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Sample records for french reactors progres

  1. 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

    electrostatic collecting 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

  2. Status of French reactors

    International Nuclear Information System (INIS)

    Ballagny, A.

    1997-01-01

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

  3. Recent technical progress in the French uranium industry; Les recents progres techniques dans l'industrie de l'uranium en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    This paper reviews the present-day uranium production situation in France. The various stages of the treatment the concentrates receive, leading to the final production of the metal, are described briefly: dissolution, purification by extraction with a mixture of tributyl phosphate and white spirit, precipitation with ammonia, drying and calcination of the trioxide, reduction with hydrogen, cracked ammonia or preferably pure ammonia gas, fluorination with anhydrous hydrofluoric acid, and production of the metal by the calcium thermite process. Recent work of an original nature is discussed in greater detail. (author) [French] L'expose fait le point de la technique actuelle en ce qui concerne la fabrication de l'uranium en France. Il retrace brievement les diverses etapes du traitement des concentres pour aboutir au metal: mise en solution, purification par extraction au melange phosphate de tributylo-white spirit, precipitation par l'ammoniaque, sechage et calcination du trioxyde, reduction a l'hydrogene, a l'ammoniac craque ou mieux au gaz ammoniac pur, fluoruration par l'acide fluorhydrique anhydre et elaboration du metal par calciothermie. De plus amples details sont donnes sur les realisations recentes d'un caractere original. (auteur)

  4. Renewal of the French fleet of nuclear reactors

    International Nuclear Information System (INIS)

    Nifenecker, Herve

    2012-01-01

    While supposing the lifetime of all present PWR reactors would be extended to sixty years, the author compares two scenarios regarding the renewal of the French fleet of nuclear reactors: the first one over 40 years and the second one over 20 years. This renewal is based on the construction of EPR reactors at different rhythms. The author compares the associated production costs and assesses the exploitation costs. A renewal scenario over 40 years seems to give better results

  5. French activities on gas cooled reactors

    International Nuclear Information System (INIS)

    Bastien, D.

    1996-01-01

    The gas cooled reactor programme in France originally consisted of eight Natural Uranium Graphite Gas Cooled Reactors (UNGG). These eight units, which are now permanently shutdown, represented a combined net electrical power of 2,375 MW and a total operational history of 163 years. Studies related to these reactors concern monitoring and dismantling of decommissioned facilities, including the development of methods for dismantling. France has been monitoring the development of HTRs throughout the world since 1979, when it halted its own HTR R and D programme. France actively participates in three CRPs set up by the IAEA. (author). 1 tab

  6. The French-German common safety approach for future reactors

    International Nuclear Information System (INIS)

    Birkhofer, A.; Chevet, P.F.

    1995-01-01

    A common safety approach has been defined for future electronuclear plants in the framework of the French-German European Pressurised water Reactor (EPR) project. Improvements in the domain of containment are required in future reactors conception to prevent any risk of core fusion under high and low pressure. Another objective is to reduce significantly the radioactive releases due to other accidents in order to reduce spatial and temporal environmental and human protection procedures. Protection against external aggressions (plane fall, explosions, earthquakes,..), prevention of pipe rupture in the primary circuits, limitation of hydrogen production in the case of water-zirconium complete reaction, cooling of the reactor in the case of core fusion, and radiologic consequences of accidents are the main points discussed by the French-German safety authorities to define the common safety standards of the EPR project. (J.S.)

  7. Alternative fuels for the French fast breeder reactors programme

    International Nuclear Information System (INIS)

    Bailly, H.; Bernard, H.; Mansard, B.

    1989-01-01

    French fast breeder reactors use mixed oxide as reference fuel. A great deal of experience has been gained in the behaviour and manufacture of oxide fuel, which has proved to be the most suitable fuel for future commercial breeder reactors. However, France is maintaining long-term alternative fuels programme, in order to be in a position to satisfy eventually new future reactor design and operational requirements. Initially, the CEA in France developed a carbide-based, sodium-bonded fuel designed for a high specific power. The new objective of the alternative fuels programme is to define a fuel which could replace the oxide without requiring any significant changes to the operating conditions, fuel cycle processes or facilities. The current program concentrates on a nitride-based, helium-bonded fuel, bearing in mind the carbide solution. The paper describes the main characteristics required, the manufacturing process as developed, the inspection methods, and the results obtained. Present indications are that the industrial manufacture of mixed nitride is feasible and that production costs for nitride and oxide fuels would be not significantly different. (author) 8 refs., 2 figs

  8. French experience in using programmable systems for the control and the protection of nuclear reactors

    International Nuclear Information System (INIS)

    Jover, P.

    1986-01-01

    The paper presents the results obtained in the use of two automated systems important to safety in 1300 MWE French nuclear reactors: the numerical integrated protection system (SPIN) and the logical control system (CONTROBLOC)

  9. French experience in design, operation and revamping of nuclear research reactors, in support of advanced reactors development

    International Nuclear Information System (INIS)

    Barre, B.; Bergeonneau, P.; Merchie, F.; Minguet, J.L.; Rousselle, P.

    1996-01-01

    The French nuclear program is strongly based on the R and D work performed in the CEA nuclear research centers and particularly on the various experimental programs carried out in its research reactors in the frame of cooperative actions between the Commissariat a l'Energie Atomique (CEA), Framatome and Electricite de France (EDF). Several types of research reactors have been built by Technicatome and CEA to carry out successfully this considerable R and D work on fuels and materials, among them the socalled Materials Testing Reactors (MTR) SILOE (35 MW) and OSIRIS (70 MW) which are indeed very well suited for technological irradiations. Their simple and flexible design and the large irradiation space available around the core, the SILOE and OSIRIS reactors can be shared by several types of applications such as fuel and material testings for nuclear power plants, radioisotopes production, silicon doping and fundamental research. It is worthwhile recalling that Technicatome and CEA have also built research reactors fully dedicated to safety experimental studies, such as the CABRI, SCARABEE and PHEBUS reactors at Cadarache, and others dedicated to fundamental research such as ORPHEE (14 MW) and the Reacteur a Haut Flux -High Flux Reactor- (RHF 57 MW). This paper will present some of the most significant conceptual and design features of all these reactors as well as the main improvements brought to most of them in the last years. Based on this wide experience, CEA and Technicatome have specially designed for export a new multipurpose research reactor named SIRIUS, with two versions depending on the utilization spectrum and the power range (5 MW to 30 MW). At last, CEA has recently launched the preliminary project study of a new MTR, the Jules Horowitz Reactor, to meet the future needs of fuels and materials irradiations in the next 4 or 5 decades, in support of the French long term nuclear power program. (J.P.N.)

  10. The Psychosis Recent Onset GRoningen Survey (PROGR-S) : Defining Dimensions and Improving Outcomes in Early Psychosis

    NARCIS (Netherlands)

    Liemburg, Edith J.; Castelein, Stynke; van Es, Frank; Scholte-Stalenhoef, Anne Neeltje; van de Willige, Gerard; Smid, Henderikus; Visser, Ellen; Knegtering, Henderikus; Bruggeman, Richard

    2014-01-01

    Psychotic disorders are among the most complex medical conditions. Longitudinal cohort studies may offer further insight into determinants of functional outcome after a psychotic episode. This paper describes the Psychosis Recent Onset in GRoningen Survey (PROGR-S) that currently contains data on

  11. Assessment of hydrogen risk in French pressurized water nuclear reactors

    International Nuclear Information System (INIS)

    Duco, J.; Rousseau, L.; Evrard, J.M.

    1983-12-01

    During the course of a severe core accident, hydrogen evolving, mainly due to zircaloy cladding-steam reaction, may form early a flammable mixture in the containment. The risk of a short-term containment failure due to a hydrogen explosion, which would result in a large radioactivity release into the environment, is currently being assessed for the various types of large dry containments existing for French PWRs. In this framework, comparisons between pressure peaks, due to the most severe conceivable hydrogen deflagration, and the realistic ultimate strength of French containment buildings have led to the conclusion that containment integrity should not be questioned. However the problem of the likehood of local detonations and of their impact on structures is still examined. Another aspect of the hydrogen risk is the possible impairment of safety-related equipment in the containment during an eventual hydrogen combustion or explosion. Information coming from the EPRI research program on hydrogen combustion and control, in which the safety body (CEA/IPSN) and the utility (EDF) jointly took a participation, is to back up our own studies on hydrogen risk analysis. Up to now all the results gathered as regards the integrity of the large, dry containments of the French PWRs against hydrogen explosion tend to relegate such a risk to the level of a residual risk. Although the studies are going on a drastic change of this trend in the future is not expected. Therefore no hydrogen specific design modification is presently required by the safety authorities

  12. Burst slug detection system in french power reactors (1961)

    International Nuclear Information System (INIS)

    Megy, J.; Roguin, A.

    1961-01-01

    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) [fr

  13. The safety of French pressurised water reactors: a regulator's perspective

    International Nuclear Information System (INIS)

    Lacoste, A.-C.

    1993-01-01

    France has invested heavily in nuclear technology and is today, arguably, the dominant player in the industry: in EdF we have a utility operating over 50 reactors; in Cogema we have a company operating in every sector of the fuel cycle industry; and in Framatome, perhaps the major nuclear reactor constructor in the world. As wedded as the country is to nuclear energy, France has to be aware of any potentially harmful developments - politically, socially and industrially. Neither can the international arena be neglected, where events can have a profound effect on France's worldwide interests. The following articles demonstrate how much energy and ingenuity France is devoting to resolving the many critical issues facing its nuclear industry, including safety, economics and waste disposal. (Author)

  14. Alternative fuels for the French fast breeder reactors programme

    International Nuclear Information System (INIS)

    Bailly, H.; Bernard, H.; Mansard, B.

    1988-01-01

    At the present time, due to the very competitive cost per kWh produced in France by the PWRs, it appears clear that, despite the improved use of uranium by FBRs, they will only be developed if the cost of the fuel cycle is sufficiently lower than that of the PWRs to compensate for the additional investment. The current economic programme has fixed the following fuel related objectives: - burn-up as high possible, the value of 150 000 MWd/t being considered as a minimum, and not a final target to be achieved, - extension of the duration of reactor operation cycles, leading to high in-pile times for fuel. Reaching the latter objective depends on obtaining high internal breeding gain performances, so that the total reactivity drop related to fuel impoverishment can be minimized. In this respect, a large diameter oxide fuel and/or an axial heterogeneous core concept can be envisaged. Dense fuels could form another solution. The feasibility of the fabrication of carbide and nitride fuels has been demonstrated in several countries and there is currently convergence towards a single type of process based on a carbothermic reaction. The optimization of fabrication procedures for these fuels must be continued to satisfy economic requirements and to obtain a fabrication cost of the same order or magnitude as that of oxide, although higher. If this target is achieved, fabrication will not be the major criterion for the selection of the FBR fuel, which will then be a function of the cost of reprocessing, performances under irradiation and reactor operating requirements

  15. Development of the French programme on fast reactors, from April 1978 to March 1979

    International Nuclear Information System (INIS)

    Vautrey, L.

    1979-01-01

    During the past year, operation of RAPSODIE and Phenix reactors was satisfactory, as shown in detail in this paper. Construction of the SUPERPHENIX at Creys Malville progressed normally. Studies of nuclear power plants which would follow SUPERPHENIX are in due course. Research and Development activities are is progress, sometimes in order to develop fundamental knowledge and for its application in necessary choice of decisions in the course of project, especially SUPERPHENIX. The order of magnitude of the costs devoted in France to fast reactors in 1978, excluding fuel cycle was 650 million french francs: about 600 in CEA, of which about 100 devoted to safety, and about 50 million at EDF. Personnel engaged amounted to 1500 without the workers in the industry which is participate in he fast reactor projects. One should add international agreements which are made to enforce this potential significantly

  16. Experience relevant to safety obtained from reactor decommissioning operations in the French Atomic Energy Commission

    International Nuclear Information System (INIS)

    Giraudel, B.; Langlois, G.

    1979-01-01

    From among the nuclear facilities constructed in France the authors cite eight large reactors, ranging from critical assemblies to power reactors, that have been finally shut-down since 1965. A brief account is given of the way in which the various operations were carried out after the final control rod drop, a distinction being drawn between the shut-down proper and the containment and dismantling work. A description is also given, from the technical and regulatory standpoint, of the final stage attained, and mention is made of French safety arrangements and of the part played by the safety services during decommissioning operations. Among the lessons derived from French experience, the authors mention the completion of operations without any serious safety problems, and with guarantees for the protection of personnel and the population as a whole, by conventional techniques; the advantage of planning decommissioning operations from the very beginning of construction of the facilities; and the importance of filing descriptive documents. In view of the experience gained, the French Atomic Energy Commission has devised internal procedures for facilitating the application of regulations governing the shut-down and decommissioning phases, which are aimed at preserving surveillance procedures similar to those in force during normal operation. (author)

  17. Acoustic detection of a cavitation noise in the French breeder reactor Phenix

    International Nuclear Information System (INIS)

    Brunet, M.; Desprets, A.

    1981-06-01

    The French Phenix reactor is provided with an in-core multi-sensor acoustic surveillance system. But its efficiency with regard to early boiling detection is still to be proven. For lack of boiling events within the core, a cavitating dummy steel subassembly has been loaded into the reactor, as a simulation of boiling signal. Cavitation is controlled through a slow rise of the primary flow in various core conditions: isothermal situation and during a rise of power. Assuming that the signal to noise ratio is of the same order of magnitude for cavitation signals as for boiling ones, the response of several signal processing techniques is evaluated. Pulse connecting seems to be the most efficient conventional method while pattern recognition appears as a promising alternative solution

  18. Evolution of the microstructure of a French reactor pressure vessel steel under neutron irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Huang, H.F.; Radiguet, B.; Pareige, P. [Groupe de physique des materiaux, UMR CNRS 6634, Universite et INSA de Rouen, avenue de l' Universite, 76801 Saint Etienne du Rouvray (France); Todeschini, P. [EDF, Materials and Mechanics of Component Department, Site des Renardieres-Ecuelles, 77818 Moret-sur-Loing cedex (France); Chas, G. [EDF, Production and Engineering Branch, CEIDRE/DLAB, CNPE de Chinon, BP 23, 37420 Avoine (France)

    2011-07-01

    The microstructure of a low copper French reactor pressure vessel steel, neutron irradiated within the frame of the EDF Surveillance Program of a production reactor, was characterised by atom probe tomography. Specimens were irradiated at low flux (2*10{sup 15} m{sup -2}/s), at 4 different fluences up to 7.6*10{sup 23} m{sup -2}. Atom Probe experiments have revealed the presence of roughly spherical clusters enriched in nickel, manganese, silicon and, in a lesser extent, phosphorus and copper at all irradiation fluences. The chemical composition of these clusters shows no evolution with fluence, as well as their diameter, close to 3 nm. On the contrary, their number density increases linearly with the neutron fluence. Continuous segregation of the elements found in the clusters is also observed along dislocation lines, with similar enrichments. (authors)

  19. France - About the possibility to stop the 19 French reactors which are over 30 years of service. Overview of conditions for phasing out nuclear under condition

    International Nuclear Information System (INIS)

    Lenoir, Yves

    2011-03-01

    After having set a 30 year limit for a nuclear reactor life, the author analyses the associated consequences in terms of loss of production (while taking the load factor of the concerned reactors into account). He indicates the French production of different resources (nuclear, conventional thermal, hydraulic, renewable) and the French energy consumption, assesses the avoided production due to the shutting down of the 19 reactors, outlines that the present reactor fleet is under-exploited, and addresses the peak issue

  20. A prospective scenario of the French nuclear fleet growth based on sodium cooled fast reactor technology

    International Nuclear Information System (INIS)

    Garzenne, Claude; Le Mer, Joel; Lemasson, David; Hoang, Manh-Hung

    2011-01-01

    Generation IV Sodium cooled Fast Reactors (SFR) deployment would allow to optimize the use of the various available resources (natural, reprocessed and depleted uranium, plutonium) thanks to breeding capacities featuring a valuable advantage with respect to the fuel cycle flexibility and fissile material management. The complete replacement of the 60 GWe French nuclear fleet by GEN IV SFRs in 2100 would require around 1000 tons of plutonium. An accurate simulation of this prospective scenario shows that the amount of plutonium issued from the French PWRs spent fuel reprocessing would not be enough. The lacking amount of plutonium could be produced with fertile blankets during the transient SFR deployment phase. A more ambitious research scenario, aimed at doubling the nuclear French fleet installed power in 2100, would require to use SFRs at their maximum breeding capacity. However, it is not possible to deploy more than about 100 GWe of SFRs in 2100, meaning that the fleet growth would have to be partially supported by GEN III PWRs. Using the scenario simulation code TIRELIRE-STRATEGIE, we have optimized the main scenario parameters: the capacities of the fuel cycle facilities, the proportion of PWRs necessary for supporting the growth phase, the kinetics of SFRs deployment compatible with the plutonium build-up, etc., while respecting industrial constraints such as a realistic cooling time before reprocessing, a fuel cycle plants utilization rate constant over several decades, etc.. We illustrate the impact of this French fleet growth scenario over the nuclear material fluxes in the fuel cycle plants, the uranium consumption, and the waste production. (author)

  1. The French Atomic Energy Commission program in the field of reactor instrumentation and control

    International Nuclear Information System (INIS)

    Golinelli, C.; Bernard, P.; Thomas, J.B.

    1992-01-01

    The worldwide slowing-down of the nuclear reactor construction must not lead to decrease the Research and Development effort. Particularly, in the field of the Nuclear Instrumentation and Control, new technologies are quickly changing: sensors, electronics, optronics, computer science... The nuclear industry is reluctant to the introduction of new concepts and of sophisticated technologies. Safety requires highly qualified systems. The development process must respect each step: - interest evaluation of the new idea, - designing and manufacturing of a prototype equipment, - qualification using an experimental facility or with a simulator, - qualification in operational condition (reliability, ageing, accidental standards...). We present an overview of the French CEA program covering the IC domain from the sensors to the operator screen

  2. Status of French R and D for advanced light water reactors

    International Nuclear Information System (INIS)

    Nigon, J.L.

    1987-01-01

    Present PWRs lead to a significant reduction of electricity cost when compared to other sources. Then it seems reasonable to keep the main features of PWRs when looking for improvements of investment cost, of operating and fuel costs, of flexibility and of safety. Besides that we have to think about uranium conservation; if nuclear starts again in many countries, as we hope, the uranium market could get into a crisis during the first half of the 21st century, and uranium shortage could become a reality. Advanced PWRs are also aimed at fissile material saving. The three French partners CEA, EdF and FRAMATOME decided to lead a three year programme 1984-1987. FRAMATOME in fact had started a little bit earlier, namely in 1982 (first publication in RNG - a French technical journal) and developed the RCVS, spectral shift convertible reactor core (for both Uranium and Plutonium fuel). FRAMATOME's effort is estimated to about 40.10 6 FF per year. EdF, R and D Division, is associated with this feasibility study. CEA performs an R and D programme, the objectives of which are: to support FRAMATOME for RCVS design; to explore a wider range of parameters in order to estimate the feasibility and the interest of tight lattice PWR cores. Simultaneously, EdF is defining the preliminary specifications of ''REP 2000'' (future standard for French PWRs in the year 2000 and following); the objectives of REP 2000 are: load follow capacity; cost effectiveness; operation flexibility. FRAMATOME's RCVS and the CEA RSM feasibility study have to be considered in this context. The main objectives are: 1) To improve performances, safety and to minimise cost; 2) To save fissile materials according to a global strategy; 3) While minimum modifications of present PWR components will be accepted. The R and D budget for PWRs (outside safety) of French CEA is around 450 10 6 FF per year. Among this, 40 10 6 FF/year are devoted to tight lattice core feasibility studies (period 1984-1987). 3 figs

  3. Breeders: operational experience with fast power reactors in five states - more intensive German-French breeder cooperation

    International Nuclear Information System (INIS)

    Hueper, R.

    1978-01-01

    In the past year contracts have been signed and implemented for German-French cooperation in LMFBR development and commercialization. - The first German nuclear power station with a sodium cooled fast reactor, KNK II in Karlsruhe, is going into operation. - Construction of the prototype SNR 300 at Kalkar (Lower Rhine) is slowing down awaiting a decision of the German Federal Constitutional Court. - On the international level, remarkable experience in the operation of fast power reactors has accumulated. - Possible fuel cycle alternatives are being evaluated by an international committee. (orig.) [de

  4. A probabilistic safety assessment of the standard French 900MWe pressurized water reactor. Main report

    International Nuclear Information System (INIS)

    1990-04-01

    To situate the probabilistic safety assessment of standardized 900 MWe units made by the Institute for Nuclear Safety and Protection (IPSN), it is necessary to consider the importance and possible utilization of a study of this type. At the present time, the safety of nuclear installations essentially depends on the application of the defence in-depth approach. The design arrangements adopted are justified by the operating organization on the basis of deterministic studies of a limited number of conventional situations with corresponding safety margins. These conventional situations are grouped in categories by frequency, it being accepted that the greater the consequences the lesser the frequency must be. However in the framework of the analysis performed under the control of the French safety authority, the importance was rapidly recognized of setting an overall reference objective. By 1977, on the occasion of appraisal of the fundamental safety options of the standardized 1300 MWe units, the Central Service for the Safety of Nuclear Installations (SCSIN) set the following global probabilistic objective: 'Generally speaking, the design of installations including a pressurized water nuclear reactor must be such that the global probability of the nuclear unit being the origin of unacceptable consequences does not exceed 10 -6 per year...' Probabilistic analyses making reference to this global objective gradually began to supplement the deterministic approach, both for examining external hazards to be considered in the design basis and for examining the possible need for additional means of countering the failure of doubled systems in application of the deterministic single-failure criterion. A new step has been taken in France by carrying out two level 1 probabilistic safety assessments (calculation of the annual probability of core meltdown), one for the 900 MWe series by the IPSN and the other for the 1300 MWe series by Electricite de France. The objective of

  5. The use of LBB concept in French fast reactors: Application to SPX plant

    Energy Technology Data Exchange (ETDEWEB)

    Turbat, A.; Deschanels, H.; Sperandio, M. [and others

    1997-04-01

    The leak before break (LBB) concept was not used at the design level for SUPERPHENIX (SPX), but different studies have been performed or are in progress concerning different components : Main Vessel (MV), pipings. These studies were undertaken to improve the defense in depth, an approach used in all French reactors. In a first study, the LBB approach has been applied to the MV of SPX plant to verify the absence of risk as regards the core supporting function and to help in the definition of in-service inspection (ISI) program. Defining a reference semi-elliptic defect located in the welds of the structure, it is verified that the crack growth is limited and that the end-of-life defect is smaller than the critical one. Then it is shown that the hoop welds (those which are the most important for safety) located between the roof and the triple point verify the leak-before-break criteria. However, generally speaking, the low level of membrane primary stresses which is favorable for the integrity of the vessel makes the application of the leak-before-break concept more difficult due to small crack opening areas. Finally, the extension of the methodology to the secondary pipings of SPX incorporating recent European works of DCRC is briefly presented.

  6. Technology transfers associated to the safety analysis of French exported reactors

    International Nuclear Information System (INIS)

    Lalere, J.; Lebouleux, P.

    1984-11-01

    The standardization of the French electronuclear program presents an important advantage: power plants exported by the French nuclear industry, identical with those conceived for the French program, profit by the eperience acquired along the realization and the exploitation of all these units, what is particularly appreciable in the safety field. This paper presents the French safety analysis with its regulation basis and its specific points. Then, a particular attention is paid to French nuclear power plants dimensionning. The IPSN participates in the safety evaluations of the exported units, what allows it to transfer to the safety organizations of customer countries a knowledge and a know-how important for the control they will exercise on the safety of their electronuclear program [fr

  7. Status of the French research in the field of molten salt nuclear reactors

    International Nuclear Information System (INIS)

    Hery, M.; Israel, M.; Fauger, P.; Lecocq, A.

    1977-01-01

    The research program of the CEA in the field of molten salt nuclear reactors has been concerned with MSBR type reactors (Molten Salt Breeder Reactor). The papers written after having performed the theoretical analysis are entitled: core, circuits, chemistry and economy; they include some criticisms and suggestions. The experimental studies consisted in: graphite studies, chemical studies of the salt, metallic materials, the salt loop and the lead loop [fr

  8. AGR-2: The first irradiation of French HTR fuel in Advanced Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, T., E-mail: thierry.lambert@cea.fr [Commissariat a l' Energie Atomique, Centre d' etudes de Cadarache, DEN/DEC, F-13108 St Paul lez Durance (France); Grover, B., E-mail: Blaine.Grover@inl.gov [Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415 (United States); Guillermier, P., E-mail: pierre.guillermier@areva.com [AREVA NP, 10 rue Juliette Recamier 69456 Lyon Cedex 06 (France); Moulinier, D., E-mail: dominique.moulinier@cea.fr [Commissariat a l' Energie Atomique, Centre d' etudes de Cadarache, DEN/DEC, F-13108 St Paul lez Durance (France); Huart, F. Imbault, E-mail: florent.imbault-huart@areva.com [AREVA NP, 10 rue Juliette Recamier 69456 Lyon Cedex 06 (France)

    2012-10-15

    AGR-2, the second irradiation of the US program for qualification of the NGNP fuel, is open to international participation within the scope of the Generation IV International Forum. In this frame, it includes in its multi-capsule irradiation rig an irradiation of French HTR fuel manufactured in the CAPRI line (GAIA facility at CEA/Cadarache and AREVA/CERCA compacting line at Romans). The AGR-2 irradiation is designed to place our first fabrications of HTR particles under operating conditions that are representative of ANTARES project while keeping close to the test range of the German fuel as much as possible, which is the reference in terms of irradiation behavior. A few batches of particles and 12 fuel compacts were produced and characterized in 2009 by CEA and CERCA. The fuel main characteristics are in conformity with our specifications and in compliance with INL requirements. The AGR-2 experiment is based on the design and devices used in the first experiment of the AGR program. The design makes it possible to monitor the irradiation conditions and in particular, the temperature, the power and the fission products released from fuel particles. The in pile equipment consists of a multi-capsule device designed to simultaneously irradiate six independent capsules with temperature control. The out-of-core part consists of the equipment for actively controlling temperature and measuring the fission products release on-line. The target conditions for the irradiation experiment were defined with the aim of comparing the results obtained under irradiation with German particles along with the objectives of reaching burn-up and fluence targets to validate the behavior of our fuel in a significant range (15% FIMA - 5 Multiplication-Sign 10{sup 25} n/m{sup 2} at 600 EFPD with centerline fuel temperature about 1100 Degree-Sign C). These conditions have to be representative of ANTARES project characteristics. These target conditions were compared with final results from

  9. The significance of the human factor in the safety of nuclear reactors: the French experience and the lessons of Three Mile Island

    International Nuclear Information System (INIS)

    Houze, C.; Oury, J.M.

    1982-05-01

    The importance of the human factor to French nuclear safety policy and the application of human fallibility as a parameter of safety analysis are described. The impact of reactor operating experience on future theoretical and practical application considerations is discussed. Particular reference is given to the lessons of Three Mile Island

  10. Description of the french graphite reactor and of the experiments performed in 1956

    International Nuclear Information System (INIS)

    Bussac, J.; Leduc, C.; Zaleski, C.P.

    1957-01-01

    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) [fr

  11. Programme of hot points eradication (Co-60) led on French PWR type reactors

    International Nuclear Information System (INIS)

    Rocher, A.; Ridoux, P.; Anthoni, S.; Brun, C.

    1998-01-01

    The question of hot points (pellets rich in cobalt 59 or in cobalt 60 in a PWR type reactor), is studied from the radiation protection point of view. The purpose is to see how to optimize the radiation protection, the elimination of these hot points can bring an improvement. (N.C.)

  12. French experience and prospects in the reprocessing of fast breeder reactor fuels

    International Nuclear Information System (INIS)

    Megy, J.

    1983-06-01

    Experience acquired in France in the field of reprocessing spent fuels from fast breeder reactors is recalled. Emphasis is put on characteristics and quantities of spent fuels reprocessed in La Hague and Marcoule facilities. Then reprocessing developments with the realisation of the new pilot plant TOR at Marcoule, new equipments and study of industrial reprocessing units are reviewed [fr

  13. Comparison between MAAP and ECART predictions of radionuclide transport throughout a French standard PWR reactor coolant system

    International Nuclear Information System (INIS)

    Hervouet, C.; Ranval, W.; Parozzi, F.; Eusebi, M.

    1996-04-01

    In the framework of a collaboration agreement between EDF and ENEL, the MAAP (Modular Accident Analysis Program) and ECART (ENEL Code for Analysis of radionuclide Transport) predictions about the fission product retention inside the reactor cooling system of a French PWR 1300 MW during a small Loss of Coolant Accident were compared. The volatile fission products CsI, CsOH, TeO 2 and the structural materials, all of them released early by the core, are more retained in MAAP than in ECART. On the other hand, the non-volatile fission products, released later, are more retained in ECART than in MAAP, because MAAP does not take into account diffusion-phoresis: in fact, this deposition phenomenon is very significant when the molten core vaporizes the water of the vessel lower plenum. Centrifugal deposition in bends, that can be modeled only with ECART, slightly increases the whole retention in the circuit if it is accounted for. (authors). 18 refs., figs., tabs

  14. Neutron fluence at the reactor pressure vessel wall - a comparison of French and German procedures and strategies in PWRs

    Energy Technology Data Exchange (ETDEWEB)

    Tricot, N. [Institut de Radioprotection et de Surete Nucleaire, IRSN/DES/SECCA, 92 - Fontenay aux Roses (France); Jendrich, U. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Garching (Germany)

    2003-01-01

    While the neutrons within the core may take part in the chain reaction, those neutrons emitted from the core are basically lost for the energy production. This 'neutron leakage' represents a loss of fuel efficiency and causes neutron embrittlement of the reactor pressure vessel (RPV) wall. The latter raises safety concerns, needs to be monitored closely and may necessitate mitigating measures. There are different strategies to deal with these two undesirable effects: The neutron emission may be reduced to some extent all around the core or just at the 'hot spots' of RPV embrittlement by tailored core loading patterns. A higher absorption rate of neutrons may also be achieved by a larger water gap between the core and the RPV. In this paper the inter-relations between the distribution of neutron flux, core geometry, core loading strategy, RPV embrittlement and its surveillance are discussed at first. Then the different strategies followed by the German and French operators are described. Finally the conclusions will highlight the communalities and differences between these strategies as different approaches to the same problem of safety as well as economy. (authors)

  15. Lois et règlements sur la faune sauvage à Madagascar : Progrès ...

    African Journals Online (AJOL)

    Lois et règlements sur la faune sauvage à Madagascar : Progrès accomplis et besoins du futur. ... Wildlife laws which control where these activities can occur, limit the timing of exploitation, or provide strict protection for some species are therefore an important component of the conservation strategy. However it is important ...

  16. How to bring the nuclear share to 50 pc without stopping any reactor, nor increasing CO2 emissions. The issue of renewal of the French nuclear reactor fleet is also part of the debate

    International Nuclear Information System (INIS)

    Nifenecker, Herve

    2013-01-01

    In a first article, after having recalled the present situation of the French energy mix, the author analyses the consequences of the shutting down of 22 nuclear reactors by 2025 to bring the nuclear share down from 75 to 50 per cent. Different options are discussed: fossil energy (but CO 2 emissions would be impacted), renewable energy (hydroelectricity cannot be further developed, biomass can be useful for heat networks, and wind energy is limited). The author examines the possibilities of decreasing electricity consumption, and of a significant contribution of gas plants. He compares direct gas- and fuel oil-based heating with heating with electricity produced by gas plants. A second article addresses the issue of renewal of the French nuclear reactor fleet. It discusses how to choose the right renewal pace, and an assessment of exploitation losses

  17. Assessment of the French and US embrittlement trend curves applied to RPV materials irradiated in the BR2 materials test reactor

    International Nuclear Information System (INIS)

    Chaouadi, R.; Gerard, R.; Boagaerts, A.S.

    2011-01-01

    The irradiation embrittlement of reactor pressure vessels (RPVs) in monitored through the surveillance programs associated with predictive formulas, the so-called embrittlement trend curves. These formulas are generally empirically derived and contain the major embrittlement-inducing elements such as copper, nickel and phosphorus. There are a number of such trend curves used in various regulatory guides used in the US, France, Germany, Russia and Japan. These trend curves are often supported by surveillance data and regularly assessed in view of updated surveillance databases. With the recent worldwide move towards life extension of existing reactors above their initially-scheduled lifetime of 40 years, adequate and accurate modeling of irradiation embrittlement becomes a concern for long term operation. The aim of this work is to assess the performance of the embrittlement trend curves used in a regulatory perspective. The work presented here is limited to US and French trend curves because the reactor pressure vessels of the Belgian nuclear power plants are either Westinghouse or Framatome design. The chemical composition of the Belgian RPVs being very close to the one of the French 900 MW units, the French trend curve is used except for the Doel 1-2 units for which these curves are not applicable due to the higher copper content of the welds. In this case, the U.S. trend curves are used. The aim of this work is to evaluate the performance of the embrittlement trend curves used in a regulatory perspective to represent the experimental data obtained in the BR2 reactor. In particular, the French (FIM, FIS) and the US (Reg. Guide 1.99 Rev. 2, ASTM E900-02, EWO and EONY) formulas are of prime interest. The results obtained clearly show that the French trend curves tend to over-estimate the actual irradiation hardening while the US curves under-estimate it. Within the long term operation perspective, both over- and under-estimating are undesirable and therefore the

  18. Recent progress in the detection of bursts in the canning in French reactors

    International Nuclear Information System (INIS)

    Goupil, J.; Grenon, M.; Raffailhac, J.; Roguin, A.

    1959-01-01

    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 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 3 . The reactor EL 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) [fr

  19. The 40 year deadline for the French nuclear stock. Decision process, strengthening option and costs associated with a possible lifetime extension beyond 40 years of EDF reactors

    International Nuclear Information System (INIS)

    Marignac, Yves

    2014-01-01

    This report first proposes an overview of the lifetime extension problematic (PLEX) for nuclear plants in a general context (strategy of lifetime extension, and uncertainty and lack of return on experience), and in the case of France (emergence of a strategy of lifetime extension, economic challenges of an extension, uncertainty on investments required by an extension, risk of imposed implicit decisions). It gives a rather detailed overview of the French nuclear reactor fleet, of the status of EDF-operated reactors (construction stages, main lifetime events, regulatory situation of currently exploited reactors) and of their characteristics (common operation principle, main components, main safety functions, main considered severe accidents). It addresses safety issues related to ageing and to the post-Fukushima re-assessment (problematic, robustness increase, limits and weaknesses of additional safety assessments). It presents the currently performed improvements (safety referential, applicable strengthening requirements like safety re-examinations and requirements introduced after Fukushima, applied strengthening prescriptions drawn from additional safety assessments or from the third decennial inspection, with their limitations and perspectives). It proposes strengthening scenarios along with their challenges (in terms of requirement level, procedure and agenda). Three scenarios are proposed (degraded safety, preserved safety, strengthened safety) and analysed in terms of protection against aggressions, diffuse robustness, prevention and management of reactor accident, prevention and management of pool accidents, ultimate control and assistance means. Scenarios are finally compared in terms of costs

  20. Jost Bürgi's aritmetische und geometrische Progreß Tabulen (1620) edition and commentary

    CERN Document Server

    Clark, Kathleen

    2015-01-01

    This monograph presents a groundbreaking scholarly treatment of the German mathematician Jost Bürgi’s original work on logarithms, Arithmetische und Geometrische Progreß Tabulen. It provides the first-ever English translation of Bürgi’s text and illuminates his role in the development of the conception of logarithms, for which John Napier is traditionally given priority. High-resolution scans of each page of the his handwritten text are reproduced for the reader and as a means of preserving an important work for which there are very few surviving copies. The book begins with a brief biography of Bürgi to familiarize readers with his life and work, as well as to offer an historical context in which to explore his contributions. The second chapter then describes the extant copies of the Arithmetische und Geometrische Progreß Tabulen, with a detailed description of the copy that is the focus of this book, the 1620 “Graz manuscript”. A complete facsimile of the text is included in the next chapter, a...

  1. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  2. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  3. Current status of the EPR (european pressurized reactor) program developed jointly by german and French nuclear industry

    International Nuclear Information System (INIS)

    Pouget-abadie, X.; Lallier, M.; Lauret, P.; Schneider, D.

    2000-01-01

    The Basic Design of the EPR is now completed and all the tasks, which were foreseen as part of this franco-german cooperation, came to a conclusion. At the origin of this project was the common decision in 1989 of Framatome and Siemens to cooperate through NPI, to design the Nuclear Island which meets the future needs of utilities. EDF and a group of the main German Utilities joined this cooperation in 1991 and since then have been totally involved to the progress of the the work. In addition, all the process was backed up to the end of 1998 by the strong cooperation between the French and the German Safety Authorities which have a long lasting cooperation to define common requirements which have to be applied to future Nuclear Power Plant. end of 2000, the French Safety Authorities are expected to issue their final recommendations

  4. French PWR Safety Philosophy

    International Nuclear Information System (INIS)

    Conte, M. M.

    1986-01-01

    The first 900 MWe units, built under the American Westinghouse licence and with reference to the U. S. regulation, were followed by 28 standardized units, C P1 and C P2 series. Increasing knowledge and lessons learned from starting and operating experience of French nuclear power plants, completed by the experience learned from the operation of foreign reactors, has contributed to the improvement of French PWR design and safety philosophy. As early as 1976, this experience was taken into account by French Safety organisms to discuss, with Electricite de France, the safety options for the planned 1300 MWe units, P4 and P4 series. In 1983, the new reactor scheduled, Ni4 series 1400 MWe, is a totally French design which satisfies the French regulations and other French standards and codes. Based on a deterministic approach, the French safety analysis was progressively completed by a probabilistic approach each of them having possibilities and limits. Increasing knowledge and lessons learned from operating experience have contributed to the French safety philosophy improvement. The methodology now applied to safety evaluation develops a new facet of the in depth defense concept by taking highly unlikely events into consideration, by developing the search of safety consistency of the design, and by completing the deterministic approach by the probabilistic one

  5. French experience in operating pressurized water reactor power stations. Ten years' operation of the Ardennes power station

    International Nuclear Information System (INIS)

    Teste du Bailler, A.; Vedrinne, J.F.

    1978-01-01

    In the paper the experience gained over ten years' operation of the Ardennes (Chooz) nuclear power station is summarized from the point of view of monitoring and control equipment. The reactor was the first pressurized water reactor to be installed in France; it is operated jointly by France and Belgium. The equipment, which in many cases consists of prototypes, was developed for industrial use and with the experience that has now been gained it is possible to evaluate its qualities and defects, the constraints which it imposes and the action that has to be taken in the future. (author)

  6. Cleanup Verification Package for the 118-H-6:2, 105-H Reactor Ancillary Support Areas, Below-Grade Structures, and Underlying Soils; the 118-H-6:3, 105-H Reactor Fuel Storage Basin and Underlying Soils; The 118-H-6:3 Fuel Storage Basin Deep Zone Side Slope Soils; the 100-H-9, 100-H-10, and 100-H-13 French Drains; the 100-H-11 and 100-H-12 Expansion Box French Drains; and the 100-H-14 and 100-H-31 Surface Contamination Zones

    Energy Technology Data Exchange (ETDEWEB)

    M. J. Appel

    2006-06-29

    This cleanup verification package documents completion of removal actions for the 105-H Reactor Ancillary Support Areas, Below-Grade Structures, and Underlying Soils (subsite 118-H-6:2); 105-H Reactor Fuel Storage Basin and Underlying Soils (118-H-6:3); and Fuel Storage Basin Deep Zone Side Slope Soils. This CVP also documents remedial actions for the following seven additional waste sties: French Drain C (100-H-9), French Drain D (100-H-10), Expansion Box French Drain E (100-H-11), Expansion Box French Drain F (100-H-12), French Drain G (100-H-13), Surface Contamination Zone H (100-H-14), and the Polychlorinated Biphenyl Surface Contamination Zone (100-H-31).

  7. Cleanup Verification Package for the 118-H-6:2, 105-H Reactor Ancillary Support Areas, Below-Grade Structures, and Underlying Soils; the 118-H-6:3, 105-H Reactor Fuel Storage Basin and Underlying Soils; the 118-H-6:6 Fuel Storage Basin Deep Zone Side Slope Soils; the 100-H-9, 100-H-10, and 100-H-13 French Drains; the 100-H-11 and 100-H-12 Expansion Box French Drains; and the 100-H-14 and 100-H-31 Surface Contamination Zones

    International Nuclear Information System (INIS)

    Appel, M.J.

    2006-01-01

    This cleanup verification package documents completion of removal actions for the 105-H Reactor Ancillary Support Areas, Below-Grade Structures, and Underlying Soils (subsite 118-H-6:2); 105-H Reactor Fuel Storage Basin and Underlying Soils (118-H-6:3); and Fuel Storage Basin Deep Zone Side Slope Soils. This CVP also documents remedial actions for the following seven additional waste sties: French Drain C (100-H-9), French Drain D (100-H-10), Expansion Box French Drain E (100-H-11), Expansion Box French Drain F (100-H-12), French Drain G (100-H-13), Surface Contamination Zone H (100-H-14), and the Polychlorinated Biphenyl Surface Contamination Zone (100-H-31)

  8. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2002-01-01

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

  9. The European pressurized water reactor. Result of the French-German cooperation of experienced NPP suppliers and operators

    International Nuclear Information System (INIS)

    Fischer, U.

    1999-01-01

    In 1989 Framatome and Siemens, the two most experienced European nuclear power plant suppliers, decided to join the efforts for the development of a new reactor type for the next generation in their equally owned subsidiary nuclear power international (NPI). In 1992 Electricite de France and the major German utilities operating nuclear power plants merged their own development programs with that of nuclear power international and initiated the European pressurized water reactor (EPR) project. In order to reach the two major targets of the project, the licensability in both countries, France and Germany, and the competitiveness of nuclear energy with other alternative energy sources, the design basis which had differently developed in the two countries needed to be harmonized. In parallel, the licensing authorities of both countries extended their existing cooperation in the field of a safety survey of existing nuclear power plants to the definition of safety criteria for the next generation of nuclear power plants. Through this cooperation the licensability of EPR in France and Germany will be assured. Continuously performed cost analysis show in addition that also the second target of the project, the competitiveness with alternative primary energy sources, can be achieved. Thanks to the fruitful cooperation between all parties involved, satisfactory results have been achieved not by a simple superposition of existing design features but through a careful evaluation and combination of the best available alternatives. At the end of 1997 the basic design results were compiled in a final report. Subsequently an optimization phase was launched that further improves the competitiveness of the power generation costs. (orig.)

  10. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

    Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

  11. Reactor

    International Nuclear Information System (INIS)

    Evans, R.M.

    1976-01-01

    Disclosed is a neutronic reactor having a moderator, coolant tubes traversing the moderator from an inlet end to an outlet end, bodies of material fissionable by neutrons of thermal energy disposed within the coolant tubes, and means for circulating water through said coolant tubes characterized by the improved construction wherein the coolant tubes are constructed of aluminum having an outer diameter of 1.729 inches and a wall thickness of 0.059 inch, and the means for circulating a liquid coolant through the tubes includes a source of water at a pressure of approximately 350 pounds per square inch connected to the inlet end of the tubes, and said construction including a pressure reducing orifice disposed at the inlet ends of the tubes reducing the pressure of the water by approximately 150 pounds per square inch. 1 claim, 16 figures

  12. French nuclear experience

    International Nuclear Information System (INIS)

    Reynolds, M.; Barre, B.

    1984-01-01

    The French nuclear attache at the French Embassy in Washington discusses his country's energy program and his role at the embassy as a representative of the French nuclear industry. He reviews the nuclear program's growth since it began in 1945, and the impetus of the OPEC oil embargo to accelerate the program since 1973. The success of France's nuclear program is due to a convergence of reasons that include incentive, the existence of a single utility that could design and manage a project of this magnitude, and the decision to focus on the pressurized water reactor (PWR) built by a single supplier and offering the benefits of standardization. Controlling the fuel cycle is the basic philosophy of both the PWR and the breeder program. Barre recommends policies of pre-approved sites, standardization, and licensing reform for the US

  13. French nuclear energy policy

    International Nuclear Information System (INIS)

    Ferrari, A.; Bertel, E.

    1980-11-01

    The French energy policy is supported by a lucid view of the situation of our country and the constraints linked to the international context. This statement implies, the definition of a French policy or energy production essentially based on national resources, uranium, and especially for long term, technical know how which allows using plutonium in breeder reactors. This policy implies an effort in R and D, and industrial development of nuclear field, both in reactor construction and at all levels of fuel cycle. This coherent scientific and financial effort has been pursued since the beginning of years 60, and has placed France among the first nuclear countries in the world. Now this effort enables the mastership of a strong nuclear industry capable to assure the energy future of the country [fr

  14. Decision no. 2011-DC-0216 of the French nuclear safety authority from May 5, 2011, ordering the Laue Langevin Institute to proceed to a complementary safety evaluation of its basic nuclear facility (high flux reactor - INB no. 67) in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

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

  15. French Foodscapes

    DEFF Research Database (Denmark)

    Hedegaard, Liselotte

    With the concept foodscapes as a point of departure, this paper explores the fundamental notions and the history of the traditional French cuisine in order to gain understanding of the ostensible rootedness of tradition in the modern French landscape of food and eating habits Concerned voices about...... the destructuralisation of eating habits have been raised since the 1980s, but numerous studies emphasise that the traditional French meal is still playing an important role in everyday life in France. Despite regional variations, the general view of the structure of a traditional French meal as based on the succession...... of flavours and the accordance with wines is widespread. Such a comprehension means giving precedence to gastronomic reasons for determining the order of dishes. However, the French meal has not always been composed in the way it is today and the reasons for the composition have not always been gastronomic...

  16. French Courses

    CERN Document Server

    2012-01-01

    General and Professional French Courses These courses are open to all persons working on the CERN site, and to their spouses. The next session will take place from 28 January to 5 April 2013. Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. The next session will take place from 28 January to 5 April 2013. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. The next session will take place from 28 January to 5 April 2013. For registration and further information on the courses, please consult our Web pages or contact Kerstin Fuhrmeister.

  17. Boron analyses in the reactor coolant system of French PWR by acid-base titration ([B]) and ICP-MS (10B atomic %): key to NPP safety

    International Nuclear Information System (INIS)

    Jouvet, Fabien; Roux, Sylvie; Carabasse, Stephanie; Felgines, Didier

    2012-09-01

    Boron is widely used by Nuclear Power Plants and especially by EDF Pressurized Water Reactors to ensure the control of the neutron rate in the reactor coolant system and, by this way, the fission reaction. The Boron analysis is thus a major factor of safety which enables operators to guarantee the permanent control of the reactor. Two kinds of analyses carried out by EDF on the Boron species, recently upgraded regarding new method validation standards and developed to enhance the measurement quality by reducing uncertainties, will be discussed in this topic: Acid-Base titration of Boron and Boron isotopic composition by Inductively Coupled Plasma Mass Spectrometer - ICP MS. (authors)

  18. French Training

    CERN Multimedia

    Françoise Benz

    2003-01-01

    General and Professional French Courses The next session will take place: from 13 October to 19 December 2003. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages or contact Mrs. Fontbonne: Tel. 72844. Writing Professional Documents in French This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF (for 8 students) For further information and registration, please consult our Web pages or contact Mrs. Fontbonne: Tel. 72844. Language Training Françoise Benz Tel.73127 language.training@cern.ch

  19. Nuclear energy: French government policy

    International Nuclear Information System (INIS)

    1998-01-01

    This report presents the French government policy concerning nuclear energy and alternative sources of energy for the next 10 years. This report overviews the situation of Super-Phenix fast reactor and presents the implications of the 30/12/1999 decree (Bataille's law) about the management of radioactive wastes

  20. Accident management on french PWRS

    International Nuclear Information System (INIS)

    Queniart, D.

    1990-06-01

    After a brief recall of French safety rationale, the reactor operation and severe accident management is given. The research and development aimed at developing accident management procedures and emergency organization in France for the case of a NPP accident are also given

  1. Assessment of management alternatives for LWR wastes. Volume 7. Cost and radiological impact associated with near-surface disposal of reactor waste (French concept)

    International Nuclear Information System (INIS)

    Malherbe, J.

    1993-01-01

    This report deals with the determination of the cost and the radiological impact associated with a near-surface disposal site (French concept) for low and medium-level radioactive waste generated during operation of a 20 GWe nuclear park composed of LWRs for 30 years. This study is part of an overall theoretical exercise aimed at evaluating a selection of management routes for LWR waste based on economical and radiological criteria

  2. French courses

    CERN Document Server

    HR Department

    2012-01-01

    General and Professional French Courses The next session will take place from 2nd May to 6th July 2012. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages or contact Kerstin Fuhrmeister.   Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. Suitable candidates should contact Kerstin Fuhrmeister (70896) in order to arrange an appointment for a test. The next session will take place from 2nd May to 6th July 2012.   Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. Suitable candidates should contact Kerstin Fuhrmeister (70896) in order to arrange an appointment for a test. The next session will take place from 2nd May to ...

  3. French courses

    CERN Multimedia

    2013-01-01

    General and Professional French Courses The next session will take place from 29 April to 5 July 2013. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages or contact Kerstin Fuhrmeister (kerstin.fuhrmeister@cern.ch). Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. Suitable candidates should contact Kerstin Fuhrmeister (70896) in order to arrange an appointment for a test. The next session will take place from 29 April to 5 July 2013. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. Suitable candidates should contact Kerstin Fuhrmeister (70896) in order to arrange an appointment for a test. The next session will take place from 29 April to 5 July...

  4. Access French

    CERN Document Server

    Grosz, Bernard

    2014-01-01

    Access is the major new language series designed with the needs of today's generation of students firmly in mind. Whether learning for leisure or business purposes or working towards a curriculum qualification, Access French is specially designed for adults of all ages and gives students a thorough grounding in all the skills required to understand, speak, read and write contemporary French from scratch. The coursebook consists of 10 units covering different topic areas, each of which includes Language Focus panels explaining the structures covered and a comprehensive glossary. Learning tips

  5. Christian Comeliau, 2006, La Croissance ou le progrès ? Croissance, décroissance, développement durable, Seuil.

    OpenAIRE

    Semal, Luc

    2007-01-01

    Dans La Croissance ou le progrès ? Croissance, décroissance, développement durable, l’économiste Christian Comeliau tente de distinguer les concepts de croissance, de développement et de progrès. S’opposer à l’un ne signifie pas nécessairement s’opposer aux autres : c’est l’erreur que font, selon lui, de nombreux partisans de la décroissance et un bon nombre de ses opposants.En effet, Christian Comeliau s’oppose à la croissance comme objectif évident et implicite de toute action humaine, mais...

  6. French experience with electropolishing

    International Nuclear Information System (INIS)

    Saurin, P.; Weber, C.; Brissaud, A.; Gouillardou, G.

    1989-01-01

    Among the various techniques to minimize corrosion products deposition on out of core areas, surface polishing has been researched. The attention of French partners was drawn to this technique and a test was conducted at Chinon B1 NPP in 1984 using six manway covers with various surface finishing (mechanical polishing, electropolishing, mechanical plus electropolishing/on reference). On the basis of the good results obtained and with beneficial cost considerations the electropolishing of SGCH has been decided for new EDF reactors. Once the decision was made feasibility and qualifications programs were developed. Taking into account the promising results obtained, EDF asked FRAMATOME to perform the first electropolishing operation on one steam generator channel head at Nogent 1 in 1987. Since 1988 the French experience consists of the electropolishing of 4SG at Nogent 2, 4SG at Cattenom 3, 4SG at Penly 1 and 4SG at Golfech 1 (NPP), and is perfectly satisfactory. The industrial operation provides excellent polishing and does not create undesired effects. The French partners are now thinking of a new device which could be realised at FRAMATOME especially for steam generator replacement. (author)

  7. French lessons in nuclear power

    International Nuclear Information System (INIS)

    Valenti, M.

    1991-01-01

    In stark contrast to the American atomic power experience is that of the French. Even the disaster at Chernobyl in 1986, which chilled nuclear programs throughout Western Europe, did not slow the pace of the nuclear program of the state-owned Electricite de France (EDF), based in Paris. Another five units are under construction and are scheduled to be connected to the French national power grid before the end of 1993. In 1989, the EDF's 58 nuclear reactors supplied 73 percent of French electrical needs, a higher percentage than any other country. In the United States, for example, only about 18 percent of electrical power is derived from the atom. Underpinning the success of nuclear energy in France is its use of standardized plant design and technology. This has been an imperative for the French nuclear power industry since 1974, when an intensive program of nuclear power plant construction began. It was then, in the aftermath of the first oil embargo, that the French government decided to reduce its dependence on imported oil by substituting atomic power sources for hydrocarbons. Other pillars supporting French nuclear success include retrofitting older plants with technological or design advances, intensive training of personnel, using robotic and computer aids to reduce downtime, controlling the entire nuclear fuel cycle, and maintaining a comprehensive public information effort about the nuclear program

  8. Propulsion reactors

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    A nuclear reactor equips the recently constructed French aircraft- carrier Charles-De-Gaulle, in a few months the second nuclear submarine (SNLE) of new generation will be operational. In last october the government launched the program Barracuda which consists of 6 submarines (SNA) whose series head will be operational in 2010. The main asset of nuclear propulsion is to allow an almost unlimited autonomy: soft water, air are produced inside the submarine and the maximum time spent underwater is only limited by human capacity to cope with confinement. CEA has 3 missions concerning country defence. First the designing, the fabrication and the maintenance of weapons, secondly the supplying of fissile materials and thirdly the nuclear propulsion. A new generation of propulsion reactors is being studied and a ground installation involving a test reactor equivalent to that on board is being built. This test reactor (RES) will simulate any type of on-board reactors by adjusting temperature, pressure, flowrate and even equipment such as steam generator. This reactor will validate the technological choices for the Barracuda program. (A.C.)

  9. French Strategy and Programs [International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), Paris, France, March 4-7, 2013

    International Nuclear Information System (INIS)

    Bigot, Bernard

    2013-01-01

    • In spite of the recent Fukushima accident, the use of nuclear energy still remains a necessity for many countries With a mastered and always improved safety, nuclear energy will go on contributing to the world energy needs, reducing fossil fuel dependency and GHG emissions. • With the help of large international collaborations, CEA is committed to demonstrate potential pathways for making significant progress for future fast neutrons reactors and their corresponding fuel cycle. • In synergy with nuclear energy, the renewable energies must be widely developed

  10. French Customs

    CERN Multimedia

    GS Department

    2010-01-01

    Please note that the French Customs (initially located in Building 904, Prévessin) are now located in Ferney-Voltaire (FR): Mrs Catherine NEUVILLE Douane de Ferney-Voltaire Rue de Genève F – 01210 Ferney-Voltaire Phone : 33 4 50 40 51 42 Email : catherine.neuville@douane.finances.gouv.fr Tom Wegelius Tel: 79947 Logistics and Site Services

  11. French visas

    CERN Multimedia

    2007-01-01

    The French Ministry of Foreign Affairs (hereinafter "MAE") has informed CERN of the following new regulations governing the visas required when submitting requests for French legitimation documents (cf. in particular paragraph b) below concerning the facilities recently granted to certain categories of persons who are not nationals of Switzerland or of a member state of the European Economic Area). This notification replaces that which appeared in Bulletin No.19/2006 (ref. CERN/DSU-DO/RH/13173/Rev.). 1. Special residence permit ("Titre de séjour special") To qualify for a special residence permit from the MAE, persons who are not nationals of Switzerland or of a member state of the European Economic Area (hereinafter "EEA") must present the following upon arrival at CERN: a)\teither a “D”-type (long-stay) French visa marked “carte PROMAE à solliciter à l’arrivée”, even if they are not subject to the requirement to obtain an entrance and short-stay visa in France...

  12. French nuclear industry exportations: companies and organisations, achievements and projects

    International Nuclear Information System (INIS)

    Faudon, V.; Pailler, S.; Miniere, D.; Pouget-Abadie, X.; Journes, F.; Ouali, F.; Brochard, D.; Choho, T.; Lagarde, D.; Anglaret, P.; Kottman, G.; Mockly, D.; Ouzounian, G.; Cordier, P.Y.; Prenez, J.C.; Arpino, J.M.; Jaouen, C.; Jolly, B.

    2013-01-01

    This document gathers a series of short articles in which the following players: French Nuclear Safety Authority (ASN), Electricity of France (EdF), French Alternative Energies and Atomic Energy Commission (CEA), AREVA, ALSTOM, the Association of French Nuclear Industry Exporters (AIFEN), the National Radioactive Waste Management Agency (ANDRA) and the French Society of Nuclear Energy (SFEN) present their competencies in their respective fields and their strategies and commercial offers for exports. 2 articles are dedicated to the achievements of the French nuclear industry in China and another details the cooperation between SFEN and its foreign counterparts. Another article briefly presents the EPR and ATMEA reactors. (A.C.)

  13. French slanguage

    CERN Document Server

    Ellis, Michael

    2012-01-01

    With this fun visual guide, simply follow the illustrated prompts and read the English words out loud: soon you'll be speaking French! Ask how someone is doing: "Comet Haley View" or say thank you very much: "Mare See Bow Cool." The simple icons are easy to follow and this pocket-sized guide is easy to carry with you. It will give you the basic phrases you need to get around while traveling, whether asking directions, ordering food at a restaurant, or shopping. But most of all, it's just plain fun!

  14. Reactor. Mind picture of the future Jules-Horowitz Reactor (RHJ)

    International Nuclear Information System (INIS)

    Eustache, S.

    1999-01-01

    This paper gives information about the future research reactor, named Reactor Jules-Horowitz (RJH). This irradiation reactor will be placed at industrialists disposal, for research concerning the competitiveness and the safety french electro-nuclear park. Principles and innovations are detailed. This reactor will respect the ALARA principle (as low as reasonably achievable). (A.L.B.)

  15. CER. Research reactors in France

    Energy Technology Data Exchange (ETDEWEB)

    Estrade, Jerome [CEA, DEN, DER, Saint-Paul-lez-Durance (France). Jules Horowitz Reactor (JHR)

    2012-10-15

    Networking and the establishment of coalitions between research reactors are important to guarantee a high technical quality of the facility, to assure well educated and trained personnel, to harmonize the codes of standards and the know-ledge of the personnel as well as to enhance research reactor utilization. In addition to the European co-operation, country-specific working groups have been established for many years, such as the French research reactor Club d'Exploitants des Reacteurs (CER). It is the association of French research reactors representing all types of research reactors from zero power up to high flux reactors. CER was founded in 1990 and today a number of 14 research reactors meet twice a year for an exchange of experience. (orig.)

  16. Progrès de la cartographie et pratique de la ville: Moscou ou la culture de la désorientation

    Directory of Open Access Journals (Sweden)

    Denis ECKERT

    1998-09-01

    Full Text Available Un plan de la ville de Moscou publié en 1997 représente un progrès remarquable de la cartographie urbaine en Russie. Cela est d'autant plus vrai qu'il est fort difficile de se repérer dans un quartier, étant donné la structure complexe du bâti et l'absence de panneaux indicateurs. L'apparition de ce plan témoigne de l'ouverture croissante de la société russe, qui tourne graduellement le dos à la culture du secret.

  17. PWR standardization: The French experience

    International Nuclear Information System (INIS)

    Bacher, P.E.

    1987-01-01

    After a short historical review of the French PWR programme with 45000 MWe in operation and 15000 MWe under construction, the paper first develops the objectives and limits of the standardizatoin policy. Implementation of standardization is described through successive reactor series and feedback of experience, together with its impact on safety and on codes and standards. Present benefits of standardization range from low engineering costs to low backfitting costs, via higher quality, reduction in construction times and start-up schedules and improved training of operators. The future of the French programme into the 1990's is again with an advanced standardized series, the N4-1400 MW plant. There is no doubt that the very positive experience with standardization is relevant to any country trying to achieve self-reliance in the nuclear power field. (author)

  18. Sodium-cooled nuclear reactors

    International Nuclear Information System (INIS)

    Berthoud, Georges; Ducros, Gerard; Feron, Damien; Guerin, Yannick; Latge, Christian; Limoge, Yves; Santarini, Gerard; Seiler, Jean-Marie; Vernaz, Etienne; Guidez, Joel; Andrieux, Catherine; Baque, Francois; Bonin, Bernard; Boullis, Bernard; Cabet, Celine; Carre, Frank; Dufour, Philippe; Gauche, Francois; Grouiller, Jean-Paul; Jeannot, Jean-Philippe; Le Flem, Marion; Le Coz, Pierre; Martin, Laurent; Masson, Michel; Mathonniere, Gilles; Nokhamzon, Jean-Guy; Pelletier, Michel; Rodriguez, Gilles; Saez, Manuel; Seran, Jean-Louis; Varaine, Frederic; Zaetta, Alain; Behar, Christophe; Provitina, Olivier; Lecomte, Michael; Forestier, Alain; Bender, Alexandra; Parisot, Jean-Francois; Finot, Pierre

    2014-01-01

    This book first explains the choice of sodium-cooled reactors by outlining the reasons of the choice of fast neutron reactors (fast neutrons instead of thermal neutrons, recycling opportunity for plutonium, full use of natural uranium, nuclear waste optimization, flexibility of fast neutron reactors in nuclear material management, fast neutron reactors as complements of water-cooled reactors), and by outlining the reasons for the choice of sodium as heat-transfer material. Physical, chemical, and neutron properties of sodium are presented. The second part of the book first presents the main design principles for sodium-cooled fast neutron reactors and their core. The third part proposes an historical overview and an assessment of previously operated sodium-cooled fast neutron reactors (French reactors from Rapsodie to Superphenix, other reactors in the world), and an assessment of the main incidents which occurred in these reactors. It also reports the experience and lessons learned from the dismantling of various sodium-cooled fast breeder reactors in the world. The next chapter addresses safety issues (technical and safety aspects related to the use of sodium) and environmental issues (dosimetry, gaseous and liquid releases, solid wastes, and cooling water). Then, various technological aspects of these reactors are addressed: the energy conversion system, main components, sodium chemistry, sodium-related technology, advances in in-service inspection, materials used in reactors and their behaviour, and fuel system. The next chapter addresses the fuel cycle in these reactors: its integrated specific character, report of the French experience in fast neutron reactor fuel processing, description of the transmutation of minor actinides in these reactors. The last chapter proposes an overview of reactors currently projected or under construction in the world, presents the Astrid project, and gives an assessment of the economy of these reactors. A glossary and an index

  19. French regulation

    International Nuclear Information System (INIS)

    Ballereau, P.

    2000-01-01

    Decrees providing for the enforcement of the radiation protection laws allow establishments to provide the individual surveillance of the workers exposure to ionizing radiations. A decree is relative to the dismantling of the fuel fabrication plant at Pierrelatte. A decree allows the Cea to modify a laboratory on irradiated fuels at Saclay. A departmental order allows EDF to continue the taking of samples in water, liquid and gaseous effluents releases for the operating site of Paluel and Flamanville. Some decrees are relative to the radioactive material transport. A law about the evaluation of environmental impact in a transfrontier context has been passed ( 17 activities such nuclear power plants, reactors, facilities devoted to the production, enrichment of nuclear fuel, storage, and processing of spent fuels are listed). A decree allows the transfer of ORIS by cea-Industry, Cea subsidiary sold to the Schering group. (N.C.)

  20. Technical advances and energy substitutions in the transportation sector; Progres techniques et substitutions energetiques dans le secteur des transports

    Energy Technology Data Exchange (ETDEWEB)

    Tromenschlager-Philippe, F.

    2002-11-01

    Alternative motorization technologies have been proposed in order to achieve energy diversification and a reduction in pollutant emissions. Fuel cell vehicles are, among others, at the centre of research carried out by car manufacturers and oil companies. The use of fuel cell vehicles could contribute, first to a less stringent long-term energy dependence of oil importing countries and, second, to pollutant reduction in the transport sector. First of all, we propose the definition of 'innovation' and its treatment in the frame of mainstream economic theories. Then we proceed to a retrospective analysis of diesel motorization of the car market. In the second part of our work, we conduct a survey among French households aiming to obtain up-to-date information about their degree of acceptance of fuel cell technology. We are concerned about highlighting the determining factors of fuel cell vehicle adoption by consumers. For this, we set up a discrete choice model linking the individual decision to the whole group of technical or socio-economical factors and characteristics. Finally, we develop patterns of fuel cell equipment of passenger cars which differ according to type of vehicle and possible purchase assistance. These patterns lead us to the analysis of long-term fuel cell vehicle development on the French car market. (authors)

  1. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

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

  2. French grammar for dummies

    CERN Document Server

    Mazet, Veronique

    2013-01-01

    The easy way to master French grammar French Grammar For Dummies is a logical extension and complement to the successful language learning book, French For Dummies. In plain English, it teaches you the grammatical rules of the French language, including parts of speech, sentence construction, pronouns, adjectives, punctuation, stress and verb tenses, and moods. Throughout the book, you get plenty of practice opportunities to help you on your goal of mastering basic French grammar and usage. Grasp the grammatical rules of French including parts of speech, sentenc

  3. 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.)

  4. Towards a French Revolution

    Science.gov (United States)

    Breach, H. T.

    1972-01-01

    Contends that secondary school students lose their appeal for French as they advance in school. Suggests that French teachers endeavor to motivate students by focusing more attention on their students and less on their own credentials. (DS)

  5. French grammar and usage

    CERN Document Server

    Hawkins, Roger

    2015-01-01

    Long trusted as the most comprehensive, up-to-date and user-friendly grammar available, French Grammar and Usage is a complete guide to French as it is written and spoken today. It includes clear descriptions of all the main grammatical phenomena of French, and their use, illustrated by numerous examples taken from contemporary French, and distinguishes the most common forms of usage, both formal and informal.Key features include:Comprehensive content, covering all the major structures of contemporary French User-friendly organisation offering easy-to-find sections with cross-referencing and i

  6. French For Dummies

    CERN Document Server

    Erotopoulos; Williams, Michelle M; Wenzel, Dominique

    2011-01-01

    The fast, informal way to learn to speak French French is known as perhaps the most beautiful of all languages. Listen to someone speak French-sure, you don't have a clue what they're saying, but aren't you enraptured by the sound of it? French is a beautiful language but quite difficult to learn. Whether you need to learn the language for a French class, or you travel overseas for business or leisure, this revised edition of French for Dummies can help. Written in an easy-to-follow format, it gives you just what you need for basic communication in FrenchExpanded coverage of necessary grammar,

  7. Would the re-structuration of the French nuclear industry be necessary?

    International Nuclear Information System (INIS)

    Finon, D.

    2011-04-01

    In this paper we analyze the recent propositions to reorganize the French industry of reactors in view to increase its efficiency on the export markets. Based on a critic of the choices of reactor technologies offered to export market, the Roussely report published on June 2010 recommends to crown the French electricity utility as the leader of a so-called 'French team' and to let him free to negotiate the sale of reactor of any technology that it would prefer as a Gen-2 reactor for example, and to place the French nuclear reactor constructor in a position of sub-contractor. The government has not followed this recommendation rightly. Based on an analysis of the changing world market of reactors, we defuse the criticism addressed to Areva on his choice, as well as the recommendation to open the present catalog of reactors to other models. The analysis leads to underline the importance of Areva's technological and industrial resources and the limited advantages of the EDF's skills in matter of architect-engineering and nuclear operation for winning export contracts. At the end of the day the mercantile approach which motivates the promoters of this tentative reform for competing with entrants prosing low cost nuclear reactors has been disapproved by the government, and that before the Fukushima accidents. We conclude by observing that only a flexible coordination between French industrial players would be useful for improving export performances of the French nuclear industry. (author)

  8. Nuclear reactor (1960)

    International Nuclear Information System (INIS)

    Maillard, M.L.

    1960-01-01

    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) [fr

  9. Decommissioning of French nuclear submarines

    International Nuclear Information System (INIS)

    Robin, B.; Buzonniere, A. de; Chenais, J.

    2003-01-01

    Since the beginning of the sixties, France has developed a fleet of nuclear powered vessels. Insofar as the ships of the 2. generation are being built, the older ones are decommissioned and enter the dismantling process. The average rate is presently one submarine decommissioned every two or three years. The overall strategy for the decommissioning of French nuclear submarines can be brought down to 3 phases: 1. Level 1 dismantling which essentially consists in: - unloading the spent fuel and storing it in a pool ; - possibly emptying the circuits which contain radioactive liquids. The level 1 is easily achieved, as it is not very different from the plant situation during ship overhaul or major refits. 2. Level 2 dismantling which consists in isolating the nuclear reactor compartment from the rest of the submarine and conditioning it for interim storage on a ground facility located inside Cherbourg Naval Dockyard. The rest of the ship is decontaminated, controlled and set for scrap like any conventional submarine. Up to now, the policy has been to keep the reactor compartment in this intermediate storage facility for at least 20 years, a duration calculated to allow enough time for short life corrosion products to disappear and hence, reduce the radioactive dose to workers during the level 3 dismantling operations. 3. Level 3 dismantling of the nuclear reactor compartment after a storage period. These operations consist in cutting into pieces all remaining structures and equipment, conditioning and sending them to ANDRA for disposal. The SSBN Le Redoutable, first French nuclear submarine which was removed from active service en 1991, underwent the first two phases but, forward and stern parts after cutting of the reactor compartment have been sealed and turned into a museum which is now part of 'La Cite de la Mer' in Cherbourg. Among the three other SSBNs removed from active service, two are at the end of phase 1 just before the separation of the reactor

  10. Seismic re-evaluation of French nuclear power plants

    International Nuclear Information System (INIS)

    Andrieu, R.

    1995-01-01

    After a presentation of the seismic inputs which have been taken into account in the design of the French Nuclear Power Plants, the re-assessed values of these inputs are shown. Some considerations about the specificity of the French PWR program with regard to the standardisation of plants are given together with the present objectives of seismic re-evaluations. Finally the main results of the seismic re-analysis being performed for the Phenix Fast Reactor are considered. (author)

  11. The fuel of nuclear reactors

    International Nuclear Information System (INIS)

    1995-03-01

    This booklet is a presentation of the different steps of the preparation of nuclear fuels performed by Cogema. The documents starts with a presentation of the different French reactor types: graphite moderated reactors, PWRs using MOX fuel, fast breeder reactors and research reactors. The second part describes the fuel manufacturing process: conditioning of nuclear materials and fabrication of fuel assemblies. The third part lists the different companies involved in the French nuclear fuel industry while part 4 gives a short presentation of the two Cogema's fuel fabrication plants at Cadarache and Marcoule. Part 5 and 6 concern the quality assurance, the safety and reliability aspects of fuel elements and the R and D programs. The last part presents some aspects of the environmental and personnel protection performed by Cogema. (J.S.)

  12. Reevaluating the French Revolution.

    Science.gov (United States)

    Stromberg, Roland N.

    1986-01-01

    Analyzes previous interpretations concerning the French Revolution. Discusses several weaknesses of the Marxist views in light of recent philosophical and sociological thinking about social change. (RKM)

  13. A comprehensive French grammar

    CERN Document Server

    Price, Glanville

    2013-01-01

    Characterized by clear and accessible explanations, numerous examples and sample sentences, a new section on register and tone, and useful appendices covering topics including age and time, A Comprehensive French Grammar, Sixth Edition is an indispensable tool for advanced students of French language and literature.A revised edition of this established, bestselling French grammarIncludes a new section on register and medium and offers expanded treatment of French punctuationFeatures numerous examples and sample sentences, and useful appendices covering topics including age, time, and dimension

  14. French essentials for dummies

    CERN Document Server

    Lawless, Laura K

    2011-01-01

    Just the core concepts you need to write and speak French correctly If you have some knowledge of French and want to polish your skills, French Essentials For Dummies focuses on just the core concepts you need to communicate effectively. From conjugating verbs to understanding tenses, this easy-to-follow guide lets you skip the suffering and score high at exam time. French 101 - get the lowdown on the basics, from expressing dates and times to identifying parts of speech Gender matters - see how a noun's gender determines the articles, adjectives, and pronouns y

  15. The AFR. An approved network of research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, Gabriele [Mainz Univ. (Germany). Arbeitsgemeinschaft fuer Betriebs- und Sicherheitsfragen an Forschungsreaktoren (AFR)

    2012-10-15

    AFR (Arbeitsgemeinschaft fuer Betriebs- und Sicherheitsfragen an Forschungsreaktoren) is the German acronym for 'Association for Research Reactor Operation and Safety Issues' which was founded in 1959. Reactor managers of European research reactors mainly from the German linguistic area meet regularly for their mutual benefit to exchange experience and knowledge in all areas of operating, managing and utilization of research reactors. In the last 2 years joint meetings were held together with the French association of research reactors CER (Club d'Exploitants des Reacteurs). In this contribution the AFR, its members, work and aims as well as the French partner CER are presented. (orig.)

  16. The E.P.R. reactor

    International Nuclear Information System (INIS)

    Sorin, F.; Echavarri, L.; Dupraz, B.; Joudon, L.; Debes, M.; Berard, E.; Fertey, G.; Dubail, A.; Paavola, M.; Esteve, B.; Olivier, E.; Azarian, M.G.; Nicaise, N.; Calamand, A.; Goebel, A.; Cornilus, P.L.; Francillon, E.; Kiehlmann, H.D.; Foret, F.; Desfontaines-Leromain, G.; Jolivet, P.; Azarian, G.; Fischer, M.; Dupuy, Ph.; Colonna, F.; Evrard, J.M.; Chaumont, B.; Manfred, S.; Grauf, E.; Kappler, F.; Petit, A.; Delpech, M.; Hensch, J.M.; Guers, R.; Seiler, J.M.

    2004-01-01

    This dossier is a detailed presentation of the reactor E.P.R. the European Pressurized water reactor. It comprises all the communications of the two-day conference on E.P.R. organized in Paris by the French nuclear energy society in december 2004. All the aspects of the generation 3, evolutionary reactor, which is the outcome of a close French/German cooperation, are presented, viz: technical characteristics; safety; operating performance; protection of the environment; competitiveness; potential market throughout Europe and worldwide. (author)

  17. French participation in the world energy council

    International Nuclear Information System (INIS)

    Carouge, Ch.; Roussely, F.; Francony, M.; Ailleret, F.; Bosseboeuf, D.; Moisan, F.; Villaron, Th.

    1999-01-01

    The Revue de l'Energie is presenting the most influential French interventions at the 17. Congress of the World Energy Council held in September 1998 in Houston, (USA). These represent only part of French participation in the congress since a total of 16 individuals from France took part in the various sessions. Their presentations cover very varied topics and are one of the things that testify to the interest that our energy industries have in the works and operations of the WEC. Some other figures also bear witness to this interest: 184 French congress members, which is one of the largest delegations after that of the United States, the host country of the congress; 11 technical presentation, covering a wide range of subjects: from the nuclear reactor of the future to the use of bagasse (cane trash) for the production of electricity, from the underground storage of natural gas to the production of extra-heavy crude petroleum. The technical exhibition associated to the Congress was a great success and there again the French presence was able to make its mark: five exhibitors were gathered in the France of 600 m 2 , the most sizeable non-American national area.But French participation in the work of the WEC is not limited to congresses. The French Energy Council [Conseil francais de l'Energie] is careful to ensure its presence both in the formal proceedings of the WEC and within the studies undertaken under its three-year programme. This active French presence is also essential in order to defend the official English-French bilingualism of the World Energy Council. In spite of the good will of the organizers and the support of the general secretary's office in London, the Houston Congress showed how difficult it was to maintain the use of the French language on English-speaking territory. This is a difficult task, one that has to be undertaken anew each time, but one that France and other French-speaking nations have decided to pursue to the end. (authors)

  18. The new French Development aid towards French-speaking Africa

    OpenAIRE

    Konate, Sindou Michel

    2013-01-01

    This project is focused on French president François Hollande new policy initiation around French Development assistance issue, particularly to French speakingAfrica South of the Sahara. President Hollande wishes to distance himself from the practices of his predecessors on French Public Development Assistance toward its former African colonies This project is focused on French president François Hollande new policy initiation around French Development assistance issue, particularly to Fre...

  19. Ship propulsion reactors technology; La technologie des reacteurs de propulsion navale

    Energy Technology Data Exchange (ETDEWEB)

    Fribourg, Ch. [Technicatome, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    2002-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-01-01

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

  1. The fast breeder reactor Rapsodie (1962)

    International Nuclear Information System (INIS)

    Vautrey, L.; Zaleski, C.P.

    1962-01-01

    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) [fr

  2. The French Revolution.

    Science.gov (United States)

    Baltimore City Public Schools, MD.

    This outline on the French Revolution is designed to illustrate how this period of French history influenced various aspects of contemporary culture. Four main sections are treated: (1) ideas that led to the Revolution, (2) the reigns of the Bourbon kings, (3) the Revolution, and (4) the rise of Napoleon as a reaction to chaos. A list of 16mm…

  3. Skiing in French.

    Science.gov (United States)

    Moeller, Paulette

    1984-01-01

    A high school French program conducted entirely in French on local ski slopes is based on the philosophy that language is a social tool for communicative purposes and can best be learned in social interaction. The successful program uses teamwork, an open attitude toward language learning, non-stressful evaluation, and innovative techniques. (MSE)

  4. School of French

    Directory of Open Access Journals (Sweden)

    M. K. Ogorodov

    2014-01-01

    Full Text Available Fundamentals of teaching French at MGIMO were laid in the 1950s - 1960s, the teachers of the Department of Romance Languages uniform. Initially, the core department of the French language teachers were MSU: Olga D. Andreeva, Simon I. Ganionsky, Sophia Yulevna Friedman, Irina B. Chachkhiani. Heads of departments of the period the greatest contribution to the development of philological science and practice of teaching Romance languages made an outstanding figure of Russian Romance Studies, Doctor of Philology, Professor Vladimir G. Gak. In 1971, after the separation of the Department of Romance languages were the departments of French and № 1 № 2. At the Department of French № 1 was successfully completed the task of developing a set of textbooks for the initial stage of training French language and created books that have become "classics of the genre".

  5. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  6. What French for Gabonese French lexicography? | Assam | Lexikos

    African Journals Online (AJOL)

    This paper is a response to Mavoungou (2013a) who has pleaded for the production of a dictionary of Gabonese French as variant B of the French language. The paper intends to com-prehend the concept of "Gabonese French". It gives an outline of the situation of French within the language diversity of Gabon as a ...

  7. Use of French, Attitudes and Motivations of French Immersion Students.

    Science.gov (United States)

    Van der Keilen, Marguerite

    1995-01-01

    Compares the degree to which pupils in the French immersion and regular English school programs speak French and initiate contact with French people. Attitudes and motivations were significantly more positive, and social tolerance and self-rated competency in French were much higher in the immersion than in English program subjects. (29…

  8. French-Finnish colloquium on safety of French and Russian type nuclear power plants

    International Nuclear Information System (INIS)

    Lukka, M.; Jaervinen, M.; Minkkinen, P.; Ukkola, A.; Levomaeki, L.

    1994-01-01

    The French-Finnish Colloquium on Safety of French and Russian Type Nuclear Power Plants was held in June, 14th - 16th, 1994, in Lappeenranta, Finland. The main topics of the colloquium were: VVER and RBMK reactors; Industrial safety studies for VVER's in FRAMATOME; Structural safety analysis of Ignalina NPP; Thermalhydraulic system (BETHSY) and analytical experiments for French NPP; Test facilities simulating VVER plants during accidents; PACTEL - facility for VVER thermal hydraulics; High burn-up fuel and reactivity accidents; Overview of severe accident research at Nuclear Protection and Safety Institute of CEA; Research of severe accidents in Finland; Review of main activities concerning computer codes used for VVER thermal-hydraulic safety analysis in OKB Gidropress; CATHARE code; APROS computer code, new developments; TRIO and TOLBIAC computer codes; ESTET and N3S softwares; HEXTRAN - 3D reactor dynamics code for VVER accident analysis; An overview the boron dilution issue in PWRs; Boron mixing transients in a 900 MW PWR vessel for a reactor start-up operation; and Problem of boric acid dilution in IVO

  9. Flirting with French

    CERN Document Server

    Alexander, William

    2015-01-01

    William Alexander is not just a Francophile, he wants to be French. It's not enough to explore the country, to enjoy the food and revel in the ambience, he wants to feel French from the inside. Among the things that stand in his way is the fact that he can't actually speak the language. Setting out to conquer the language he loves (but which, amusingly, does not seem to love him back), Alexander devotes himself to learning French, going beyond grammar lessons and memory techniques to delve into the history of the language, the science of linguistics, and the art of translation. Along

  10. Modern French Grammar Workbook

    CERN Document Server

    Lang, Margaret

    2012-01-01

    An innovative new workbook of exercises and language tasks for intermediate and advanced learners of French. This Workbook can be used independently or alongside Modern French Grammar.This Workbook provides exercises in:* Essential grammatical structures* Everyday functions such as agreeing and disagreeing* Role-plays set in a wide range of different contextsIt is suitable for group or pair work and for private study.A comprehensive answer key at the back of the Workbook enables you to check on your progress.This Workbook is ideal for all learners who have a basic knowledge of French, includin

  11. The French and energy

    International Nuclear Information System (INIS)

    Rouquette, Celine; Moreau, Sylvain; Bottin, Anne; Reperant, Patricia

    2012-08-01

    In 2012, as in 2011, the French are favourable to renewable energy. If they could, around 60% of them would opt for solar, fuelwood or heat pumps for heating. Wind power is also viewed favourably. Aware of environmental issues, the French are prepared to change their habits in the face of climate change, and two-thirds are even prepared to make sacrifices. One-third declares having already taken action or intending to do so to reduce their energy consumption. The cost of energy remains a central issue: faced with higher prices, half of French people would reduce their consumption. However, information on the subject of energy needs to be improved. (authors)

  12. The use of PSA in the French regulatory practice

    International Nuclear Information System (INIS)

    Mennesiez, H.

    1994-01-01

    The presentation gives a description of fundamental documents (since 1977-1978) through which have been set up in France probabilistic objectives, and PSAs, including shutdown states, performed for 900-1300 MWe PWR-type nuclear power plants. PSA developments and use, including fire PSA, level 2 and PSA for the future French-German European Pressurized Reactor (EPR) are also discussed

  13. French Expansion in North America.

    Science.gov (United States)

    Jaenen, Cornelius J.

    2001-01-01

    Explores the French colonization in North America. Presents background information on New France, focusing on the French in Canada. Covers topics, such as how the French became interested in North American expansion, the French in Louisiana, colonial economics, and the reasons for the collapse of New France. Includes a bibliography. (CMK)

  14. French plutonium management program

    International Nuclear Information System (INIS)

    Greneche, D.

    2002-01-01

    The French plutonium management program is summarized in this paper. The program considers nuclear generation as a major component of national electric power supply and includes the reprocessing of the spent fuel. (author)

  15. Report on the behalf of the inquiry commission related to past, present and future costs of the nuclear sector, to the reactor exploitation duration, and to various economic and financial aspects of production and commercialization of nuclear electricity within the frame of the French and European electric mix, as well as to the consequences of the shutting down and dismantling of nuclear reactors, notably the Fessenheim power plant - Nr 2007

    International Nuclear Information System (INIS)

    Brottes, Francois; Baupin, Denis

    2014-01-01

    fourth-generation reactors: choice made by France of the MOX option, research options for fourth-generation reactors. The seventh part addresses the nuclear risks: new tools of crisis management, a compensation system which only partially takes risks into account. The next part addresses the share of nuclear in the French energy mix: national debate on energy transition, characteristics of the main scenarios. The inquiry commission states that a life extension of the nuclear fleet seems necessary to face the increasing demand, but useless in case of a possible demand decrease. The last part addresses issues of commercialization of nuclear electricity in a context of market liberalization

  16. 500 French verbs for dummies

    CERN Document Server

    Erotopoulos

    2013-01-01

    Vexed by French verbs? Fear no more! In 500 French Verbs For Dummies, beginning French language learners can find a quick reference for verbs in the basic present tenses. More advanced French speakers can utilize this book to learn more complex verb tenses and conjugations as well as advanced verbs with irregular endings. One page for each of the 500 most commonly used verbs in the French language -alphabetically arranged and numbered for easy referenceSpecial designation of the 50 most essential French verbsA summary of basic French grammar that incl

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  18. Material accountancy and control practice at a research reactor facility

    International Nuclear Information System (INIS)

    Bouchard, J.; Maurel, J.J.; Tromeur, Y.

    1982-01-01

    This session surveys the regulations, organization, and accountancy practice that compose the French State System of Accountancy and Control. Practical examples are discussed showing how inventories are verified at a critical assembly facility and at a materials testing reactor

  19. English and French courses

    CERN Document Server

    2014-01-01

    If one of your New Year’s resolutions is to learn a language, there is no excuse anymore!   You can attend one of our English or French courses and you can practise the language with a tandem partner! General and Professional French Courses The next session will take place from 27 January to 4 April 2014. These courses are open to all persons working on the CERN site, and to their spouses. Oral Expression This course is aimed at students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. The next session will take place from 27 January to 4 April 2014. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. The next session will take place from 27 January to 4 April 2014. Cours d’anglais général et professionnel La prochaine session se déroulera du 3 mars a...

  20. RHTF 2, a 1200 MWe high temperature reactor

    International Nuclear Information System (INIS)

    Brisbois, Jacques

    1978-01-01

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

  1. The French coal board and French society

    International Nuclear Information System (INIS)

    Ladoucette, Ph. de

    2004-01-01

    On 19 April 1946 the French national assembly passed a law for nationalizing the mineral fuel industry by a vote of 516 against only 31. 'Charbonnages de France' (CDF), the French coal board, was created and prospects were promising. During the reconstruction period (1945 - 1960), coal industry was a pillar of the French economy, the production of coal had been steadily growing to reach its top in 1958 with 59 Mt. The sixties showed the beginning of the decline of coal to the benefit of oil, natural gas and later nuclear energy. As early as 1967 CDF had a policy of promoting new industries in regions of mines in order to break down the mono-industry scheme and to favor staff conversion massively. In 1947 the number of people on the payroll of CDF was 360.000, this number was decreasing steadily to reach 23.000 in 1990. In 2004 the last deep mine to work in France was closed down. This article tells the story of coal mining in France by describing its ups and downs and by assessing its social impact

  2. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    Dupraz, B.; Bertel, E.

    2003-01-01

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

  3. French development program on fuel cycle

    International Nuclear Information System (INIS)

    Viala, M.; Bourgeois, M.

    1991-01-01

    The need to close the fuel cycle of fast reactors makes the development of the cycle installations (fuel fabrication, irradiated assembly conditioning before reprocessing, reprocessing and waste management) especially independent with the development of the reactor. French experience with the integrated cycle over a period of about 25 years, the tonnage of fuels fabricated (more than 100 t of mixed oxides) for the Rapsodie, Phoenix and SuperPhoenix reactors, and the tonnage of reprocessed fuel (nearly 30 t of plutonium fuel) demonstrate the control of the cycle operations. The capacities of the cycle installations in existence and under construction are largely adequate for presents needs, even including a new European EFR reactor. They include the Cadarache fuel fabrication complex, the La Hague UP2-800 reprocessing plant, and the Marcoule pilot facility. Short- and medium-term R and D programs are connected with fuel developments, with the primary objective of very high burnups. For the longer term and for a specific plant to reprocess fast reactor fuels, the programs could concern new fabrication and reprocessing systems and the study of the consequences of the reduction in fuel out-of-core time

  4. H Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

  5. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    Jaouen, C.; Beroux, P.

    2012-01-01

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

  6. Adding prefilters to French containment venting systems

    Energy Technology Data Exchange (ETDEWEB)

    Kaercher, M.V. (EdF, Villeurbanne (France))

    1992-11-01

    The sand-bed filters installed on all French Pressurized Water Reactors were intended to retain the source term of radioactivity for 24h after the beginning of a core meltdown. But because of its size the sand filter is outside the containment and therefore the source term, which may be inside the sand filter, could produce very high radiation levels on site. To solve this problem a prefilter has been designed. This is to be located inside the containment and aims to retain the source term there. (author).

  7. Prospects for the French nuclear fuel management

    International Nuclear Information System (INIS)

    Presta, M.; Guiheux, J.M.

    1990-01-01

    In France, the present share of nuclear electricity generation is about 70 percent. In order to reduce fuel costs, EDF, the French utility, is dedicated to improve the management of the reloads for the 50 reactors it has to manage. Several decisions are now on the way. They affect the adjustment of the reloads to the situation of electricity consumption, the development of higher burn-up fuels and 1/4 reloads, and the recycling of reprocessing materials. It results that some new features in the management of the fuel cycle have been developed. That is why, COGEMA and other French fuel cycle companies have prepared some new processes to bring new solutions to the utility needs. First, new flexibilities have been created in the enrichment and fabrication management system in order to procure assemblies to EDF according to its needs with both right enrichment levels and fuel capabilities. Second, the recycling of reprocessing materials has been largely studied and large industrial facilities are now either operating or planned: they deal with conversions in UREP plants, enrichment of reprocessed uranium in EURODIF or by laser process, fabrication for REPU fuels by FRAGEMA or for MOX fuels by COMMOX. COGEMA relies on its experience acquired during the large French nuclear program development that let the company to adapt flexibly to the various EDF fuel management improvements. With this background, COGEMA offers services to foreign customers as well. With all these new features, the French nuclear system is now on a good way to ensure a good transition from the phase of building and development to a phase of sophisticated management and optimized use of French nuclear industrial facilities in the next 20 years. (author). 3 figs

  8. The French energy policy

    International Nuclear Information System (INIS)

    Maillard, D.; Baulinet, Ch.; Lajoinie, A.

    2001-01-01

    France has to face strong energy challenges: a heavy energy bill, increasing supplies risk, no decreasing CO 2 emissions, deregulation of energy markets, nuclear controversy etc.. In consequence, the French government has defined a voluntaristic energy policy with a better balance between the development of renewable energies and the mastery of energy and without renouncing the advantages of nuclear energy. In parallel, the electric power and natural gas industries have to cope with the deregulation of energy markets and the resulting competition. This issue of 'Energies et Matieres Premieres' newsletter comprises 3 articles. The first one gives a general presentation of the French energy policy ('mobilizing our margins of manoeuvre without renouncing our stakes'): challenges of the energy policy (greenhouse effect, security of supplies, long-term worldwide energy context, European integration, nuclear contestation), stakes for France (evolution of production structure, advantages of the French energy status), renewable energies and energy saving, long-term view of the nuclear industry, managing together the dynamism of competition and the advantages of public utilities. The second article entitled 'energy for everybody: a challenge for the 21. century' is a reprint of the introduction of the information report registered on January 31, 2001 by the commission of production and exchanges of the French national assembly. The third article is a reprint of the summary of conclusions and recommendations of the IEA about the French energy policy. (J.S.)

  9. Fast breeder reactors

    International Nuclear Information System (INIS)

    Ollier, J.L.

    1987-01-01

    The first industrial-scale fast breeder reactor (FBR) is the Superphenix I at Crays-Melville. It was designed and built by Novatome, a French company, and Ansaldo, an Italian company. The advantages of FBRs are summarized. The status of Superphenix and the testing schedule is given. The stages in its power escalation in 1986 are given. The article is optimistic about the future for FBRs and expects FBRs to take over from PWRs at the beginning of the 21st Century. To achieve economic viability, European financial cooperation for the research and development programme is advocated. (UK)

  10. The Oklo reactor

    International Nuclear Information System (INIS)

    McNeil, Russell

    1986-01-01

    The construction of a reactor, capable of producing a controlled nuclear chain reaction, has been one of the most complex achievements of modern science. That a similar reaction might take place in nature did not play a role in the thinking of the nuclear scientists responsible for it. Yet, 14 years ago, French scientists discovered that just such a phenomenon apparently occurred in western Africa almost 2 billion years ago. In this article Russell McNeil describes this fascinating curiosity and a recent attempt to model it mathematically

  11. French Antilles and Guiana.

    Science.gov (United States)

    1983-11-01

    This discussion of French Antilles and Guiana cover the following: the people, geography, history, government, political conditions, economy, and relations with the US. In 1983 the population totaled 303,000 with an annual growth rate of 0.09%. The infant mortality rate (1981) was 12.6/1000 and life expectancy 68 years. About 98% of the people of Martinique are of Afro European or Afro European Indian descent. The remainder are the old planter families and a sizable number of metropolitan French. Most of the work force are employed in agriculture or food processing and associated industries. Most permanent residents of Guadeloupe are of mixed Afro European descent. A few thousand Metropolitan French reside there. Most French Guianese live along the coast, about 1/2 of them in the capital. Martinique is the northernmost of the Windward Islands, which are part of the Lesser Antilles chain in the Caribbean Sea southeast of Puerto Rico. Guadeloupe comprises 2 of the Leeward Islands, which are also part of the Lesser Antilles chain. French Guiana is located on the northern coast of South America, a few degrees north of the Equator. Indians were the 1st known indigenous inhabitants of French Guiana and the French Antilles. Columbus sighted Guadeloupe in 1493, Martinique in 1493 or 1502, and the Guiana coast probably during his 3rd voyage in 1498. French Guiana, Guadeloupe, and Martinique, as overseas departments of France since 1946, are integral parts of the French Republic. Their relationship to Metropolitan France is somewhat similar to that of Alaska and Hawaii to the counterminous US. Each department has a general council composed of 1 representative elected by each canton. Guadeloupe and Martinique each elect 2 senators to the French Senate and 3 deputies to the National Assembly. French Guiana elects 1 senator and 1 deputy. In each of the 3 departments exist individuals and small political parties that advocate immediate independence, but their adherents form only

  12. The French energy programme

    International Nuclear Information System (INIS)

    Bohnen, U.

    1980-01-01

    The challenge of the oil crisis made French energy policy react chiefly by means of a programme for the rapid expansion of nuclear energy which has become unparalleled because of its systematic realization. The following article gives a survey of this programme and its political preconditions. The French energy programme deserves special attention as the utilization of nuclear energy in France including all related activities has reached a more advanced stage than in most other countries. The effects and requirements connected with such an extensive programme which can therefore be investigated with the help of the French example migth be of importance also for other countries in a similar way. (orig./UA) [de

  13. Language Training - French Training

    CERN Multimedia

    HR Department

    2008-01-01

    General and Professional French Courses The next session will take place from 26 January to 3rd April 2009. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Writing Professional Documents in French The next session will take place from 26 January to 3rd April 2009. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Nathalie Dumeaux Tel. 78144 mailto:nathalie.dumeaux@cern.ch

  14. Language Training - French Training

    CERN Multimedia

    HR Department

    2009-01-01

    General and Professional French Courses The next session will take place from 26 January to 3rd April 2009. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Writing Professional Documents in French The next session will take place from 26 January to 3rd April 2009. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Nathalie Dumeaux Tel. 78144 mailto:nathalie.dumeaux@cern.ch

  15. French grammar in context

    CERN Document Server

    Jubb, Margaret

    2013-01-01

    Instructors' edition without answer keysDiscount of 20% offered when 10 ebooks are sold- e.g. they will be sold for 263.60/ £151.90 instead of 329.50/£189.90French Grammar in Context presents a unique and exciting approach to learning grammar. Authentic texts from a rich variety of sources, literary and journalistic, are used as the starting point for the illustration and explanation of key areas of French grammar. Each point is consolidated with a wide range of written and spoken exercises. Grammar is presented not as an end in itself, but as a

  16. School of Economic French

    Directory of Open Access Journals (Sweden)

    I. S. Franceva

    2014-01-01

    Full Text Available Economic French at MGIMO-University is based on the teaching methods developed by talented Methodist practitioner assistant professor L.L. Potushanskoy. She and her colleagues G.M. Kotova, N. Kolesnikova, I.A. Yudina created well-known in our country methodical complex of three textbooks. This complex is built on clear guidelines to facilitate the natural development of language skills "from simple to complex" and represents the effective approach to language learning: Currently, the department is constantly expanding its boundaries of school teaching economic and business of the French language in accordance with the emerging new special courses on the economics faculties.

  17. French courses for Beginners

    CERN Multimedia

    2008-01-01

    French courses for beginners (level 0) will take place from 14 July to 28 August 2008. •\tTimetable: Mondays, Tuesdays, Wednesdays, Thursdays (13.00 to 15.00 or 15.30 to 17.30) •\tDuration: 56 hours (8 hours a week) •\tPrice: 728 CHF For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Nathalie Dumeaux : Tel. 78144. Language Training French Training Nathalie Dumeaux - 78144 mailto:nathalie.dumeaux@cern.ch

  18. French courses for Beginners

    CERN Multimedia

    2008-01-01

    French courses for beginners (level 0) will take place from 14 July to 28 August 2008. •\tTimetable: Mondays, Tuesdays, Wednesdays, Thursdays (13.00 to 15.00 or 15.30 to 17.30) •\tDuration: 56 hours (8 hours a week) •\tPrice: 728 CHF For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Dumeaux : Tel. 78144. Language Training French Training Nathalie Dumeaux - 78144 mailto:nathalie.dumeaux@cern.ch

  19. The French Revolution and the French Language: A Paradox?

    Science.gov (United States)

    Djite, Paulin

    1992-01-01

    Explores the relationship between revolutionary ideals and the subsequent expansion and promotion of the French language. It is shown, through a linguistic and sociopolitical history of the French Revolution and the French language, that there is no incompatibility between the two and that the movement of Francophonie is a continuation of France's…

  20. Comparing Written Competency in Core French and French Immersion Graduates

    Science.gov (United States)

    Lappin-Fortin, Kerry

    2014-01-01

    Few studies have compared the written competency of French immersion students and their core French peers, and research on these learners at a postsecondary level is even scarcer. My corpus consists of writing samples from 255 students from both backgrounds beginning a university course in French language. The writing proficiency of core French…

  1. Teaching French via American Football

    Science.gov (United States)

    Berwald, Jean-Pierre

    1974-01-01

    Outlines the methods of using football in teaching French in the American classroom by using French Canadian newspapers and other visual media available in the United States, in addition to specific language activities. (LG)

  2. Multimedia on nuclear reactors physics

    International Nuclear Information System (INIS)

    Dies, Javier; Puig, Francesc

    2010-01-01

    The paper present an example of measures that have been found to be effective in the development of innovative educational and training technology. A multimedia course on nuclear reactor physics is presented. This material has been used for courses at master level at the universities; training for engineers at nuclear power plant as modular 2 weeks course; and training operators of nuclear power plant. The multimedia has about 785 slides and the text is in English, Spanish and French. (authors)

  3. The French electronuclear programme

    International Nuclear Information System (INIS)

    Boiteux, M.

    1977-01-01

    The objective of the French electronuclear program is to meet a quarter of the national energy demand by 1985, and 35 to 50 per cent by 2000. The reasons for this objective are described, and methods of achieving it are suggested [fr

  4. The French nuclear law

    International Nuclear Information System (INIS)

    Ito, Hiroshi

    2013-01-01

    The nuclear law had been out of the environmental law. The act on the transparency and the security of the nuclear matter was enacted in 2006 and set in the code of the environment in 2012. It means that the nuclear law is part of the environmental law and that it is advanced. I will report the French nuclear law. (author)

  5. The French Collection

    NARCIS (Netherlands)

    Vergeest, Aukje

    2000-01-01

    'What's happening right now in Paris?' This must have been the question that preoccupied many a 19th-century art dealer and artist. For the modern artist who wanted to make it in that period, Paris was no doubt the place to be. And it's from here that considerable amounts of French art managed to

  6. Teaching the French Revolution.

    Science.gov (United States)

    Adams, Thomas M.

    1989-01-01

    Reports on presentations made at a symposium sponsored by the Connecticut Humanities Council. Papers dealt with teaching the French Revolution by presenting European history in new relationships with the rest of the world and by examining the Declaration of the Rights of Man as it related to the role of women. (KO)

  7. French chemical exchange process

    International Nuclear Information System (INIS)

    Frejacques, C.; Lerat, J.-M.; Plurien, P.

    1979-01-01

    A new chemical exchange reaction between two forms of uranium compounds with a high elementary separation coefficient and good kinetics has been discovered at the French Energy Commission ten years ago and developed to the industrial stage. We give here some general characteristics of the process and discuss some parameters of the kinetics exchange

  8. French Theory's American Adventures

    Science.gov (United States)

    Cusset, Francois

    2008-01-01

    In this article, the author discusses how it is simply too late to be still speaking about French theory and its role in the intellectual life of the United States today. It seems to many observers that the gap between real-life politics and theory's guerrillas is much too wide already, after 30 years of academic fever, for the two worlds to even…

  9. I Can Speak French.

    Science.gov (United States)

    New York City Board of Education, Brooklyn, NY. Div. of Curriculum and Instruction.

    The guide presents content and techniques for teaching conversational French in the elementary grades. It contains an introductory section and 20 units for classroom instruction. The introduction includes notes on the overall objectives of the course, general guidelines on classroom procedure, and specific techniques for use of the materials…

  10. [Films in French.

    Science.gov (United States)

    Encyclopaedia Britannica, Inc., Chicago, IL.

    This list of approximately 100 educational films in French covers a wide variety of topics including films for use in social studies, language arts, humanities, physical and natural sciences, safety and health, and fine arts classes. Many films feature life patterns among particular ethnic groups. Catalogue numbers and sale prices of films in both…

  11. REPLACEMENT OF FRENCH CARDS

    CERN Document Server

    HR/SOC

    2001-01-01

    The French Ministry of Foreign Affairs has informed the Organization that it is shortly to replace all diplomatic cards, special cards and employment permits ('attestations de fonctions') now held by members of the personnel and their families. Between 2 July and 31 December 2001, these cards are to be replaced by secure, computerized equivalents. The old cards may continue to be used until 31 December 2001. For the purposes of the handover, members of the personnel must go personally to the cards office (33/1-015), in order to fill in a 'fiche individuelle' form, taking the following documents for themselves and members of their families already in possession of a French card : A recent identity photograph in 4.5 cm x 3.5 cm format. The French card in their possession. An A4 photocopy of the same French card, certified by the cards office as being a true copy. Those members of the personnel whose cards (and/or cards belonging to members of their families) are shortly due to expire, or have recently done...

  12. REPLACEMENT OF FRENCH CARDS

    CERN Document Server

    Human Resources Division; Cards.Service@cern.ch

    2001-01-01

    The French Ministry of Foreign Affairs is currently replacing all diplomatic cards, special cards and employment permits («attestations de fonctions») held by members of the personnel and their families. These cards are replaced by secure, computerized equivalents. The old cards may no longer be used after 31 December 2001. For the purposes of the handover, members of the personnel must go personally to the cards office (33/1-015) between 8h30 and 12h30, in order to fill in a «fiche individuelle» form, taking the following documents for themselves and members of their families already in possession of a French card : A recent identity photograph in 4.5 cm x 3.5 cm format, the French card in their possession, an A4 photocopy of the same French card, certified by the cards office as being a true copy. Those members of the personnel whose cards (and/or cards belonging to members of their families) are shortly due to expire, or have recently done so, are also requested...

  13. REPLACEMENT OF FRENCH CARDS

    CERN Multimedia

    Human Resources Division

    2001-01-01

    The French Ministry of Foreign Affairs has informed the Organization that it is shortly to replace all diplomatic cards, special cards and employment permits ('attestations de fonctions') now held by members of the personnel and their families. Between 2 July and 31 December 2001, these cards are to be replaced by secure, computerized equivalents. The old cards may continue to be used until 31 December 2001. For the purposes of the handover, members of the personnel are asked to go to the cards office (33/1-015), taking the following documents for themselves and members of their families already in possession of a French card : A recent identity photograph in 4.5 cm x 3.5 cm format, The French card in their possession, an A4 photocopy of the same French card, certified by the cards office as being a true copy. Those members of the personnel whose cards (and/or cards belonging to members of their families) are shortly due to expire, or have recently done so, are also requested to take these items to the c...

  14. Complete French Teach Yourself

    CERN Document Server

    Graham, Gaelle

    2010-01-01

    The best-selling complete course for a fun and effective way to learn French. This ISBN is for the paperback book. The corresponding audio support (ISBN: 9781444100068) is also available. The book and audio support can also be purchased as a pack (ISBN: 9781444100051).

  15. French Wines on the Decline?:

    DEFF Research Database (Denmark)

    Steiner, Bodo

    2004-01-01

    French wines, differentiated by geographic origin, served for many decades as a basis for the French success in the British wine market. However in the early 1990s, market share began to decline. This article explores the values that market participants placed on labelling information on French...

  16. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  17. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  18. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  19. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

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

  20. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

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

  1. Status of fast reactors and ADS programmes in France in 2001

    International Nuclear Information System (INIS)

    Astegiano, J.C.

    2002-01-01

    Status of French fast reactor and ADS program in France covers the following topics: data on power generation from NPPs; status of fast reactors, namely Rapsodie, Phenix and Super Phenix; research and development programs concerned with fast gas cooled and sodium cooled reactors

  2. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Martens, Frederick H. [Argonne National Laboratory; Jacobson, Norman H.

    1968-09-01

    This booklet discusses research reactors - reactors designed to provide a source of neutrons and/or gamma radiation for research, or to aid in the investigation of the effects of radiation on any type of material.

  3. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

    Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

  4. The future of the French civil nuclear sector. Report synthesis

    International Nuclear Information System (INIS)

    2010-01-01

    Considering the evolution of the French civil nuclear industry by 2030, this study examines its different dimensions: energy policy, safety and security of uranium supplies, nuclear competitiveness, environmental and safety issues, public acceptance, consequences of non proliferation international and French policies, industrial, human and research capacities, and so on. Thus, this report presents the actors involved in the French civil nuclear sector, gives an overview of the reactor market, highlights the main aspects of the fuel cycle and of the waste management, stresses the need of a new organisation for this sector to face the domestic as well as the international challenges. It discusses the possible ways for a wider financing and a higher competitiveness. It identifies new means for an ambitious civil nuclear policy. Fifteen recommendations are proposed

  5. Report: demonstrable progresses of the France according the Kyoto protocol; Rapport: progres demontrables de la France selon le protocole de Kyoto

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-06-15

    This document constitutes the report of the France on the demonstrable progresses according the application of the 3 article of the Kyoto protocol. The first chapter is a description of the french climatic policy, as the second presents the tendencies and the projections concerning the greenhouse effect gases emissions. The chapter 3 details the policies effects and the measures ( energy, transport, industry and wastes). The last chapter is devoted to the respect of the other engagements articles 10 and 11 of the Kyoto protocol. (A.L.B.)

  6. Electricity supplies in a French nuclear power station

    International Nuclear Information System (INIS)

    2011-01-01

    As the operation of a nuclear power station requires a power supply system enabling this operation as well as the installation safety, this document describes how such systems are designed in the different French nuclear power stations to meet the requirements during a normal operation (when the station produces electricity) or when it is stopped, but also to ensure power supply to equipment ensuring safety functions during an incident or an accident occurring on the installation. More precisely, these safety functions are provided by two independent systems in the French nuclear power stations. Their operation is briefly described. Two different types of nuclear reactors are addressed: pressurised water reactors (PWR) of second generation, EPR (or PWR of third generation)

  7. Reactor Neutrinos

    OpenAIRE

    Kim, Soo-Bong; Lasserre, Thierry; Wang, Yifang

    2013-01-01

    We review the status and the results of reactor neutrino experiments. Short-baseline experiments have provided the measurement of the reactor neutrino spectrum, and their interest has been recently revived by the discovery of the reactor antineutrino anomaly, a discrepancy between the reactor neutrino flux state of the art prediction and the measurements at baselines shorter than one kilometer. Middle and long-baseline oscillation experiments at Daya Bay, Double Chooz, and RENO provided very ...

  8. BOILING REACTORS

    Science.gov (United States)

    Untermyer, S.

    1962-04-10

    A boiling reactor having a reactivity which is reduced by an increase in the volume of vaporized coolant therein is described. In this system unvaporized liquid coolant is extracted from the reactor, heat is extracted therefrom, and it is returned to the reactor as sub-cooled liquid coolant. This reduces a portion of the coolant which includes vaporized coolant within the core assembly thereby enhancing the power output of the assembly and rendering the reactor substantially self-regulating. (AEC)

  9. Leak before break application in French PWR plants under operation

    Energy Technology Data Exchange (ETDEWEB)

    Faidy, C. [EDF SEPTEN, Villeurbanne (France)

    1997-04-01

    Practical applications of the leak-before break concept are presently limited in French Pressurized Water Reactors (PWR) compared to Fast Breeder Reactors. Neithertheless, different fracture mechanic demonstrations have been done on different primary, auxiliary and secondary PWR piping systems based on similar requirements that the American NUREG 1061 specifications. The consequences of the success in different demonstrations are still in discussion to be included in the global safety assessment of the plants, such as the consequences on in-service inspections, leak detection systems, support optimization,.... A large research and development program, realized in different co-operative agreements, completes the general approach.

  10. The N4 plant: culmination of French PWR experience

    International Nuclear Information System (INIS)

    Bellet, J.; Houyez, A.; Journet, J.; Pierrard, J.H.

    1985-01-01

    The model N4 series of 1400MWe class PWR plants has been developed in France from a unique base of technical and operating experience. It meets the French government's requirement for a reactor free of constraints due to licensing agreements with overseas companies, with enhanced safety features and incorporating the lessons of Three Mile Island. In particular, improvements have been made to the reactor vessel, the steam generators, the primary pumps and control systems. The units are capable of daily load following and extended operation between refuelling. The N4 plant includes a new design of turbine-generator. (author)

  11. Reactor vessel

    NARCIS (Netherlands)

    Makkee, M.; Kapteijn, F.; Moulijn, J.A.

    1999-01-01

    A reactor vessel (1) comprises a reactor body (2) through which channels (3) are provided whose surface comprises longitudinal inwardly directed parts (4) and is provided with a catalyst (6), as well as buffer bodies (8, 12) connected to the channels (3) on both sides of the reactor body (2) and

  12. French courses for Beginners

    CERN Multimedia

    HR Department

    2009-01-01

    French courses for beginners (level 0) will take place from 13 July to 27 August 2009. •\tTimetable: Mondays, Tuesdays, Wednesdays, Thursdays (11:00 to 13:00 or 13:30 to 15:30) •\tDuration: 56 hours (8 hours a week) •\tPrice: 728 CHF For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Dumeaux, tel. 78144.

  13. French courses for Beginners

    CERN Multimedia

    HR Department

    2009-01-01

    French courses for beginners (level 0) will take place from 13 July to 27 August 2009. •\tTimetable: Mondays, Tuesdays, Wednesdays, Thursdays (11:00 to 13:00 or 13:30 to 15:30) •\tDuration: 56 hours (8 hours a week) •\tPrice: 728 CHF For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Dumeaux: Tel. 78144.

  14. French courses for Beginners

    CERN Multimedia

    HR Department

    2009-01-01

    French courses for beginners (level 0) will take place from 13 July to 27 August 2009. •\tTimetable: Mondays, Tuesdays, Wednesdays, Thursdays (11.00 to 13.00 or 13.30 to 15.30) •\tDuration: 56 hours (8 hours a week) •\tPrice: 728 CHF For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Dumeaux : Tel. 78144.

  15. French courses for Beginners

    CERN Multimedia

    HR Department

    2010-01-01

    French courses for beginners (level 0) will take place from 12 July to 27 August 2010. Timetable: Mondays, Tuesdays, Wednesdays, Thursdays (11.00 to 13.00 or 13.30 to 15.30; Duration: 56 hours (8 hours a week); Price: 728 CHF. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Dumeaux : Tel. 78144.

  16. REPLACEMENT OF FRENCH CARDS

    CERN Multimedia

    Human Resources Division

    2001-01-01

    The French Ministry of Foreign Affairs has informed the Organization that it is shortly to replace all diplomatic cards, special cards and employment permits ('attestations de fonctions') now held by members of the personnel and their families. Between 2 July and 31 December 2001, these cards are to be replaced by secure, computerized equivalents. A 'personnel office' stamped photocopy of the old cards may continue to be used until 31 December 2001. For the purposes of the handover, members of the personnel must go personally to the cards office (33/1-015), between 8:30 and 12:30, in order to fill a 'fiche individuelle' form (in black ink only), which has to be personally signed by themselves and another separately signed by members of their family, taking the following documents for themselves and members of their families already in possession of a French card : A recent identity photograph in 4.5 cm x 3.5 cm format (signed on the back) The French card in their possession an A4 photocopy of the same Fre...

  17. Language Training: French

    CERN Multimedia

    Françoise Benz

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training' form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt.General and Professional French Courses The next session will take place from 26 April to 02 July 2004. These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127. Writing Professional Documents in French The next session will take place from 26 April to 02 July 2004. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF (for 8 students) For further information and registra...

  18. Science Diplomacy: French Experience

    Directory of Open Access Journals (Sweden)

    Alexei V. Shestopal

    2016-01-01

    Full Text Available The article deals with the formulation in France in the early twenty-first century of a new kind of diplomacy - science diplomacy. It studies the reasons for this process and its problems. On the one hand, the French foreign policy doctrine presupposes an ability to exercise certain influence on its international partners. However, its goals in this area are reduced to mere survival under conditions dictated by other countries. Modern trends in the world of science, which lead to integration, force to reconsider the attitude towards staff training, to research itself, and to its place and role in politics and diplomacy. However, an achievement of the French political class is an understanding of the main aspects of what is happening. This understanding leads to the search for ways to adapt to the new situation. At the same time, diplomats can operate only with those resources that are available to them. Competition with the US, China and other countries for scientific personnel and achievements cannot be won by diplomatic means alone, without backing by appropriate legal, economic and other efforts which provide favorable conditions for winning the competition. The main causes of France's unfavorable position in the struggle for an independent science are economic and political. It is they that lead to conditions, which prohibit French scientists to live up to their potential at home.

  19. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  20. Nuclear power: which industrial approach will preserve a French asset?

    International Nuclear Information System (INIS)

    Machenaud, H.

    2012-01-01

    France's strategic decision in favor of nuclear energy in the 1970's has given rise to an organization of this industry with clearly defined roles and responsibilities for all parties. This has led to the mastering of industrial production of the whole chain from mining to fuel reprocessing and to waste disposal. Nuclear safety was at any stage of the chain the priority number one. The French nuclear industry is present on the international scene and thus maintain its know-how and capacities despite the ups and downs of the nuclear market. Today 240.000 people work in France in the nuclear sector. France has followed a consistent energy policy during the last 50 years and benefits from an important and homogeneous fleet of reactors which has generated a rich feedback experience on reactor operation. The tasks that face the French nuclear industry are: -) to comply with the requirements of the Complementary Safety Assessments that have been performed on all French nuclear facilities, -) to maintain and upgrade the power plants (most of them are facing their 3. decennial overhaul), -) to prepare the nuclear systems of tomorrow, and -) to export the French know-how

  1. Recent advances in the designing and the equipment of high activity laboratories; Progres recents dans la conception et l'equipement des laboratoires de haute activite

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The authors described the general principles governing the design of a laboratory for experimenting and handling radioactive substances. The difficulties encountered are of two types: 1) those due to the dangers of external irradiation; 2) those due to the dangers of internal contamination. As an example, the authors describe the French achievements in this field and in particular: - the high-activity laboratories at Saclay; - the laboratory for the examination of irradiated fuels at Saclay; - the 'hot' laboratory of the CEN-Grenoble; - the alpha, beta and gamma laboratories of the CEN-Fontenay-aux-Roses. Finally, the report describes the protective materials used for these installations. (author) [French] Les auteurs exposent quels sont les principes generaux qui president a la conception d'un laboratoire a des travaux et des manipulations sur des substances radioactives. Les difficultes a surmonter sont de deux ordres: 1) celles qui proviennent du danger d'irradiation externe; 2) celles qui proviennent du danger de contamination interne. A titre d'exemple, les auteurs decrivent les realisations francaises dans ce domaine et en particulier: - le laboratoire de haute activite de Saclay, - le laboratoire d'examen des combustibles irradies de Saclay, - le laboratoire chaud du CEN-Grenoble, - les laboratoires alpha, beta, gamma du CEN-Fontenay-aux-Roses. Enfin, le rapport decrit les materiaux de protection mis en oeuvre pour ces realisations. (auteur)

  2. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

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

  3. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

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

  4. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Nagatomi, Shozo.

    1976-01-01

    Object: To provide a jet and missile protective wall of a configuration being inflated toward the center of a reactor container on the inside of a body of the reactor container disposed within a biological shield wall to thereby increase safety of the reactor container. Structure: A jet and missile protective wall comprised of curved surfaces internally formed with a plurality of arch inflations filled with concrete between inner and outer iron plates and shape steel beam is provided between a reactor container surrounded by a biological shield wall and a thermal shield wall surrounding the reactor pressure vessel, and an adiabatic heat insulating material is filled in space therebetween. (Yoshino, Y.)

  5. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  6. French public finances at risk?

    Directory of Open Access Journals (Sweden)

    Creel Jérôme

    2014-01-01

    Full Text Available Using descriptive evidence, this paper contributes to the debate on French public finances’ consolidation by examining the long-term sustainability of France’s fiscal position. We trace the historical trends of government’s tax receipts and expenditures. We illustrate that while the level of public expenditure in France is larger than in the Euro Area, its trend is comparable to its neighbours. French net debt is comparable to Eurozone’s while French net wealth remains positive. However, the French tax system is not progressive with only 6% of compulsory levies raised that way, and too complex. The paper then acknowledges the efficient debt management of French authorities. As a conclusion, we see no risk of future unsustainability linked to the nature or the level of current French public finances.

  7. French historians and collective violence

    OpenAIRE

    Roberts, Penny

    2017-01-01

    French historians and French history have dominated the study of early modern violence. This essay addresses why this is so and what has characterized French historians’ approaches to collective violence in particular, whether in the form of popular revolt, confessional division or revolutionary violence. It posits that historians are essentially uncomfortable in defending and explaining popular violence in the past, that they ought to address this issue more directly and not to establish too...

  8. Future of French refining

    International Nuclear Information System (INIS)

    Calvet, B.

    1993-01-01

    Over recent years, the refining industry has had to grapple with a growing burden of environmental and safety regulations concerning not only its plants and other facilities, but also its end products. At the same time, it has had to bear the effects of the reduction of the special status that used to apply to petroleum, and the consequences of economic freedom, to which we should add, as specifically concerns the French market, the impact of energy policy and the pro-nuclear option. The result is a drop in heavy fuel oil from 36 million tonnes per year in 1973 to 6.3 million in 1992, and in home-heating fuel from 37 to 18 million per year. This fast-moving market is highly competitive. The French market in particular is wide open to imports, but the refining companies are still heavy exporters for those products with high added-value, like lubricants, jet fuel, and lead-free gasolines. The competition has led the refining companies to commit themselves to quality, and to publicize their efforts in this direction. This is why the long-term perspectives for petroleum fuels are still wide open. This is supported by the probable expectation that the goal of economic efficiency is likely to soften the effects of the energy policy, which penalizes petroleum products, in that they have now become competitive again. In the European context, with the challenge of environmental protection and the decline in heavy fuel outlets, French refining has to keep on improving the quality of its products and plants, which means major investments. The industry absolutely must return to a more normal level of profitability, in order to sustain this financial effort, and generate the prosperity of its high-performance plants and equipment. 1 fig., 5 tabs

  9. [French immigration policy].

    Science.gov (United States)

    Weil, P

    1994-01-01

    From the late nineteenth century through 1974, France permitted immigration to furnish workers and to compensate for the low level of fertility. Intense immigration from North Africa, the economic crisis of the 1970s, and other factors led to policy changes in 1974. French immigration policy since 1974 has fluctuated between guaranteeing foreigners equal rights regardless of their religion, race, culture, or national origin, and attempting to differentiate among immigrants depending on their degree of assimilability to French culture. From 1974 to 1988, France had five different policies regarding whether to permit new immigration and what to do about illegal immigrants. In July 1984, the four major political parties unanimously supported a measure in Parliament that definitively guaranteed the stay in France of legal immigrants, whose assimilation thus assumed priority. Aid for return to the homeland was no longer to be widely offered, and immigration of unskilled workers was to be terminated except for those originating in European Community countries. Major changes of government in 1988 and 1993 affected only the modalities of applying these principles. The number of immigrants has fluctuated since 1974. Unskilled workers, the only category whose entrance was specifically controlled by the 1984 measures, have declined from 174,000 in 1970 to 25,000 in the early 1990s. The number of requests for political asylum declined from 60,000 in 1989 to 27,000 in 1993, and in 1991, 15,467 persons were granted refugee status. The number of immigrants of all types permitted to remain in France declined from 250,000 or 3000 per year in the early 1970s to around 110,000 at present. Although the decline is significant, it appears insufficient to the government in power since 1993. Although migratory flows are often explained as the product of imbalance in the labor market or in demographic growth, the French experience suggests that government policies, both in the sending and

  10. Research reactor safety - an overview of crucial aspects

    International Nuclear Information System (INIS)

    Laverie, M.

    1998-01-01

    Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

  11. FRENCH PROTOCOL CARDS

    CERN Multimedia

    Division du Personnel

    1999-01-01

    Senior officials, holders of FRENCH PROTOCOL cards (blue cards) due to expire on 31.12.1999, are requested to return these cards and those of family members, for extension to:Bureau des cartes, bâtiment 33.1-025Should the 3 spaces for authentication on the back of the card be full, please enclose 2 passport photographs for a new card.In the case of children aged 14 and over, an attestation of dependency and a school certificate should be returned with the card.Personnel DivisionTel. 79494/74683

  12. FRENCH PROTOCOL CARDS

    CERN Multimedia

    Division des Ressources Humaines; Human Resources Division; Tel. 74683-79494

    2000-01-01

    Senior officials, holders of FRENCH PROTOCOL cards (blue cards) due to expire on 31.12.2000, are requested to return these cards and those of family members, for extension to: Bureau des cartes, Bât 33.1-009/1-015 Should the three spaces for authentication on the back of the card be full, please enclose two passport photographs for a new card. In the case of children aged 14 and over, an attestation of dependency and a school certificate should be returned with the card.

  13. The French nuclear context

    International Nuclear Information System (INIS)

    Havard, J.; Israel, M.

    1977-01-01

    The mean- and longer-range energy needs, that can be now forecasted in France, are analyzed, together with the special character of the French energy market. A resort to nuclear power is first shown to be necessary to limit the increase in the demand for imported fossil fuels, then this resort is shown to offer some real possibilities. The energy balance proves that the industrial stage of power plant construction is reached. The conditions of realization of the program have been settled with a set of provisions that render the risk and environmental impact as negligible as possible [fr

  14. 1001 easy French phrases

    CERN Document Server

    McCoy, Heather

    2010-01-01

    The perfect companion for tourists and business travelers in France and other places where the French language is spoken, this book offers fast, effective communication. More than 1,000 basic words, phrases, and sentences cover everything from asking directions and renting a car to ordering dinner and finding a bank.Designed as a quick reference tool and an easy study guide, this inexpensive and easy-to-use book offers completely up-to-date terms for modern telecommunications, idioms, and slang. The contents are arranged for quick access to phrases related to greetings, transportation, shoppin

  15. The French Revolution on Film: American and French Perspectives

    Science.gov (United States)

    Harison, Casey

    2005-01-01

    It is not hard to locate negative or condescending images of the French Revolution in aspects of popular American culture, including film. Despite a handful of instances where nuanced or ambiguous "messages" may be identified, the number of American film interpretations of the French Revolution that might be judged historically…

  16. Invitation Refusals in Cameroon French and Hexagonal French

    Science.gov (United States)

    Farenkia, Bernard Mulo

    2015-01-01

    Descriptions of regional pragmatic variation in French are lacking to date the focus has been on a limited range of speech acts, including apologies, requests, compliments and responses to compliments. The present paper, a systematic analysis of invitation refusals across regional varieties of French, is designed to add to the research on…

  17. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  18. Adding prefilters to French containment venting systems

    Energy Technology Data Exchange (ETDEWEB)

    Kaercher, M.V. [Electricite de France (EDF), 75 - Paris (France); Boissieu, P. de

    1995-12-31

    To avoid the need for extra biological shielding round the sand-bed filters in its Pressurized Water Reactor containment venting systems, Electricite de France is installing prefilters. The sand-bed filters filters installed on all French PWRs were intended to retain the source term of radioactivity for 24 hours after the beginning of a core meltdown. But because of its size the sand filter is outside the containment and therefore the source term, which may be inside the sand filter, could produce very high radiation levels on site. To solve this problem a prefilter has been designed. This is to be located inside the containment and aims to retain the source term there. (Author).

  19. Language Training: French Training

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. LANGUAGE TRAINING Françoise Benz tel. 73127 language.training@cern.ch General and Professional French Courses The next session will take place from 26 April to 02 July 2004. These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127. Writing Professional Documents in French The next session will take place from 26 April to 02 July 2004. This course is designed for people with a good level of s...

  20. Language Training: French Training

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. LANGUAGE TRAINING Françoise Benz tel. 73127 language.training@cern.ch General and Professional French Courses The next session will take place from 26 April to 02 July 2004. These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127. Writing Professional Documents in French The next session will take place from 26 April to 02 July 2004. This course is designed for people with a good level...

  1. The French capacity mechanism

    International Nuclear Information System (INIS)

    2014-01-01

    The French capacity mechanism has been design to ensure security of supply in the context of the energy transition. This energy transition challenges the electricity market design with several features: peak load growth, the development of renewables, demand response,... To ensure security of supply in this context, a capacity mechanism is being implemented in France. It is a market wide capacity obligation on electricity suppliers, based on market principles. Suppliers are responsible for forecasting their obligation, which corresponds to their contribution to winter peak load, and must procure enough capacity certificates to meet their obligations. Capacity certificates are granted to capacities through a certification process, which assesses their contribution to security of supply on the basis of availability commitments. This certification process is technology neutral and performance based, associated with controls and penalties in case of non compliance. Demand Side is fully integrated in the market, either through the reduction of suppliers' capacity obligation or direct participation after certification. In addition to the expected benefits in terms of security of supply, the French capacity market will foster the development of demand response. The participation of foreign capacities will require adaptations which are scheduled in a road-map, and could pave the way for further European integration of energy policies. (authors)

  2. Wind: French revolutions

    International Nuclear Information System (INIS)

    Jones, C.

    2006-01-01

    Despite having the second best wind resources in Europe after the UK, the wind industry in France lags behind its European counterparts with just 6 W of installed wind capacity per person. The electricity market in France is dominated by the state-owned Electricite de France (EdF) and its nuclear power stations. However, smaller renewable generators are now in theory allowed access to the market and France has transposed the EU renewables directive into national law. The French governement has set a target of generating 10,000 MW of renewable capacity by 2010. The announcement of an increased feed-in tariff and the introduction of 'development zones' (ZDEs) which could allow fast-tracking of planning for wind projects are also expected to boost wind projects. But grid access and adminstrative burdens remain major barriers. In addition, French politicians and local authorities remain committed to nuclear, though encouraged by the European Commission, wind is beginning to gain acceptance; some 325 wind farms (representing 1557 MW of capacity) were approved between February 2004 and January 2005. France is now regarded by the international wind energy sector as a target market. One of France's leading independent wind developers and its only listed wind company, Theolia, is expected to be one of the major beneficiaries of the acceleration of activity in France, though other companies are keen to maximise the opportunities for wind. France currently has only one indigenous manufacturer of wind turbines, but foreign suppliers are winning orders

  3. Heterogeneous reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

  4. Smart grids - French Expertise

    International Nuclear Information System (INIS)

    2015-11-01

    The adaptation of electrical systems is the focus of major work worldwide. Bringing electricity to new territories, modernizing existing electricity grids, implementing energy efficiency policies and deploying renewable energies, developing new uses for electricity, introducing electric vehicles - these are the challenges facing a multitude of regions and countries. Smart Grids are the result of the convergence of electrical systems technologies with information and communications technologies. They play a key role in addressing the above challenges. Smart Grid development is a major priority for both public and private-sector actors in France. The experience of French companies has grown with the current French electricity system, a system that already shows extensive levels of 'intelligence', efficiency and competitiveness. French expertise also leverages substantial competence in terms of 'systems engineering', and can provide a tailored response to meet all sorts of needs. French products and services span all the technical and commercial building blocks that make up the Smart Grid value chain. They address the following issues: Improving the use and valuation of renewable energies and decentralized means of production, by optimizing the balance between generation and consumption. Strengthening the intelligence of the transmission and distribution grids: developing 'Supergrid', digitizing substations in transmission networks, and automating the distribution grids are the focus of a great many projects designed to reinforce the 'self-healing' capacity of the grid. Improving the valuation of decentralized flexibilities: this involves, among others, deploying smart meters, reinforcing active energy efficiency measures, and boosting consumers' contribution to grid balancing, via practices such as demand response which implies the aggregation of flexibility among residential, business, and/or industrial sites. Addressing

  5. Planning and developing the French nuclear programme

    International Nuclear Information System (INIS)

    Carle, R.

    1983-01-01

    Since France has been compelled to free itself from the domination of oil, it has undertaken a nuclear programme capable of providing for nearly one third of its energy needs by 1990. Some years after the first oil crisis, a good part of the battle has already been won: 22 reactor units of 900 MW each have been connected to the grid and account for 40% of the electricity produced in France, while 12 other 900 MW units, together with the first 1300 MW units, are under construction. Nuclear power has thus become an industrial reality possessed of the tools appropriate for the whole fuel cycle, which has managed to cope with costs and meet deadlines, and has developed a safe and reliable product. With these positive results despite inevitable incidents the French nuclear industry has come of age. There are, however, handicaps which remain to be overcome: high investment costs, operating constraints and continuing doubt on the part of the public. The efforts deployed in these three spheres are beginning to bear fruit. As a result, implementation of the French nuclear programme is being continued, albeit at a slower rate, for the aim is no longer to replace oil by nuclear power as soon as possible, but rather to keep up with the rise in consumption. In pursuing its nuclear efforts, France will henceforth be stressing progress in terms of quality, which can still be achieved in terms of increased reliability (incorporation of feedback), better economic return (initiation of a new series known as ''N4''), easier operation (improvement of the man-machine interface) and also more independence. The ''frenchification'' of the light-water reactor has from the beginning been seen as one of the means of achieving this independence. This also applies to mastery of the whole fuel cycle. And finally, fast breeders represent the next stage

  6. Development of the French Photovoltaic Program

    Energy Technology Data Exchange (ETDEWEB)

    Brunet, M.

    1980-07-01

    The French photovoltaic research program is reviewed, listing companies involved. Projections of module and system costs are discussed. French industrial experience in photovoltaics is reviewed and several French systems operating in developing countries are mentioned. (MHR)

  7. EDF's (Electricite de France) in service control for GCR type reactor vessels

    International Nuclear Information System (INIS)

    Douillet, M.G.

    1979-01-01

    This paper presents the performance of the data acquisition and processing systems developed by the French EDF for controlling and testing the mechanical properties (thermal stress, deformations, cracks,...) of prestressed concrete vessels for GCR type reactors

  8. EDF's PWR power plants: anomalies concerning the reactor core instrumentation system

    International Nuclear Information System (INIS)

    1985-10-01

    This report presents the problems of fatigue and leaks found on the internal core instrumentation thimbles of several French PWR power plants, as also the solutions chosen according the reactor has already or not been operating [fr

  9. Essential French Vocabulary Teach Yourself

    CERN Document Server

    Saint-Thomas, Noel

    2010-01-01

    Essential French Vocabulary is the course for you if you need help with your study of French. This fully revised edition of our best-selling course now comes with free downloadable audio support containing hints on how to learn vocabulary effectively.

  10. The French Revolution and "Revisionism."

    Science.gov (United States)

    Langlois, Claude

    1990-01-01

    Outlines revisionist interpretations of the French Revolution that challenged the dominant historiographical tradition during the 1950s and 1960s. Distinguishes four central characteristics of revisionist works. Identifies a key split in current French Revolution historiography between reflection on nineteenth-century…

  11. French Immersion Programs in Canada.

    Science.gov (United States)

    Safty, Adel; And Others

    1988-01-01

    Five articles on issues associated with French immersion approaches and bilingual education within the Canadian educational system are presented. Topics include attitudes, impacts, children's reading processes, early versus late immersion programs in British Columbia, and a study of writing ability of English-speaking students in French-speaking…

  12. Women in the French Underground.

    Science.gov (United States)

    Rossiter, Margaret

    1980-01-01

    French women filled many positions in the development of the clandestine French Resistance Press. The press expanded from a handful of papers in 1940 to over 100 national papers by 1944. Papers directed specifically to women urged their support of the Resistance Movement. (PMJ)

  13. Publications in psychology: French issues

    OpenAIRE

    FRANK ARNOULD; ENZA MORALE; LAURENT PANES

    2009-01-01

    This paper discusses the situation of psychology publications in France, in particular, the visibility of French research through journals and bibliographic databases; the role of publications for the evalua-tion of researchers and laboratories, and the contribution of French psychologists to a national publica-tions archiving platform.

  14. Vitrification of reactor wastes

    Energy Technology Data Exchange (ETDEWEB)

    Jouan, A. [CEA Centre d`Etudes de la Vallee du Rhone, 30 - Marcoule (France). Dept. des Procedes de Retraitement; Sussmilch, J. [Nuclear Research Institut, Rez (Czech Republic)

    1993-12-31

    The vitrification of low and intermediate level wastes from the NPP operation has been studied in the frame of a Franco-Czech agreement. The laboratory experiments concentrated on a search for a suitable borosilicate glass matrix which could incorporate relatively high quantities of boron and sodium, main components of liquid wastes from the WWER reactor type NPPs. A relatively wide area of waste compositions has been studied and properties of glasses suitable for the technology and waste disposal were measured. Great attention has been paid to the chemical stability (leachability), other properties like thermal dependence of viscosity and electrical conductivity of melts, and the microstructure of the final solidification product have also been evaluated. The feasibility of the vitrification process has been proved during pilot plant tests which were accomplished at the French establishment in Marcoule. The results of tests were promising. (authors). 4 tabs., 7 figs.

  15. Vitrification of reactor wastes

    International Nuclear Information System (INIS)

    Jouan, A.

    1993-01-01

    The vitrification of low and intermediate level wastes from the NPP operation has been studied in the frame of a Franco-Czech agreement. The laboratory experiments concentrated on a search for a suitable borosilicate glass matrix which could incorporate relatively high quantities of boron and sodium, main components of liquid wastes from the WWER reactor type NPPs. A relatively wide area of waste compositions has been studied and properties of glasses suitable for the technology and waste disposal were measured. Great attention has been paid to the chemical stability (leachability), other properties like thermal dependence of viscosity and electrical conductivity of melts, and the microstructure of the final solidification product have also been evaluated. The feasibility of the vitrification process has been proved during pilot plant tests which were accomplished at the French establishment in Marcoule. The results of tests were promising. (authors). 4 tabs., 7 figs

  16. General and Professional French Courses

    CERN Multimedia

    HR Department

    2010-01-01

    The next session will take place from 11 October to 17 December 2010. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux, tel. 78144. NEW COURSES Specific French courses -Exam preparation/ We are now offering specific courses in English and French leading to a recognised external examination (e.g. DELF 1 and 2). If you are interested in following one of these courses and have at least an intermediate level of French, please enrol through the following link: French courses or contact: Lucette Fournier, tel.  73483 (French courses).

  17. Fabrication and irradiation performance of French HTGR fuel

    International Nuclear Information System (INIS)

    Moreau, C.; Ballagny, A.; Bujas, R.; Holder, J.; Ranc, R.; Soulhier, R.

    1977-01-01

    The fabrication of fuel for high-temperature reactors has been carried out in France either by using the techniques of the General Atomic Company or by adapting European techniques to the characteristics of the American fuel. Currently, the principal efforts are directed towards fuel containing enriched uranium and thorium. Prior to this, a large body of experience had been accumulated on the low enriched fuel of the type used in the Dragon reactor. Installations now in service permit fabrication, at realistic levels, of all the different parts comprising the fuel block. The kernels of fissile particles are made by loading of ion-exchange resin beads and conversion by thermal treatment. The fertile kernels are obtained by dry agglomeration of thorine powder. The coatings, of either BISO or TRISO design (pyrocarbon or pyrocarbon and silicon carbide), are deposited in a fluidized bed in a 127-mm-diameter industrial furnace. The fuel rods (or compacts) are obtained by injecting a pitch loaded with graphite powder into a bed of particles. Another technique, which is now under development, consists of hot-pressing the particles which have been mixed with resin-impregnated graphite powder and then polymerizing them. In both cases, a final thermal treatment is carried out at 1800 0 C. Research and development in the machining of the prismatic graphite blocks has been performed by the Atelier ''Graphite'' at the Marcoule Research Centre. A large programme of irradiations has permitted testing of the individual fuel components followed by tests on complete fuel assemblies. Particles, fuel rods and graphite have been tested in capsules placed in experimental French reactors. Fuel elements have been proof-tested either in the irradiation loops of the Osiris and Pegasus reactors or in the Dragon reactor. The results of these tests have shown that the French fuel can withstand the operating conditions in a power reactor (temperature, fast fluence, burnup) without exceeding the

  18. EPR by Areva. EPR the 1600+ MWe reactor

    International Nuclear Information System (INIS)

    2008-01-01

    This brochure presents the GEN III+ EPR reactor designed by the Areva and Siemens consortium. The EPR reactor is a direct descendent of the well-proven N4 and KONVOI reactors, the most modern reactors in France and Germany. The EPR was designed by teams from KWU/Siemens and Framatome, EDF in France and the major German utilities, working in collaboration with both French and German safety authorities. The EPR integrates the results of decades of R and D programs, in particular those performed by the CEA (French Atomic Energy Commission) and the Karlsruhe Research Center in Germany. The EPR benefits from the experience of several thousand reactor-years of operation of pressurized water reactor technology. This experience has put 87 AREVA PWRs online throughout the world. Innovative Features: - An outer shell covering the reactor building, the spent fuel building and two of the four safeguard buildings provides protection against large commercial or military aircraft crash. - A heavy neutron reflector that surrounds the reactor core lowers uranium consumption. - An axial economizer inside the steam generator allows a high level of steam pressure and therefore high plant efficiency. - A core catcher allows passive collection and retention of the molten core should the reactor vessel fail in the highly unlikely event of a core melt. - A digital technology and a fully computerized control room with an operator friendly man-machine interface improve the reactor protection system

  19. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  20. 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

    The French natural uranium-graphite power-reactor programme has been developing - from EDF 1 to EDF 4 - in the direction of an increase of the unit power of the installations, of the specific and volume powers, and of an improvement in the operational security conditions. The high power of EDF 4 (500 MWe) and the integration of the primary circuit into the reactor vessel, which is itself made of pre-stressed concrete, make it possible to make the most of the annular fuel elements already in use in EDF 1, and to arrive thus at a very satisfactory solution. The use of an internally cooled fuel element (an annular element) has led to a further step forward: it now becomes possible to increase the pressure of the cooling gas without danger of causing creep in the uranium tube. The use of a pre-stressed concrete vessel makes this pressure increase possible, and the integration of the primary circuit avoids the risk of a rapid depressurization which would be in this case a major danger. This report deals with the main problems presented by this new type of nuclear power station, and gives the main lines of research and studies now being carried out in France. - Neutronic and thermal research has made it possible to consider using large size fuel elements (internal diameter = 77 mm, external diameter 95 mm) while still using natural uranium. - The problems connected with the production of these elements and with their in pile behaviour are the subject of a large programme, both out of pile and in power reactors (EDF 2) and test reactors (Pegase). - The increase in the size of the element leads to a large lattice pitch (35 to 40 cm). This makes it possible to consider having one charging aperture per channel or for a small number of channels, whether the charge machine be inside or outside the pressure vessel. In conclusion are given the main characteristics of a project for a 500 MWe power station using such a fuel element. In particular this project is compared to EDF 4

  1. French courses for beginners

    CERN Multimedia

    Françoise Benz

    2006-01-01

    If you wish to participate in one of the following courses, please tell to your supervisor and apply electronically from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training'form available from your Departmental Secretariat or from your DTO (Departmental Training Officer). Applications will be accepted in the order in which they are received. French courses for beginners (level 0) From 17 July to 31 August 2006. Mondays, Tuesdays, Wednesdays and Thursdays(8 hours a week / between 11.00 and 15.30) Duration: 56 hours Price: 728 CHF For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127.

  2. The French nuclear programme

    International Nuclear Information System (INIS)

    Bacher, Pierre

    1987-01-01

    France has a civil nuclear power generation programme second only to the USA with 49 nuclear units in operation and 13 under construction. The units in service are described. These include 33 PWR 900 MW and 9 PWR 1300 MW units. The electricity consumption and generation in France is illustrated. The absence of a powerful anti-nuclear lobby and two main technical options have contributed to the success of the French nuclear programme. These are the PWR design and the plant standardization policy which allows the setting up of an effective industrial complex (eg for analysis of operating conditions and of safety and reliability information). The programme and the reasons for its success are reviewed. Research programmes and future plans are also discussed. (UK)

  3. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  4. Contribution of computerization to alarm processing: A French safety view

    International Nuclear Information System (INIS)

    Cette, W.

    1997-01-01

    Following the TMI accident and according to the requirement of the French safety authority, very important studies were performed by the French utility, Electricite de France (EDF), and assessed by the Institute for Nuclear Safety and Protection (IPSN) on reactor operation in conventional control rooms, particularly on alarm processing. These studies dealt with the man-machine interface, as well as design and exploitation requirements, presentation and management of alarm signals, and associated operating documents. The conclusions of these studies have led to improvements in French conventional control rooms. The current state of these control rooms and links between alarm sets and operating documents will be shortly presented in the first part of the paper. More recently, the computerized means implemented in the PWR 1400 MWe control rooms (N4) profoundly modified reactor operation. In particular, major advances concern alarm processing in comparison with conventional control rooms. The N4 plants provide a more rigorous approach in processing and presentation of alarms than in the past. Indeed, EDF wanted to have less alarms switched on during plant upsets and to make them more characteristic of a specific situation of the process. For example, computerization makes it easier to validate or inhibit alarms according to the situation, to allow the operator to manage alarm presentation and to propose on-line alarm sheets to the operator etc. This approach in comparison with conventional control rooms, and the IPSN assessment will be presented in the second part of this paper. (author)

  5. French ESPN order, codes and nuclear industry requirements

    International Nuclear Information System (INIS)

    Laugier, C.; Grandemange, J.M.; Cleurennec, M.

    2010-01-01

    Work on coding safety regulations applicable to large equipment was undertaken in France as of 1978 to accompany the construction of a French nuclear plant. The needs of manufacturers were threefold: translate the design rules from the American licensor, meet the safety objectives expressed in French regulations published at that time through coding of industrial practices (order of February 26, 1974) and stabilize the work reference system between the operator - consultant - and the manufacturer responsible for applying technical recommendations. Significant work was carried out by AFCEN (the French Association for the Design, Construction and Operating Supervision of the equipment for Electronuclear boilers), an association created for this purpose, leading to the publication of a collection of rules related to mechanical equipment for pressurised water reactors, RCC-M and RSE-M, which will be discussed later, and also in several other technical fields: particularly mechanical equipment in fast neutron reactors, RCC-MR, electricity (RCC-E), and fuel (RCC-C). (authors)

  6. Science and the French Empire.

    Science.gov (United States)

    Osborne, Michael A

    2005-03-01

    Scholarly interest in French colonial science, interpreted to include colonial medical and scientific institutions as well as personages and other "actors" in France serving colonial agendas, has been robust for some two decades. This essay characterizes the complex and interlinked historical relationships between French metropolitan and colonial science as one of asymmetric coevolution. In analyzing scholarship on diverse topics from physics and military technology to colonial botany, medicine, geography, and racial theory, it interrogates the concepts of French nation and French empire and questions the historiographical and explanatory utility of the core-periphery model. Special scrutiny falls on a trope common to historigraphical studies of the postrevolutionary era, that of a firm French nationalism enabling largely rational colonial agendas and the promotion of these agendas by highly centralized Parisian bureaucracies. The essay calls for a reading of French history inclusive of regional colonialist activities and argues for the prevalence of municipal and regional maritime, technological, scientific, and military interests in constructing the modern French empire.

  7. Practising French grammar a workbook

    CERN Document Server

    Dr Roger Hawkins; Towell, Richard

    2015-01-01

    This new edition of Practising French Grammar offers a set of varied and accessible exercises for developing a practical awareness of French as it is spoken and written today. The lively examples and authentic texts and cartoons have been updated to reflect current usage. A new companion website provides a wealth of additional interactive exercises to help consolidate challenging grammar points. Practising French Grammar provides concise summaries of key grammatical points at the beginning of each exercise, as well as model answers to the exercises and translations of difficult words, making i

  8. Nuclear energy: French government policy; Politique nucleaire et diversification energetique: orientations gouvernementales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-02

    This report presents the French government policy concerning nuclear energy and alternative sources of energy for the next 10 years. This report overviews the situation of Super-Phenix fast reactor and presents the implications of the 30/12/1999 decree (Bataille's law) about the management of radioactive wastes.

  9. French regulatory requirements concerning severe accidents in PWRs and associated research programme

    International Nuclear Information System (INIS)

    L'Homme, A.; Pelce, J.

    1986-07-01

    This report gives a global view of the French reactor safety approach; aspects in relation with severe accidents are pointed out: safety goals regarding population, and safety goals regarding plant design. Ultimate or U procedures involving physical phenomena of severe accidents are then described. R. and D. programs have been defined with regard to the priorities resulting from this approach [fr

  10. [The French Comprehensive Cancer Centers in the French oncology landscape].

    Science.gov (United States)

    Reiffers, Josy

    2013-06-01

    For more than 60 years, the French Comprehensive Cancer Centers participate in public hospital service and are exclusively dedicated to the fight against cancer. This article returns on their history, their model, their group strategy with the creation of UNICANCER, their place in French cancer research and treatments today, their contribution to the cancer plans and the challenges and issues they will face in the next 10 years.

  11. SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Evans, D.J.R.; Downs, W.E.

    1974-01-01

    The SLOWPOKE reactor is described, which is a small pool type with thermal neutron fluxes ranging from 10 11 -10 12 n cm -2 sec -1 . It differs in many ways from conventional pool type, namely small critical mass, beryllium reflector and a closed reactor container. The reactor is designed as small and simply as possible, and consistently with safety and good operating practice. Access to the present model is via pneumatic irradiation tubes only, which limits the use of the facility to activation analysis, tracer production and training. (Mori, K.)

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  13. French Literature Abroad: Towards an Alternative History of French Literature

    Directory of Open Access Journals (Sweden)

    Simon Gaunt

    2015-07-01

    Full Text Available What would a history of medieval literature in French that is not focused on France and Paris look like? Taking as its starting point the key role played in the development of textual culture in French by geographical regions that are either at the periphery of French-speaking areas, or alternatively completely outside them, this article offers three case studies: first of a text composed in mid-twelfth century England; then of one from early thirteenth-century Flanders; and finally from late thirteenth-century Italy. What difference does it make if we do not read these texts, and the language in which they are written, in relation to French norms, but rather look at their cultural significance both at their point of production, and then in transmission? A picture emerges of a literary culture in French that is mobile and cosmopolitan, one that cannot be tied to the teleology of an emerging national identity, and one that is a bricolage of a range of influences that are moving towards France as well as being exported from it. French itself functions as a supralocal written language (even when it has specific local features and therefore may function more like Latin than a local vernacular.

  14. 7 CFR 993.7 - French prunes.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false French prunes. 993.7 Section 993.7 Agriculture... Order Regulating Handling Definitions § 993.7 French prunes. French prunes means: (a) Prunes produced from plums of the following varieties of plums: French (Prune d'Agen, Petite Prune d'Agen), Coates (Cox...

  15. 21 CFR 169.115 - French dressing.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 2 2010-04-01 2010-04-01 false French dressing. 169.115 Section 169.115 Food and... § 169.115 French dressing. (a) Description. French dressing is the separable liquid food or the... fabricated shall be safe and suitable. French dressing contains not less than 35 percent by weight of...

  16. English Grammar for Students of French.

    Science.gov (United States)

    Morton, Jacqueline

    This grammar is a self-study manual intended to aid native speakers of English who are beginning the study of French. It is designed to supplement the French textbook, not to replace it. The common grammatical terms that are necessary for learning to speak and write French are explained in English and illustrated by examples in both French and…

  17. French study and research program on water cooled reactor safety

    International Nuclear Information System (INIS)

    Zammite, R.

    1985-05-01

    Electricite de France and the CEA (Commissariat a l'Energie Atomique), joined to obtain, in several fields, the knowledge and qualified calculation tools, they need to develop new means to face the potential consequences of accidents. The bringing on of an important number of PWR units in France in the eightys involves a focusing on these studies. The main fields concerned are the following ones: core cooling accidents and severe accident prevention; fuel behavior in case of accident; containment behavior in accidental situation; emission, transfer and release of fission products in case of accident; probabilistic risk analysis, human factor and earthquakes [fr

  18. Scenario for commercialization of fast breeder reactors

    International Nuclear Information System (INIS)

    Kumaoka, Yoshio; Sato, Morihiko

    1989-01-01

    To realize the commercialization of fast breeder reactors (FBRs), it is essential to reduce construction costs to the same level as those for the current light water reactors. For this target to be attained, a highly important factor is to reduce to the lowest-levels possible the quantities of materials and volume of the buildings required for the primary and secondary sodium loops of the FBR. In this direction, an innovative compact FBR plant concept which holds promise for commercialization has been developed by introducing the pooltype reactor concept with the shortest possible secondary sodium loops, realized by coupling electromagnetic pumps with the steam generators. In comparison with the French Super Phenix reactor, for example, the construction of this 1,300-MWe FBR plant could be achieved with half the material quantities and plant volume required by the former type. (author)

  19. Feudalism and the French Revolution.

    Science.gov (United States)

    Kaiser, Thomas E.

    1979-01-01

    Reviews and questions the traditional established interpretation that the French Revolution was about feudalism. Concludes that revisionist historians have cast doubt upon the orthodox theory but that they have not supplied an alternative explanation. (Author/DB)

  20. General and professionnal French courses

    CERN Multimedia

    2013-01-01

    The next session will take place from 27 January to 4 April 2014. These courses are open to everyone working on the CERN site and to their spouses.   Oral Expression This course is aimed at students with a good knowledge of French who want to enhance their oral communication skills. Activities will include discussions, meeting simulations, role-plays, etc. The next session will take place from 27 January to 4 April 2014. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. The next session will take place from 27 January to 4 April 2014. For registration and further information on the courses, please consult our web site or contact Kerstin Fuhrmeister (70896 - language.training@cern.ch).

  1. General and professionnal French courses

    CERN Document Server

    2013-01-01

    The next session will take place from 27 January to 4 April 2014. These courses are open to everyone working on the CERN site and to their spouses.   Oral Expression This course is aimed at students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. The next session will take place from 27 January to 4 April 2014. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. The next session will take place from 27 January to 4 April 2014. For registration and further information on the courses, please consult our web site or contact Kerstin Fuhrmeister (70896 - language.training@cern.ch).

  2. French switch off in protest

    CERN Document Server

    McCabe, H

    1999-01-01

    French scientists have refused to restart two synchrotron machines after the summer vacation. They are protesting at the government decision to give money to the British synchrotron project Diamond, so ending hopes of the construction of the proposed

  3. Reshuffle lifts French synchrotron hopes

    CERN Multimedia

    McCabe, H

    2000-01-01

    The sacking of Claude Allegre as research minister has raised doubts over the level of France's promised participation in the construction of Diamond but reawakened French hopes that the synchrotron Soleil may now be built (1 page).

  4. NUCLEAR REACTOR

    Science.gov (United States)

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

    1958-01-21

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

  5. Reactor Neutrinos

    Directory of Open Access Journals (Sweden)

    Soo-Bong Kim

    2013-01-01

    Full Text Available We review the status and the results of reactor neutrino experiments. Short-baseline experiments have provided the measurement of the reactor neutrino spectrum, and their interest has been recently revived by the discovery of the reactor antineutrino anomaly, a discrepancy between the reactor neutrino flux state of the art prediction and the measurements at baselines shorter than one kilometer. Middle and long-baseline oscillation experiments at Daya Bay, Double Chooz, and RENO provided very recently the most precise determination of the neutrino mixing angle θ13. This paper provides an overview of the upcoming experiments and of the projects under development, including the determination of the neutrino mass hierarchy and the possible use of neutrinos for society, for nonproliferation of nuclear materials, and geophysics.

  6. REACTOR SHIELD

    Science.gov (United States)

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  7. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

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

  8. Chemical Reactors.

    Science.gov (United States)

    Kenney, C. N.

    1980-01-01

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

  9. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  10. English and French courses

    CERN Document Server

    2014-01-01

    If one of your New Year’s resolutions is to learn a language, there is no excuse anymore!   You can attend one of our English or French courses and you can practise the language with a tandem partner! Cours d’anglais général et professionnel La prochaine session se déroulera du 3 mars au 27 juin 2014. Ces cours s’adressent à toute personne travaillant au CERN ainsi qu’à leur conjoint. Pour vous inscrire et voir tout le détail des cours proposés, consultez nos pages web : http://cern.ch/Training. Oral Expression The next session will take place from 3 March to 27 June 2014. This course is intended for people with a good knowledge of English who want to enhance their speaking skills. There will be an average of 8 participants in a class. Speaking activities will include discussions, meeting simulations, role-plays etc. depending on the needs of the students. Writing Profe...

  11. 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.)

  12. Anglicism in the French language

    Directory of Open Access Journals (Sweden)

    Firoozeh Asghari

    2014-09-01

    Full Text Available There is no question nowadays as to the international and powerful status of English at a global scale and, consequently, as to its presence in non-English speaking countries at different levels.  It is the languages which have mostly influenced French after the Two World War. So that now Anglicism exists in all levels of French. In this paper, besides the phenomenon of Anglicism, we will mainly focus on the reasons of increasing French interest in using of this phenomenon and also on the reactions taken against it in France. The method used in this research is descriptive – analytical.   The Result of this study shows that there is no purely linguistic reason for “Anglicism” in a country like France. In fact this paper remarks that the strong impact of English on French rather than being influenced by linguistic reasons is influenced by the cultural & social reasons. Additionally, the finding shows that the French especially the youth like using English for several reasons which include “prestige”, “snobbery” and “superiority”. Amongst the mentioned reasons in this paper, what caused the French to worry about the spread of Anglicism is due to fear of the American cultural influence, what is changing in the American cultural hegemony.

  13. Future of nuclear power plants and reactor dismantling

    International Nuclear Information System (INIS)

    Tanguy, P.; Cregut, A.

    1994-01-01

    After some considerations on dismantling experience, technology, legislation and costs, the various causes for dismantling a reactor are reviewed (research program termination, plant obsolescence, ageing and safety problems) and the present and future situation concerning the French nuclear park is examined. The various tools, equipment and techniques for reactor dismantling and the related researches are presented: cutting techniques, decontamination techniques, remote control, robotics and automation, waste processing and conditioning

  14. Nuclear energy. The innovations of the N4 reactor

    International Nuclear Information System (INIS)

    Anon.

    1998-01-01

    The coupling to the electric network of the two first units of N4 type reactors, on the site of Chooz in the Ardennes, marks the third great step of the French nuclear programme of PWR type reactors, after the realization of 34 units of 900 MWe and 20 units of 1300 M We. The nuclear boiler N4, realizes a new evolution in power, in performances and in reliability. (N.C.)

  15. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

  16. Fuel assemblies for PWR type reactors: fuel rods, fuel plates. CEA work presentation

    International Nuclear Information System (INIS)

    Delafosse, Jacques.

    1976-01-01

    French work on PWR type reactors is reported: basic knowledge on Zr and its alloys and on uranium oxide; experience gained on other programs (fast neutron and heavy water reactors); zircaloy-2 or zircaloy-4 clad UO 2 fuel rods; fuel plates consisting of zircaloy-2 clad UO 2 squares of thickness varying between 2 and 4mm [fr

  17. Breeding characteristics analysis of a commercial fast reactor cooled with sodium liquid

    International Nuclear Information System (INIS)

    Kosaka, N.; Shigehiro, A.

    1982-01-01

    The fast reactor breeding characteristics and its safety is analysed. As reference, for a preliminar analysis, the specifications of Super-Phenix, reactor french of 1200 MWe, are used, varying some parameters after aiming to verify its effects on duplication time. (E.G.) [pt

  18. Integrating wind power in the (French) power system

    International Nuclear Information System (INIS)

    Pellen, A.

    2007-03-01

    RTE and EDF have no other technological option than to restrain the contribution of the French wind power fleet to base-load generation where it comes in direct competition with the nuclear power plants. The author aims to explain this situation and answer the following questions. Why the fossil fueled reactor fleet in France will not be affected by an evolution of the wind power capacity? Why, in France electric power generation-demand SYSTEM wind power cannot be a substitute for fossil fueled thermal units? (A.L.B.)

  19. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1978-01-01

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given. (UK)

  20. Reactor utilization

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-01-01

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel

  1. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  2. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Araki, Takao; Saito, Yasushi.

    1987-01-01

    Purpose: To reduce the seismic wave responsivity of an exhaust duct shields thereby preventing the release of tritium in an evacuating device due to failures upon earthquakes. Constitution: The ends on the cutting side of upper outer exhaust duct shields of a thermonuclear reactor are connected with a plurality of support beams. In a case where seismic vibrations are exerted to such a thermonuclear reactor, since the ends on the cutting side are coupled with the support beams, vibrations of the upper outer exhaust duct shields are greatly restricted. Thus, since there is no more such a possibility, for example, that an exhaust duct connected to the upper portion of a reactor main body is greatly distorted due to the seismic response of the upper outside exhaust duct shields to result in the failure of the connection portion with a vacuum pump, the release of tritium due to failure of the evacuating device can be prevented. (Yoshino, Y.)

  3. Comparing Written Competency in Core French and French Immersion Graduates

    Directory of Open Access Journals (Sweden)

    Kerry Lappin-Fortin

    2014-12-01

    Full Text Available Abstract Few studies have compared the written competency of French immersion students and their core French peers, and research on these learners at a postsecondary level is even scarcer. My corpus consists of writing samples from 255 students from both backgrounds beginning a university course in French language. The writing proficiency of core French and French immersion graduates was compared based on total output and several measures of grammatical and syntactical accuracy. Few statistically significant differences emerge. However, a subgroup of core French learners who had benefitted from an authentic immersion experience appears to outperform both regular core French and French immersion groups. The purpose of this quantitative study is primarily diagnostic; the results should help universities better serve the needs of first-year students. Résumé Les études comparant la compétence écrite des étudiants de programmes d’immersion française et de français cadre sont peu nombreuses—particulièrement au niveau postsecondaire. Mon corpus consiste en des échantillons du français écrit de 255 étudiants issus de ces deux formations qui commencent un cours de français à l’université. J’ai comparé leur production globale et leur précision sur le plan morphosyntaxique. Peu de différences statistiquement significatives en émergent. Toutefois, un sous-groupe d’étudiants cadre ayant bénéficié d’une expérience d’immersion authentique se révèle comme le plus compétent selon plusieurs des mesures utilisées. Les résultats de cette étude quantitative devraient aider les universités à mieux répondre aux besoins des étudiants de première année.

  4. The French electricity report 2009

    International Nuclear Information System (INIS)

    2010-01-01

    RTE is the company responsible for running the French electricity transmission system. It is a public service operator, tasked with operating, maintaining and developing the high and extra high voltage network. It guarantees the reliability and proper operation of the power network. These missions were entrusted to it by the Law of 10 February 2000. With 100,000 km of lines between 63,000 and 400,000 volts and 45 cross-border lines, the network operated by RTE is the biggest in Europe. In 2008, RTE posted turnover of euros 4,221 m and currently employs around 8,500 staff. RTE, by virtue of the missions entrusted to it by the Law of 10 February 2000, is the central player in the French power system. For the purpose of maintaining the real time balance between supply and demand, and managing contractual relations with customers connected to its network, RTE monitors all the electrical energy that enters and leaves the public transmission system. Through its management of the 45 interconnection lines linking France with its neighbours, RTE also tracks all import and export data, on behalf of players in the French and European electricity market. RTE constantly records and examines data provided by all market players. Using the data, monthly and annually, it publishes exhaustive figures for the French power system (demand, generation, imports and exports), which offer the only truly accurate reflection of the real state of the sector's economy. This report presents these figures for the year 2009. Contents: 1 - French electricity demand down by 1.6% on 2008; 2 - A drop in French electricity generation; 3 - The balance of cross-border exchanges falls, but remains positive; 4 - RTE continues to invest in a robust network capable of keeping up with developments in the electricity industry; 5 - Appendix 1: New infrastructures on the RTE network in 2009; 6 - Appendix 2: Electricity quality; 7 - Appendix 3: Mature market mechanisms

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  6. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  7. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  8. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  9. Neutronic reactor

    International Nuclear Information System (INIS)

    Carleton, J.T.

    1977-01-01

    A graphite-moderated nuclear reactor includes channels between blocks of graphite and also includes spacer blocks between adjacent channeled blocks with an axis of extension normal to that of the axis of elongation of the channeled blocks to minimize changes in the physical properties of the graphite as a result of prolonged neutron bombardment. 3 claims, 6 figures

  10. French revolution or industrial revolution?

    DEFF Research Database (Denmark)

    Weisdorf, Paul R. Sharp Jacob L.; Weisdorf, Jacob Louis

    2012-01-01

    At the end of the eighteenth century, England and France both underwent revolutions: France the French Revolution, England the industrial revolution. This note sheds new light on these contrasting experiences in the histories of England and France by looking at the evolution of real consumer prices...... to maintain a decent living, and often had to cut consumption to make ends meet. The exercise conducted in the present paper gives a quantitative and economic underpinning to the notion that the French revolution did not arise out of nowhere, but rather had its roots in centuries of hardship amongst working...

  11. Food studies in French History

    DEFF Research Database (Denmark)

    Hedegaard, Liselotte

    The overarching question of this paper is whether it is possible to identify concepts that define a specifically French tradition regarding food. Two themes seem central. The first theme is the relationship between food and place as it emerges in concepts such as authenticity and terroir. The sec......The overarching question of this paper is whether it is possible to identify concepts that define a specifically French tradition regarding food. Two themes seem central. The first theme is the relationship between food and place as it emerges in concepts such as authenticity and terroir...

  12. French regulation and waste management

    International Nuclear Information System (INIS)

    1984-08-01

    The organization and the role played by French safety authorities for waste management are described. The French policy for storage and conditioning: basic objectives and waste management optimization are specified. Safety requirements are based on the barrier principle, they are mentioned for packaging and storage. The ''Institut de Protection et Surete Nucleaire'' deals not only with safety analysis but also help the ''autorites ministerielles'' for the development of fundamental safety rules. Examples for spent fuel storage and radioactive materials transport are treated in appendixes [fr

  13. EPR (European Pressurized water Reactor) The advanced nuclear reactor

    International Nuclear Information System (INIS)

    2004-01-01

    Nuclear energy, which provides a steady supply of electricity at low cost, has its rightful place in the energy mix of the 21. century, which puts the emphasis on sustainable development. The EPR is the only 3. generation reactor under construction today. It is an evolutionary reactor that represents a new generation of pressurized water reactors with no break in the technology used for the most recent models. The EPR was developed by Framatome and Siemens, whose nuclear activities were combined in January 2001 to form Framatome ANP, a subsidiary of AREVA and Siemens. EDF and the major German electricity companies played an active part in the project. The safety authorities of the two countries joined forces to bring their respective safety standards into line and draw up joint design rules for the new reactor. The project had three objectives: meet the requirements of European utilities, comply with the safety standards laid down by the French safety authority for future pressurized water reactors, in concert with its German counterpart, and make nuclear energy even more competitive than energy generated using fossil fuels. The EPR can guarantee a safe, inexpensive electricity supply, without adding to the greenhouse effect. It meets the requirements of the safety authorities and lives up to the expectations of electricity utilities. This document presents the main characteristics of the EPR, and in particular the additional measures to prevent the occurrence of events likely to damage the core, the leak-tight containment, the measures to reduce the exposure of operating and maintenance personnel, the solutions for an even greater protection of the environment. The foreseen development of the EPR in France and abroad (Finland, China, the United States) is summarized

  14. The PWR fuel cycle. Utilization of uranium in a reactor

    International Nuclear Information System (INIS)

    Mignot, E.

    After having briefly described the core of a pressurized water reactor, the fuel is examined and, in particular, the change in reactivity that governs the renewal of the fuel. The present French nuclear units are taken as example and it is shown that with the development of the nuclear complex, it is no longer possible to reason on the basis of an isolated reactor, since the running of a reactor is set by the network and its working constraints become a priority. The optimization of the fuel control must therefore cover the total cost [fr

  15. French how to speak and write it

    CERN Document Server

    Lemaître, Joseph

    1978-01-01

    Probably the most delightful, useful, and comprehensive elementary book available for learning spoken and written French, either with or without a teacher. Includes colloquial French conversations as well as grammar, vocabulary, and idiom studies.

  16. The operating experience of French PWRs

    International Nuclear Information System (INIS)

    Meclot, B.

    1984-01-01

    Since March 1, 1984, 27 PWR plants of 900 MW have been connected to the French grid, and their installed capacity of 24,280 MW constitutes a half of the thermal power plants of Electricite de France. The energy production of the PWR plants amounted to 126 TWh in 1983, that is, 68 % of the thermal output. At the beginning of 1984, the total operating experience of 27 plants reached 87 reactor years, and 47 shutdowns have been made for inspection and refueling. In 1984, six new plants are to be commissioned, and two of these are the first 1,300 MW plants. When the proportion of nuclear power plants becomes substantial, they tend to be operated in load-following mode, and such situation has begun as early as 1982 in France. The availability of 23 plants of one year old was 55 %, that of 21 plants of two years old was 56 %, and that of 16 plants of three years old was 67 %. The policy of the standardized technical design has resulted in very beneficial series effect. All the collected data and their follow up have been stored in the Event File, and as of March 1, 1984, more than 7,000 events have been processed. The adaptation to power regulation, the extension of refueling intervals, and the shutdown for maintenance and refueling are reported. (Kako, I.)

  17. French pharmacovigilance: Missions, organization and perspectives.

    Science.gov (United States)

    Vial, Thierry

    2016-04-01

    Pharmacovigilance aims to identify unknown adverse drug reactions once clinical development is complete, in order to promote improved use of drugs, and thus a reduction in risk for every exposed patient. We describe in this article the missions of French pharmacovigilance system, including French drug agency, Regional Centers of Pharmacovigilance, health professionals, pharmaceutical companies, patients and their associations. We also develop the French pharmacovigilance organization, its perspectives and challenges, both in French and European levels. Copyright © 2016. Published by Elsevier Masson SAS.

  18. French lessons - can they help the US nuclear industry?

    International Nuclear Information System (INIS)

    Jasper, J.M.

    1987-01-01

    Many analyses of the politics and economics of nuclear energy in the United States rely on comparisons of US reactor programs with those of France, which have proven to be more successful. The kernel of the comparison is that France has a large and growing nuclear system that produces most of the country's electricity, little political resistance, electric rates that are among the lowest in Europe, and independence from the vicissitudes of the oil markets. By contrast, in the US there are widespread political resistance and unfavorable public opinion, uncertainty about future plans for nuclear energy, and a generally costly set of reactors that produce about 15% of the country's electricity. What is more, the relatively expensive American plants are often thought of to be less safe than their cheaper French counterparts. In attempting to explain the French success and the US failure, observers have been all too prone to single out as the root cause a particular political or economic factor that differs between the two countries. One of the major shortcomings of this approach is that there are a number of relevant differences, any of which could play a part in affecting the countries' nuclear programs and which may not be easily changed. Moreover, implicit in each explanation is a prescription for how to aid the ailing nuclear industry in the United States--a prescription that may well be questionable

  19. The role of research in nuclear regulation: A French perspective

    International Nuclear Information System (INIS)

    Livolant, M.

    1997-01-01

    Roughly speaking, the French Nuclear Protection and Safety Institute's role is similar in the French situation to the NRC administration role but with less authority role, which corresponds to another body in France. They define themselves as a technical support of the safety authorities. On the other hand, they have their own research laboratories. Among them, the most famous are the Phebus reactor and the Cabri reactor about which we have heard a lot these two days. They work on safety but also on protection of man and environment, management of accident conditions, security of transport, and safeguards. They have a relationship with utilities and with government authorities. With the utilities they have two types of technical evaluations. They make detailed technical studies of the safety reports presented to the authorities by the utility. On the research side, they participate in common research programs to resolve issues and to increase knowledge and understanding about safety related questions. With the governmental authorities, their role is to give advice on safety reports of existing or being-built installations and on more general policy questions like, for example, the safety principle to apply to the next generation of power plants. The decisions are left to the safety authorities, but they give a lot of advice and detailed studies about questions of safety

  20. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  1. The development of fast reactors in France

    International Nuclear Information System (INIS)

    Vautrey, L.

    1982-01-01

    Only minor changes were introduced in the French nuclear programme by the new government in 1981. The operating conditions of Rapsodie were very satisfactory up to January 1982. After a leak in the double primary jacket (nitrogen circuit) the reactor was shut down for investigations. Phenix is continuing to operate smoothly. Construction of Super Phenix (Creys Malville power plant) is proceeding normally though with some delay. The studies for the future (after Creys Malville) are following their way both for the Project 1500 (Super Phenix 2) and for the specific plants of the fuel cycle. Research and development are largely directed toward Super Phenix 1 needs and the prospects of Super Phenix 2. International cooperation remains very intensive. The financial resources devoted to the development of fast reactors are globally stable. Including fuel cycle and safety (but excluding the Phenix operation) about 1300 millions of francs will be devoted to fast reactors by the C.E.A. in 1982. (author)

  2. The Kyoto conference: French perspective

    International Nuclear Information System (INIS)

    Orliange Philippe

    1998-02-01

    The present article approaches the problem of the climate change from a French perspective, describing the process that let the topic acquire importance in the national government level. Also, they stand out the difficulties generated in the negotiations of the Kyoto Protocol, because the opposing positions have United States and the European block

  3. Revis(iting French palatalization

    Directory of Open Access Journals (Sweden)

    Ali Tifrit

    2016-06-01

    Full Text Available This paper explores the diachrony of French and reconsiders the classical analysis of French palatalizations. It is widely admitted that the transition from Latin dorsal stops to French palatal fricatives is triggered by an external palatalizing object which affects the constitution of the targeted consonant. While this analysis can satisfyingly explain the palatalization of dorsals before /i/, it makes the palatalization before /a/, which occurred a few centuries later, completely opaque. Revising the internal structure and the melody used to describe segments (Government Phonology 2.0 – Pöchtrager 2006 allows us to give a unified analysis of both palatalizations: whether /i/ or /a/, the vocalic environment is indeed the trigger, as it interferes with the structure of dorsals and lead to internal changes. However, while /i/ adds palatality to the consonant, /a/, by its lack of melody (Pöchtrager & Živanović 2010, leads to an internal reconfiguration of the dorsal, which already contains . In other words, we face two kinds of palatalization: an external one and an internal one. Furthermore, our analysis takes the intermediate stages from Latin dorsals to French palatals into consideration and attested dialectal variations observed in Northern France.

  4. Fair period in French solar

    International Nuclear Information System (INIS)

    Pradel, P.

    1997-01-01

    The French solar industry decreased from 1992, but five years later, the situation changes and this industry is increasing again. The energy policy takes in account the renewable energies in a greater part, secondly, the technical reliability and a prices decreasing allow to this market to gain some ground. (N.C.)

  5. Stars War in French Gastronomy

    DEFF Research Database (Denmark)

    Gergaud, Olivier; Smeets, Valérie; Warzynski, Frederic

    In this paper, we analyze the careers from a sample of more than 1,000 top French chefs over more than twenty years and link it to the success or reputation of the restaurants where they have worked. This allows us to test what are the determinants of success but also to investigate the dynamics...

  6. General and Professional French Courses

    CERN Multimedia

    HR Department

    2011-01-01

    The next session will take place from 10th of October to 16th of December 2011. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://hr-training.web.cern.ch/hr-training/ or contact Kerstin Fuhrmeister (kerstin.fuhrmeister@cern.ch) Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. Suitable candidates should contact Kerstin Fuhrmeister (70896) or Martine Zuffi (73483) in order to arrange an appointment for a test. The next session will take place from 10th of October to 16th of December 2011. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. Suitable candidates should contact Kerstin Fuhrmeister (70896) or Martine Zuffi (73483) in order to arr...

  7. General and Professional French Courses

    CERN Multimedia

    HR Department

    2011-01-01

    The next session will take place from 30th of January to 5th of April 2012. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://hr-training.web.cern.ch/hr-training/ or contact Kerstin Fuhrmeister (kerstin.fuhrmeister@cern.ch) Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. Suitable candidates should contact Kerstin Fuhrmeister (70896) or Martine Zuffi (73483) in order to arrange an appointment for a test. The next session will take place from 30th of January to 5th of April 2012. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. Suitable candidates should contact Kerstin Fuhrmeister (70896) or Martine Zuffi (73483) in order to arrange an ...

  8. Dictionaries compiled with French and

    African Journals Online (AJOL)

    Information Technology

    The rising from the earth (referred to as "levée de terre" in. Gabonese French) generally follows this ceremony. Finally, after a year, a cele- bration is officially ..... Lexical items in this table are differentiated by topographic means. Items in bold type refer to lemmata as they appear in the dictionaries consulted, whereas words ...

  9. REMINDER REPLACEMENT OF FRENCH CARDS

    CERN Multimedia

    Human Resources Division; Cards.Service@cern.ch

    2001-01-01

    The French Ministry of Foreign Affairs is currently replacing all diplomatic cards, special cards and employment permits («attestations de fonctions») held by members of the personnel and their families. These cards are replaced by secure, computerized equivalents. The old cards may no longer be used after 31 December 2001. For the purposes of the handover, members of the personnel must go personally to the cards office (33/1-015) between 8h30 and 12h30, in order to fill in a «fiche individuelle» form, taking the following documents for themselves and members of their families already in possession of a French card : A recent identity photograph in 4.5 cm x 3.5 cm format, the French card in their possession, an A4 photocopy of the same French card, certified by the cards office as being a true copy. Those members of the personnel whose cards (and/or cards belonging to members of their families) are shortly due to expire, or have recently done so, are also requested...

  10. Female gender stereotype in French advertising texts

    Directory of Open Access Journals (Sweden)

    А С Борисова

    2008-06-01

    Full Text Available This article deals with the problem of female gender stereotypes in French advertising texts. On the ground of the practical analysis of advertising texts published in some modern French periodicals, we managed to expose and define general and national-cultural female gender stereotypes fixed in collective consciousness of the French.

  11. The French Revolution: A Simulation Game

    Science.gov (United States)

    Kiernan, James Patrick

    1978-01-01

    Describes a college-level simulation game about the French Revolution. Based on George Lefebvre's "The Coming of the French Revolution," the role-play focuses on social and economic causes of the revolution and allows students to understand citizens' grievances against the French government. (AV)

  12. Report: Immersion French at Meriden Junior School

    Science.gov (United States)

    Esposito, Marie-Josee

    2006-01-01

    In this article, the author describes the French immersion program at Meriden Junior School, an Anglican school for girls from pre-Kindergarten to Year 12 in Sydney. Four teachers (one of whom is the coordinator) and three assistants are involved in the program. They include six French native speakers and one non-French-born teacher who speaks…

  13. Rethinking Teaching Strategies for Intensive French

    Science.gov (United States)

    Collins, Jacquie; Stead, Shelley; Woolfrey, Sid

    2004-01-01

    This article gives the perspectives of three teachers of intensive French (IF) as they adjusted their thinking to teaching in a French as a second language (FSL) classroom that was very different from the core French classroom and developed teaching strategies to facilitate effective learning of communication skills by the students. Four major…

  14. France: Africans and the French Revolution.

    Science.gov (United States)

    Fatunde, Tunde

    1989-01-01

    The French Revolution had profound and long-term effects for Africans, both in Africa and throughout the Western hemisphere. Revolutionary leaders not only opposed the emancipation of slaves in French territories but supported an intensified slave trade, sparking numerous rebellions. French exploitation of Africans extended well into the twentieth…

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Gibbons, J.F.; McLaughlin, D.J.

    1978-01-01

    In the pressure vessel of the water-cooled nuclear reactor there is provided an internal flange on which the one- or two-part core barrel is hanging by means of an external flange. A cylinder is extending from the reactor vessel closure downwards to a seat on the core cupport structure and serves as compression element for the transmission of the clamping load from the closure head to the core barrel (upper guide structure). With the core barrel, subject to tensile stress, between the vessel internal flange and its seat on one hand and the compression of the cylinder resp. hold-down element between the closure head and the seat on the other a very strong, elastic sprung structure is obtained. (DG) [de

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.; Struensee, S.

    1976-01-01

    The invention concerns the use of burnable poisons in a nuclear reactor, especially in PWRs, in order to improve the controllability of the reactor. An unsymmetrical arrangement in the lattice is provided, if necessary also by insertion of special rods for these additions. It is proposed to arrange the burnable poisons in fuel elements taken over from a previous burn-up cycle and to distribute them, going out from the side facing the control rods, over not more than 20% of the lenth of the fuel elements. It seems sufficient, for the burnable poisons to bind an initial reactivity of only 0.1% and to become ineffective after normal operation of 3 to 4 months. (ORU) [de

  17. Reactor container

    International Nuclear Information System (INIS)

    Otsuka, Hiroaki; Yoshida, Takashi.

    1979-01-01

    Purpose: To prevent rain water falling along the outer wall of the container during the construction work of an atomic power plant from making ingress into the inner part of a reactor container through a large size material carry-in port. Constitution: A weir for preventing the ingress of rain water is provided on the border between the foot floor of a large material carry-in port provided on the side surface at the bottom part of the reactor container and the floor surface of the building. This weir is of a semi-circular plate shape, and formed so that the lower semi-circular part of the carry-in port is tightly closed. (Kamimura, M.)

  18. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Saba, Kazuhisa.

    1979-01-01

    Purpose: To improve the earthquake resistance as well as reduce the size of a container for a nuclear reactor with no adverse effects on the decrease of impact shock to the container and shortening of construction step. Constitution: Reinforcing profile steel materials are welded longitudinally and transversely to the inner surface of a container, and inner steel plates are secured to the above profile steel materials while keeping a gap between the materials and the container. Reactor shielding wall planted to the base concrete of the container is mounted to the pressure vessel, and main steam pipeways secured by the transverse beams and led to the outside of container is connected. This can improve the rigidity earthquake strength and the safetiness against the increase in the inside pressure upon failures of the container. (Yoshino, Y.)

  19. Reactor container

    International Nuclear Information System (INIS)

    Oyamada, Osamu; Furukawa, Hideyasu; Uozumi, Hiroto.

    1979-01-01

    Purpose: To lower the position of an intermediate slab within a reactor container and fitting a heat insulating material to the inner wall of said intermediate slab, whereby a space for a control rod exchanging device and thermal stresses of the inner peripheral wall are lowered. Constitution: In the pedestal at the lower part of a reactor pressure vessel there is formed an intermediate slab at a position lower than diaphragm floor slab of the outer periphery of the pedestal thereby to secure a space for providing automatic exchanging device of a control rod driving device. Futhermore, a heat insulating material is fitted to the inner peripheral wall at the upper side of the intermediate slab part, and the temperature gradient in the wall thickness direction at the time of a piping rupture trouble is made gentle, and thermal stresses at the inner peripheral wall are lowered. (Sekiya, K.)

  20. Neutronic reactor

    International Nuclear Information System (INIS)

    Lewis, W.R.

    1978-01-01

    Disclosed is a graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

    Purpose: To prevent cladding tube injuries due to thermal expansion of each of the pellets by successively extracting each of the control rods loaded in the reactor core from those having less number of notches, as well as facilitate the handling work for the control rods. Constitution: A recycle flow control device is provided to a circulation pump for forcibly circulating coolants in the reactor container and an operational device is provided for receiving each of the signals concerning number of notches for each of the control rods and flow control depending on the xenon poisoning effect obtained from the signals derived from the in-core instrument system connected to the reactor core. The operational device is connected with a control rod drive for moving each of the control rods up and down and a recycle flow control device. The operational device is set with a pattern for the aimed control rod power and the sequence of extraction. Upon extraction of the control rods, they are extracted successively from those having less notch numbers. (Moriyama, K.)

  2. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

    At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

  3. French Military Adaptation in the Afghan War

    DEFF Research Database (Denmark)

    Schmitt, Olivier

    2017-01-01

    For some, a specific feature of the French armed forces' adaptation process would be the capacity to look inward instead of outward in order to identify relevant solutions to tactical/doctrinal problems. This article questions such a narrative, and argues that the French armed forces are as quick...... as any to borrow from other countries’ experiences. In order to do so, this article introduces the concept of ‘selective emulation’, and compares the French and German military adaptation processes in Afghanistan. The article argues that there is indeed something distinctive about French military...... adaptation, but it is not what the fiercest defenders of the French ‘exceptionalism’ usually account for....

  4. Radiation protection on EPR: comparative approach of the French and Finnish regulatory reviewing process and optimization at the design phase

    International Nuclear Information System (INIS)

    Arial, E.; Couasnon, O.; Latil-querrec, N.; Evrard, J.M.; Herviou, K.; Riihiluoma, V.; Beneteau, Y.; Foret, J.L.

    2010-01-01

    Taking the opportunity to evaluate the preliminary safety report of the French EPR reactor built in Flamanville, the IRSN proposes to assess the history of EPR, from the decision to implement studies in the 90's to the French and German cooperation, and finally to the construction of a unit in Finland and in France, and to make a synthesis of the assessment of radiation protection arrangements. This assessment presents the dose targets (calculated reference doses) planned by the nuclear operators in the design phase as well as the global radiation protection optimization process and a comparison of French and Finnish analyses. In France, for example, EDF performed a detailed optimization analysis of selected tasks known to have a major contribution to the annual average collective dose (thermal insulation, logistics, valve maintenance, opening/closing of the vessel, preparation and checks of steam generators, on-site spent fuel management, and waste management). The optimization process is based (in France) on an iterative method. A comparison between the EPR collective dose target and doses received in other pressurized water reactors that are close to the EPR design (Konvoi of German design, French existing units, etc.) is also presented. This synthesis was carried out by the IRSN, the expert body of the French nuclear safety authority, in association with Electricite de France (EDF), the French operator, and the authority for nuclear safety in Finland (STUK). It summarizes more than 15 years of studies and partnership, focusing on radiation protection, in the design phase of the EPR. (authors)

  5. French roots of French neo-lamarckisms, 1879-1985.

    Science.gov (United States)

    Loison, Laurent

    2011-01-01

    This essay attempts to describe the neo-Lamarckian atmosphere that was dominant in French biology for more than a century. Firstly, we demonstrate that there were not one but at least two French neo-Lamarckian traditions. This implies, therefore, that it is possible to propose a clear definition of a (neo)Lamarckian conception, and by using it, to distinguish these two traditions. We will see that these two conceptions were not dominant at the same time. The first French neo-Lamarckism (1879-1931) was structured by a very mechanic view of natural processes. The main representatives of this first period were scientists such as Alfred Giard (1846-1908), Gaston Bonnier (1853-1922) and Félix Le Dantec (1869-1917). The second Lamarckism - much more vitalist in its inspiration - started to develop under the supervision of people such as Albert Vandel (1894-1980) and Pierre-Paul Grassé (1895-1985). Secondly, this essay suggests that the philosophical inclinations of these neo-Lamarckisms reactivated a very ancient and strong dichotomy of French thought. One part of this dichotomy is a material, physicalist tradition, which started with René Descartes but developed extensively during the 18th and 19th centuries. The other is a spiritual and vitalist reaction to the first one, which also had a very long history, though it is most closely associated with the work of Henri Bergson. Through Claude Bernard, the first neo-Lamarckians tried to construct a mechanical and determinist form of evolutionary theory which was, in effect, a Cartesian theory. The second wave of neo-Lamarckians wanted to reconsider the autonomy and reactivity of life forms, in contrast to purely physical systems.

  6. Revisiting the cost escalation curse of nuclear power. New lessons from the French experience

    International Nuclear Information System (INIS)

    Escobar Rangel, Lina; Leveque, Francois

    2012-01-01

    Since the first wave of nuclear reactors in 1970 to the construction of Generation III+ reactors in Finland and France in 2005 and 2007 respectively, nuclear power seems to be doomed to a cost escalation curse. In this paper we reexamine this issue for the French nuclear power fleet. Using the construction costs from the Cour des Comptes report, that was publicly available in 2012, we found that previous studies overestimated the cost escalation. Although, it is undeniable that the scale-up ended up in more costly reactors, we found evidence of a learning curve within the same size and type of reactors. This result confirms that standardization is a good direction to look, in order to overcome the cost escalation curse. (authors)

  7. The relationship of French people with energy

    International Nuclear Information System (INIS)

    Levy, Jean-Daniel; Potereau, Julien; Gautier, Antoine

    2017-12-01

    This Power Point document presents graphs and tables containing results of a survey performed on the relationship French people have with energy. After a presentation of the survey methodology, it addresses how France commitment in the struggle against climate change is perceived (French people think that their country could do better), which perceptions French people have of stakes and of the French energy policy (the management of the energy issue is perceived as perfectible, and French people have a positive view on energy transition and on the development of renewable energies), and which investments French people stand for (French people are in favour of a more important role of Europe and of citizen cooperatives in the field of energy)

  8. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

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

  9. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

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

  10. French people and energy issues

    International Nuclear Information System (INIS)

    Chesnais, L.

    2006-01-01

    An opinion poll made in France in 2006 shows that: - French people backs nuclear energy with a slight margin (45% versus 42%), - French people agrees with the electricity production policy led by the government, - about 4 people out of 10 expect a sharp increase in prices concerning car fuels, natural gas and heating fuels in a near future, on the other hand fewer people than in previous years are expecting a price rise for electricity. In this article some figures concerning the consumption of energy in France are given: - 230.000 jobs are directly or indirectly involved in the energy sector, this sector represents 5% of all investment, - a total bill of 24 milliard euros for the energy imports, and - energy spending represents 7.6% of the household budget. (A.C.)

  11. Venus transits - A French view

    Science.gov (United States)

    Débarbat, Suzanne

    2005-04-01

    After a careful study of Mars observations obtained by Tycho Brahé (1546-1601), Kepler (1571-1630) discovered the now-called Kepler's third law. In 1627 he published his famous Tabulae Rudolphinae, a homage to his protector Rudolph II (1552-1612), tables (Kepler 1609, 1627) from which he predicted Mercury and Venus transits over the Sun. In 1629 Kepler published his Admonitio ad Astronomos Advertisement to Astronomers (Kepler 1630), Avertissement aux Astronomes in French Au sujet de phénomènes rares et étonnants de l'an 1631: l'incursion de Vénus et de Mercure sur le Soleil. This was the beginning of the interest of French astronomers, among many others, in such transits, mostly for Venus, the subject of this paper in which dates are given in the Gregorian calendar.

  12. New french uranium mineral species

    International Nuclear Information System (INIS)

    Branche, G.; Chervet, J.; Guillemin, C.

    1952-01-01

    In this work, the authors study the french new uranium minerals: parsonsite and renardite, hydrated phosphates of lead and uranium; kasolite: silicate hydrated of uranium and lead uranopilite: sulphate of uranium hydrated; bayleyite: carbonate of uranium and of hydrated magnesium; β uranolite: silicate of uranium and of calcium hydrated. For all these minerals, the authors give the crystallographic, optic characters, and the quantitative chemical analyses. On the other hand, the following species, very rare in the french lodgings, didn't permit to do quantitative analyses. These are: the lanthinite: hydrated uranate oxide; the α uranotile: silicate of uranium and of calcium hydrated; the bassetite: uranium phosphate and of hydrated iron; the hosphuranylite: hydrated uranium phosphate; the becquerelite: hydrated uranium oxide; the curite: oxide of uranium and lead hydrated. Finally, the authors present at the end of this survey a primary mineral: the brannerite, complex of uranium titanate. (author) [fr

  13. French Prime Minister tours CERN

    CERN Multimedia

    Anaïs Schaeffer

    2012-01-01

    On 30 July, Jean-Marc Ayrault, the Prime Minister of the French Republic, and Geneviève Fioraso, the Minister of Higher Education and Research, visited the Laboratory.   After being met by the Director-General at LHC Point 5, they visited the CMS control centre and experiment cavern, and got a glimpse of the LHC tunnel at Point 5. The visit ended with a round-table discussion with French and other international members of CERN’s scientific community. During the discussion, the Prime Minister reaffirmed that “support for fundamental research has to be maintained, and France must continue to invest in education, research and innovation.” He also paid tribute to CERN's role in international cooperation, which he qualified as “a fine example of science without borders.”

  14. Reminder: Swiss and French cards

    CERN Multimedia

    2012-01-01

    Communication from the HR Department to members of personnel holding an employment or association contract, above 50% and for more than 3 months, with the Organization. The HR Department would like to remind all members of personnel concerned that they are obliged to: • hold a valid Swiss  Légitimation card AND a valid French card (“Titre de séjour spécial” or “attestation de fonctions”) at all times during the exercise of their functions in the Organization; • return these documents as soon as their functions in the Organization cease. Not following these rules could be prejudicial to the Organization and appropriate measures may be taken towards the member of personnel concerned. Information and procedures concerning Swiss and French cards (first application, renewal, theft/loss, etc.) are available in the Admin e-guide. Users and Unpaid Associates must contact the Users Office HR Department Tel.: 729...

  15. Swiss and French cards - Reminder

    CERN Multimedia

    HR Department

    2011-01-01

    Communication from the HR Department to members of personnel holding an employment or association contract, above 50% and for more than 3 months, with the Organization. The HR Department would like to remind all members of the personnel concerned that they are obliged to: hold a valid Swiss Légitimation card AND a valid French card (“Titre de séjour spécial” or “attestation de fonctions”) at all times during the exercise of their functions in the Organization; return these documents as soon as their functions in the Organization cease. Not following these rules could be prejudicial to the Organization and appropriate measures may be taken with respect to the member of the personnel concerned. Information and procedures concerning Swiss and French cards (first application, renewal, theft/loss, etc.) are available in the Admin e-guide: https://cern.ch/admin-eguide/cartes/proc_cartes_home.asp Users and Unpaid Associates must ...

  16. French people and nuclear wastes

    International Nuclear Information System (INIS)

    D'Iribarne, Ph.

    2005-01-01

    On March 21, 2005, the French minister of industry gave to the author of this document, the mission to shade a sociological light on the radioactive wastes perception by French people. The objective of this study was to supply an additional information before the laying down in 2006 of the decisions about the management of high-level and long-lived radioactive wastes. This inquiry, carried out between April 2004 and March 2005, stresses on the knowledge and doubts of the questioned people, on the vision they have of radioactive wastes and of their hazards, and on their opinion about the actors in concern (experts, nuclear companies, government, anti-nuclear groups, public). The last two parts of the report consider the different ways of waste management under study today, and the differences between the opinion of people living close to the Bure site and the opinion of people living in other regions. (J.S.)

  17. The French deterrence from 1945

    International Nuclear Information System (INIS)

    Bouchard, J.

    1997-01-01

    Here is presented a particular lighting of deterrence history, by sciences and technologies which have allowed their creation and development. Accompanying the historical evolution of the French deterrence forces during the first phase of these sciences constitution, these sciences and technologies are at the base of the nuclear weapons conception, but they also contributed to the realization of the industrial building and to a doctrine constitution. (N.C.)

  18. New Abbreviations in Colloquial French

    Directory of Open Access Journals (Sweden)

    Vladimir Pogačnik

    2015-12-01

    Full Text Available The author of the article treats the process of abbreviations, which he explored forty years ago in his master thesis. The article is based on the corpus created on the basis of Télématin broadcast on French television network TV5. According to the author, clipping is a widespread process that occurs primarily in various forms of oral communication.

  19. The French natural gas industry

    International Nuclear Information System (INIS)

    1999-01-01

    This little folder summarizes in few pages the main economical data of the French natural gas industry: supplies according to the country of origin, length of transport and distribution networks, LNG tanker ship fleet, underground storage capacity, population of LNG-fueled vehicles, cogeneration installations, consumption by sectors and by industrial activities, LPG consumption, supplies, distribution and sales, LPG-fuel for vehicles, CO 2 and NO x releases, equipment of households. (J.S.)

  20. Photocatalytic reactor

    Science.gov (United States)

    Bischoff, Brian L.; Fain, Douglas E.; Stockdale, John A. D.

    1999-01-01

    A photocatalytic reactor for processing selected reactants from a fluid medium comprising at least one permeable photocatalytic membrane having a photocatalytic material. The material forms an area of chemically active sites when illuminated by light at selected wavelengths. When the fluid medium is passed through the illuminated membrane, the reactants are processed at these sites separating the processed fluid from the unprocessed fluid. A light source is provided and a light transmitting means, including an optical fiber, for transmitting light from the light source to the membrane.

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Gruber, E.A.

    1979-01-01

    A nuclear reactor with control rods in channels between fuel assemblies wherein the fuel assemblies incorporate guide rods which protrude outwardly into the control rod channels to prevent the control rods from engaging the fuel elements. The guide rods also extend back into the fuel assembly such that they are relatively rigid members. The guide rods are tied to the fuel assembly end or support plates and serve as structural members which are supported independently of the fuel element. Fuel element spacing and support means may be attached to the guide rods. 9 claims

  2. French opinion on Nuclear Energy

    International Nuclear Information System (INIS)

    Bucaille, A.

    2003-01-01

    Contrary to what many think or say, most French people do not have a clear-cut opinion about nuclear power. And until public opinion can be accurately assessed, we should be worried of speaking on its behalf. More than half the population of France believes that nuclear power is the cheapest option, but 40% of them have no idea what the situation really is. The French are keenly aware of the what is at stake at the international level, and the fact that energy is becoming a worldwide issue. What they are most concerned about is nuclear waste and the possibility of a catastrophe of the Chernobyl type occurring. Disquiet about the first is now dissipating, after having increased. But attitudes about the second are ambivalent. A quarter of the French are very ignorant about radioactivity. 20% of the population complain that not enough information is forthcoming, particularly as concerns advances in technology. As can be anticipated, awareness of the question of climate change is growing year by year, with increased reporting of storms, floods and heat waves

  3. French statutory approach of the evaluation of the safety level of old nuclear divisions

    International Nuclear Information System (INIS)

    Delage, M.

    1994-06-01

    The legal French procedures include three steps which have to be followed during the exam of the safety in nuclear plants (creation authorization, loading authorization, actual running of the plant). After listing the different types of evaluation of safety in fraction of plants, this report presents the main themes encountered during the safety assessment: state of the reactor, maintenance, tracking of the incidents, personnel training, radioprotection, radioactive releases. The Fessenheim and Bugey list of reevaluation themes is also given. (TEC)

  4. D and DR Reactors

    Data.gov (United States)

    Federal Laboratory Consortium — The world's second full-scale nuclear reactor was the D Reactor at Hanford which was built in the early 1940's and went operational in December of 1944.D Reactor ran...

  5. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

    The subject is covered in chapters, entitled: concepts of reactor physics; neutron diffusion; core heat transfer; reactivity; reactor operation; variables of core management; computer code modules; alternative reactor concepts; methods of optimization; general system aspects. (U.K.)

  6. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T [Huntington Beach, CA; Sahimi, Muhammad [Altadena, CA; Fayyaz-Najafi, Babak [Richmond, CA; Harale, Aadesh [Los Angeles, CA; Park, Byoung-Gi [Yeosu, KR; Liu, Paul K. T. [Lafayette Hill, PA

    2011-03-01

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

  7. Reactor container

    International Nuclear Information System (INIS)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-01-01

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.)

  8. Reactor container

    Energy Technology Data Exchange (ETDEWEB)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-09-07

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.).

  9. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

    The device of the present invention monitors a reactor so that each of the operations for the relocation of fuel assemblies and the withdrawal and the insertion of control rods upon exchange of fuel assemblies and control rods in the reactor. That is, when an operator conducts relocating operation by way of a fuel assembly operation section, the device of the present invention judges whether the operation indication is adequate or not, based on the information of control rod arrangement in a control rod memory section. When the operation indication is wrong, a stop signal is sent to a fuel assembly relocating device. Further, when the operator conducts control rod operation by way of a control rod operation section, the device of the present invention judges in the control rod withdrawal judging section, as to whether the operation indication given by the operator is adequate or not by comparing it with fuel assembly arrangement information. When the operation indication is wrong, a stop signal is sent to control rod drives. With such procedures, increase of nuclear heating upon occurrence of erroneous operation can be prevented. (I.S.)

  10. The status of fast reactors programme in France in 2005

    International Nuclear Information System (INIS)

    Astegiano, J.C.; Baque, F.; Berson, X.; Dufour, Ph.; Martin, L.; Dumaz, P.; Garnier, J.C.; Rouault, J.

    2007-01-01

    From an overall point of view, four events must be pointed out: The new French law on energy: After the national debate organised in 2003 on energy policies for the next 30 years to come, the French government issued a White book on Energy, which contributed to the debate and gathered many contributions from French national representative organisations. In 2005, the French government proposed a new bill, adopted by French parliament on June 3, 2005. This law identified four major ideas for the future development of energy in France: - The economising of energy for a mastery of energy consumption, - The diversification of French energy resources with three activities involved: - Keeping the nuclear option open and building an EPR reactor as an industrial prototype before launching a series. - Supporting the development of renewable energies such as solar energy, biomass (including wood and bio-fuels), hydraulics and wind energy with the objective of reaching 21% of the electricity production in 2010. - Ensuring the safety of supply in the fields of oil, gas and coal. - The development of research in the energy sector, particularly an improvement of competitiveness for renewable energies, support for the nuclear energy option, the development of future reactor technologies, the hydrogen option. - The transport and distribution of energy that contributes considerably to economic and social development. This law, governing the orientations of the new energy policy also provides for the continued support of the nuclear option in France, which is a decisive option for three of the objectives in terms of the new energy policy defined within the texts of the law, namely 1) safeguard the independence of the French national energy resources and safety in their procurement, 2) fight against the Green House Effect and 3), ensure regular and competitive prices for electricity. It is therefore of the greatest importance to keep all options open for the replacement of present

  11. Nuclear. Areva, a French fission

    International Nuclear Information System (INIS)

    Dupin, Ludovic

    2015-01-01

    This article comments the difficulties and problems faced by Areva for its activity of nuclear reactor construction, and which leaded to the transfer of this activity from Areva to EDF while Areva will keep its uranium providing and fuel enrichment activities. These difficulties and problems concern the Flamanville EPR (the construction is 5 years late, vessel defects have just been identified, cost overruns), the Finnish EPR (7 years late, a 5 billions cost overrun), the Jules Horowitz research reactor (5 years late, cost overrun), and strategic choices (notably with respect to the post-Fukushima context). The article also outlines that other activities (mining, enrichment, reactor maintenance) are still doing well, and then briefly discusses the future of Areva NP

  12. French electric power balance sheet 2009

    International Nuclear Information System (INIS)

    Lartigau, Thierry; Riere, Alexia

    2010-01-01

    The mission of RTE, the French electricity Transportation grid, a public service assignment, is to balance the electricity supply and demand in real time. This report presents RTE's technical results for the year 2009: key figures of the French electricity consumption, lowering of the French power generation, decrease of trade balance at borders but still positive, continuation of RTE's investments for the improvement of the grid performance. New RTE's infrastructures, electricity quality data, and the evolution of market mechanisms are presented in appendixes

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Schabert, H.P.; Weber, R.; Bauer, A.

    1975-01-01

    The refuelling of a PWR power reactor of about 1,200 MWe is performed by a transport pipe in the containment leading from an external to an internal fuel pit. A wagon to transport the fuel elements can go from a vertical loading position to an also vertical deloading position in the inner fuel pit via guide rollers. The necessary horizontal movement is effected by means of a cable line through the transport pipe which is inclined at least 10 0 . Gravity thus helps in the movement to the deloading position. The cable line with winch is fastened outside the containment. Swivelling devices tip the wagon from the horizontal to the vertical position or vice versa. Loading and deloading are done laterally. (TK/LH) [de

  14. NEUTRONIC REACTOR

    Science.gov (United States)

    McGarry, R.J.

    1958-04-22

    Fluid-cooled nuclear reactors of the type that utilize finned uranium fuel elements disposed in coolant channels in a moderater are described. The coolant channels are provided with removable bushings composed of a non- fissionable material. The interior walls of the bushings have a plurality of spaced, longtudinal ribs separated by grooves which receive the fins on the fuel elements. The lands between the grooves are spaced from the fuel elements to form flow passages, and the size of the now passages progressively decreases as the dlstance from the center of the core increases for the purpose of producing a greater cooling effect at the center to maintain a uniform temperature throughout the core.

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

    In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread

  16. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  17. Appropriating Written French: Literacy Practices in a Parisian Elementary Classroom

    Science.gov (United States)

    Rockwell, Elsie

    2012-01-01

    In this article, I examine French language instruction in an elementary classroom serving primarily children of Afro-French immigrants in Paris. I show that a prevalent French language ideology privileges written over oral expression and associates full mastery of written French with rational thought and full inclusion in the French polity. This…

  18. French Policies towards the Chinese in Vietnam

    OpenAIRE

    Amer, Ramses

    2012-01-01

    This study examines the patterns of Chinese migration to and from Vietnam as well as the demographic changes relating to the Chinese residing in the country. It also outlines how the French authorities responded to the arrival of the Chinese and how they treated them. The focus is on the period of French control over the whole of Vietnam from 1883 to 1954. The French authorities did pay considerable attention to the Chinese migration to Vietnam. The policies of the French aimed at keeping a c...

  19. Crisis in the French nuclear industry

    International Nuclear Information System (INIS)

    Nectoux, F.

    1991-02-01

    This report discusses the economics of the French nuclear power industry. It considers the dominant position of nuclear power in the French energy system, stresses the scale and causes of the current (1990) economic crisis and dispels the popular misconceptions on the cost efficiency of the French programme. The evidence is based on widely available French documents and articles. The report begins by looking at the background of nuclear power in France then discusses the problem of overcapacity, the technical problems and fall in load factors, generating costs and electricity prices and finally, strategic issues are considered. (UK)

  20. Colloquial French the complete course for beginners

    CERN Document Server

    Demouy, Valérie

    2015-01-01

    Colloquial French: The Complete Course for Beginners has been carefully developed by an experienced teacher to provide a step-by-step course to French as it is written and spoken today. Combining a clear, practical and accessible style with a methodical and thorough treatment of the language, it equips learners with the essential skills needed to communicate confidently and effectively in French in a broad range of situations. No prior knowledge of the language is required. Colloquial French is exceptional; each unit presents a wealth of grammatical points that are reinforced with a wide range

  1. General meeting. Technical reunion: the numerical and experimental simulation applied to the Reactor Physics

    International Nuclear Information System (INIS)

    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.)

  2. 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

  3. French programme for HTR fuel

    International Nuclear Information System (INIS)

    Gillet, R.M.

    1991-01-01

    It is reported that in the frameworks of the French HTR research program, stopped in 1979 the HTR coated particle fuel, fuel rod and prismatic fuel element design have been successfully developed and irradiation tested in France and specific examination methods for irradiated fuel particles, rods and graphite blocks have been developed. Currently CEA is involved in fission product transport experiments sponsored by the US Department of Energy and performed in the COMEDIE loop. Finally the CEA follows progress and developments in HTR fuel research and development throughout the world. 1 tab

  4. French uranium mining sites remediation

    International Nuclear Information System (INIS)

    Roche, M.

    2002-01-01

    Following a presentation of the COGEMA's general policy for the remediation of uranium mining sites and the regulatory requirements, the current phases of site remediation operations are described. Specific operations for underground mines, open pits, milling facilities and confining the milled residues to meet long term public health concerns are detailed and discussed in relation to the communication strategies to show and explain the actions of COGEMA. A brief review of the current remediation situation at the various French facilities is finally presented. (author)

  5. To question of NPP power reactor choice for Kazakhstan

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Makhanov, Y.M.; Reznikova, R.A.; Sidorenco, A.V.

    2004-01-01

    Full text: The requirements to NPP power reactors that will be under construction in Kazakhstan are proved and given in the report. A comparative analysis of the most advanced projects of power reactors with light and heavy water under pressure of large, medium and low power is carried out. Different reactors have been considered as follows: 1. Reactors with high-power (700 MW(el) and up) such as EPR, French - German reactor; CANDU-9, Canadian heavy-water reactor; System 80+, developed by ABB Combustion Engineering company, USA; KNGR, Korean reactor of the next generation; APWR, Japanese advanced reactor; WWER-1000 (V-392) - development of Atomenergoproect /Gydropress, Russian Federation; EP 1000, European passive reactor. 2. Reactors with medium power (300 MW (el) - 700 MW (el): AP-600, passive PWR of the Westinghouse company; CANDU-6, Canadian heavy-water reactor; AC-600, Chinese passive PWR; WWER-640, Russian passive reactor; MS-600 Japanese reactor of Mitsubishi Company; KSNP-600, South Korean reactor. 3. Reactors with low power (a few MW(el)- 300 MW(el)): IRIS, reactor of IV generation, developed by the International Corporation of 13 organizations from 7 countries, SMART, South Korean integrated reactor; CAREM, Argentina integrated reactor; MRX, Japanese integrated reactor; 'UNITERM', Russian NPP with integrated reactor, development of NIKIET; AHEC-80, Russian NPP, developed by OKBM. A comparison of the projects of the above-mentioned power reactors was carried out with respect to 15 criteria of nuclear, radiating, ecological safety and economic competitiveness, developed especially for this case. Data on a condition and prospects of power production and power consumption, stations and networks in Kazakhstan necessary for the choice of projects of NPP reactors for Kazakhstan are given. According to the data a balance of power production and power consumption as a whole in the country was received at the level of 59 milliard kw/h. However, strong dis balance

  6. To question of NPP power reactor choice for Kazakhstan

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Makhanov, Y.M.; Reznikova, R.A.; Sidorenco, A.V.

    2004-01-01

    The requirements to NPP power reactors that will be under construction in Kazakhstan are proved and given in the report. A comparative analysis of the most advanced projects of power reactors with light and heavy water under pressure of large, medium and low power is carried out. Different reactors have been considered as follows: 1. Reactors with high-power (700 MW(el) and up) such as EPR, French - German reactor; CANDU-9, Canadian heavy-water reactor; System 80+, developed by ABB Combustion Engineering company, USA; KNGR, Korean reactor of the next generation; APWR, Japanese advanced reactor; WWER-1000 (V-392) - development of Atomenergoproect /Gydropress, Russian Federation; EP 1000, European passive reactor. 2. Reactors with medium power (300 MW (el) - 700 MW (el): AP-600, passive PWR of the Westinghouse company; CANDU-6, Canadian heavy-water reactor; AC-600, Chinese passive PWR; WWER-640, Russian passive reactor; MS-600 Japanese reactor of Mitsubishi Company; KSNP-600, South Korean reactor. 3. Reactors with low power (a few MW(el)- 300 MW(el)): IRIS, reactor of IV generation, developed by the International Corporation of 13 organizations from 7 countries, SMART, South Korean integrated reactor; CAREM, Argentina integrated reactor; MRX, Japanese integrated reactor; 'UNITERM', Russian NPP with integrated reactor, development of NIKIET; AHEC-80, Russian NPP, developed by OKBM. A comparison of the projects of the above-mentioned power reactors was carried out with respect to 15 criteria of nuclear, radiating, ecological safety and economic competitiveness, developed especially for this case. Data on a condition and prospects of power production and power consumption, stations and networks in Kazakhstan necessary for the choice of projects of NPP reactors for Kazakhstan are given. According to the data a balance of power production and power consumption as a whole in the country was received at the level of 59 milliard kw/h. However, strong dis balance in the

  7. French participation in the world energy council; Presence francaise au conseil mondial de l`energie

    Energy Technology Data Exchange (ETDEWEB)

    Carouge, Ch. [Secretariat General du Conseil francais de l`Energie (France); Roussely, F.; Francony, M. [Electricite de France (EDF), 75 - Paris (France); Ailleret, F. [Conseil francais de l`Energie (France); Bosseboeuf, D.; Moisan, F. [ADEME, Agence de l`Environnement et de la Maitrise de l`Energie, 75 - Paris (France); Villaron, Th. [Conseil Mondial de l`Energie (France)

    1999-02-01

    The Revue de l`Energie is presenting the most influential French interventions at the 17. Congress of the World Energy Council held in September 1998 in Houston, (USA). These represent only part of French participation in the congress since a total of 16 individuals from France took part in the various sessions. Their presentations cover very varied topics and are one of the things that testify to the interest that our energy industries have in the works and operations of the WEC. Some other figures also bear witness to this interest: 184 French congress members, which is one of the largest delegations after that of the United States, the host country of the congress; 11 technical presentation, covering a wide range of subjects: from the nuclear reactor of the future to the use of bagasse (cane trash) for the production of electricity, from the underground storage of natural gas to the production of extra-heavy crude petroleum. The technical exhibition associated to the Congress was a great success and there again the French presence was able to make its mark: five exhibitors were gathered in the France of 600 m{sup 2}, the most sizeable non-American national area.But French participation in the work of the WEC is not limited to congresses. The French Energy Council [Conseil francais de l`Energie] is careful to ensure its presence both in the formal proceedings of the WEC and within the studies undertaken under its three-year programme. This active French presence is also essential in order to defend the official English-French bilingualism of the World Energy Council. In spite of the good will of the organizers and the support of the general secretary`s office in London, the Houston Congress showed how difficult it was to maintain the use of the French language on English-speaking territory. This is a difficult task, one that has to be undertaken anew each time, but one that France and other French-speaking nations have decided to pursue to the end. (authors)

  8. Department of reactor technology

    International Nuclear Information System (INIS)

    1980-01-01

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  9. Survey of research reactors

    International Nuclear Information System (INIS)

    Boek, H.; Villa, M.

    2004-06-01

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  10. FBR type reactor

    International Nuclear Information System (INIS)

    Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

    1994-01-01

    In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

  11. Monitoring and aid to diagnosis of French PWRs

    International Nuclear Information System (INIS)

    Jousellin, A.; Trenty, A.; Benas, J.C.; Renault, Y.; Busquet, J.L.; Mouhamed, B.

    1996-01-01

    In order to improvise safety and availability in its nuclear power plants, EDF has designed a new generation of monitoring systems integrated into a workstation for monitoring and aid to diagnosis (PSAD). These systems perform on-line monitoring of the main power plant components and PSAD stations provide homogeneous aid to diagnosis which enable plant personnel to pinpoint the mechanical behavior of plant equipments. The objective of PSAD is to provide them with high-efficiency and user-friendly tools which can considerably free them from routine tasks. The first version of the prototype is working on a French plant at Tricastin. This version includes the software host structure and two monitoring functions: the reactor coolant pumps and the turbo-generator monitoring functions. Internal Structures Monitoring (ISM) and Loose Parts Detection function (LPD) are under development and should be integrated into PSAD prototype in 1996. (authors)

  12. Vertebral Malformations in French Bulldogs

    Directory of Open Access Journals (Sweden)

    Mária KURICOVÁ

    2017-07-01

    Full Text Available The aim of this study was to detect vertebral malformations among French Bulldogs admitted between the years 2011 – 2016 due to the high popularity of the breed and the intentions to increase the breed welfare by reducing the occurrence of congenital anomalies. Besides, we aimed to look for gender predisposition, possible vertebral predisposition, occurrence of clinical symptoms and radiographic findings. A total of 73 French Bulldogs met the inclusion criteria (radiographs of the whole spine. In 67.12% (49 dogs we confirmed a vertebral anomaly and 32.88% (24 dogs were free of any vertebral anomaly. We identified a total of 67 abnormal vertebrae in 49 dogs, 13 cervical vertebrae (19.4%, 43 thoracic vertebrae (64.2%, and 11 abnormal lumbar vertebrae (16.4%. In this study, we found 44 hemivertebrae (65.7% out of 67 abnormal vertebrae. We identified 64.4% (47/73 dogs with clinical signs (30 males, 17 females and 36.6% (26/73 dogs without clinical signs (19 males, 7 females. Although the incidence of male dogs was higher in this study, the statistical evaluation did not confirm any predisposed gender, and we found no statistically significant predisposition for any particular abnormal vertebra.

  13. [Pathology seen in French "Hikikomori"].

    Science.gov (United States)

    Furuhashi, Tadaaki; Figueiredo, Cristina; Pionnié-Dax, Nancy; Fansten, Maïa; Vellut, Natacha; Castel, Pierre-Henri

    2012-01-01

    Young people who meet the definition of "Hikikomori" have come to be seen in France since around 2008. However, simply "fitting the definition" does not necessarily mean that they are the same as "Hikikomori" in Japan. Rather, it is important to ask what kind of young people "fit the definition of Hikikomori in France" and what kind of pathology they have. With these questions, our Japanese-French joint research team comprising specialists in various fields conducted a survey of "Hikikomori" in French youth, with support from a Grant-in-Aid for Scientific Research B (overseas research), and started a comparative joint study on "Hikikomori" in Japan and "Hikikomori" in France. In that study it was found that whereas one aspect of "Hikikomori" in Japan is described by the word déraillement (coming off the "rails"), "Hikikomori" in France is a state closer to dropping out and is accompanied by a type of "sense of insufficiency". This "sense of insufficiency" is above all related to something in the society and culture of France, and an investigation of how it is linked to "Hikikomori" is an issue for the future.

  14. Fessenheim simulator for OECD Halden Reactor Project

    International Nuclear Information System (INIS)

    Oudot, G.; Bonnissent, B.

    1998-01-01

    A full scope NPP simulator is presently under manufacture by THOMSON TRAINING and SIMULATION (TTandS) in Cergy (France) for the OECD HALDEN REACTOR PROJECT. The reference plant of this simulator is the Fessenheim CP0 PWR power plant operated by the French utility EDF, for which TTandS has delivered a full scope training simulator in mid 1997. The simulator for HALDEN Reactor Project is based on a software duplication of the Fessenheim simulator delivered to EDF, ported on the most recent computers and O.S. available. This paper outlines the main features of this new simulator generation which reaps benefit of the advanced technologies of the SIPA design simulator introduced inside a full scope simulator. This kind of simulator is in fact the synthesis between training and design simulators and offers therefore added technical capabilities well suited to HALDEN needs. (author)

  15. Fast breeder reactors

    International Nuclear Information System (INIS)

    Heinzel, V.

    1975-01-01

    The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

  16. Determining Reactor Neutrino Flux

    OpenAIRE

    Cao, Jun

    2011-01-01

    Flux is an important source of uncertainties for a reactor neutrino experiment. It is determined from thermal power measurements, reactor core simulation, and knowledge of neutrino spectra of fuel isotopes. Past reactor neutrino experiments have determined the flux to (2-3)% precision. Precision measurements of mixing angle $\\theta_{13}$ by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understa...

  17. Nuclear reactor coolant channels

    International Nuclear Information System (INIS)

    Macbeth, R.V.

    1978-01-01

    A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  19. Reactor container

    International Nuclear Information System (INIS)

    Kagawa, Tatsuo; Yanai, Ryoichi.

    1976-01-01

    Object: To provide a reactor container which is free from water shock action or condensing vibrations and cannot be readily broken by a missile from a pump impeller, pipe whipping, steam jet reaction, etc., and which also quickly condenses issuing steam and possesses a large vibration-proof strength. Structure: A high pressure containment vessel accommodating a pressure container includes a plurality of pressurized water tanks arranged along its inner periphery, and a pneumatic valve is provided in a lower portion of each of these pressurized water tanks. If an accident occurs, vapor is caused to issue from the pressure container into the vessel. When a certain value is reached, the pneumatic valves are opened, whereby the gas within the pressurized water tanks causes pressurized water to flow through the pipe and be ejected from spray nozzles to cause condensation of water within the vessel. Further, water of a pool within the container is circulated to allow heat release to the outside. (Horiuchi, T.)

  20. Pellet-Cladding Mechanical Interaction Failure Threshold for Reactivity Initiated Accidents for Pressurized Water Reactors and Boiling Water Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, Carl E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Geelhood, Kenneth J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-06-01

    Pacific Northwest National Laboratory (PNNL) has been requested by the U.S. Nuclear Regulatory Commission to evaluate the reactivity initiated accident (RIA) tests that have recently been performed in the Nuclear Safety Research Reactor (NSRR) and CABRI (French research reactor) on uranium dioxide (UO2) and mixed uranium and plutonium dioxide (MOX) fuels, and to propose pellet-cladding mechanical interaction (PCMI) failure thresholds for RIA events. This report discusses how PNNL developed PCMI failure thresholds for RIA based on least squares (LSQ) regression fits to the RIA test data from cold-worked stress relief annealed (CWSRA) and recrystallized annealed (RXA) cladding alloys under pressurized water reactor (PWR) hot zero power (HZP) conditions and boiling water reactor (BWR) cold zero power (CZP) conditions.

  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. French for Specific Purposes: The Hawaiian Experience.

    Science.gov (United States)

    Benouis, Mustapha

    1986-01-01

    Describes the development of and the reaction to a course in Business French at the University of Hawaii. Its success, coupled with its recognition by state and academic officials, brought about the initiation of similar courses in other languages and the development of French for travel industry management majors. (SED)

  3. French Romanticism and Napoleon's "Geometric Men."

    Science.gov (United States)

    Cole, Robert A.

    1982-01-01

    French intellectual thought changed during the Napoleonic Era. The effects of the Enlightenment philosophers, the French Revolution, the Industrial Revolution, and Romanticism on the development of Napoleon's philosophical outlook are used to illustrate the changes occurring in France as a whole in the early nineteenth century. (AM)

  4. Reading Speed of Contracted French Braille

    Science.gov (United States)

    Laroche, Louise; Boule, Jacinthe; Wittich, Walter

    2012-01-01

    This study was designed to address three hypotheses: (1) The reading speed of both readers of French braille and readers of French print will be faster in the silent condition; however, this gain in speed will be larger for print readers; (2) Individuals who acquired braille before age 10 will display faster reading speeds at lower error rates…

  5. The French Language in the Americas.

    Science.gov (United States)

    Valdman, Albert, Ed.

    The annual bulletin of the French 8 section of the Annual Meeting of the Modern Language Association of America is presented with the texts of papers read at both the 1969 and 1970 sessions. The 1970 papers, in French, include Jean Louis Darbelnet's "Etude Sociolinguistique des contacts entre 1'Anglais et le Francais au Canada et en…

  6. A Mini-Film on French Kinesics.

    Science.gov (United States)

    Walz, Joel

    This paper describes a silent film made by the author which illustrates various French gestures. The format is Super 8, and the film lasts five minutes. The script is given, along with an English translation. The story concerns several French students at an outdoor cafe wondering about one of their friends. The conversation includes 10 typical…

  7. Gabonese French Dictionaries: Survey and Perspectives*

    African Journals Online (AJOL)

    Gabonese French Dictionaries: Survey and Perspectives*. Paul Achille Mavoungou, Département des Sciences du Langage,. Université Omar Bongo, Libreville, Gabon. (moudika2@yahoo.fr). Abstract: This article is a survey study of lexicographic activities with regards to the French lan- guage as it is spoken in Gabon, ...

  8. Introduction Robin Melrose The French philosopher Jacques ...

    African Journals Online (AJOL)

    Robin Melrose. The French philosopher Jacques Derrida has exercised an enourmous influence on French thought over the last twenty years, particularly with his technique of deconstruction, and more recently the influence has spread to English-speaking countries, in fields as diverse as literary theory, the study of popular ...

  9. TEACHING AND LEARNING OF FRENCH: IMPERATIVE FOR ...

    African Journals Online (AJOL)

    Prof

    Abstract. This paper seeks to reflect on the importance of French Language. Teaching and Learning as a veritable tool for educational opportunities, transformation and national development. Undoubtedly, Nigeria's position in the world geography makes French language acquisition imperative for her population. It is no ...

  10. Introduction Robin Melrose The French philosopher Jacques ...

    African Journals Online (AJOL)

    The French philosopher Jacques Derrida has exercised an enourmous influence on French thought over the last twenty years, particularly with his technique of deconstruction, and more recently the influence has spread to English-speaking countries, in fields as diverse as literary theory, the study of popular culture, feminist ...

  11. French petroleum demand stable since thirteen years

    International Nuclear Information System (INIS)

    Chauvot, M.

    2005-01-01

    The French union of petroleum industries (Ufip) has presented a globally satisfactory status of the French petroleum situation. However, the refining capacities are not always well adapted to the evolution of the demand and the production of diesel fuels remains insufficient while France exports gasoline. Short paper. (J.S.)

  12. Radical Reform of the French University System

    Science.gov (United States)

    Bereziat, Gilbert

    2008-01-01

    The French university system is in crisis. After its dismantlement during the French revolution, its rebirth was progressive under the third republic (1871-1945). But it was only after 1968 that the current universities developed, with an autonomy that is strictly supervised by the state. Since 1986 all experiments at modernizing the management of…

  13. Instrumentation for nuclear reactor control and protection in France

    International Nuclear Information System (INIS)

    Weill, J.; Remus, L.

    1983-10-01

    The instrumentation for nuclear reactor control and protection is completely made by the French industry. The research and development works are often realized by CEA in the frame of cooperation with EdF (Electricite de France), and societies such as FRAMATOME and NOVATOME and the manufacturers of electronic equipments. In this paper, the main components used in the nuclear instrumentation are described: radiation detectors and electronic equipments for signal processing. There, the control and protection systems manufactured by MERLIN-GERIN for the 900 MWe and 1300 MWe nuclear reactors are described [fr

  14. Development of Gender Typicality and Felt Pressure in European French and North African French Adolescents.

    Science.gov (United States)

    Hoffman, Adam J; Dumas, Florence; Loose, Florence; Smeding, Annique; Kurtz-Costes, Beth; Régner, Isabelle

    2017-11-14

    Trajectories of gender identity were examined from Grade 6 (M age  = 11.9 years) to Grade 9 in European French (n = 570) and North African French (n = 534) adolescents, and gender and ethnic group differences were assessed in these trajectories. In Grade 6, boys of both ethnic groups reported higher levels of gender typicality and felt pressure for gender conformity than girls. European French girls and boys and North African French girls reported decreasing gender typicality from Grade 6 to Grade 9, whereas North African French boys did not change. Felt pressure decreased among girls, did not change in European French boys, and increased in North African French boys. Ethnic and gender differences in gender identity development are discussed. © 2017 The Authors. Child Development © 2017 Society for Research in Child Development, Inc.

  15. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

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

  16. Crispy in the french breakfast

    Directory of Open Access Journals (Sweden)

    Alain Drouard

    2003-09-01

    Full Text Available Bien qu’il y ait eu du croquant et du croustillant dans l’alimentation des Français avant l’époque contemporaine (pain, gâteaux, fruits frais ou secs sa place a augmenté récemment à la suite des changements intervenus dans le petit déjeuner. Le but de cet article est d’analyser historiquement la pénétration et la diffusion du croquant et du croustillant dans le petit déjeuner français. Celle ci s’est faite d’abord dans les villes sous l’influence de modèles étrangers et principalement Anglo-Saxons qui font une place importante au croustillant. Les partisans des nouveaux petits déjeuners à base de lait, de céréales et de fruits ne cherchaient pas seulement à promouvoir le végétarisme mais aussi à lutter contre la « dégénérescence » qui menaçait à leurs yeux la société moderne. Après avoir rappelé la naissance du petit déjeuner français, on étudiera le rôle des modèles étrangers dans l’évolution de la consommation d’aliments croustillants.Though crispy items were present in French food before the contemporary period (what with bread, cakes, fresh or dried fruits, they have recently played a more important part as breakfast underwent a series of changes. The aim of this article is to make an historical analysis of the emergence and spread of crispy food in the French breakfast. The influence of foreign and more especially Anglo-Saxon models contributed to increasing its importance. Those who advocated these new breakfasts at the beginning of the XXth century were convinced to fight also against “degeneracy” which they thought was a threat to modern society. I shall first briefly explain how the French breakfast was born, then I shall focus on the influence and impact of foreign models.

  17. Multimedia Course on Nuclear Reactors Physics, Application to a Tailored On the Job Training Course

    International Nuclear Information System (INIS)

    Dies, Javier

    2014-01-01

    In order to improve education and training quality, a Multimedia on Nuclear Reactor Physics has been developed. In some institutions, this course is called Fundamentals of Nuclear Reactor Operation. Nowadays, this multimedia has about 800 slides and the text is in Spanish, English, French and Russian. Until now about 126 institutions from 53 countries have applied for the multimedia. The teacher uses the multimedia during his lectures. Students use it at home to study this course

  18. The fast breeder reactor

    International Nuclear Information System (INIS)

    Collier, J.

    1990-01-01

    The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

  19. Disputing Rossellini: Three French perspectives

    Directory of Open Access Journals (Sweden)

    James Harvey-Davitt

    2014-12-01

    Full Text Available In his burgeoning body of film theoretical work the French philosopher Jacques Rancière repeatedly turns to some canonical films by Neorealist pioneer Roberto Rossellini. Not simply retreading tired motifs of Neorealism, Rancière’s comments offer some profound new insights, revolutionising prior perspectives on Rossellini. In this article I shall put Rancière’s perspective into dialogue with two of the most significant of these perspectives: André Bazin’s and Gilles Deleuze’s. In doing so I shall claim that Rancière’s approach departs radically from the canonised, standardised Neorealist conception of Rossellini. Instead, I wish to claim that he describes a modernist artist primarily concerned with aesthetic clashes. In doing so I shall contemplate how the meaning of these films has evolved since the era of their contemporary reception, demonstrating the congruence and disparity between these three disparate approaches.

  20. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

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

  1. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

    The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

  2. Impact of French advertising campaign

    International Nuclear Information System (INIS)

    Chaussade, Jean-Pierre; Ansel, Philippe

    1993-01-01

    'Today, some 75 % of France's electricity is generated by nuclear plants'. This was the theme of the advertising campaign launched for the second time in May 1992 by Electricite de France in national daily newspapers and magazines, in regional publications, on cinema and on TV. Compared to 1991 the second campaign was a new step in communication: first, was the wish to inform better the public. A Minitel program '3614 EDF' was created and connected by general public including a lot of information about nuclear energy and the way to visit a nuclear plant; secondly, was the use of TV media to target a larger population. The TV spot, 'the nuclear drill', uses humor to get more impact on the public. The campaign received an encouraging reception from the press, which admired its boldness and originality. As far as the general public is concerned, the campaign achieved its goals, as illustrated by the results of post-campaign surveys carried out to measure its effect. The segment of population targeted by campaign was mainly the so called 'pragmatics'. 'Pragmatics', who account for 25 % of the French population, are young, have a good education and are well informed. This category was selected as it shows a subtle attitude towards nuclear power, with more doubts than certainties. Moreover, this segment of the population has proven to be open to information issued by EDF and also plays a key role in influencing social trends. 63% of the segment targeted by the campaign (pragmatics) and 56% of the whole french population saw the ads

  3. CROSS-LINGUISTIC INTERFERENCE OF FRENCH TO ENGLISH IN INDONESIAN STUDENTS OF FRENCH DEPARTMENT OF UNNES

    Directory of Open Access Journals (Sweden)

    Ahmad Yulianto

    2017-04-01

    Full Text Available Despite the fact that English is the first foreign language learnt by French Department‘ students of UNNES, this language doesn‘t seem to enjoy the place it is supposed to have. Students of French Department of UNNES have mostly learned both English and French since they were in high school. However, it doesn‘t mean that they understand English as well as they understand French. Regardless lexical and grammatical similarity between these two languages, mastering English is quite problematic to most students. This paper is adopted from the study attempting to investigate how currenty-learned foreign language (French influences, or not to say overrides, previously-learned one (English. Two groups of 28 students were analyzed in terms of their English lexical, grammatical abilities and pronunciation. The results indicate that French (L3 has a great influence on English (L2 of learners who have had more exposure to French (L3. The results also suggest that French exposure (L3 seems to have influenced learners‘ ability to use their knowledge of L3 in order to overcome lexical difficulties in L2. It is disadvantageous to some degree since English and French share numerous lexically similar words which are totally different in use. In addition, it was also found that most students fail to pronounce English words correctly especially when these words also exist in French.

  4. The French nuclear team ready to conquer new market shares

    International Nuclear Information System (INIS)

    Levy, J.B.; Varin, P.; Verwaerde, D.

    2016-01-01

    In order to reinforce their partnership, EDF, CEA and AREVA have founded the France Nuclear Platform (FNP). FNP is a tripartite body that will allow EDF, CEA and AREVA to build a consistent common position to respond to the worldwide demand in terms of nuclear reactors, fuel cycle or spent fuel processing. Potential clients and particularly first-time buyers want to buy far more than nuclear reactors, they want to buy the whole experience of the most important nuclear operator in the world which is a guarantee of success, safety and security. In order to stay ahead of the competition, the French nuclear industry can rely on high quality standards, a policy of innovation and a well-developed safety culture. Today's promising markets for nuclear energy are concentrated in Asia: in China a growth rate of 60% over the next 15 years is expected for nuclear power, in India projects for the construction of several EPR are ongoing. (A.C.)

  5. French Society Abroad: The Popularization of French Dance throughout Europe, 1600-1750

    Directory of Open Access Journals (Sweden)

    Adam Paul Rinehart

    2017-09-01

    Full Text Available This paper explores the dissemination of French dance, dance notation, and dance music throughout Europe, and it explains the reasons why French culture had such an influence on other European societies from 1600-1750. First, the paper seeks to prove that King Louis XIV played a significant role in the outpour of French dance and the arts. Next, the paper discusses prominent French writers of dance notation who influenced the spread of French dance literature and training throughout Europe. Finally, the paper delineates European composers and their involvement in the development and production of French dance music. Using academic, peer-reviewed journal articles, books, and other scholarly sources, this paper seeks to accurately present the information in an orderly fashion. The paper contains visual evidence of dance and music notation to assist the reader in understanding the subject matter. Additionally, theories of contemporary authors as well as authors from the time period are discussed to present concrete evidence. The two main types of dance discussed in the paper are ballroom and court dances, which were prominent within the French royal court. One major finding of the research is the fact that French court and ballroom dances were specifically designed to communicate the power and prestige of King Louis XIV; consequently, other European countries were influenced to strive for similar prestige. Another finding is that many forms of French dance notation were translated and published in other countries, which increased the use of French dance throughout Europe. Musically, European composers such as Handel and Mozart included elements of French dance music in their compositions, and thus played a significant role in prevalence of French dance music throughout Europe. Overall, this paper proves that French dance received wide recognition due to political influence, availability of dance notation, and the involvement of prominent composers.

  6. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

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

  7. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

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

  8. Postcolonial Freud: psychoanalysis in the French Antilles.

    Science.gov (United States)

    Simek, Nicole

    2011-01-01

    While Martinique and Guadeloupe were assimilated into the French state in 1946, traces of colonial power relations and economic structures persist despite the islands' current status as French 'départements' equal to any other. This article examines the contributions of Freud's thought to the shift in critical perspective that has allowed the continued "colonial" status of these islands, and the cultural alienation of its people, to be identified as a problem or phenomenon requiring analysis and rectification. Speaking of "postcolonial Freud" in this context is tantamount to asking: which postcolony for the French Antillean future, and which Freud for the thought emerging from this space?

  9. The cost of French military nuclear programs

    International Nuclear Information System (INIS)

    Barrillot, B.

    1999-02-01

    The author tries to find out the real cost of French nuclear weaponry. According to this study the total cost of the French military nuclear programs for 1960-1998 period is about 1499 milliard francs (MdF). This cost can be distributed as follows: i) fabrication of the bomb: 690 MdF; ii) display of the bomb: 727 MdF; iii) control of the bomb: 50 Mdf; iv) protection against nuclear attacks: 9 MdF; and v) dismantling of the bomb: 23 MdF. It goes without saying that these figures exceed by far those given by French authorities. (A.C.)

  10. Colloquial French the complete course for beginners

    CERN Document Server

    Demouy, Valérie

    2014-01-01

     COLLOQUIAL FRENCH is easy to use and completely up to date!Specially written by experienced teachers for self-study or class use, the course offers a step-by-step approach to written and spoken French. No prior knowledge of the language is required.What makes COLLOQUIAL FRENCH your best choice in personal language learning?Interactive - lots of exercises for regular practiceClear - concise grammar notesPractical - useful vocabulary and pronunciation guideComplete - including answer key and reference sectionWhether you''re a business traveller, or about to take up a daring challenge in adventu

  11. A French Imperial Meridian, 1814–1870

    OpenAIRE

    Todd, David

    2011-01-01

    The period stretching from the restoration of Louis XVIII in 1814 until the fall of Napoleon III in 1870 remains the terra incognita of the history of French global ambitions. Even the volume of L’Aventure coloniale de la France, covering the years 1789–1870, stresses that the French ‘cautiously withdrew into themselves’ after the collapse of the first Napoleonic Empire.1 Such a view, this article argues, relies on an extraordinary neglect for the resilience of French formal and, above all, i...

  12. Research reactor instrumentation

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2001-02-01

    This is a textbook on research reactor instrumentation for training purposes, it gives a survey on research reactor instrumentation requirements and eight exercises covering the major aspects of this topic are presented. (author)

  13. Nuclear reactors; graphical symbols

    International Nuclear Information System (INIS)

    1987-11-01

    This standard contains graphical symbols that reveal the type of nuclear reactor and is used to design graphical and technical presentations. Distinguishing features for nuclear reactors are laid down in graphical symbols. (orig.) [de

  14. Hybrid plasmachemical reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lelevkin, V. M., E-mail: lelevkin44@mail.ru; Smirnova, Yu. G.; Tokarev, A. V. [Kyrgyz-Russian Slavic University (Kyrgyzstan)

    2015-04-15

    A hybrid plasmachemical reactor on the basis of a dielectric barrier discharge in a transformer is developed. The characteristics of the reactor as functions of the dielectric barrier discharge parameters are determined.

  15. Fusion reactor design studies

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Santarius, J.F.

    1990-01-01

    This report discusses the following topics on the ARIES tokamak: systems; plasma power balance; impurity control and fusion ash removal; fusion product ripple loss; energy conversion; reactor fueling; first wall design; shield design; reactor safety; and fuel cost and resources

  16. Reactor shutdown method

    International Nuclear Information System (INIS)

    Nishino, Yoshitaka; Sawa, Toshio; Matsumoto, Takayuki; Osumi, Katsumi; Usui, Naoshi.

    1991-01-01

    A device for injecting a hydrogen gas, a chelating agent or a reducing agent is disposed in a reactor water recycling system. Upon reactor shutdown, the hydrogen gas, the chelating agent or the reducing agent is injected to primary coolants. With such a procedure, radioactive ions formed by the dissolution of oxide layers at the surface of pipelines and equipments in a reactor water recycling system and a reactor water cleanup system are removed from the primary coolants by a reactor water cleanup device. Accordingly, since the dose rate at the surface of the pipelines can be reduced, the operator's radiation dose can be reduced upon periodical inspection for a power plant. Further, the inner pressure of the reactor is kept higher than the saturated steam pressure at the reactor water temperature to suppress boiling of the reactor water. This can suppress the peeling of cruds deposited to the surface of the fuel cladding tube. (I.N.)

  17. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    Edwards, R.M.; Power, M.A.; Bryan, M.

    1992-01-01

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

  18. Reactor System Design

    International Nuclear Information System (INIS)

    Chi, S. K.; Kim, G. K.; Yeo, J. W.

    2006-08-01

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

  19. Alice Primi, Femmes de progrès. Française et Allemandes engagées dans leur siècle 1848-1870, Rennes, PUR, Archives du féminisme, 2010, 317 p., Préface de Michèle Riot-Sarcey.

    Directory of Open Access Journals (Sweden)

    Paul Pasteur

    2011-10-01

    Full Text Available Dans cet ouvrage qui reprend la thèse qu’elle a soutenue en 2006, Alice Primi retrace le parcours de femmes qui, de chaque côté du Rhin, ont tenté des années 1848 à 1870, de faire entendre leur voix et de peser sur les changements sociaux. On regrette que l’expression de Jenny P. d’Héricourt « filles de [leur] siècle » bien plus proche du titre de la thèse n’ait pas été conservée dans le titre de l’ouvrage et ait été remplacée par « femmes de progrès », bien vague, bien trop polysémique et tr...

  20. Complementary safety assessments - Report by the French Nuclear Safety Authority

    International Nuclear Information System (INIS)

    2011-12-01

    As an immediate consequence of the Fukushima accident, the French Authority of Nuclear Safety (ASN) launched a campaign of on-site inspections and asked operators (mainly EDF, AREVA and CEA) to make complementary assessments of the safety of the nuclear facilities they manage. The approach defined by ASN for the complementary safety assessments (CSA) is to study the behaviour of nuclear facilities in severe accidents situations caused by an off-site natural hazard according to accident scenarios exceeding the current baseline safety requirements. This approach can be broken into 2 phases: first conformity to current design and secondly an approach to the beyond design-basis scenarios built around the principle of defence in depth. 38 inspections were performed on issues linked to the causes of the Fukushima crisis. It appears that some sites have to reinforce the robustness of the heat sink. The CSA confirmed that the processes put into place at EDF to detect non-conformities were satisfactory. The complementary safety assessments demonstrated that the current seismic margins on the EDF nuclear reactors are satisfactory. With regard to flooding, the complementary safety assessments show that the complete reassessment carried out following the flooding of the Le Blayais nuclear power plant in 1999 offers the installations a high level of protection against the risk of flooding. Concerning the loss of electrical power supplies and the loss of cooling systems, the analysis of EDF's CSA reports showed that certain heat sink and electrical power supply loss scenarios can, if nothing is done, lead to core melt in just a few hours in the most unfavourable circumstances. As for nuclear facilities that are not power or experimental reactors, some difficulties have appeared to implement the CSA approach that was initially devised for reactors. Generally speaking, ASN considers that the safety of nuclear facilities must be made more robust to improbable risks which are not

  1. Reports by the Parliamentary Office for scientific and technological assessments. Tuesday, May 24, 2011. Hearing on the protection of a reactor core and critical circuit

    International Nuclear Information System (INIS)

    2011-05-01

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

  2. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  3. PUSPATI TRIGA Reactor

    International Nuclear Information System (INIS)

    Masood, Z.

    2016-01-01

    The PUSPATI TRIGA Reactor is the only research reactor in Malaysia. This 1 MW TRIGA Mk II reactor first reached criticality on 28 June 1982 and is located at the Malaysian Nuclear Agency premise in Bangi, Malaysia. This reactor has been mainly utilised for research, training and education and isotope production. Over the years several systems have been refurbished or modernised to overcome ageing and obsolescence problems. Major achievements and milestones will also be elaborated in this paper. (author)

  4. Mechanical surveillance of French PWR's

    International Nuclear Information System (INIS)

    Puyal, C.; Brillon, A.; Aupied, J.; Bernard, P.; Carre, J.C.; Epstein, A.

    1981-08-01

    It is expected that, by the end of 1986, almost forty 900 MWe nuclear power plants would be operating in France. In order to increase their availability, a surveillance has been set from the startup of the first unit Fessenheim 1. Mechanical surveillance is only considered here, that is, the surveillance of internal structures vibrations, and the detection of loose parts. The surveillance of vibrations aims to detect an anomaly in internals vibratory behaviour. For that, signals are used from accelerometers located on the pressure vessel and from ex core ion chambers. Signatures of these signals (Power Spectral Densities) are obtained periodically on site and automatically compared with the initial reference signature. Their interpretation is based on theoretical and experimental studies. Early detection of loose parts also is important to maintain the integrity of internal structures. We use the impulses obtained by accelerometers located on the primary circuit, due to shocks of metallic parts and surface wave propagation. Tests have been performed on site to determine the system sensitivity: the detection of a loose part inside a steam generator hot box during the preoperational test and the malfunction of a valve. Now, the progressive commissioning of new 900 and 1300 MWe nuclear power plants has lead us to automatize on site anomaly detection, in order to reduce the operator's work. Other developments are being carried out, such as the realization of specific devices, the development of a data bank, including data from each reactor, from each family of identical reactors and data related to particular incidents

  5. The French CAT: An Assessment of Its Empirical Validity.

    Science.gov (United States)

    Burston, Jack

    1995-01-01

    Investigates the empirical validity of the Monash-Melbourne computer adaptive test for French (French CAT). The article focuses on the accuracy of the French CAT as a tool for streaming incoming university students into three levels of a first-year (post-high school) French course. The test is demonstrated to be a good predictor of short-term…

  6. developing french for specific purposes in the nigerian university ...

    African Journals Online (AJOL)

    Ada

    Following the changing role of the French Language from a vehicle of French culture to a vehicle of Science, Technology, Commerce and Diplomacy, the teaching of French as a foreign language (FFL) around the world has shifted emphasis from literary studies to what has come to be known as French for Specific Purposes ...

  7. Developing French for specific purposes in the Nigerian University ...

    African Journals Online (AJOL)

    Following the changing role of the French Language from a vehicle of French culture to a vehicle of Science, Technology, Commerce and Diplomacy, the teaching of French as a foreign language (FFL) around the world has shifted emphasis from literary studies to what has come to be known as French for Specific Purposes ...

  8. Utilization Of French Graduates In Secondary Schools In Makurdi ...

    African Journals Online (AJOL)

    Much has been said about the need for French or the reason why French should be taught in Nigeria. French is a modern language that is spoken, written and used like all the other world's modern languages. Despite its importance, It is unfortunate that the wide use of French has often been overlooked by Nigerians hem ...

  9. Health Information in French (français)

    Science.gov (United States)

    ... Bugs - français (French) MP3 Minnesota Department of Agriculture Benefits of Exercise Starting an Exercise Program - français (French) ... français (French) PDF American Cancer Society Blood Sugar Fasting Blood Sugar Test - français (French) Bilingual PDF Health ...

  10. CARRYING OF FRENCH VISAS FOR HOLDERS OF CATEGORY 'EF' FRENCH ATTESTATIONS DE FONCTIONS

    CERN Multimedia

    Service des Relations avec les Pays Hôtes

    1999-01-01

    The French Ministry of Foreign Affairs has informed the Organisation that members of the personnel resident in Switzerland and holding Category 'EF' French Attestations de functions are not obliged to be in possession of French visas. When temporarily travelling through France on OFFICIAL CERN BUSINESS, provided they are carrying the valid Attestation and a valid national passport with them.Relations with the Host States Servicehttp://www.cern.ch/relations/Tel. 72848

  11. Reactor power measuring device

    International Nuclear Information System (INIS)

    Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

    1993-01-01

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  12. Ulysse, mentor reactor

    International Nuclear Information System (INIS)

    Bouquin, B.; Rio, I.; Safieh, J.

    1997-01-01

    On July 23, 1961, the ULYSSE reactor began its first power rise. Designed at that time to train nuclear engineering students and reactor operators, this reactor still remains an indispensable tool for nuclear teaching and a choice instrument for scientists. (author)

  13. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    1993-11-01

    The results of nuclear fusion researches in JAERI are summarized. In this report, following themes are collected: the concept of fusion reactor (including ITER), fusion reactor safety, plasma confinement, fusion reactor equipment, and so on. Includes glossary. (J.P.N.)

  14. Refuelling nuclear reactors

    International Nuclear Information System (INIS)

    Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

    1981-01-01

    An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

  15. The Jules Horowitz reactor

    International Nuclear Information System (INIS)

    2003-01-01

    The Jules Horowitz reactor is the future european reactor for irradiation. It will be used for materials and new fuels irradiation. Experiments for the safety and the validation of neutronics calculation will be also realized. This paper presents the design and the performance of the reactor and the schedule of the remaining design studies. (A.L.B.)

  16. Spain in quandry over French synchrotron

    CERN Multimedia

    Bosch, X

    2000-01-01

    The French government has invited Spain to participate in the funding and operation of its proposed synchrotron Soleil. This could result though in the end of Spanish scientists' hopes for their own machine (1 page).

  17. French bank mergers and acquisitions performance

    Directory of Open Access Journals (Sweden)

    Houda Ben Said

    2017-11-01

    Full Text Available In this paper, we empirically investigate the impact of mergers and acquisitions on French bank performance. Performance is measured by potential gains in efficiency and value creation. We first analyzed efficiency using the data envelopment analysis (DEA under input oriented with variable returns to scale to obtain the efficiency scores. Second, we analyzed the impact on French bank value creation following mergers-acquisitions operations of a set of control variables (model 1 and explicative variables measuring strategic similarities between bidders and targets (model 2. The sample studied is composed of French bank mergers-acquisitions happening between 1996 and 2006 and implying one of the 14 greatest French banking groups. Empirical result showed that mergers and acquisitions have been traduced by an improvement in the overall efficiency by 17.82% and a shareholder value reduction by 5.14%

  18. The French civilian nuclear: connections and stakes

    International Nuclear Information System (INIS)

    2010-01-01

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

  19. Opening of the French gas market

    International Nuclear Information System (INIS)

    Syrota, J.

    2002-01-01

    A report on the opening of the French gas market has been established, on the request of both the French minister of economy, finances and industry and the state secretary of industry, as expressed in their respective letters addressed to the president of the commission of electric power regulation (CRE). This report follows the step report on the opening of the French gas market published on January 15, 2002. It presents a status of the French gas market since August 2000, date of the enforcement of the European Union directive 98/30/CE, and expresses some recommendations about the main questions that should fall into the field of the future gas regulation. This report was elaborated before the project of law relative to the energy markets and published on October 24, 2002. These recommendations will have to be adapted to the dispositions of the law. This article presents some excerpts of the synthesis report. (J.S.)

  20. Colloquial French 2 the next step in language learning

    CERN Document Server

    Broady, Elspeth

    2014-01-01

    Do you know French already and want to go a stage further? If you''re planning a visit to France, need to brush up your French for work, or are simply doing a course, Colloquial French 2 is the ideal way to refresh your knowledge of the language and to extend your skills.Colloquial French 2 is designed to help those involved in self-study, and structured to give you the opportunity to listen to and read lots of modern, everyday French. It has been developed to work systematically on reinforcing and extending your grasp of French grammar and vocabulary.Key features of Colloquial French 2 includ

  1. Colloquial French 2 the next step in language learning

    CERN Document Server

    Broady, Elspeth

    2015-01-01

    Do you know French already and want to go a stage further? If you're planning a visit to France, need to brush up your French for work, or are simply doing a course, Colloquial French 2 is the ideal way to refresh your knowledge of the language and to extend your skills.Colloquial French 2 is designed to help those involved in self-study, and structured to give you the opportunity to listen to and read lots of modern, everyday French. It has been developed to work systematically on reinforcing and extending your grasp of French grammar and vocabulary.Key features of Colloquial French 2 include

  2. Unforgettable French Memory Tricks to Help You Learn and Remember French Grammar

    CERN Document Server

    Rice-Jones, Maria

    2010-01-01

    Unforgettable French uses memory tricks to teach and reinforce major points of rench grammar from the basics up to high school level, to learners of all ages. It may be used: by anyone who wishes to gain confidence in speaking French, as a evision aid, to consolidate the learner's grasp of grammatical points, to complement whatever French scheme you are using, and by French teachers at all levels, from elementary school through to adult. These tried-and-tested memory tricks help to explain "tri

  3. Cooperation between the French and German safety authorities: a process of progress

    International Nuclear Information System (INIS)

    Lacoste, A.C.; Hennenhoefer, G.

    1996-01-01

    Considerable efforts are devoted in several countries worldwide for the designing of a new generation of electro-nuclear reactors with noticeable safety improvements with respect to the existing units. The EPR (European Pressurized water Reactor) project is the first example of a joint survey and collaboration effort between two countries, France and Germany, both characterized by a strong nuclear industry and competence. Franco-German relations have considerably expanded in recent years, enabling the French and German electricians, manufacturers (EDF, Siemens, Framatome..), and safety authorities (DSIN, IPSN, BMU, GRS..) to adopt common positions and decisions on fundamental topics about technical aspects of safety. This kind of collaboration and alignment was obviously only possible because two conditions were fulfilled: the discussion concerned future reactors and not those already built for which safety rules and provisions are not easily modified; and a common industrial project existed and had consequently to comply with jointly defined safety objectives. These two conditions are still fulfilled, so it should be possible for the work between French and German safety authorities to continue successfully, even in the next more delicate stage, involving definition of common positions on more detailed technical provisions. Finally, it is unthinkable that this important work undertaken by France and Germany could be carried out without frequent consultation of the safety authorities of other nuclear countries, notably in Europe. (J.S.). 1 fig

  4. French feminism: national and international perspectives

    OpenAIRE

    Allwood, G; Wadia, K

    2002-01-01

    During the 1980s, the French media proclaimed the death of feminism, but although the 1970s women’s movement had demobilised, feminists were still active in issue-specific groups, in academia and within the institutions of the state. Paying careful attention to the difficulties associated with defining feminisms and national feminisms in particular, this article situates an analysis of French feminism since the 1980s in a context of growing international feminist dialogue and activism and a r...

  5. State intervention in the french film industry

    OpenAIRE

    Owe, Nikolai Østråt

    2001-01-01

    Recent events in the French media have shed light on the extensive protectionism that exists in the French Film Industry. An analysis is presented to attempt to explain the protectionist policies of the government. Three theoretical perspectives are presented. The first explains the protectionism based on neo-classical economics, and the theory of comparative advantage. France benefits from those comparative advantages such as the language and the culture, elements that cannot easily be ...

  6. Indoor air quality in French dwellings

    OpenAIRE

    Kirchner, Séverine; Derbez, Mickael; Duboudin, Cedric; Elias, Patrick; Gregoire, Anthony; Lucas, Jean-Paul; Pasquier, Nathalie; Ramalho, Olivier; Weiss, Nathalie

    2008-01-01

    International audience; Set up by the French authorities, the Observatory on Indoor Air Quality (OQAI) aims at collecting data on population exposure to indoor pollutants in various indoor environments. Accordingly, OQAI undertook a national survey in order to assess the air quality inside the French dwellings. A large amount of information has been collected from 567 dwellings (1,612 individuals questioned), representative of dwellings in France. This snapshot of indoor pollution focuses on ...

  7. French effort in field NDT nuclear plant

    International Nuclear Information System (INIS)

    Saglio, R.

    1983-12-01

    For the in-service inspection of nuclear generating stations, the French Atomic Commission has built up a program first to increase the defect detection probability, secondly to increase the reliability and recently to improve the characterization of defects. Focused Ultrasound and multiple frequency eddy current techniques, developped by French Atomic Energy Commission are well known. In this paper we will present the latest developments made in relation with defect characterization

  8. Diaphasic variation and change in French pronouns

    DEFF Research Database (Denmark)

    Hansen, Anita Berit

    2013-01-01

    The French pronominal paradigm demonstrates a colloquial variation between expressing the 1st person plural as on and as nous (On est 19 dans ma classe meaning the same as Nous sommes 19 dans ma classe). This use of definite on is stigmatized by some as working class and incorrect and seen...... to look into their other uses of on, in search of an explanation of the increasing popularity of this pronoun in French....

  9. French strategy for green finance. Executive summary

    International Nuclear Information System (INIS)

    Lemmet, Sylvie; Ducret, Pierre; Berthaud, Cecilia; Evain, Julie; Scolan, Maria

    2017-12-01

    The authors present their report on the French Strategy for Green Finance. Green finance has expanded rapidly since 2015 but much remains to be done to make capital flows consistent with the goals of the Paris Agreement. France can continue to play a pioneering role to promote the energy and ecological transition, and to support Paris's role as a financial centre. The task force is putting forward recommendations along four axes for a French strategy to foster green finance

  10. Activating teaching methods in french language teaching

    OpenAIRE

    Kulhánková, Anna

    2009-01-01

    The subject of this diploma thesis is activating teaching methods in french language teaching. This thesis outlines the issues acitvating teaching methods in the concept of other teaching methods. There is a definition of teaching method, classification of teaching methods and characteristics of each activating method. In the practical part of this work are given concrete forms of activating teaching methods appropriate for teaching of french language.

  11. New generation of French ISIM

    International Nuclear Information System (INIS)

    Besse, J.; Cattiaux, G.; Clicques, J.; Landez, J.P.; Birac, A.M.; Benoist, P.; Viard, J.

    1986-11-01

    Up to now, 110 pre- or inservice inspections of PWR vessels have been performed both in France and aboard by the mean of the first generation of french ISIM named MIS. Due to the increase of the number inspections which have to be realized in the next years, a new generation of ISIM have been developed. The first one is named MIS 5. The general structure of the mechanical part of MIS has not been changed, some improvements have been introduced to take in account the experience and facilitate maintenance, mounting, dismounting and transportation. The main changes lie in the control system and data acquisition and analysis equipment. The versatility of computers is widely used. A parametrizing unit allows to set all the parameters both for the tools and for the ultrasonic equipment and the data acquisition system. The ultrasonic equipment is able of managing 32 channels. Data are recorded simultaneously on Winchester disk, bulk memory and cassette of a HP 1000 computer (serial 900) and cassette. SOFTWARES have been developed by INTERCONTROLE for acquisition and analysis which allow to exhibit results automatically on screen printer or/and plotter. All the electronics and computer equipment are set in a shelter outside of the containement, linked to the MIS by 2 cables. 7 refs

  12. French natural gas industry statistics

    International Nuclear Information System (INIS)

    2004-01-01

    The opening of the French natural gas market is effective since August 2000. In this context, some information, which were published in the past, have become confidential and strategic and can no longer be revealed. The data published in this 2004 edition concern only the years 2001 and 2002 for which data are available. The year 2000 inquiry could not be exploited. A first part presents the natural gas industry in France (consumption, supplies, production, storage, distribution, definition of gases, information sources, energy equivalence, map of transportation networks, storage, compression and production facilities). The statistical data are summarized in the second part in the form of tables: resources and uses in 1999, 2001 and 2002; sectoral use of the network distributed gas since 1972; regional distribution of gas production; domestic production and imports since 1972; sectoral distribution of network gas supplies; pipelines and distribution systems; personnel in the gas industry; gas supplies in 2002; supplies to the residential-tertiary sector in 2002; supplies to the industry in 2002; regional supplies in 2002; share of gas supplies per use in each region; regional distribution of gas supplies for each use. A comparison between the 2002 inquiry results and the provisional status is given in appendix. The 2002 energy status and the 2002 questionnaire are also given in appendixes. (J.S.)

  13. [The French medecine pricing committee].

    Science.gov (United States)

    Giorgi, D

    2017-09-01

    The French medicine pricing committee (CEPS) has to reconcile several major constraints, including optimal patient access to medicines and a good control of expenditures on reimbursable medicines. From 2013 to 2015, drug price decreases and discounts obtained by CEPS contributed more than € 5 billion to the balance of the health insurance accounts. As for price setting, there is a significant drop in the prices of medicines in France once they are registered for reimbursement. France is affected by a limited, but costly, flow of innovative medicines, whose prices are higher than those of previous generations, a reflection of an international gradient to which France is obviously subject, despite prices that remain at the low end of the range in Western Europe. The provision of innovative medicines for all patients who need them has been ensured in France over the last fifteen years at a controlled cost. But with the arrival of new expensive products, a resolute policy of control of expenditures must take over from the fall in prices, and original financing channels will have to be explored. Copyright © 2017 Académie Nationale de Pharmacie. Published by Elsevier Masson SAS. All rights reserved.

  14. The French Sleep Disturbance Scale for Children.

    Science.gov (United States)

    Putois, Benjamin; Leslie, Wendy; Gustin, Marie Paule; Challamel, Marie-Josèphe; Raoux, Aude; Guignard-Perret, Anne; Weick, Diane; Sauzeau, Jean-Baptiste; Herbillon, Vania; Zourou, Filio; Spruyt, Karen; Franco, Patricia

    2017-04-01

    The psychometric properties of the Sleep Disturbance Scale for Children (SDSC) have been shown to be accurate, even when translated into several languages. The aim of the present study was to translate, adapt, and validate the SDSC for a French-speaking population. After forward- and back-translation, the tool was further translated and adapted into the French language. It was then pretested in terms of clarity on 33 French-speaking parents. Pretesting demonstrated that the questionnaire was well understood, indicating good clarity. During the validation phase, a total of 447 French-speaking parents of children aged between 4 and 16  years completed the SDSC. Among these, 66 children were diagnosed with sleep disorders by a pediatric specialist after a sleep consultation and polysomnographic recordings. The factor analysis revealed five factors: difficulty in initiating and maintaining sleep (DIMS), sleep breathing disorders (SBD), disorders of excessive somnolence (DOES), parasomnias (PARA) and non-restorative sleep (NRS). This psychometric structure is reliable and logical in comparison with the experts' diagnoses. Convergent validity, divergent and internal reliability are very good. Inter-parental concordance in scoring the child's sleep problem does show differences in the ways in which parents report their children's sleep patterns. Cut-off was calculated for the total score (45). This study validated a 25-item French version of the questionnaire. The French SDSC could therefore be used to aid screening of sleep disorders in the general population. Copyright © 2016 Elsevier B.V. All rights reserved.

  15. French in the XX Century: Development Tendencies

    Directory of Open Access Journals (Sweden)

    Taisiya I. Skorobogatova

    2017-06-01

    Full Text Available This article is devoted to the disclosure of changes that occurred in the French language in the XX century. The task of the authors is to present the main features characteristic of the French language of the 20th century, taking into account external history and to give their perspective assessment. World wars, the development of communication tools and the creation of new technologies, the strengthening of cultural and economic ties between France and other countries of the world had a significant impact on the evolution of the French language. Important results of the development of the French language in the period under review include: fixing a new phoneme [ŋ] in the consonantial system of the French language; enrichment of the lexical system at the expense of internal resources and at the expense of other languages; strengthening the dynamics of the development of the non-literary part of the language; increase in the number of syntactic Anglicisms. In general, the authors of the article attempted to give a detailed answer to the question: if there was the impoverishment of the French language in the twentieth century.

  16. [The medical French-speaking world].

    Science.gov (United States)

    Gouazé, André

    2002-01-01

    Medicine has always been and remains the most solid base of the French-speaking world which was born in Africa and Indochina with the admirable action of "colonial" military physicians, the implantation of the Pasteur Institutes and the emergence of resulting overseas medical schools. Obviously, we are referring to the French-speaking medical world. Since the first International Conference of the Deans of French-Speaking Medical Schools in Abidjan in 1981, today medical schools from 40 French-speaking countries participate. The conference undertakes co-operative medical school initiatives in a multi-lateral spirit, comprised by concrete, practical actions to assist universities in developing countries strive for excellence. These actions, which are conducted with the help of both institutional (AUF, MAE, WHO, UNESCO) and private partners mainly concentrate on promoting medical education of medicine, the evaluation of medical schools, the development of scientific and technical information and training teachers in the methodology of scientific clinical research and in public health. For the future, the Conference has three important objectives, to assist in training researchers and consequently in the development of research centres in emerging countries, to promote continuing medical education in rural areas far from medical schools by taking advantage of modern computer technology, and finally to open horizons toward other communities which speak other languages, and first of all, towards non French-speaking countries who live in a French-speaking environment.

  17. Thorium fueled reactor

    Science.gov (United States)

    Sipaun, S.

    2017-01-01

    Current development in thorium fueled reactors shows that they can be designed to operate in the fast or thermal spectrum. The thorium/uranium fuel cycle converts fertile thorium-232 into fissile uranium-233, which fissions and releases energy. This paper analyses the characteristics of thorium fueled reactors and discusses the thermal reactor option. It is found that thorium fuel can be utilized in molten salt reactors through many configurations and designs. A balanced assessment on the feasibility of adopting one reactor technology versus another could lead to optimized benefits of having thorium resource.

  18. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

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

  19. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

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

  20. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1981-12-01

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  1. French military plans for Superphenix

    International Nuclear Information System (INIS)

    Albright, D.

    1984-01-01

    France refuses to rule out military use of the plutonium produced by the planned breeder reactor Superphenix, although other nations, including the US, have contributed nuclear materials to it. US policy has been to separate military and civilian nuclear programs to set an example. France has not stated an intention to use Superphenix for military purposes, but is reserving the right to do so. It does not separate the two kinds of nuclear materials for economic reasons. The Non-Proliferation Treaty (NPT) does not address the possibility that plutonium pledged to peaceful use might be commingled with plutonium for military use in a civilian facility within a weapons state. The US could work to strengthen the US-Euratom Agreement on the basis of the contamination principle. 11 references

  2. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    2010-03-01

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  3. Spinning fluids reactor

    Science.gov (United States)

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

    2012-11-20

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

  4. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  5. Reactor power control device

    International Nuclear Information System (INIS)

    Ishii, Yoshihiko; Arita, Setsuo; Miyamoto, Yoshiyuki; Fukazawa, Yukihisa; Ishii, Kazuhiko

    1998-01-01

    The present invention provides a reactor power control device capable of enhancing an operation efficiency while keeping high reliability and safety in a BWR type nuclear power plant. Namely, the device of the present invention comprises (1) a means for inputting a set value of a generator power and a set value of a reactor power, (2) a means for controlling the reactor power to either smaller one of the reactor power corresponding to the set value of the generator power and the set value of the reactor power. With such procedures, even if the nuclear power plant is set so as to operate it to make the reactor power 100%, when the generator power reaches the upper limit, the reactor power is controlled with a preference given to the upper limit value of the generator power. Accordingly, safety and reliability are not deteriorated. The operation efficiency of the plant can be improved. (I.S.)

  6. One piece reactor removal

    International Nuclear Information System (INIS)

    Chia, Wei-Min; Wang, Song-Feng

    1993-01-01

    The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

  7. Heavy-Water Power Reactors. Proceedings Of A Symposium

    International Nuclear Information System (INIS)

    1968-01-01

    Proceedings of a Symposium organized by the IAEA and held in Vienna, 11-15 September 1967. The timeliness of the meeting was underlined by the large gathering of over 225 participants from 28 countries and three international organizations. Contents: Experience with heavy-water power and experimental reactors and projects (14 papers); New and advanced power reactor designs and concepts (8 papers); Development programmes and thorium cycle (9 papers); Economics and prospects of heavy-water power reactors (7 papers); Physics and fuel management (8 papers); Fuels (5 papers); Safety, control and engineering (6 papers); Panel discussion. Except for one Russian paper, which is published in English, each paper is in its original language (49 English and 8 French) and is preceded by an abstract in English with a second one in the original language if this is not English. Discussions are in English. (author)

  8. The high moderating ratio reactor using 100% MOX reloads

    International Nuclear Information System (INIS)

    Barbrault, P.

    1994-06-01

    This report presents the concept of a High Moderating ratio Reactor, which should accept 100% MOX reloads. This reactor aims to be the plutonium version of the European Pressurized Reactor (EPR), which is developed jointly by French and German companies. A moderating ration of 2.5 (instead of the standard value of 2.0) is obtained by replacing several fuel rods by water holes. The core would contain 241 Fuel Assemblies. We present some advantages of over-moderation for plutonium fuel, a description of the core and assemblies, calculations of fuel reload schemes and Reactivity Shutdown Margins, and the behavior of the core during two occidental transients. (author). 2 refs., 9 figs., 2 tabs

  9. Gastric cancer: the French survey.

    Science.gov (United States)

    Meyer, Ch; Lozac'h, P; Rohr, S; Topar, P; Youssef, Ch

    2002-01-01

    Presentation of a multicentric retrospective french study concerning 4,655 cases of gastric cancer operated between 1980 and 1996. The mean age was 67.4 years old with a male predominance of 63.1%. Pains was the predominant presenting symptom (60%) followed by alteration of the general condition (44%) and anaemia (20%). 35.5% of tumors were of distal, 18.8% of middle and 18.6% of proximal localisation. As regard cancer stages, 40% were of stage I,-II and 60% of stages III,-IV. Subtotal gastrectomy was realised in 44%, total radical gastrectomy in 42.1% and other surgical procedures in 14% of cases (proximal gastric resection or atypical resection). D1 lymphadenectomy was associated in 58.4% and D2 in 41.6%. Morbidity was of 23% and mortality of 11.9% which passed from 19% during the first (1980,-85) to 8% in the last interval of time (1990,-96). The 5 years survival was 41% in case of gastric resection. In univariate analysis the 5 years relative survival was better in female patients (44% at 5 years), in patients younger than 50 years old (46%), when pain was the only clinical symptom (52.7%), in middle and distal third localisation (47%), in case of subtotal distal resection (47%) and in less advanced stages (79% at 5 years for stage I cancer). In multivariate analysis the 5 years survival was essentially correlated to the stage of the tumor and no real prognosis improvement was shown during the period of the study.

  10. Fast Reactor Physics Vol. I. Proceedings of a Symposium on Fast Reactor Physics and Related Safety Problems

    International Nuclear Information System (INIS)

    1968-01-01

    Proceedings of a Symposium organized by the IAEA and held in Karlsruhe, 30 October - 3 November 1967. The meeting was attended by 183 scientists from 23 countries and three international organizations. Contents: (Vol.1) Review of national programmes (5 papers); Nuclear data for fast reactors (12 papers); Experimental methods (3 papers); Zoned systems (7 papers); Kinetics (7 papers). (Vol.11) Fast critical experiments (8 papers); Heterogeneity in fast critical experiments (5 papers); Fast power reactors (13 papers); Fast pulsed reactors (3 papers); Panel discussion. Each paper is in its original language (50 English, 11 French and 3 Russian) and is preceded by an abstract in English with a second one in the original language if this is not English. Discussions are in English. (author)

  11. Education and Training at Research Reactors: Sharing the Experiences from Europe with Asia and Africa

    International Nuclear Information System (INIS)

    Sklenka, L.; Foulon, F.

    2017-01-01

    Education and training at research reactors has long tradition in Europe and for several decades it is has been regular part of educational processes at universities in France, Czech Republic, Austria, Slovenia, Hungary, Germany, Italy or Finland. Several European research reactors have bilateral agreement of collaboration in nuclear education and training with research reactors and Africa and Asia, but most of the collaborations are carried out under various IAEA activities and projects. Based on experiences from EERRI – Eastern European Research Reactor Initiative dedicated IAEA questionnaire has been developed where the capabilities and needs in nuclear education and training in Africa are described in details. One regional workshop and one regional training course were also organised with strong involvement of lecturers from European research reactors. Regional workshop on enhanced use of research reactors for education and training purposes was organised in Rabat at Moroccan TRIGA reactor in 2013 which was attended by 12 participants from 7 African countries. Regional training course on the safety of research reactors was also organised in Rabat in 2014 which was attended by 12 participants from 7 African countries. Another ongoing project where European research reactors are involved in Africa is Internet reactor laboratory where French reactor ISIS will serve as host reactor for broadcasting of education to several African countries. Similarly as in Africa, bilateral collaborations between Europe and Asia involving several research reactors have been established. During IAEA regional workshop on education and training practices with research reactors organised in 2012 in Prague, the first contact between Europe and South - East Asia has been established. Under IAEA PUI project the first regional training course with strong involvement of lecturers from European research reactors was organised in Selangor at Malaysian TRIGA reactor in 2013. This training

  12. CEA celebrates the jubilee of ZOE reactor

    International Nuclear Information System (INIS)

    Loverini, M.J.

    1998-01-01

    This article reviews the saga of the first French nuclear reactor ZOE. As soon as 1939 Frederic Joliot had an intuition of the possibility of using fissioning nuclei to produce energy. 3 patents describing the concept of a nuclear reactor highlighting the role of natural uranium as fuel, heavy water as moderator, were registered. The only producer in the world of heavy water was a Norwegian firm, a fierce competition with Germany for the control of deuterium broke out. Eventually 185 Kg of heavy water were secretly convoyed in Great-britain. Because of the development of the war, the small scientist team in charge of the project has had to move from France to Great-britain then to Canada. At the end of the war, the 'Commissariat a l'energie atomique' (CEA) was created, its first aim was to design a nuclear reactor as soon as possible. In 1948 the first criticality of ZOE is reached, 6 years later than the team led by Enrico Fermi did in Chicago. In 1976 ZOE was decommissioned and is now a small museum dedicated to nuclear energy. (A.C.)

  13. Hierarchies of Authenticity in Study Abroad: French from Canada versus French from France?

    Science.gov (United States)

    Wernicke, Meike

    2016-01-01

    For many decades, Francophone regions in Canada have provided language study exchanges for French as a second language (FSL) learners within their own country. At the same time, FSL students and teachers in Canada continue to orient to a native speaker standard associated with European French. This Eurocentric orientation manifested itself in a…

  14. Optimum use of CDOT French and Hamburg data (French and Hamburg tests).

    Science.gov (United States)

    2013-11-01

    The Colorado Department of Transportation (CDOT) has been collecting data from the Hamburg Rutter and the : French Rutter for over 20 years. No specifications have been written in that time for either the Hamburg Rutter : or the French Rutter. This r...

  15. Calculated leaching of certain fission products from a cylinder of French glass

    International Nuclear Information System (INIS)

    Blomqvist, G.

    1977-07-01

    The probable total leaching of the most important fission products and actinides have been tabulated for a cylinder of French HLW glass with approximately 9 percent fission products. The calculations cover the period between 30 and 10000 years after removal from the reactor. The cylinder is of the type planned for the introduction of the HLW into Swedish crystalline rocks. All the components are supposed to have the same leach rate. The calculations also include the probable thickness of eroded glass layer/year. (author)

  16. Human performance in an operational event - how to improve it? An initiative in a French NPP

    International Nuclear Information System (INIS)

    Meslin, M.

    1998-01-01

    In the case of the Saint-Laurent-des-Eaux French nuclear power station, the author comments the elements and principles of human factor policy which have been implemented, the organizational implications of this implementation (building up of an internal human factors network), and briefly evokes studies and initiatives aimed at improving the quality of operation from a general point of view and through projects aiming at analyzing and at a valorisation of human reliability in activities dealing with reactor operation. He also comments the perception and appropriation of quality in the different departments

  17. Recent and future evolution of the conception of French PWR facing safety and reliability

    International Nuclear Information System (INIS)

    Vignon, D.; Morin, R.; Brisbois, J.

    1987-11-01

    The realization of French construction of REP(54 units) has conducted at an original approach of the safety. Now this approach is finished and the totality of detained dispositions are taken in consideration for the conception of the new standardized plant series N4. For the future, after this rationalization of this safety approach, a research on the simplification of the conception is provided. This new conception is based on the experience returns and on the results of the probabilistic studies on the 900 and 1300 MWe reactors. This rationalization, the new concepts and the research of simplifications are illustrated by concrete examples in this presentation [fr

  18. The French Disconnection – Reducing the nuclear share in France’s energy mix

    OpenAIRE

    2014-01-01

    France is debating its energy transition, triggered by President Hollande’s pledge to reduce nuclear power’s dominant share in the country’s electricity mix. The debate has yet to produce a new energy law, but has shaken French complacency that they completed their energy transition years ago by decarbonising their electricity through nuclear power. It has also raised the question of the long term future and replacement of France’s 58 reactors. This paper argues against early closure of react...

  19. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

    The invention deals with disengaging the coupling of a reactor coolant pump of a nuclear reactor feeding pressurized coolant. The disengaging coupling has two parts joined by bolts, at least one of them containing a driving agent within a bore. This is provided with a speed-depending ignition device in such manner that, if the critical speed is reached, the driving charge is ignited and the coupling is disengaged by destroying the bolts. (UWI) [de

  20. Neutron fluxes in test reactors

    Energy Technology Data Exchange (ETDEWEB)

    Youinou, Gilles Jean-Michel [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-01

    Communicate the fact that high-power water-cooled test reactors such as the Advanced Test Reactor (ATR), the High Flux Isotope Reactor (HFIR) or the Jules Horowitz Reactor (JHR) cannot provide fast flux levels as high as sodium-cooled fast test reactors. The memo first presents some basics physics considerations about neutron fluxes in test reactors and then uses ATR, HFIR and JHR as an illustration of the performance of modern high-power water-cooled test reactors.

  1. Le francais d'afrique noire, francais creole ou creole francais (The French of Black Africa, Creole French or French Creole)?

    Science.gov (United States)

    Manessy, G.

    1978-01-01

    Examines factors common to the various dialects of the French employed in Africa and demonstrates how these factors (1) determine the uniqueness of these dialects with relation to standard French, and (2) the resemblance of these dialects to African French-based Creoles. (AM)

  2. Thai research reactor

    International Nuclear Information System (INIS)

    Aramrattana, M.

    1987-01-01

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  3. Increased sharing of renewable energies in the electricity production system: what impact on the reactor fleet?

    International Nuclear Information System (INIS)

    Cany, C.; Devezeaux de Lavergne, J.G.; Mansilla, C.; Mathonniere, G.

    2017-01-01

    This article presents the flexibility of an individual reactor and of the complete fleet of reactors as a means to cope with the variability of renewable energies like solar or wind energies. Flexibility means the ability for load following and this ability is limited by both safety rules and limits on the release of radionuclides in the environment. The flexibility of the fleet depends on individual reactor flexibility but also on organisational and economic constraints. The participation of a reactor to load following depends on: its availability (not in maintenance or testing phase), its position in the cycle, the positioning of its scheduled shutdowns and the minimization of the volume of effluents. The study presents the future need of flexibility for the reactor fleet as the shares of wind and solar energies increase in the French energy mix. (A.C.)

  4. [Emergency eye care in French university hospitals].

    Science.gov (United States)

    Bourges, J-L

    2018-03-20

    The patient's request for urgent care in ophthalmology (PRUCO) at health care centers is constantly growing. In France, university hospitals are managing 75% of these cases. We sought to quantify PRUCO referred to French university hospital emergency units as well as to approach the structure and the territorial distribution of emergency eye care provided by French university hospitals. We conducted a quick cross-sectional survey sent to the 32 metropolitan and overseas French university hospitals. It inquired for each hospital whether emergency eye care units were available, whether ophthalmologists were on duty or on call overnight and how many PRUCO were managed in 2016. The 32 university hospitals completed the survey. A total of 398650 PRUCO were managed in French university hospitals in 2016. The emergency unit was exclusively dedicated to eye care for 70% of the hospitals, with 47% (15/32) of them employing an ophthalmologist on duty overnight. Every hospital but one had at least one ophthalmologist on call. The city of Paris set aside, university hospitals took care of an annual mean of 9000 PRUCO (min=500; max=32,250). The 32 French university hospitals are actively responding to patient's requests for urgent care in ophthalmology with very heterogeneous patient volumes and organizational systems. Half of them employ ophthalmologists on duty. Copyright © 2018 Elsevier Masson SAS. All rights reserved.

  5. Hybrid reactors. [Fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Moir, R.W.

    1980-09-09

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of /sup 233/U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m/sup -2/, and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid.

  6. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

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

  7. Multipurpose research reactors

    International Nuclear Information System (INIS)

    1988-01-01

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

  8. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Matsuura, Shojiro; Nakahara, Yasuaki; Takano, Hideki

    1982-09-01

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

  9. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1985-08-01

    Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

  10. Spectral shift reactor control method

    International Nuclear Information System (INIS)

    Impink, A.J. Jr.

    1981-01-01

    A method of operating a nuclear reactor having a core and coolant displacer elements arranged in the core wherein is established a reator coolant temperature set point at which it is desired to operate said reactor and first reactor coolant temperature band limits are provided within which said set point is located and it is desired to operate said reactor charactrized in that said reactor coolant displacer elements are moved relative to the reactor core for adjusting the volume of reactor coolant in said core as said reactor coolant temperature approaches said first band limits thereby to maintain said reactor coolant temperature near said set point and within said first band limits

  11. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The aim of this invention is the provision of improved seals for reactor vessels in which fuel assemblies are located together with inlets and outlets for the circulation of a coolant. The object is to provide a seal arrangement for the rotatable plugs of nuclear reactor closure heads which has good sealing capacities over a wide gap during operation of the reactor but which also permits uninhibited rotation of the plugs for maintenance. (U.K.)

  12. Power reactors operational diagnosis

    International Nuclear Information System (INIS)

    Dach, K.; Pecinka, L.

    1976-01-01

    The definition of reactor operational diagnostics is presented and the fundamental trends of research are determined. The possible sources of power reactor malfunctions, the methods of defect detection, the data evaluation and the analysis of the results are discussed in detail. In view of scarcity of a theoretical basis and of insufficient in-core instrumentation, operational diagnostics cannot be as yet incorporated in a computer-aided reactor control system. (author)

  13. Pressurised water reactor operation

    International Nuclear Information System (INIS)

    Birnie, S.; Lamonby, J.K.

    1987-01-01

    The operation of a pressurized water reactor (PWR) is described with respect to the procedure for a unit start-up. The systems details and numerical data are for a four loop PWR station of the design proposed for Sizewell-'B', United Kingdom. A description is given of: the initial conditions, filling the reactor coolant system (RCS), heat-up and pressurisation of the RCS, secondary system preparations, reactor start-up, and reactivity control at power. (UK)

  14. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

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

  15. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

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

  16. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  17. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.

    1999-01-01

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  18. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1988-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  19. Correspondence Theory and Phonological Blending in French

    Directory of Open Access Journals (Sweden)

    Lee Scott

    2014-07-01

    Full Text Available Though less productive than rival word-formation processes like compounding and affixation, blending is still a rich source of neologisms in French. Despite this productivity, however, blends are often seen by scholars as unpredictable, uninteresting, or both. This analysis picks up where recent studies of blending have left off, using Correspondence Theory and a bundle of segmental constraints to deal with this phenomenon as it pertains to French. More specifically, it shows that blending is the result of a single output standing in correspondence with two or more other outputs, and that we do not need to refer to prosodic information, which is crucial in accounts of blending in languages with lexical stress like English, to account for the process in French. The analysis also differs from previous studies in that it locates blending exclusively within the phonology, leaving its morphological and semantic characteristics to be handled by other processes in the grammar.

  20. French dissatisfactions on the European electricity market

    International Nuclear Information System (INIS)

    Glachant, J.M.

    2007-01-01

    The author first notices that the French electricity professional consumers are dissatisfied with the results of the creation of the European domestic electricity market in 1997: price increase either on bills or on the wholesale markets, and even more price increases are to come. The author proposes to examine several issues: what has been done during the 6 or 7 past years, that is since the California crisis in 2000-2001, to put the European electrical reforms on a virtuous track? Have the basic market economy principles been respected to protect competitiveness of all energy consumer professionals? How and why the French government or EDF will make us pay gas, coal or CO 2 emission permits like in England or Germany whereas the French electricity production has mainly (90 or 95 per cent) a nuclear or hydraulic origin?

  1. New reactor concepts

    International Nuclear Information System (INIS)

    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

  2. Remote Reactor Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dazeley, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dobie, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marleau, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brennan, Jim [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gerling, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sumner, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sweany, Melinda [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-10-21

    The overall goal of the WATCHMAN project is to experimentally demonstrate the potential of water Cerenkov antineutrino detectors as a tool for remote monitoring of nuclear reactors. In particular, the project seeks to field a large prototype gadolinium-doped, water-based antineutrino detector to demonstrate sensitivity to a power reactor at ~10 kilometer standoff using a kiloton scale detector. The technology under development, when fully realized at large scale, could provide remote near-real-time information about reactor existence and operational status for small operating nuclear reactors out to distances of many hundreds of kilometers.

  3. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  4. Multi purpose research reactor

    International Nuclear Information System (INIS)

    Raina, V.K.; Sasidharan, K.; Sengupta, Samiran; Singh, Tej

    2006-01-01

    At present Dhruva and Cirus reactors provide the majority of research reactor based facilities to cater to the various needs of a vast pool of researchers in the field of material sciences, physics, chemistry, bio sciences, research and development work for nuclear power plants and production of radio isotopes. With a view to further consolidate and expand the scope of research and development in nuclear and allied sciences, a new 20 MWt multi purpose research reactor is being designed. This paper describes some of the design features and safety aspects of this reactor

  5. Trench reactor: an overview

    International Nuclear Information System (INIS)

    Spinrad, B.I.; Rohach, A.F.; Razzaque, M.M.; Sankoorikal, J.T.; Schmidt, R.S.; Lofshult, J.; Ramin, T.; Sokmen, N.; Lin, L.C.

    1988-01-01

    Recent fast, sodium-cooled reactor designs reflect new conditions. In nuclear energy these conditions are (a) emphasis on maintainability and operability, (b) design for more transparent safety, and (c) a surplus of uranium and enrichment availability that eases concerns about light water reactor fueling costs. In utility practice the demand is for less capital exposure, short construction time, smaller new unit sizes, and low capital cost. The PRISM, SAFR, and integral fast reactor (IFR) concepts are responses to these conditions. Fast reactors will not soon be deployed commercially, so more radical designs can be considered. The trench reactor is the product of such thinking. Its concepts are intended as contributions to the literature, which may be picked up by one of the existing programs or used in a new experimental project. The trench reactor is a thin-slab, pool-type reactor operated at very low power density and- for sodium-modest temperature. The thin slab is repeated in the sodium tank and the reactor core. The low power density permits a longer than conventional core height and a large-diameter fuel pin. Control is by borated steel slabs that can be lowered between the core and lateral sodium reflector. Shutdown is by semaphore slabs that can be swung into place just outside the control slabs. The paper presents major characteristics of the trench reactor that have been changed since the last report

  6. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2002-01-01

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

  7. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  8. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Moir, R.W.

    1978-01-01

    We have carried out conceptual design studies of fusion reactors based on the three current mirror confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fission fuel for fission reactors. We have designed a large commercial hybrid based on standard mirror confinement, and also a small pilot plant hybrid. Tandem mirror designs include a commercial 1000 MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single cell pilot plant

  9. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    Frisch, E.; Andrews, H.N.

    1976-01-01

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  10. French contribution to develop Prussian blue.

    Science.gov (United States)

    Besse Bardot, Isabelle; Bardot, Sebastien; Menetrier, Florence; Leiterer, Alexandra; Pech, Annick

    2014-11-01

    Prussian blue is an antidote indicated for the treatment of internal cesium radioisotope contamination. The French armed forces develop and manufacture some antidotal drugs meeting regulatory, analytical and pharmaceutical requirements in order to submit marketing authorization documentation. Prior to an initial meeting with the French National Agency for Medicines and Health Products Safety (ANSM) in 2011, the authors were following regulatory developments in free cyanide release, active pharmaceutical ingredient (API) synthesis, API specifications, ability of cesium/Prussian blue binding products and collection of pre-clinical data. Free cyanide release was assessed by ultraviolet-visible (UV-Vis) spectrometry at 615 nm. The kinetics of cesium were evaluated in vitro by flame atomic absorption. Good laboratory practice (GLP) and mutagenic assays were examined in rat studies to assess 'no absorption'. A validated method makes it possible to assess the free cyanide in API according to the published tolerability in humans. The French synthesizer meets good manufacturing practice (GMP) to give a drug that is compliant with all specifications, ensuring its high quality. Two standard mutagenic assays showed mutagenic potential, leading to further tests to obtain more information on any induced chromosomal aberrations. Absorption could be an important factor in determining the risk posed by the drug. The French health service provides the country with several antidotal drugs reducing Chemical, Biological, Radiological and Nuclear (CBRN) risks. Using their GMP manufacturing facilities and pharmaceutical expertise, the French armed forces have contributed to developing drugs with marketing authorization, such as pentetate calcium trisodium (Ca-DTPA) for infusion, or under development with the French Alternative Energies and Atomic Energy Commission (CEA), such as Ca-DTPA by inhalation.

  11. French enterprises build on wind power

    International Nuclear Information System (INIS)

    Rap, C.

    2013-01-01

    Being confronted by the economic crisis French enterprises look for diversification towards sectors which appear to bear promise of growth. The wind industry is one of them despite the slowing demand for land-based installations. A wind turbine is made of 11 components which represents a total of 3000 parts. A series of French enterprises benefit from this market by specialising in narrow market niches like bearings, toothed wheels,... This document gathers short information notes on the following enterprises: SKF, Mersen, les Forges de Trie-Chateau, Guerton, Rollix, and NTN-SNR. (A.C.)

  12. Edexcel international GCSE and certificate French

    CERN Document Server

    Grime, Yvette

    2013-01-01

    This brand-new Student Book provides a grammar-led approach with extensive exam preparation that will help you develop independent, culturally aware students of French ready for the exam. The book is written to the latest Edexcel specification by experienced teachers. Extensive use of French reflects the style of the exams and, with specific exam advice and practice, it helps to build all the skills needed for success. Topics on Francophone cultures are integrated throughout to ensure students gain the cultural awareness that is at the heart of this qualification. The book provides up-to-date

  13. Population distribution around French nuclear sites

    International Nuclear Information System (INIS)

    Bastien, M.C.

    1985-10-01

    With the help of two files respectively from the Institut geographique national (IGN) containing the geographic reference of all cities in France, and from the Institut national de la statistique et des etudes economiques (INSEE) containing the population figures of the 1982 census, the distribution of the population around a geographic point can be determined according to a given grid. Tables of population distribution around the 30 french nuclear sites were obtained by this method; however, at a short distance from a site, a detailed local examination/survey/investigation is necessary. Data shall have to be collected to estimate the non-french population around frontier sites [fr

  14. [French immigration policy at a turning point?].

    Science.gov (United States)

    Wihtol De Wenden, C

    1995-01-01

    The author examines the changes to French immigration law adopted in 1993 in the light of current trends and pressures affecting migration to France. The focus is on the changes in the rules concerning the acquisition of French nationality, and the assimilation of existing immigrants from developing countries. The difficulties of resolving such problems at the national level while migration regulations are being developed at the European Community level are noted. Problems involving the control of the nation's borders, illegal immigration, and the growing demand for political asylum are also discussed. The author raises the possibility that immigration could be better managed in light of current labor market conditions in France.

  15. Acoustic aspects of vowel harmony in French

    OpenAIRE

    Nguyen, Noël; Fagyal, Zsuzsanna

    2008-01-01

    International audience; This paper examines acoustic aspects of vowel harmony (VH), understood as regressive vowel-to-vowel assimilation, in two regional varieties of French in six speakers' productions of 107 disyllabic word pairs. In each word pair, the word-initial vowel (V1) was phonemically either /e/ or /o/, and the word-final stressed vowel (V2) alternated between /e-E/, /ø-oe/, /o-O/ or /i-a/. Results are consistent with the idea that VH in French entails variations in tongue height a...

  16. Reactor core monitor for nuclear reactor

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

    The device of the present invention provides a various information of a wide adaptability, such as a power distribution, to an operator by determining a reactor core performance of the reactor by a performance calculation with improved accuracy. That is, a calculation means determines a neutron flux distribution of the reactor and coolant temperature based on the neutron flux distribution. A measuring means measures a cooled temperature of a reactor core inlet and a temperature at the exit of a fuel assembly. The result of coolant temperature by the measuring means and the result of the calculation by the calculation means are compared. The result of the calculation for the neutron flux distribution obtained by the calculation means is corrected based on the result of the comparison. The calculation means introduces calculation at higher accuracy by adopting two-dimensional balance in the fuel assembly. Further, a more accurate three-dimensional neutron diffusion calculation model is introduced in an on-line computer. Then, the accuracy of the calculation for the neutron flux distribution, power distribution, temperature distribution, etc. is improved. In view of the above, adaptability of a reactor core monitor is widened. (I.S.)

  17. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

    Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

  18. Fast reactors bulk sodium coolant disposal NOAH process application

    International Nuclear Information System (INIS)

    Magny, E. de; Berte, M.

    1997-01-01

    Within the frame of the fast reactors decommissioning, the becoming of contaminated sodium coolant from primary, secondary and auxiliary circuits is an important aspect. The 'NOAH' sodium disposal process, developed by the French Atomic Energy Commission (CEA), is presented as the only process, for destroying large quantities of contaminated sodium, that has attained industrial status. The principles and technical options of the process are described and main advantages such as safety , operating simplicity and compactness of the plant are put forward. The process has been industrially validated in 1993/1994 by successfully reacting the 37 metric tons of primary contaminated sodium from the French Rapsodie experimental reactor. The main outstanding aspects and experience gained from this so called 'DESORA' operation (DEstruction of SOdium from RApsodie) are recalled. Another industrial application concerns the current project for destroying more than 1500 metric tons of contaminated sodium from the British PFR (Prototype Fast Reactor) in Scotland. Although the design is in the continuity of DESORA, it has taken into account the specific requirements of PFR application and the experience feed back from Rapsodie. The main technical options and performances of the PFR sodium reaction unit are presented while mentioning the design evolution. (author)

  19. French scientists offered time to set up companies

    CERN Multimedia

    Butler, D

    1999-01-01

    The French minister of national education, research and technology announced that French researchers working for public research institutes and universities are to be offered up to six years sabbatical leave to set up their own companies (11 para)

  20. Presentation of decay heat removal computer codes used for gas cooled reactors

    International Nuclear Information System (INIS)

    Carvallo, G.; Dobremelle, M.; Mejane, A.

    1992-01-01

    For the existing French Magnox type reactors, two computer codes have been developed to analyze the transient after reactor shutdown: - The first one ('GITA', is representative of the short term evolution (less than 2 days) and it includes a refined representation of all the reactor components. - The second one, 'LOTE', has been developed to represent the long term evolution (from 2 days to several months) with a simplified representation of the main components of the reactor. One example of accident simulation is presented for existing Magnox reactor. Moreover, as a part of the French program on the future reactors, an analysis of the modular high temperature has been initiated. 2D and 3D general flow and conduction codes are used for this analysis: - DELFINE is a 2D conduction code including a 1D thermosyphon model, it has been used for decay heat removal analysis. TRIO is a 3D flow code including 3D radiation, conduction and convection heat transfer. It is used for detailed thermal analysis during accidental conditions