variantes et avant-projet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This two-part report for the Swiss Federal Office of Energy (SFOE) presents several variants and two preliminary projects with respect to schemes for the use of hydropower in the Turtmanntal valley in the Swiss Alps. The various possible sites for the power stations both on the left and right-hand sides of the main valley are described. Technical details and prognoses for costs and energy production are discussed for all these variants. In the second part of the report, preliminary projects for hydropower installations on the Braendji and Piji streams are presented. Costs and economic viability are discussed and time-scales for the realisation are examined.

  7. Considérations sur l’alimentation des habitants des Principautés Roumaines dans la vision des consuls et des voyageurs français de la période d’avant 1848

    Directory of Open Access Journals (Sweden)

    Violeta-Anca Epure

    2012-12-01

    Full Text Available The French influence in the Romanian Principalities was not exercised only by French secretaries and tutors. The travelers and consuls, who came into contact with the Romanians and their living space in the period before the revolution of 1848, noted the striking differences between ordinary people’s and boyar’s food. French guests also observed Turkish influences in the area of Wallachian and Moldavian cuisine: in the menus from the aristocratic courts were introduced by Greek chain Turkish foods. Towards the middle of the nineteenth century, the cuisine from the Principalities will also record Western influences, particularly French. At the boyar meals, they consumed local wines, but also expensive wines brought from Western Europe (Madeira, French, and stronger drinks such as brandy or rum. Peasants subsisted on products produced most often in their household.

  8. Autour de l’exposition du Grand Palais « Mexique 1900-1950. Diego Rivera, Frida Kahlo, José Clemente Orozco et les avant-gardes »

    OpenAIRE

    Giraud, Paul-Henri

    2016-01-01

    « L’année du Mexique en France » programmée en 2011 aurait dû marquer l’excellence des relations bilatérales entre les deux pays. Une liste imposante de manifestations culturelles était organisée, mais tout fut annulé au dernier moment en raison d’un différend diplomatique. L’affaire Florence Cassez, du nom de la jeune Française alors incarcérée à Mexico, avait définitivement brouillé les Présidents Nicolas Sarkozy et Felipe Calderón. En 2014, le voyage officiel de François Hollande au Mexiqu...

  9. Evolution oligo-miocène de l'Altiplano occidental ( arc et avant arc du nord du Chili, Arica ) : tectonique , volcanisme, sédimentation, géomorphologie et bilan érosion-sédimentation.

    OpenAIRE

    Garcia , Marcelo

    2001-01-01

    The oligo-neogene geodynamic evolution of Altiplano, at the latitude od "Codo de Arica", is characterised by an important compressive defonnation and volcanism. In the eastern part of the chain (Bolivia), the shortening is weIl documented (190-280 km), and it explain a very thick crust (65 km). However, in the western part, the geological history is not weIl known and in part controversial. The study of the Arica region, on three regional transects (to scale 1:50.000), permit to propose a rep...

  10. Adding a hydroelectric power station to the public water supply of St-Jean; Projet de construction d'une centrale hydraulique sur le reservoir principal de la commune de St-Jean. Etude d'avant projet

    Energy Technology Data Exchange (ETDEWEB)

    Perruchoud, A. [Sierre Energie SA, Sierre (Switzerland); Denis, V. [MHyLab, Montcherand (Switzerland)

    2005-07-01

    Drinking water for the community of St-Jean, southwestern Switzerland is collected at three different locations with altitudes of 2004, 1998 and 1958 m respectively, and is fed into a common chamber at 1933 m. The project foresees the construction of an intermediate reservoir at the elevation of 1460 m, the total hydraulic head of 473 m being used to drive a Pelton turbine of 110 kW nominal power. The useful net height difference after deduction of the pressure drop in the piping is 373 meters at a typical water flow rate of 0.034 m{sup 3}/s. At this flow rate the turbine efficiency is estimated to 0.89. The asynchronous generator rotates at 1500 rpm and has a nominal electric power output of 125 kW. The estimated annual production amounts to 450,000 kWh and the investment costs to 449,000 Swiss francs. Depending on the time of amortization assumed (20 to 40 years), the production cost is estimated to 0.0615 to 0.0845 Swiss francs/kWh, a value considered favorable for the realization of the project.

  11. The small-scale hydroelectric power plant project 'Les Esserts' in Boudry, Switzerland - Feasibility study and preliminary planning; Centrale des Esserts a Boudry. Etude de faisabilite et avant-projet detaille

    Energy Technology Data Exchange (ETDEWEB)

    Roelli, P; Croci, S; Ernst, J -R

    2004-07-01

    This report describes in details the project of the installation of a small-scale hydroelectric power plant on the river Areuse in Switzerland. Located on a 4 m high waterfall the plant includes a 10-13 m{sup 3}/s Kaplan turbine, which should deliver roughly 1.6 GWh/year for an installed power of about 500 kVA. The authors insist on the ecological aspect of the project. The plant will be built underground; the river track will be practically unchanged and the existing fish ladder maintained. The report includes maps and pictures of the site as well as technical drawings of the installation. An economic analysis of the project is presented and its viability is discussed. Finally, the authors state that the energy produced by this plant will certainly be certified under one of the Swiss labels 'naturemade star' or 'naturemade basic', in the framework of the federal government's promotion of renewable energy sources.

  12. Power generation using the irrigation water in the community of Venthone. Preliminary project; Turbinage des eaux d'irrigation de la commune de Venthone. Etude d'avant-projet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This final report prepared for the Swiss Federal Office of Energy (SFOE) presents a nice example of how electric power from renewable energy sources can be generated using an existing infrastructure. The irrigation system of Venthone in the southwestern Swiss Alps collects water from various mountain torrents into a reservoir at 885 m above sea level from where it is distributed over 3 branches to the vineyards. Due to various boundary conditions (especially the priority of the irrigation requirements) only a quarter of the full potential for power generation can be used, but nevertheless the project remains promising, providing electricity at a cost of 0.107 CHF/kWh. The usable height-difference amounts to 267 m and some pipe sections would have to be replaced by ones with larger diameters to avoid excessive pressure losses. The authors recommend a Pelton turbine with a single injector. Due to the lack of water in winter, power generation would be restricted to 8 months per year, i.e. mid-March to mid-November.

  13. La antropofagia como actitud: en las vanguardias, en el tropicalismo y en la literatura periférica / Cannibalism as an Attitude: The Avant-garde in Literature Tropicalia and Periphera

    OpenAIRE

    Victor Hugo Adler Pereira

    2014-01-01

    This paper presents an analysis of the configuration of cannibalism as a metaphor central to the development of political and artistic movements in the twentieth century of Brazil. Based on the presentation made in the “Manifesto cannibal” by Oswald de Andrade are analyzed dialogues and influences and nuances that emerged in both literary and musical performances. Also the paper highlights the role of cannibalism in the search for a national identity immersed in processes, which confronted di...

  14. Joannès (F.), (Dir.), Rendre la justice en Mésopotamie, Archives judiciaires du Proche-Orient ancien (IIIe-Ier millénaires avant J.-C)

    OpenAIRE

    Klock-Fontanille, Isabelle

    2009-01-01

    Pour celui qui s'intéresse aux droits cunéiformes, il existe un matériel épigra-phique très riche. Mais d'une part, ce matériel n'est pas facilement accessible et d'autre part ce qui est surtout connu, ce sont les lois, comme les lois d'Ur-Nammu ou le code de Hammurabi. Or, comme l'annonce le sous-titre, ce n'est pas ce type de texte que vise ce livre : il sera question de documentation judiciaire au sens large, incluant, comme le rappelle Sophie Lafont, « non seulement les minutes de procès,...

  15. The radiation linked to uranium natural radioactivity enlightened by Abel Niepce long time before Henri Becquerel;Les rayonnements lies a la radioactivite naturelle de l'uranium mis en evidence par Abel Niepce bien avant Henri Becquerel

    Energy Technology Data Exchange (ETDEWEB)

    Fournier, J.; Niepce, J.C.

    2009-09-15

    Abel Niepce was rarely mentioned during the celebration of the centenary of the radioactivity discovery.This discovery, supposed due to chance alone, is entirely attributed to Henri Becquerel. But Abel Niepce who made the first observation of radiation from uranium with the impression of a photographic plate, but without giving it meaning. This is a slow process which in forty years, from an observation misunderstood by Abel Niepce to its interpretation by Frederick Soddy, through the experiments of Henri Becquerel and thanks to developments in other knowledge (electron, X-rays) has led to a scientific progress known under the term of radioactivity, name given by Marie Slodowska-Curie. (N.C.)

  16. Vandellos 1 Graphite Solubilisation and Activity Determination of 36Cl, 99Tc and 129I

    International Nuclear Information System (INIS)

    Rodríguez Alcalá, Marina; Piña Lucas, Gabriel; López Gutiérrez, Jose María; Leganés Nieto, Jose Luis

    2016-01-01

    During the characterization processes of irradiate graphite performed in the dismantling of the UNGG NPP of Vandellós 1, and as a consequence of the sample treatment carried out for measuring the main radionuclides of interest included in the El Cabril inventory, it was not possible to measure the activity of 99 Tc, 129 I and 36 Cl. Further R&D projects have been developed to solve this issue and finally a proper sample treatment has been accomplished. (author)

  17. Hydrogen production by water dissociation from a nuclear reactor; Production d'hydrogene par dissociation de l'eau a partir d'un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    This memento presents the production of hydrogen by water decomposition, the energy needed for the electrolysis, the thermochemical cycles for a decomposition at low temperature and the possible nuclear reactors associated. (A.L.B.)

  18. Contribution to the use of a solid moderator gas reactor, for naval propulsion; Contribution a l'etude d'un reacteur a gaz, a moderateur solide, pour propulsion navale

    Energy Technology Data Exchange (ETDEWEB)

    Pheline, J.; Gautier, A.

    1960-01-04

    In this contribution, the authors discuss works performed in France for the development of nuclear propulsion in merchant ships, notably for an oil tanker of 50.000 tons with 17 knot speed, i.e. a 20.000 Hp engine with an energy produced by a 60 MW gas reactor with a solid moderator and comprising 400 channels loaded with uranium oxide enriched ay 2.8 per cent and sheathed with a refractory alloy. The authors discuss the possible materials for the moderator, the heat transfer medium, the sheath, the fuel and the structures, and report technological studies (mechanical tests, irradiation tests) performed to investigate material properties and their behaviour in operation conditions. They report tests performed to investigate core structure characteristics with respect to neutrons. They finally briefly present a prototype.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-02-20

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

  20. General meeting. Technical reunion: the numerical and experimental simulation applied to the Reactor Physics; Assemblee generale. Reunion technique: la simulation numerique et experimentale appliquee a la physique des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-10-01

    The SFEN (French Society on Nuclear Energy), organized the 18 october 2001 at Paris, a technical day on the numerical and experimental simulation, applied to the reactor Physics. Nine aspects were discussed, giving a state of the art in the domain:the french nuclear park; the future technology; the controlled thermonuclear fusion; the new organizations and their implications on the research and development programs; Framatome-ANP markets and industrial code packages; reactor core simulation at high temperature; software architecture; SALOME; DESCARTES. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Bayle, J

    1996-11-05

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

  2. Tridimensional ultrasonic images analysis for the in service inspection of fast breeder reactors; Analyse d'images tridimensionnelles ultrasonores pour l'inspection en service des reacteurs a neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Dancre, M

    1999-11-01

    Tridimensional image analysis provides a set of methods for the intelligent extraction of information in order to visualize, recognize or inspect objects in volumetric images. In this field of research, we are interested in algorithmic and methodological aspects to extract surface visual information embedded in volume ultrasonic images. The aim is to help a non-acoustician operator, possibly the system itself, to inspect surfaces of vessel and internals in Fast Breeder Reactors (FBR). Those surfaces are immersed in liquid metal, what justifies the ultrasonic technology choice. We expose firstly a state of the art on the visualization of volume ultrasonic images, the methods of noise analysis, the geometrical modelling for surface analysis and finally curves and surfaces matching. These four points are then inserted in a global analysis strategy that relies on an acoustical analysis (echoes recognition), an object analysis (object recognition and reconstruction) and a surface analysis (surface defects detection). Few literature can be found on ultrasonic echoes recognition through image analysis. We suggest an original method that can be generalized to all images with structured and non-structured noise. From a technical point of view, this methodology applied to echoes recognition turns out to be a cooperative approach between morphological mathematics and snakes (active contours). An entropy maximization technique is required for volumetric data binarization. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Bokov, P.M

    2005-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-10-01

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

  6. Study of a criticality accident involving fuel rods and water outside a power reactor; Etude d'un accident de criticite mettant en presence des crayons combustibles et de l'eau hors reacteur de puissance

    Energy Technology Data Exchange (ETDEWEB)

    Beloeil, L

    2000-05-30

    It is possible to imagine highly unlikely but numerous accidental situations where fuel rods come into contact with water under conditions close to atmospheric values. This work is devoted to modelling and simulation of first instants of the power excursion that may result from such configurations. We show that void effect is a preponderant feedback for most severe accidents. The formation of a vapour film around the rods is put forward and confirmed with the help of experimental transients using electrical heating. We propose then a vapour/liquid flow model able to reproduce void fraction evolution. The vapour film is treated as a compressible medium. Conservation balance equations are solved on a moving mesh with a two-dimensional scheme and boundary conditions taking notice of interfacial phenomena and axial escape possibility. Movements of the liquid phase are modelled through a non-stationary integral equation and a dissipative term suited to the particular geometry of this flow. The penetration of energy into the liquid is also calculated. Thus, the coupling of aerodynamic and hydrodynamic modules gives results in excellent agreement with experiments. Next, neutronic phenomena into the fuel pellet, their feedback effects and the distribution of power through the rod are numerically translated. For each developed module, validation tests are provided. Then, it is possible to simulate the first seconds of the whole criticality accident. Even if this calculation tool is only a way of study as a first approach, performed simulations are proving coherent with reported data on recorded accidents. (author)

  7. Fuel cycle: the transition between the third and the fourth generation of reactors; Cycle du combustible: faire la transition vers les 3eme et 4eme generations de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Many challenges arrive today for the french research and development on the fuel cycle: promote the industrial technologies, improve the world increase of the nuclear and adapt the fuel cycle technologies to the future reactors. In this framework the report presents after a recall on the fuel cycle, the researches on the fuel, the optimization of the recycling, the wastes management, the simulation and Phenix an experimentation tool for the fuel. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Gaudier, F

    1999-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Viollet, P.L.

    1995-06-01

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

  10. Modeling in fast dynamics of accidents in the primary circuit of PWR type reactors; Modelisation en dynamique rapide d'accidents dans le circuit primaire des reacteurs a eau pressurisee

    Energy Technology Data Exchange (ETDEWEB)

    Robbe, M.F

    2003-12-01

    Two kinds of accidents, liable to occur in the primary circuit of a Pressurized Water Reactor and involving fast dynamic phenomena, are analyzed. The Loss Of Coolant Accident (LOCA) is the accident used to define the current PWR. It consists in a large-size break located in a pipe of the primary circuit. A blowdown wave propagates through the circuit. The pressure differences between the different zones of the reactor induce high stresses in the structures of the lower head and may degrade the reactor core. The primary circuit starts emptying from the break opening. Pressure decreases very quickly, involving a large steaming. Two thermal-hydraulic simulations of the blowdown phase of a LOCA are computed with the Europlexus code. The primary circuit is represented by a pipe-model including the hydraulic peculiarities of the circuit. The main differences between both computations concern the kind of reactor, the break location and model, and the initialization of the accidental operation. Steam explosion is a hypothetical severe accident liable to happen after a core melting. The molten part of the core (called corium) falls in the lower part of the reactor. The interaction between the hot corium and the cold water remaining at the bottom of the vessel induces a massive and violent vaporization of water, similar to an explosive phenomenon. A shock wave propagates in the vessel. what can damage seriously the neighbouring structures or drill the vessel. This work presents a synthesis of in-vessel parametrical studies carried out with the Europlexus code, the linkage of the thermal-hydraulic code Mc3d dedicated to the pre-mixing phase with the Europlexus code dealing with the explosion, and finally a benchmark between the Cigalon and Europlexus codes relative to the Vulcano mock-up. (author)

  11. Analyse of the potential of the high temperature reactor with respect to the use of fissile materials; Analyse des capacites des reacteurs a haute temperature sous l'aspect de l'utilisation des matieres fissiles

    Energy Technology Data Exchange (ETDEWEB)

    Damian, F

    2001-07-01

    The high temperature reactors fuel is made of micro-particles dispersed in a graphite matrix. This configuration makes it possible to reach high burnup, higher than 700 GWj/t. Thanks to the decoupling between the thermal and the neutronic behaviors in the core many types of fuels can be used. These characteristics give to HTR reactor very good capacities to burn fissile materials. This work was done in the frame of the evaluation of HTR capacities to enhance the value of the plutonium stocks. These stocks are currently composed of the irradiated fuels discharged from classical PWR or the dismantling of the nuclear weapons and represent a significant energy potential. These studies concluded that high cycles length can be reached whatever the plutonium quality is (from 50 % to 94 % of fissile plutonium). In addition, it was demonstrated that the moderator temperature coefficient becomes locally positive for highly burn fuel while the core global moderator temperature coefficient remained negative in the operation range of the reactor. A significant share of this work was first devoted to the setting of a modeling of the fuel element but also of the reactor's core with the codes of system SAPHYR. The whole of modeling was validated by reference calculations. This work of code assessment is justified by a preliminary work that showed that the classical calculation scheme used for PWR could not be transposed directly to HTR core. (author)

  12. A multi-agent design for a pressurized water reactor (P.W.R.) control system; Modelisation multi-agents pour la conduite d'un reacteur a eau sous pression (REP)

    Energy Technology Data Exchange (ETDEWEB)

    Aimar-Lichtenberger, M. [Paris-11 Univ., 91 - Orsay (France)

    1999-01-01

    This PhD work is in keeping with the complex industrial process control. The starting point is the analysis of control principles in a Pressurized Water Reactor (P.W.R). In order to cope with the limits of the present control procedures, a new control organisation by objectives and means is defined. This functional organisation is based on the state approach and is characterized by the parallel management of control functions to ensure the continuous control of the installation essential variables. With regard to this complex system problematic, we search the most adapted computer modeling. We show that a multi-agent system approach brings an interesting answer to manage the distribution and parallelism of control decisions and tasks. We present a synthetic study of multi-agent systems and their application fields.The choice of a multi-agent approach proceeds with the design of an agent model. This model gains experiences from other applications. This model is implemented in a computer environment which combines the mechanisms of an object language with Prolog. We propose in this frame a multi-agent modeling of the control system where each function is represented by an agent. The agents are structured in a hierarchical organisation and deal with different abstraction levers of the problem. Following a prototype process, the validation is realized by an implementation and by a coupling to a reactor simulator. The essential contributions of an agent approach turn on the mastery of the system complexity, the openness, the robustness and the potentialities of human-machine cooperation. (author)

  13. Elaboration by tape-casting and co-sintering of multilayer catalytic membrane reactor- performances; Elaboration par coulage en bande et cofrittage de reacteurs catalytiques membranaires multicouches-performances

    Energy Technology Data Exchange (ETDEWEB)

    Julian, A

    2008-12-15

    This research deals with the increasing interest of the conversion of natural gas into liquid fuels (diesel, kerosene) using the Gas To Liquid (GTL) process. Within this context, Catalytic Membrane-based Reactors (CMR) would allow an improvement of the process efficiency and a reduction of investment and production costs with respect to the present technologies. They allow performing the separation of oxygen from air, and the conversion of natural gas into synthesis gas within a single step. After having highlighted the economical and technological advantages of using a ceramic membrane for the production of syngas (H{sub 2} + CO{sub 2}), the author describes the protocols of synthesis of powders selected for the dense membrane and the porous support, and their physical characteristics. The obtained powders are then adapted to the tape-casting forming process. Graded-composition multilayer structures and microstructure are then elaborated by co-sintering. Performances in terms of membrane oxygen flows are presented. Mechanisms limiting the oxygen flow are discussed in order to propose ways of improving membrane performances. The limits of the studied system are defined in terms of elastic properties, and optimization ways are proposed for the dense membrane material composition in terms of mechanical properties and performance in oxygen semi-permeation.

  14. 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 results. However, these results were obtained without taking into account the presence of atomic hydrogen in the plasma. A thorough study of the effect of atomic hydrogen on the metastable structures produced in simulation is thus carried out. The study of the interaction of atomic hydrogen on the surface of the cluster gives the possibility of finding the proportion of mechanisms (Eley-Rideal hydrogen desorption, hot atom mechanism or absorption on the surface of the cluster) in agreement with experiments on recombination on silicon surfaces. The interaction of atomic hydrogen with the surface of the clusters also induces a modification of the internal organization of the silicon atoms. The organization of the internal silicon atoms of the clusters as a function of cluster size (magic number) makes it possible to understand why the experimental observations indicate the presence of crystalline structures. Finally this study leads to the prediction of a particularly stable structure which could be used as precursor for the growth of silicon nano-wires. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Kerdraon, D

    2001-10-01

    Accelerator Driven Systems (ADS), based on a proton accelerator and a sub-critical core coupled with a spallation target, offer advantages in order to reduce the nuclear waste radiotoxicity before repository closure. Many studies carried out on the ADS should lead to the definition of an experimental plan which would federate the different works in progress. This thesis deals with the neutronic Monte Carlo simulations with the MCNPX code to optimize such a system in view of a pilot reactor building. First, we have recalled the main neutronic properties of an hybrid reactor. The concept of gas-cooled eXperimental Accelerator Driven System (XADS) chosen for our investigations comes from the preliminary studies done by the Framatome company. In order to transmute minor actinides, we have considered the time evolution of the main fuels which could be reasonably used for the demonstration phases. The neutronic parameters of the reactor, concerning minor actinide transmutation, are reported. Also, we have calculated the characteristic times and the transmutation rates in the case of {sup 99}Tc and {sup 129}I isotopes. We have identified some neutronic differences between an experimental and a power ADS according to the infinite multiplication coefficient, the shape factor and the level of flux to extend the demonstrator concept. We have proposed geometric solutions to keep the radial shape factor of a power ADS acceptable. In the last part, beyond the experimental XADS scope, we have examined the possible transition towards an uranium/thorium cycle based on Molten Salt Reactors using a power ADS in order to generate the required {sup 233}U proportion. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Rubiolo, P.R

    2000-03-01

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

  17. Characterization of a siphonal flow electro-coagulation reactor for the water de-pollution; Caracterisation d'un reacteur d'electrocoagulation a ecoulement siphoide pour la depollution des eaux

    Energy Technology Data Exchange (ETDEWEB)

    Deffontaines, B.; Deffontaines-Fourez, M.; Thivel, P.X. [Unversite du Littoral - Cote d' Opale, Centre Universitaire Descartes, Lab. d' Etude en Genie Industriel et Management Environnemental, 62 - Longuenesse (France)

    2001-07-01

    The aim of this study is the establishment of a global quantitative relation between the kinetic and the hydrodynamic of a siphonal flow reactor. First results of the application in dyeing effluents recycling illustrate the reactor performance on the MES abatement and the turbidity of the recycling waters in the production cycle. (A.L.B.)

  18. Rare earths as burnable poison for extended cycles control in electricity generation reactors; Etude des terres rares en tant que poison consommable pour le controle des cycles allonges pour les reacteurs electrogenes

    Energy Technology Data Exchange (ETDEWEB)

    Asou, M

    1995-05-12

    The search of an optimization of the French electronuclear network operations leads to a necessary optimization of the core performances. All the economic studies performed by the utilities had shown that there is a real gain to minimize shut down periods for refueling. So, increasing the cycle length from 12 to 18 months will present a gain of shut down for a three years operation period. The theoretical burnable absorber will be a fuel admixed material bringing the required initial negative reactivity with a burn-up kinetic well suited to the fuel and allowing the lowest residual penalty as possible. The residual penalty us defined in this case by the non complete burn up of the poison, by the low of fissile material and by the accumulate of residual isotopes or nuclides. Because of the well known use of gadolinium as burnable absorber for BWR`s and PWR`s operations, the search for the best compromise to optimize all the above stress is pointed towards the rare earths. In the nuclides family, considering criteria such as cross sections, natural abundance and availability only five nuclides can play the role as burnable absorbers, namely: gadolinium, samarium, dysprosium, europium and erbium. The study presented here will show that only gadolinium and erbium will be considered to control the reactivity of the PWR`s. (author). 58 refs., 65 figs., 47 tabs.

  19. Hydrodynamic and biological study of a methanogenic bio-film process: the inverse turbulent bed reactor; Etude hydrodynamique et biologique d'un procede de methanisation a biofilm: le reacteur a lit turbule inverse

    Energy Technology Data Exchange (ETDEWEB)

    Michaud, S.

    2001-11-01

    This work deals with the operation and start-up of a turbulent bed reactor with ExtendospheresO as a support, for the anaerobic treatment of a food process wastewater. An hydrodynamic study was carried out to characterise the liquid flow and mixing with this carrier of small size (147 {mu}m) and density (0.7). Phase behaviour during fluidizing gas injection can be described by an homogeneous liquid-solid pseudo-fluid whose apparent viscosity depends on the solid concentration. A biological study showed that the initial contact between cells and particles caused a physiological adaptation of microorganisms to the presence of solid after a transitory inhibition of methane production. The methane yield has been showed to be an interesting parameter to monitor bio-film formation and detachment. A low hydraulic retention time during the start-up period has been decisive to reduce the lag-period during carrier colonization. A robust continuous operation of the reactor has been obtained using a pH-controlled feeding. Gas velocity has been shown to be an important parameter to control cells concentration, density and durability of the bio-film. (author)

  20. Homogenization of some radiative heat transfer models: application to gas-cooled reactor cores; Homogeneisation de modeles de transferts thermiques et radiatifs: application au coeur des reacteurs a caloporteur gaz

    Energy Technology Data Exchange (ETDEWEB)

    El Ganaoui, K

    2006-09-15

    In the context of homogenization theory we treat some heat transfer problems involving unusual (according to the homogenization) boundary conditions. These problems are defined in a solid periodic perforated domain where two scales (macroscopic and microscopic) are to be taken into account and describe heat transfer by conduction in the solid and by radiation on the wall of each hole. Two kinds of radiation are considered: radiation in an infinite medium (non-linear problem) and radiation in cavity with grey-diffuse walls (non-linear and non-local problem). The derived homogenized models are conduction problems with an effective conductivity which depend on the considered radiation. Thus we introduce a framework (homogenization and validation) based on mathematical justification using the two-scale convergence method and numerical validation by simulations using the computer code CAST3M. This study, performed for gas cooled reactors cores, can be extended to other perforated domains involving the considered heat transfer phenomena. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Seiler, J.M.; Froment, K

    2003-07-01

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

  2. 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.

  3. AREVA Technical Days (ATD) session 3: operations of the reactors and services division, technical and economic aspects; AREVA Technical Days (ATD) session 3: les activites du pole reacteurs et services, aspects techniques et economiques

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This third session deals with the reactors technologies basics, the EPR and SWR 1000 issues and outlook, the nuclear systems of the future, the business opportunities and business models. (A.L.B.)

  4. Slug-Burst Detection in the G3 Reactor; La detection de rupture de gaine au reacteur G3; Obnaruzhenie razryva obolochki v reaktore G3; Deteccion de fallas del revestimiento en el reactor G3

    Energy Technology Data Exchange (ETDEWEB)

    Plisson, J. [Centre d' Etudes Nucleaires de Marcoule (France)

    1963-10-15

    The author explains the principles underlying slug-burst detection and describes the construction of the apparatus concerned. The main features are a) fully automatic operation, b) centralization of data in the control room and c) measurement by electrostatic collection on a turntable. (author) [French] Dans ce memoire, l'auteur expose les principes sur lesquels est fondee la detection de rupture de gaines et il decrit la realisation des installations. Les caracteristiques principales sont a) l'automatisme integral, b) la centralisation des informations dans la salle de commande et c) mesure par collection electrostatique sur plaque tournante. (author) [Spanish] El autor expone los principios en que se basa la deteccion de las fallas en los revestimientos de los elementos combustibles y describe las caracteristicas principales de la instalacion, que son: a) automatizacion integral, b) centralizacion de las informaciones en la sala de mandos, y c) medicion por recoleccion electrostatica sobre una placa giratoria. (author) [Russian] Izlagayutsya printsipy, na kotorykh osnovano obnaruzhenie razryva obolochki, opisyvaetsya konstruirovanie ustanovok. Osnovnye kharakteristiki takovy: a) integral'nyj avtomatizm, b) tsentralizatsiya informatsii v komandnom zale i c) izmerenie putem ehlektrostaticheskogo sobiraniya na povorachivayushchejsya plastinke. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Allais, V

    1998-03-01

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

  6. Turbulent precipitation of uranium oxalate in a vortex reactor - experimental study and modelling; Precipitation turbulente d'oxalate d'uranium en reacteur vortex - etude experimentale et modelisation

    Energy Technology Data Exchange (ETDEWEB)

    Sommer de Gelicourt, Y

    2004-03-15

    Industrial oxalic precipitation processed in an un-baffled magnetically stirred tank, the Vortex Reactor, has been studied with uranium simulating plutonium. Modelling precipitation requires a mixing model for the continuous liquid phase and the solution of population balance for the dispersed solid phase. Being chemical reaction influenced by the degree of mixing at molecular scale, that commercial CFD code does not resolve, a sub-grid scale model has been introduced: the finite mode probability density functions, and coupled with a model for the liquid energy spectrum. Evolution of the dispersed phase has been resolved by the quadrature method of moments, first used here with experimental nucleation and growth kinetics, and an aggregation kernel based on local shear rate. The promising abilities of this local approach, without any fitting constant, are strengthened by the similarity between experimental results and simulations. (author)

  7. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Barale, M

    2006-12-15</