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Sample records for des installations nucleaires

  1. The control of base nuclear installations; Le controle des installations nucleaires de base (INB)

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    2009-04-15

    The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear base installations during november, december 2008 and january 2009, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

  2. The decommissioning of nuclear facilities; Le demantelement des installations nucleaires de base

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    Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R

    2008-11-15

    ,; the fifth part presents the external points of view on dismantling with: the decommissioning of Saint-Laurent A, as seen by the local information committee, decommissioning: the urge for a public consultation, an evaluation of the work of the 'conseil superieur de la surete et de linformation nucleaire' (C.S.S.I.N.) - a consultative body dealing with information in the field of nuclear safety) on the issue of decommissioning basic nuclear installations, monitoring the decommissioning of nuclear facilities and examining applications. (N.C.)

  3. Fatigue damage of nuclear facilities; Endommagement par fatigue des installations nucleaires

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    NONE

    2001-07-01

    The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

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

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

    1960-07-01

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

  5. Inventory of chemical releases of nuclear installations in the North-Cotentin; Inventaire des rejets chimiques des installations nucleaires du Nord-Cotentin

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    NONE

    2002-05-15

    The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

  6. The control of base nuclear facilities (I.N.B.); Le controle des installations nucleaires de base (INB)

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    2009-02-15

    The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear basic installations during august, september, october 2008, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

  7. Status of safety at Areva group facilities. 2006 annual report; Etat de surete des installations nucleaires. Rapport annuel 2006

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    NONE

    2006-07-01

    This report presents a snapshot of nuclear safety and radiation protection conditions in the AREVA group's nuclear installations in France and abroad, as well as of radiation protection aspects in service activities, as identified over the course of the annual inspections and analyses program carried out by the General Inspectorate in 2006. This report is presented to the AREVA Supervisory Board, communicated to the labor representation bodies concerned, and made public. In light of the inspections, appraisals and coordination missions it has performed, the General Inspectorate considers that the nuclear safety level of the AREVA group's nuclear installations is satisfactory. It particularly noted positive changes on numerous sites and efforts in the field of continuous improvement that have helped to strengthen nuclear safety. This has been possible through the full involvement of management teams, an improvement effort initiated by upper management, actions to increase personnel awareness of nuclear safety culture, and supervisors' heightened presence around operators. However, the occurrence of certain events in facilities has led us to question the nuclear safety repercussions that the changes to activities or organization on some sites have had. In these times of change, drifts in nuclear safety culture have been identified. The General Inspectorate considers that a preliminary analysis of the human and organizational factors of these changes, sized to match the impact the change has on nuclear safety, should be made to ensure that a guaranteed level of nuclear safety is maintained (allowance for changes to references, availability of the necessary skills, resources of the operating and support structures, etc.). Preparations should also be made to monitor the changes and spot any telltale signs of drift in the application phase. Managers should be extra vigilant and the occurrence of any drift should be systematically dealt with ahead of

  8. Evaluation of the impact and the releases of operating nuclear facilities; Evaluation de l'impact et des rejets des installations nucleaires en fonctionnement normal

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    NONE

    2005-07-01

    The monitoring of nuclear installations releases, the associated impacts evaluation and the radiation monitoring of the environment are of an increase interest since the last ten years. Theses two days, organized by the environment section of the SFRP (French Society of Radiation Protection), aim to discuss the following topics: the development of the methods to improve radioactive elements and toxic substances releases in the environment; the structure of the environment control and the objectives of this control; the association of the local actors to the releases monitoring and to the environment control; the perspectives of evolution in matter of nuclear facilities releases management. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  12. Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA; Evaluation complementaire de la surete des installations nucleaires de base - Site du Tricastin - AREVA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This complementary safety assessment analyses the robustness of the Areva part of the Tricastin nuclear site to extreme situations such as those that led to the Fukushima accident. This study includes the following facilities: Areva NC Pierrelatte, EURODIF production, Comurhex Pierrelatte, Georges Besse II plant and Socatri. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 5 main measures to be taken to limit the risks linked to natural disasters: -) continuing the program for replacing the current conversion plant and the enrichment plant; -) renewing the storage of hydrofluoric acid at the de-fluorination workshop; -) assessing the seismic behaviour of some parts of the de-fluorination workshop and of the fluorine fabrication workshop; -) improving the availability of warning and information means in case of emergency; and -) improving the means to mitigate accidental gaseous releases. (A.C.)

  13. The dismantling of nuclear installations and the radioactive wastes management. Report of the President of the Republic followed by the answers of concerned administrations and organisms; Le demantelement des installations nucleaires et la gestion des dechets radioactifs. Rapport au President de la Republique suivi des reponses des administrations et des organismes interesses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    The discussed subjects concerns the situation and the challenges of the nuclear installations dismantling and the radioactive wastes management (main intervenors, panorama of the situation, rules applied to the dismantling and the radioactive wastes), the first experiences of dismantling and radioactive wastes disposal (experiences at the CEA and EDF, implementing of solutions for the disposal), interrogations and certainties (provision for future expenses, public information). (A.L.B.00.

  14. Nuclear installations safety and protection: thirty years of researches on earthquakes at the IRSN; Surete et protection des installations nucleaires: trente ans de recherches a l'IRSN sur les seismes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-03-01

    Every years more than one hundred earthquakes occur in France. Taking into account this risk is essential for the safety of nuclear installations. In this context the IRSN develops research programs on earthquakes and realizes evolutions of safety procedures. This paper presents three sheets of researches realized by the IRSN on earthquakes risk assessment in the nuclear installations design and exploitation and the example of the Saint-Die earthquake. (A.L.B.)

  15. Demonstration of the 3D PANTHERE software for the simulation of gamma dose rates for complex nuclear installations; Demonstration du logiciel 3D panthere pour la simulation des debits de doses gamma pour installations nucleaires complexes

    Energy Technology Data Exchange (ETDEWEB)

    Longeot, M.; Dupont, B. [EDFISEPTENITE, 12-14 avenue Dutrievoz, 69628 Villeurbanne Cedex (France); Schumm, A.; Zweers, M. [EDF/R and D/SINETICS, 1 avenue du General de Gaulle, 92141 Clamart Cedex (France); Malvagi, F.; Trama, J.C. [CEA Saclay, SERMA, 91 - Gif-sur-Yvette (France)

    2010-07-01

    The authors present the two successive versions of the PANTHERE simulation software developed by EDF-SEPTEN to determine gamma dose flow rate in complex industrial installations. This software predicts dose rates and thus enables interventions in irradiating environment to be optimized. The authors report the demonstration of the industrial version (PANTHEREv1) and of the currently under development version (PANTHEREv2). They outline the evolutions brought to the first version to develop the second one such as the direct importation of CAD models, ergonomic improvements, etc.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-12-15

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

  17. 16. national conference of the presidents of the local commissions of information (C.L.I.) around nuclear facilities; 16. conference nationale des presidents de commissions locales d'information (CLI) autour des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This conference contained two plenary sessions. The first one concerned the epidemiology with the following subjects: the epidemiology, its contributions and its limits; the epidemiological surveillance of cancers in France: role of registers within the device; the aggregates of leukaemia near the nuclear installations; perception and management of the risk; the point of view of the scientific committee of the A.N.C.L.I.; Followed a work in a workshop on the subjects relative to the functioning of the C.L.I. (Organization, relations, information) then the second plenary session with as subjects: organization and functioning of C.L.I., relations and links with A.N.C.L.I., information received and diffused by the C.L.I. (N.C.)

  18. Choice of optimum size of installations for dual-purpose production of desalted water and electricity, using nuclear power; Le dimensionnement optimum des installations de production mixte d'eau sessalee et d'electricite faisant intervenir l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Gaussens, J [Commissariat a l' Energie Atomique, Paris (France)

    1966-07-01

    The author used a method starting with water and power demand curves; this leads to the rational allocation of production costs to water and power within a given market. The power demand curve is needed as it seems improbable to sell at a constant price the enormous quantity of electricity produced by a dual purpose plant. Criteria based on principles of classical economics, help to select objectively desalination methods and plant sizes. On these criteria, normative methods for tariffing action of water and power can be based, while adhering as closely as possible to structure of demand. Examples of such criteria are the maximum profit of the supplier or the maximum satisfaction of the consumers taken collectively. In the first case marginal costs must be equated to marginal revenue, in the second one marginal cost to marginal satisfaction (theory of surpluses). The plant size often determines the choice of desalination process. Therefore the shape of the water demand curve and the economic criterion adopted (public or private ownership, capital restrictions etc.) often determine in this way both size and type of plant. Before deciding on the desalination technique, market surveys and rather subtle economic analyses are therefore necessary. (author) [French] Le probleme est presente en introduisant la notion de courbes de demande d'eau et d'electricite, ce qui permet d'aboutir a un partage rationnel des couts de revient entre eau et electricite dans ]e cadre d'un marche. L'objet de l'etude est, a partir des principes de l'economie classique, de donner des criteres objectifs de selection des dimensions des installations et des techniques de dessalement et d'en deduire une methode normative de tarification des deux produits lies: eau et electricite, en collant autant que possible a la structure de la demande. Ces criteres sont en particulier, soit le maximum de benefice de l'exploitant, soit le maximum de satisfaction des utilisateurs, c'est-a-dire la realisation d

  19. Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes; Prise en compte du risque sismique a la conception des ouvrages de genie civil d'installations nucleaires de base a l'exception des stockages a long terme des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This guide aims to define, for the nuclear installations excepted the long term storage of radioactive wastes, from site data, the design specifications of earthquake resistant civil engineering and the possible methods for: the determination of the seismic response of the buildings, taking into account the interactions with the materials and the evaluation of the associated strains to size the installation; the determination of seismic displacements to be considered to size the materials. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

    measurements. Statistical analysis is used extensively in connection with the control of measurements and to minimize the number of chemical analyses. However, the application of statistics to the evaluation of inventory discrepancies has not been successful. This paper will discuss the details of the material control techniques which have been listed and some of the problems associated with them. (author) [French] L'usine Y-12 exploitee par la Commission de l'energie atomique a Oak Ridge, Tennessee, procede depuis plus de 20 ans au traitement et a la recuperation d'uranium enrichi non irradie se presentant sous diverses formes. A l'heure actuelle, les installations de recuperation d'Y-12 executent une serie d'operations distinctes en chaine semi-continue, par exemple, dissolution, combustion, evaporation, extraction, denitrification et hydrofluoration. Les installations de traitement et de stockage ont une geometrie restreinte et leur capacite globale est de plusieurs centaines de kilogrammes d'uranium enrichi par mois. L'uranium entrant provient de l'usine elle-meme ainsi que d'autres installations de la Commission de l'energie atomique, situees aux Etats-Unis. Depuis sa creation, l'usine Y-12 a recu pratiquement toutes les sortes de dechets d'uranium enrichi non irradie. Le controle des operations est assure a l'aide des methodes suivantes: 1. Utilisation du materiel concu de maniere a faciliter le nettoyage et l'echantillonnage ainsi qu'a reduire au minimum le 'piegeage ' de matieres; 2. Controle permanent de tous les rebuts et dechets liquides, en particulier des effluents evacues a l'egout ou dans l'atmosphere et des dechets contamines; 3. Inventaires periodiques des stocks; 4. Echantillonnages et analyses de toutes les matieres entrantes et sortantes; 5. Controle strict de la qualite des mesures analytiques et de l'echantillonnage; 6. Attribution de la responsabilite du controle des matieres au personnel charge des operations plutot qu'a des comptables; 7. Formation

  1. Siloette, Siloe mock-up; Siloette, modele nucleaire de siloe

    Energy Technology Data Exchange (ETDEWEB)

    Delcroix, V; Jeanne, G; Mitault, G; Schulhof, P [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    Siloette is the Siloe mock-up. The main installations are described: various tanks, building, auxiliaries, control systems... Precis ions are given about precautions taken for using spent fuel elements. (authors) [French] Siloette est le modele nucleaire de SILOE. On decrit ses diverses installations: bassins, batiments, auxiliaires, controle... Des precisions sont donnees sur les precautions prises pour y utiliser des elements uses. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The rapid development of nuclear energy demands an urgent solution to the health problems arising from the discharge into the environment of radioactive residues produced by nuclear installations. - To be able to evaluate the risks run by the population and to fix tolerance limits for waste discharge, it is necessary to possess an exact knowledge of the course taken by the radioelements discharged, from their source until they reach man. The incorporation of radioelements in food cycles is the first risk to take into consideration. The factors involved in all stages of this transmission must be foreseen, whether they concern physical or biological media, because of their continuity and their interdependence. Finally, socio-economic and dietetic data must be collected in order that the risks and tolerance levels estimated are based on concrete and experimental rather than theoretical knowledge. The risk of nuclear accidents in the atomic industry, although very improbable, must be taken into consideration because of the seriousness of their consequences. The health problems arise in the field of professional hygiene on the one hand and in that of public hygiene on the other. In the first field the risk is two-fold and involves irradiation and contamination. The public sphere is reduced essentially to the risk of contamination by radioactive substances accidentally released in the surrounding medium. The health studies to be conducted in this field therefore include research not only on irradiation or contamination therapeutics but also on the transfer of radioelements from the accident site to man, mainly through food cycles, in their physical and in their biological components. Studies of this kind form the basis of decisions in the health field which would have to be taken in the case of an accident. (authors) [French] Le developpement rapide de l'energie nucleaire rend urgente la solution des problemes sanitaires poses par le rejet dans le milieu ambiant des

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-06-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

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

  8. Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-09-01

    A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux

  9. Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-09-01

    A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux millimetres fonctionnent

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  13. Evaluation guideline for the study of the radiological impact of based nuclear installations (INB) presented in support of releases authorization demands; Guide d'examen pour l'etude de l'impact radiologique d'une installation nucleaire de base (INB) fournie a l'appui des demandes d'autorisation de rejets

    Energy Technology Data Exchange (ETDEWEB)

    Chartier, M; Despres, A; Supervil, S; Conte, D; Hubert, P; Oudiz, A; Champion, D

    2002-10-01

    In the case of a license demand for the effluents release and water taking for a nuclear installation, the operating must realize a study of the nuclear effluents radiological impact on the environment and the public health. In this context, the study presents technical and methodological specifications which led the Direction of the Nuclear Installations Safety (DSIN) and the General Direction of the Health (DGS) to ask the IPSN the elaboration of a guideline to help these studies evaluation. The guideline presents the regulatory context, the description of the installations, the treatment and the control processes, the rules of management, the description of the environment, the estimation of the radiological impacts and the environment control system definition. (A.L.B.)

  14. Evaluation guideline for the study of the radiological impact of based nuclear installations (INB) presented in support of releases authorization demands; Guide d'examen pour l'etude de l'impact radiologique d'une installation nucleaire de base (INB) fournie a l'appui des demandes d'autorisation de rejets

    Energy Technology Data Exchange (ETDEWEB)

    Chartier, M.; Despres, A.; Supervil, S.; Conte, D.; Hubert, P.; Oudiz, A.; Champion, D

    2002-10-01

    In the case of a license demand for the effluents release and water taking for a nuclear installation, the operating must realize a study of the nuclear effluents radiological impact on the environment and the public health. In this context, the study presents technical and methodological specifications which led the Direction of the Nuclear Installations Safety (DSIN) and the General Direction of the Health (DGS) to ask the IPSN the elaboration of a guideline to help these studies evaluation. The guideline presents the regulatory context, the description of the installations, the treatment and the control processes, the rules of management, the description of the environment, the estimation of the radiological impacts and the environment control system definition. (A.L.B.)

  15. General phenomenology of underground nuclear explosions; Phenomenologie generale des explosions nucleaires souterraines

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    An essentially qualitatively description is given of the phenomena related to underground nuclear explosions (explosion of a single unit, of several units in line, and simultaneous explosions). In the first chapter are described the phenomena which are common to contained explosions and to explosions forming craters (formation and propagation of a shock-wave causing the vaporization, the fusion and the fracturing of the medium). The second chapter describes the phenomena related to contained explosions (formation of a cavity with a chimney). The third chapter is devoted to the phenomenology of test explosions which form a crater; it describes in particular the mechanism of formation and the different types of craters as a function of the depth of the explosion and of the nature of the ground. The aerial phenomena connected with explosions which form a crater: shock wave in the air and focussing at a large distance, and dust clouds, are also dealt with. (authors) [French] On donne une description essentiellement qualitative des phenomenes lies aux explosions nucleaires souterraines (explosion d'un seul engin, d'engins en ligne et explosions simultanees). Dans un premier chapitre sont decrits les phenomenes communs aux explosions contenues et aux explosions formant un cratere (formation et propagation d'une onde de choc provoquant la vaporisation, la fusion et la fracturation du milieu). Le deuxieme chapitre decrit les phenomenes lies aux tirs contenus (formation d'une cavite et d'une cheminee). Le troisieme chapitre est consacre a la phenomenologie des tirs formant un cratere et decrit notamment le mecanisme de formation et les differents types de crateres en fonction de la profondeur d'explosion et de la nature du terrain. Les phenomenes aeriens lies aux explosions formant un cratere: onde de pression aerienne et focalisation a grande distance, nuages de poussieres, sont egalement abordes. (auteurs)

  16. Reports by the Parliamentary Office for scientific and technological assessments. Thursday, May 19, 2011. The French nuclear installations in front of natural risks; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 19 mai 2011. Les installations nucleaires francaises face aux risques naturels

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-05-15

    Members of the French Parliament, representatives of the French nuclear safety authority (ASN), of the Academy of Sciences, researchers, and associations argue on major natural risks and their evaluation, notably by referring to the earthquake and tsunami which caused the Fukushima accident. They discuss the predictability of these phenomena, and evoke the context and consequences of climate change. A representative of the Academy of Technologies discusses the risks of land-slips and dam failure, outlines that earthquakes only caused some cracks in dams, and evokes the legal context and organisation regarding dam safety. Possible effects of earthquakes in France are discussed. A second part addresses the way natural risks are taken into account in the protection of nuclear installations

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The rapid development of nuclear energy demands an urgent solution to the health problems arising from the discharge into the environment of radioactive residues produced by nuclear installations. - To be able to evaluate the risks run by the population and to fix tolerance limits for waste discharge, it is necessary to possess an exact knowledge of the course taken by the radioelements discharged, from their source until they reach man. The incorporation of radioelements in food cycles is the first risk to take into consideration. The factors involved in all stages of this transmission must be foreseen, whether they concern physical or biological media, because of their continuity and their interdependence. Finally, socio-economic and dietetic data must be collected in order that the risks and tolerance levels estimated are based on concrete and experimental rather than theoretical knowledge. The risk of nuclear accidents in the atomic industry, although very improbable, must be taken into consideration because of the seriousness of their consequences. The health problems arise in the field of professional hygiene on the one hand and in that of public hygiene on the other. In the first field the risk is two-fold and involves irradiation and contamination. The public sphere is reduced essentially to the risk of contamination by radioactive substances accidentally released in the surrounding medium. The health studies to be conducted in this field therefore include research not only on irradiation or contamination therapeutics but also on the transfer of radioelements from the accident site to man, mainly through food cycles, in their physical and in their biological components. Studies of this kind form the basis of decisions in the health field which would have to be taken in the case of an accident. (authors) [French] Le developpement rapide de l'energie nucleaire rend urgente la solution des problemes sanitaires poses par le rejet dans le milieu ambiant des

  18. Installation and testing of the 150keV high current pulsed accelerator installed at the Service de Physique Nucleaire in Bruyeres-le-Chatel

    International Nuclear Information System (INIS)

    Dandine, Andre; Sinopoli, Louis.

    1976-01-01

    A 150keV accelerator installed at the Service de Physique Nucleaires in Bruyeres-le-Chatel is described which has been equipped especially for the preparation of the nuclear experiments carried out with the EN 7MV tandem Van de Graaff, and for the completion of totally independent experiments. Details of the ion optical arrangement and the pulsing system are presented; unanalysed beams of intensity 1 to 2mA are obtained accelerating either protons or deuterons. In the pulsed mode, at 1.25 MHz or 2.5MHz, the average intensity of the analysed beam is 8 to 10μA and the pulse length is 2ns [fr

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

  20. Performances of nuclear installations in the world; Performances des installations nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    Pate, Z.T. [World Association of Nuclear Operators (WANO), 75 - Paris (France)

    1999-01-01

    During the last years the operators of nuclear power plants in the world, have realized numerous improvements. This success is imputable to several factors, especially an important data exchange. The Chernobyl accident, in 1986, provoked the creation of the World Association of Nuclear Operators (W.A.N.O.). It allowed to exchange information and to develop cooperation in order to go beyond cultural barriers, linguistics and policies. Then, operators in the world have brought important improvements in matter of safety, reliability. (N.C.)

  1. Improvement of pressure-vessel surveillance of a PWR-power plant of the Societe d'Energie Nucleaire Franco-Belge des Ardennes (S.E.N.A.)

    International Nuclear Information System (INIS)

    Bevilacqua, A.; Lloret, R.; Riehl, R.

    1984-01-01

    This paper describes a new dosimetry, installed inside and outside the Pressure Vessel of CHOOZ Nuclear Power Plant of the Societe d'Energie Nucleaire Franco-Belge des Ardennes (S.E.N.A.), during its 1982-83 operation cycle. The inner dosimetry deals with a simulated capsule located under the reactor plate, and includes copper, nickel, iron, niobium, copper-cobalt, neptunium and uranium dosimeters. Its aim is to qualify the information given by the existing copper dosimetry. The spectrum used with these measurements is obtained by the 1 D ANISN Code and BIP-N 2 library. The outer dosimety is the fluence determination along the outer wall of the vessel. Two tubes, equiped by neutron dosimeters, seven meters long, were fixed along the vessel. On the median plane, the results are compared to a 2 D DOT transport calculation. Preliminary results are given which improve the vessel and specimens neutronic characterisation. (Auth.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-12-15

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

  3. Y2K bug and nuclear installations; Le passage a l'an 2000 sur les installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    1999-10-01

    Most nuclear installations except power plants, will be shut down on the eve of new year. By september 1999, EDF will have realized all the corrective and preventive actions that are necessary to pass Y2K. CEA has committed to present to safety authorities a complete report concerning preventive actions in its own basic nuclear installations. Safety authorities plan to organize a crisis center in order to face any problem. (A.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

  7. Analytic index for nuclear physicians uses; Repertoire analytique a l'usage des physiciens nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R.; Barloutaud, R.; Bernas, R.; Bretonneau, P.; Chaminade, R.; Cohen, R.; Conjeaud, M.; Cotton, E.; Faraggi, H.; Grjebine, T.; Joffre, H.; Laboulaye, H. de; Lesueur, C.; Leveque, A.; Moreau, J.; Naggiar, V.; Papineau, L.; Prugne, P.; Schuhl, C.; Studinowski, FJ.; Netter, F.; Raievski, V.; Valladas, G. [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Marty, N.; Renard, G. [College de France, Lab. de Chimie Nucleaire (France)

    The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of new publications, always more numerous and more varied. To remedy to this facts that we tried, in the service of Nuclear Physics of the CEA, to give to the documentation a character of a collective and systematized work. The present report covers the literature appeared between first January 1950 and first July 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le premier Janvier 1950 et le premier Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

  9. Study of some continuous spectra produced by nuclear reactions with light nuclei; Etude de quelques spectres continus produits par reactions nucleaires avec des noyaux legers

    Energy Technology Data Exchange (ETDEWEB)

    Marquez, L

    1966-07-01

    The continuous spectra coming from several nuclear reactions with light nuclei were measured. The spectra can be explained by a two-step reaction mechanism; however, the reactions produced by {sup 6}Li are different. A mechanism was proposed to explain their spectra based on the following assumptions: {sup 6}Li makes a nuclear molecule with the target which subsequently breaks up in such a way that an {alpha} particle comes out with the kinetic energy that it has in the molecule. The calculated spectra and those measured are in good agreement. (author) [French] Nous avons mesure les spectres continus produits dans plusieurs reactions nucleaires avec des noyaux legers. A l'exception des spectres produits par {sup 6}Li, on a trouve qu'on pouvait expliquer ces spectres par le mecanisme des reactions en deux etapes. Nous avons propose un mecanisme pour expliquer les spectres produits par {sup 6}Li. On suppose que {sup 6}Li forme une molecule nucleaire avec la cible qui eclate ensuite de facon telle qu'une particule alpha de la molecule sort avec l'energie cinetique de son mouvement propre dans la molecule. Les spectres calcules avec ces hypotheses et les spectres mesures sont en bon accord. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

  11. Administrative Arrangement between the Atomic Control Board of Canada and le Service central de surete des installations nucleaires du Ministere de l'Industrie et de l'Amenagement du Territoire de la Republique francaise for the Exchange of Technical Information and Cooperation in the Regulation of Nuclear Safety

    International Nuclear Information System (INIS)

    1991-01-01

    This Arrangement between the Atomic Energy Control Board of Canada (AECB) and the French Central Service for the Safety of Nuclear Installations (SCSIN) entered into force on the date of its signature and will remain in effect for five years. The Arrangement provides for the exchange of information between both agencies on the regulation of nuclear facilities and intervention measures in cases of emergency. This includes information on regulatory procedures for the safety of designated nuclear facilities, notification of important events, such as serious operating incidents, reactor shutdowns ordered by the regulatory authorities, etc. (NEA) [fr

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1952-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

  15. Contribution to the study of the action of electromagnetic fields on the angular correlations of nuclear radiation (1960); Contribution a l'etude de l'action des champs electromagnetiques sur les correlations angulaires des rayonnements nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-01-15

    This work deals with the study of interaction of E.M. fields with nuclear moments of nuclei emitting gamma rays. We describe first experiments on delayed angular correlation showing the role played by statistic quadrupole interaction. We have measured the magnetic moment of the second excited state of {sup 19}F using an external magnetic field. In the case of {sup 19}O, experiments of angular distributions and angular correlations of gamma -rays taking into account the possibility of perturbations, allow us to determine the spin and parities of the three first levels. (author) [French] Le present travail concerne l'etude de l'interaction des champs electromagnetiques et des moments nucleaires de noyaux emettant des rayonnements gamma. Nous decrivons des experiences de correlation angulaire differee dont l'interpretation met en coincidence le role joue par les interactions quadrupolaires statiques. Nous avons mesure le moment magnetique de {sup 19}F dans un etat excite en utilisant un champ magnetique exterieur a la source radioactive. Enfin, dans le cas de {sup 19}O, nous montrons l'utilite d'un examen des possibilites de perturbations dans l'interpretation des resultats fournis par des correlations ou des distributions angulaires. (auteur)

  16. Contribution to the study of the action of electromagnetic fields on the angular correlations of nuclear radiation (1960); Contribution a l'etude de l'action des champs electromagnetiques sur les correlations angulaires des rayonnements nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-01-15

    This work deals with the study of interaction of E.M. fields with nuclear moments of nuclei emitting gamma rays. We describe first experiments on delayed angular correlation showing the role played by statistic quadrupole interaction. We have measured the magnetic moment of the second excited state of {sup 19}F using an external magnetic field. In the case of {sup 19}O, experiments of angular distributions and angular correlations of gamma -rays taking into account the possibility of perturbations, allow us to determine the spin and parities of the three first levels. (author) [French] Le present travail concerne l'etude de l'interaction des champs electromagnetiques et des moments nucleaires de noyaux emettant des rayonnements gamma. Nous decrivons des experiences de correlation angulaire differee dont l'interpretation met en coincidence le role joue par les interactions quadrupolaires statiques. Nous avons mesure le moment magnetique de {sup 19}F dans un etat excite en utilisant un champ magnetique exterieur a la source radioactive. Enfin, dans le cas de {sup 19}O, nous montrons l'utilite d'un examen des possibilites de perturbations dans l'interpretation des resultats fournis par des correlations ou des distributions angulaires. (auteur)

  17. Guide relative to the modalities of statements and to the codification of criteria relative to the significant events involving the safety, the radiation protection or the environment applicable to the base nuclear installations and to the transport of radioactive matters; Guide relatif aux modalites de declaration et a la codification des criteres relatifs aux evenements significatifs impliquant la surete, la radioprotection ou l'environnement applicable aux installations nucleaires de base et au transport de matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    It is necessary to analyze the events detected on an installation in order to be sure that an already occurred event does not be repeated, by taking into account the appropriate remedial measures, to avoid a worsen situation could occur by analyzing the potential consequences of precursory events of more serious ones, to promote the correct practices to improve the safety. The present guide has for vocation to define the arrangements enforceable to nuclear operators about the statements modalities of such events when these ones concern the safety of nuclear facilities, transport of radioactive matters, radiation protection or environmental protection. In any case it can substitute to the specific obligations coming from the work code, public health code and environment code, licensing decrees about releases. (N.C.)

  18. J.O. no. 10 of the 13 january 2004, page 991, text no. 14. Decrees, orders. General texts. Decree no. 2004-47 of the 12 january 2004 modifying the decree no. 96-978 of the 31 october 1996 relative to the creation of the nuclear installation no. 162 named EL4-D, installation of storage for the Monts d'Arree power plants materials; J.O. no. 10 du 13 janvier 2004, page 991, texte no. 14. Decrets, arretes, circulaires. Textes generaux. Decret no. 2004-47 du 12 janvier 2004 modifiant le decret no. 96-978 du 31 octobre 1996 relatif a la creation de l'installation nucleaire de base no. 162 denommee EL4-D, installation d'entreposage de materiels de la centrale nucleaire des monts d'Arree

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-06-01

    The reactor EL4, implemented in december 1966, has definitely shutdown on the 31 july 1985. This reactor was an industrial prototype, built and exploited by Cea and EDF. In the framework of the partial dismantling of the installation, the decree 96-978 of the 31 october 1996 agreed the Cea to modify the installation to become a storage installation. (A.L.B.)

  19. Contribution to the study of radio toxicity of aromatic and medicinal plants using solid state nuclear track detectors; Contribution a l etude de la radio toxicite des plantes aromatiques et medicinales au moyen des detecteurs solides de traces nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Mortassim, A; Misdaq, M A; Naaman, A

    2009-07-01

    The concentrations of uranium (238 U), thorium (232 Th), radon (222 Rn) and thoron (220 Rn) were measured in twenty aromatic and medicinal plants in {sup f}ind a new method based on using solid state nuclear track detectors type Cr-39 and Rs-115. He emerges from this study that the verbena and salvia have higher levels of uranium (radon) higher than that of other plants while the leaves of olive and saturja have concentrations of thorium (thoron) higher than other plants therefore radio toxicity of these plants is higher than that of others and may pose a radiological hazard if the masses are incorporated by consumers high. [French] Les concentrations en uranium (238U), thorium (232Th), radon (222Rn), et thoron (220Rn) ont ete mesurees dans vingt plantes aromatiques et medicinales en utilsant une nouvelle methode basee sur l utilisation des detecteurs solides de traces nucleaires de types CR-39 et LR-115. Il en sort de cette etude que la verveine et la salvia presentent des teneurs en uranium (radon) superieurs a celle des autres plantes alors que les feuilles d olivier et la saturja presentent des concentrations en thorium (thoron) plus elevee que celles des autres plantes par consequent la radio toxicite de ces plantes est superieure a celles des autres et peuvent presenter un risque radiologique si les masses incorporees par les consommateurs sont elevees.

  20. The nuclear in Italy - state of the art; Le nucleaire en Italie - etat des lieux

    Energy Technology Data Exchange (ETDEWEB)

    Schifano, F.; Ziller, T

    2007-02-15

    This report aims to evaluate the italian situation in matter of the nuclear, following the referendum of 1987 which decided to stop the nuclear power plants in the country. The first part is devoted to the historical aspects of the nuclear sector in Italy. The second chapter presents the institutional and legislative framework. The third chapter discusses the today situation and the italian actors of the nuclear, from the radioactive wastes management and the dismantling of nuclear installations to the engineering service realized in other countries. It discusses also the research and development programs. The last chapter proposes perspectives of the debate around a possible restart of the nuclear activity in Italy.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1952-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-12-15

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

  6. Can-rupture detection in gas-cooled nuclear reactors; La detection des ruptures de gaine dans les piles nucleaires refroidies par gaz

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    Can-rupture detection (DRG) is one important aspect of pile safety, more particularly so in the case of gas-cooled reactors. A rapid and sure detection constitutes also an improvement as far as the efficiency of electricity-producing nuclear power stations are concerned. Among the numerous can-rupture detection methods, that based on the measurement of the concentration of short-lived fission gases in the heat-carrying fluid has proved to be the most sensitive and the most rapid. A systematic study of detectors based on the electrostatic collection of the daughter products of fission gases has been undertaken with a view to equip the reactors EL 2, G 3, EDF 1, EDF 2 and EDF 3, the gas loops of PEGASE and EL 4. The different parameters are studied in detail in order to obtain a maximum sensitivity and to make it possible to construct detection devices having the maximum operational reliability and requiring the minimum maintenance. The primary applications of these devices are examined in the case of the above-mentioned reactors. (author) [French] La Detection des Ruptures de Gaines (D. R. G.) est un aspect important de la securite des piles et plus particulierement des piles refroidies par un gaz. Une detection rapide et sure constitue aussi un element d'amelioration du rendement des centrales nucleaires productrices d'energie electrique. Parmi les nombreuses methodes de detection des ruptures de gaines, la mesure de la concentration dans le fluide caloporteur des gaz de fission a vie courte s'est revelee comme la plus sensible et la plus rapide. Une etude systematique des detecteurs a collection electrostatique des descendants des gaz de fission a ete entreprise en vue d'equiper les piles EL 2, G 3, EDF 1, EDF 2 et EDF 3, les boucles a gaz de la pile Pegase et la pile EL 4. Les divers parametres sont etudies en detail pour obtenir une sensibilite maximum et permettre la realisation de dispositifs de detection ayant le maximum de securite de

  7. Can-rupture detection in gas-cooled nuclear reactors; La detection des ruptures de gaine dans les piles nucleaires refroidies par gaz

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    Can-rupture detection (DRG) is one important aspect of pile safety, more particularly so in the case of gas-cooled reactors. A rapid and sure detection constitutes also an improvement as far as the efficiency of electricity-producing nuclear power stations are concerned. Among the numerous can-rupture detection methods, that based on the measurement of the concentration of short-lived fission gases in the heat-carrying fluid has proved to be the most sensitive and the most rapid. A systematic study of detectors based on the electrostatic collection of the daughter products of fission gases has been undertaken with a view to equip the reactors EL 2, G 3, EDF 1, EDF 2 and EDF 3, the gas loops of PEGASE and EL 4. The different parameters are studied in detail in order to obtain a maximum sensitivity and to make it possible to construct detection devices having the maximum operational reliability and requiring the minimum maintenance. The primary applications of these devices are examined in the case of the above-mentioned reactors. (author) [French] La Detection des Ruptures de Gaines (D. R. G.) est un aspect important de la securite des piles et plus particulierement des piles refroidies par un gaz. Une detection rapide et sure constitue aussi un element d'amelioration du rendement des centrales nucleaires productrices d'energie electrique. Parmi les nombreuses methodes de detection des ruptures de gaines, la mesure de la concentration dans le fluide caloporteur des gaz de fission a vie courte s'est revelee comme la plus sensible et la plus rapide. Une etude systematique des detecteurs a collection electrostatique des descendants des gaz de fission a ete entreprise en vue d'equiper les piles EL 2, G 3, EDF 1, EDF 2 et EDF 3, les boucles a gaz de la pile Pegase et la pile EL 4. Les divers parametres sont etudies en detail pour obtenir une sensibilite maximum et permettre la realisation de dispositifs de detection ayant le maximum de securite de fonctionnement et le

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

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

  9. Circumstances and consequences of Oural nuclear plant spoils; Circonstances et consequences des rejets des installations nucleaires de l`Oural

    Energy Technology Data Exchange (ETDEWEB)

    Nenot, J C

    1994-12-31

    The environment pollution frames serious long-dated problem. The civil nuclear power unhappily does not rest. The liquid waste fuel cycle plant prospective, particularly at their working beginning. 14 refs., 5 tabs.

  10. Factors and uncertainties in the profitability of using nuclear energy in desalination of water; Facteurs et incertitudes de la rentabilite du recours a l'energie nucleaire dans le dessalement des eaux

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L; Lievre, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-07-01

    One of the economic advantages of nuclear energy consists of the small proportional element in its cost structure. Economies of scale favour the nuclear station as compared with the conventional thermal one, and when the demand for electricity and heat, in particular for desalination, are sufficient, nuclear energy may, subject to certain conditions, prove advantageous. The object of this paper is to discuss the validity of the conclusions reached according to the hypotheses adopted. In the first part, the different kind of uncertainties connected with technical, economic and financial data (the various transmission coefficients, the life of equipment according to the choice of materials, changes in prices, the form of price functions and interest rates), and with the various constraints, are examined and discussed. In the second part the uncertainties connected with the method of optimisation used and the criterion of selection adopted are examined and discussed. It is shown thereby that it is usually extremely difficult to assume absolutely the competitiveness, or conversely the non-competitiveness, of using nuclear energy in the desalination of water, and that a large number of aspects have to be carefully examined. (author) [French] On sait que l'un des avantages economiques de l'energie nucleaire reside dans la faible part proportionnelle dans la structure de son cout. Les economies d'echelle favorisent le nucleaire par rapport au thermique classique, et lorsque les demandes d'electricite et de chaleur, notamment pour le dessalement, sont suffisantes on peut envisager favorablement, sous certaines hypotheses, le recours a l'energie nucleaire. L'objet de cette communication est de discuter la validite des conclusions auxquelles on parvient selon les hypotheses envisagees. Dans une premiere partie, on etudie et on discute les differentes sortes d'incertitudes, liees aux donnees techniques, economiques et financieres (les divers coefficients de transmission, les

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

    ; elles dependent donc de ce service pour les renseignements precis dont elles ont besoin pour assumer leurs responsabilites. C'est en premier lieu a la personne chargee de la surveillance generale du circuit qu'il incombe de veiller a ce qu'en aucun point les matieres nucleaires ne puissent, par inadvertance, atteindre l'etat critique. Pour mettre au point des mesures preventives, il faut tenir compte d'au moins trois categories de problemes, a savoir: a) Les problemes scientifiques et techniques lies a l'evaluation des risques que presente une certaine quantite de matieres fissiles disposee selon une certaine geometrie dans un certain endroit; b) Les problemes materiels souleves par les restrictions qu'imposent les considerations scientifiques ou techniques; c) Les problemes purement administratifs a resoudre pour respecter les restrictions et les conditions particulieres imposees par les considerations techniques et materielles. Pour aider le responsable de la surveillance a s'acquitter de sa tache, certaines organisations prevoient des groupes ou des comites specialises dans des domaines particuliers. Les problemes techniques sont le plus souvent soumis a des specialistes de la criticite, generalement constitues en comites de securite nucleaire, qui connaissent bien les donnees experimentales des systemes critiques et peuvent, par le calcul, exploiter cette experience pour resoudre les problemes qui se posent. En ce qui concerne les problemes materiels, ils sont soumis a des groupes de techniciens que l'on met au courant des conditions particulieres qu'imposent les facteurs techniques et qui connaissent bien les limites de fonctionnement de l'installation. Quant aux problemes administratifs, le responsable de la surveillance se charge de les resoudre' en reglementant les activites en consequence. Le service de gestion des matieres nucleaires peut apporter une aide precieuse au responsable de la surveillance. C'est tout d'abord a ce service qu'il incombe d'alerter le

  15. Case Study in Internal Audit of Nuclear Material; Etude d'un Systeme de Verification Comptable Interne des Matieres Nucleaires; Izuchenie primera organizatsii vnutrennego ucheta yadernykh materialov na predpriyatii; Estudio de la Fiscalizacion Interna de los Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kops, S. [United States Atomic Energy Commission, Argonne, IL (United States)

    1966-02-15

    sont generalement les principaux facteurs a considerer lorsque l'on veut determiner s'il y a lieu d'etablir un systeme classique de verification comptable interne. L'auteur analyse les besoins et les caracteristiques d'un systeme de verification comptable interne dans le cas particulier d'une organisation qui manipule des matieres brutes ou des produits fissiles speciaux (matieres nucleaires), en les confrontant a ceux d'un systeme de verification classique. Il montre comment, etant donne le prix eleve et la valeur strategique des matieres, il est necessaire d'etablir un systeme special de verification comptable. Le memoire etudie en detail l'organisation du systeme de verification comptable interne dans une installation produisant des matieres nucleaires; il indique notamment comment fixer la date des controles et comment proceder a la verification des livres et inventaires. Il indique egalement la competence et les qualifications professionnelles que doit avoir le personnel charge de la verification comptable, ainsi que les considerations d'ordre statistique a appliquer pour determiner les donnees qui devront faire l'objet d'une verification. Le memoire decrit de facon detaillee la maniere dont ces dispositions sont appliquees dans la pratique de la verification comptable interne. Il indique les modifications qui peuvent etre apportees aux normes etablies ainsi que les differentes manieres d'envisager le probleme de la verification des comptes et montre que, s'il est possible dans le cas d'autres fabrications de proceder simplement a une verification comptable des stocks, il est necessaire dans l'industrie nucleaire de proceder effectivement a l'inventaire materiel du stock. Le memoire presente les divers moyens utilises pour communiquer les resultats de la verification interne. La presentation du rapport comptable et sa teneur sont determinees en fonction des besoins des differents services. Le memoire indique les diverses manieres dont le rapport comptable peut

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  17. Plutonium: resuspension of aerosols in nuclear installations: bibliographic survey; Le plutonium: mise en suspension d'aerosols dans les installations nucleaires: synthese bibliographique

    Energy Technology Data Exchange (ETDEWEB)

    Guetat, Ph; Monfort, M; Armand, P [CEA Bruyeres-le-Chatel, Dept. Analyse Surveillance Environnement, Service Radioanalyse Chimie Environnement, 91 (France); Alloul-Marmor, L [Societe APTUS, 78 - Versailles (France)

    2006-07-01

    This document presents an analysis and a bibliographical synthesis of the studies on resuspension factors for plutonium. It aims at helping the engineers of safety to specify the scenarios of accidents which relate to their activities and to bring elements justified for the definition of their term-source 'installation' in the safety reports of the installations. (authors)

  18. Plutonium: resuspension of aerosols in nuclear installations: bibliographic survey; Le plutonium: mise en suspension d'aerosols dans les installations nucleaires: synthese bibliographique

    Energy Technology Data Exchange (ETDEWEB)

    Guetat, Ph.; Monfort, M.; Armand, P. [CEA Bruyeres-le-Chatel, Dept. Analyse Surveillance Environnement, Service Radioanalyse Chimie Environnement, 91 (France); Alloul-Marmor, L. [Societe APTUS, 78 - Versailles (France)

    2006-07-01

    This document presents an analysis and a bibliographical synthesis of the studies on resuspension factors for plutonium. It aims at helping the engineers of safety to specify the scenarios of accidents which relate to their activities and to bring elements justified for the definition of their term-source 'installation' in the safety reports of the installations. (authors)

  19. Analytic catalog for the use of the nuclear physicists; Repertoire analytique a l'usage des physiciens nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R.; Barloutaud, R.; Bernas, R.; Chaminade, R.; Cohen, R.; Conjeaud, M.; Cotton, E.; Faraggi, H.; Grjebine, T.; Laboulaye, H. de; Lehmann, P.; Leveque, A.; Levi, C.; Moreau, J.; Naggiar, V.; Olkowsky, J.; Papineau, L.; Papineau, L.; Prugne, P.; Schuhl, C.; Szteinsznaider, D.; Tzara, C.; Valladas, G. [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires; Marty, N.; Renard, G. [College de France, Lab. de Chimie Nucleaire (France)

    1952-07-01

    The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of publications, always more numerous and more varied. To remedy to this problem, we tried, at the Nuclear Physics Services of the CEA, to give to the documentation the character of a collective and systematized work. The present report covers the literature appeared between January 1, 1950 and July 1, 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le 1 Janvier 1950 et le 1 Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

  20. Analytic catalog for the use of the nuclear physicists; Repertoire analytique a l'usage des physiciens nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R; Barloutaud, R; Bernas, R; Chaminade, R; Cohen, R; Conjeaud, M; Cotton, E; Faraggi, H; Grjebine, T; Laboulaye, H de; Lehmann, P; Leveque, A; Levi, C; Moreau, J; Naggiar, V; Olkowsky, J; Papineau, L; Papineau, L; Prugne, P; Schuhl, C; Szteinsznaider, D; Tzara, C; Valladas, G [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires; Marty, N; Renard, G [College de France, Lab. de Chimie Nucleaire (France)

    1952-07-01

    The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of publications, always more numerous and more varied. To remedy to this problem, we tried, at the Nuclear Physics Services of the CEA, to give to the documentation the character of a collective and systematized work. The present report covers the literature appeared between January 1, 1950 and July 1, 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le 1 Janvier 1950 et le 1 Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-07-01

    Automation has long been an established feature of power plants. In some applications, the use of automation has been the significant factor which has enabled plant technology to progress to its current state. Societal demands for increased levels of safety have led to greater use of redundancy and diversity and this, in turn, has increased levels of automation. However, possibly the greatest contributory factor in increased automation has resulted from improvements in information technology. Much recent attention has been focused on the concept of inherently safe reactors, which may simplify safety system requirements and information and control system complexity. The allocation of tasks between man and machine may be one of the most critical activity in the design of new nuclear plants and major retro-fits and it therefore warrants a design approach which is commensurate in quality with the high levels of safety and production performance sought from nuclear plants. Facing this climate, in 1989 the International Atomic Energy Agency (IAEA) formed an advisory group from member countries with extensive experience in nuclear power plant automation. The task of this group was to advise on the appropriate balance between manual and automatic actions in plant operation. (author) [French] L'automatisation a longtemps ete une caracteristique bien etablie des centrales nucleaires. Dans certaines applications, l'utilisation de l'automatisation a ete le facteur decisif qui a permis a la technologie des centrales de progresser jusqu'a son etat actuel. Les exigences de l'opinion publique en matiere de securite renforcee ont conduit a l'utilisation d'une plus grande redondance et a une plus grande diversification et ceci, en retour, a encore accru le niveau d'automatisation. Toutefois, il est possible que le facteur preponderant de cet accroissement de l'automatisation soit constitue par les progres effectues dans la technologie de l'information. Plus recemment, l'attention s

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-11-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

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

  4. Installation for Studying the Scattering of Cold Neutrons; Installation pour l'etude de la diffusion des neutrons thermiques; Ustanovka dlya izucheniya rasseyaniya kholodnykh nejtronov; Instalacion para estudiar la dispersion de neutrones frios

    Energy Technology Data Exchange (ETDEWEB)

    Golikov, V V; Shapiro, F L; Shkatula, A; Yanik, E A [Ob' edinennyj institut yadernykh issledovanij, Dubna, Union of Soviet Socialist Republics (Russian Federation)

    1963-01-15

    Using the pulsed fut reactor in the Joint Institute for Nuclear Research, an installation was set up to investigate the spectrometry of cold neutrons. The moderator, adjoining the reactor reflector, and the beryllium filter were at the temperature of liquid nitrogen. The scatterer, located at a distance of about 0. 6 m from the moderator, was irradiated by flashes of cold neutrons, whose duration was determined by the lifetime of the neutrons in the moderator and the dispersion of the times-of-flight over a distance of 0. 6 m. The frequency of the flashes was 8/s. The steep beryllium edge of the spectrum, lying around 200 {mu}s, was used for spectrometry in the quasi-elastic range. The energy of the scattered neutrons was determined by the time-of-flight over the distance between scatterer and detector, which was about 10-40 m. ZnS + 10{sub 2}{sup 10} O{sub 3} scintillation detectors with surfaces of 300 and 2 000 cm{sup 2} were used and the efficiency, for fast neutrons, was about 60%. (author) [French] A l'aide du reacteur a flux pulse de neutrons rapides de l'Institut unifie de recherches nucleaires, les auteurs ont mis au point une installation pour la spectrometrie des neutrons thermiques. Le ralentisseur contigu au reflecteur du reacteur et le filtre deberyllium sont maintenus a la temperature de l'azote liquide. Le diffuseur, place a environ 60 cm du ralentisseur, est irradie par une bouffee de neutrons thermiques dont la duree est determinee par la vie moyenne des neutrons dans le ralentisseur et par l'etalement des temps de vol necessaires pour parcourir la distance de 60 cm. La frequence des bouffees est de 8/s. Pour la spectrometrie dans la region quasi-elastique, on utilise la bande en bordure du spectre qui correspond au beryllium et s'etale sur environ 200 {mu}s. L'energie des neutrons diffuses est determinee par la duree du parcours entre le diffuseur et le detecteur. Les auteurs ont utilise des detecteurs a scintillation a ZnS + 10{sub 2}{sup 10} O

  5. The nuclear installations dismantling and the management of radioactive wastes; Le demantelement des installations nucleaires et la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    As other industrial activities, the nuclear industry causes risks. The risks bound to the dismantling operations are known and controlled. After a presentation of the dismantling and radioactive wastes challenge, this document proposes recommendations based on the first experiences of dismantling and wastes storage. It aims then to answer to the questions relative to the cost and the financing of the operations. Finally it wonders on the public information modalities. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Maragnon, J; Delperie, C

    1967-12-01

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

  7. New Frontiers for Non-Destructive Testing in the Nuclear Age; Perspectives des Essais Non Destructifs a l'Ere Nucleaire; ''Novye rubezhi'' nedestruktivnykh ispytanij v yadernyj vek; Nuevas Posibilidades de los Ensayos No Destructivos en la Era Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ballard, D. W. [Sandia Laboratory Albuquerque, NM (United States)

    1965-10-15

    suitable for remote television displays and recording. Test parameters, display capabilities, and continuous monitoring systems are discussed. These possibilities have. already been demonstrated in laboratory testing and their use must be extended to production testing if a new level of reliability of components in the nuclear industry is to be achieved. (author) [French] On peut attribuer en grande partie l'extraordinaire developpement des essais non destructifs depuis la deuxieme guerre mondiale aux specifications extremement strictes imposees aux materiaux et produits de l'industrie nucleaire. La complexite des installations et de leurs elements et les incidences financieres des arrets de fonctionnement ont atteint des proportions telles qu'il est imperieux de mettre au point des methodes plus efficaces d'essais non destructifs et de les appliquer tout au long de la duree de vie des produits, depuis leur mise en fabrication jusqu'a leur declassement. En meme temps que, pour tenter de satisfaire aux imperatifs techniques de perfection, on developpe considerablement les possibilites offertes par des methodes d'essais confirmees, comme la radiographie, les ultrasons et l'electromagnetisme, on met au point de nouveaux principes d'essais destines expressement au controle des performances statiques et dynamiques. Le memoire porte sur ces methodes particulierement rapides et sensibles qui ouvrent vraiment de nouvelles perspectives aux essais non destructifs. Au nombre des methodes d'essais les plus recentes discutees dans le memoire figure le controle par les infra- rouges de l'integrite des soudures. Le controle cineradiographique des structures au cours des essais de vibration, pour etudier leur comportement dynamique, est egalement traite. La detection des fuites est extremement importante pour assurer la qualite des elements combustibles. Le memoire decrit une methode de controle des elements combustibles sous gaine, qui est fondee sur l'utilisation d'un gaz radioactif et

  8. Study of cartridge rupture detection installations; Contribution a l'etude des installations de detection de ruptures de gaine

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    Very numerous physical or technological parameters are involved in the preparation of projects for can rupture detection installations. These parameters are connected essentially with the design of the reactor, the detector used, the disposition of the pneumatic circuits, the type of fuel and the safety required. The present report analyses the main problems arising and their mutual compatibilities; it defines a certain number of ideas which had up till now been accepted implicitly in the design. (authors) [French] De tres nombreux parametres physiques ou technologiques interviennent dans l'etablissement du projet d'une installation de detection de ruptures de gaines. Ces parametres decoulent essentiellement de la conception de la pile, du detecteur utilise, de l'organisation des circuits pneumatiques, du type du combustible et de la securite souhaitee. Le present document analyse les principaux problemes qui se posent ainsi que leurs compatibilites reciproques et precise un certain nombre de notions jusqu'alors admises implicitement lors de l'etablissement des projets. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  10. La circulation des poissons migrateurs : le transit à travers les turbines des installations hydroélectriques

    Directory of Open Access Journals (Sweden)

    LARINIER M.

    1989-01-01

    Full Text Available La réussite des programmes de restauration des populations de poissons migrateurs (salmonidés, alose... lancés en France ces dernières années nécessite que leur libre circulation soit assurée notamment au niveau des installations hydroélectriques. Lors de la migration d'avalaison, les dommages subis par les juvéniles au cours de leur passage à travers les turbines sont difficilement prévisibles et peuvent se révéler importants. Entre 1984 et 1986, sept expérimentations ont été réalisées en France sur divers types de turbines (FRANCIS, KAPLAN, OSSBERGER, afin de mettre au point un protocole standard d'évaluation des mortalités. Les résultats obtenus lors de ces études ont permis de compléter les données disponibles dans la bibliographie et de réaliser une analyse statistique d'ensemble. Cette analyse a montré que l'importance des dommages est étroitement liée aux caractéristiques de la turbine et à la taille des poissons. Sur les turbines FRANCIS, la mortalité est influencée par des paramètres comme les vitesses absolue et relative en entrée de roue, la vitesse de rotation ainsi que par le rapport taille du poisson à l'espace inter-aubes. Sur les turbines KAPLAN, la mortalité est surtout liée au rapport de la taille du poisson à l'espace inter-pales. Des équations de régression ont été établies qui permettent de prédire l'ordre de grandeur de la mortalité sur ces deux types de turbines pour les salmonidés et les anguillidés.

  11. The health physics of installations for decladding irradiated fuels or for handling radio-elements at Marcoule; La radioprotection des installations de degainage des combustibles irradies et des radio-elements a Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Chassany, J; Guillermin, P; Mallet, P [Commissariat a l' Energie Atomique, Centre de Production de Plutonium de Marcoule, 30 - Chusclan (France)

    1966-07-01

    Radiation protection practices for handling reactor fuel elements are described. Elements of considerable specific radioactivity are handled under water. A study was made of water filtration and of ventilation in the building. The installations are divided up into zones depending on the radioactive risks, and the radiation level atmospheric contamination are the object of a systematic control at various points. A description is given of all aspects of health physics which have been encountered during six years: storage, transfer of radioactive material; decladding, rolling, waste disposal, specialized operations, installations in operation and at rest, and transport. In spite of the gradual increase in the activity of these installations, the total doses received by the personnel have hardly altered and the number of cases of physical contamination has diminished. (authors) [French] Dans ces installations, se manipulent sous l'eau des elements a radioactivite specifique considerable. La filtration de l'eau, la ventilation ont ete particulierement etudiees. L'ensemble a ete divise en lieux classes en fonction des risques radioactifs et des appareils controlent en permanence l'irradiation et la contamination atmospherique en certains points. Tous les aspects de la radioprotection resultant de six annees d'experience relatifs: au stockage, au deconteneurage, au degainage, au laminage, a l'evacuation des residus, aux travaux particuliers, installations en marche et a l'arret, et aux transports sont successivement decrits. Malgre l'accroissement progressif de l'activite de cet ensemble, les doses integrees par le personnel n'ont pratiquement pas augmente et le nombre des cas de contamination corporelle a diminue. (auteurs)

  12. Contrôle des installations d’assainissement non collectif : l’apport déterminant des outils de diagnostic non destructifs

    Directory of Open Access Journals (Sweden)

    FORQUET, Nicolas

    2012-12-01

    Full Text Available Depuis juillet 2012, un nouveau cadre juridique s’applique aux installations d’assainissement non collectif, visant à améliorer leur contrôle et leur rénovation progressive. Cette note nous présente une méthodologie de contrôle simplifié des installations élaborée grâce l’apport déterminant des outils de diagnostic non destructifs.

  13. Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Chooz - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  14. Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Flamanville - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

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

  16. Physics of phenomena in the zone close to an underground nuclear explosion; Physique des phenomenes en zone proche des explosions nucleaires souterraines

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    After a description of the phenomenology of underground explosions, the basic laws governing the propagation in the ground of the energy produced by the explosion are given. The reports considers hydrodynamics, the mechanics of solids, the equations of state for solids and gases in the case of very high and medium pressures, and the dynamical strength of solids. These various elements make it possible to draw up a system of equations which define completely the changes with time of the shock-wave produced in the ground by the explosion. (authors) [French] Apres une description de la phenomenologie des explosions souterraines, on expose les lois fondamentales regissant la propagation dans le sol de l'energie degagee par l'explosion. L'expose comprend des developpements sur l'hydrodynamique, la mecanique des solides, les equations d'etat des solides et des gaz, aux tres fortes et moyennes pressions, et sur la resistance dynamique des solides. Ces differents elements permettent d'ecrire un systeme d'equations qui definissent completement l'evolution dans le temps de l'onde de choc emise dans le sol par l'explosion. (auteurs)

  17. Physics of phenomena in the zone close to an underground nuclear explosion; Physique des phenomenes en zone proche des explosions nucleaires souterraines

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    After a description of the phenomenology of underground explosions, the basic laws governing the propagation in the ground of the energy produced by the explosion are given. The reports considers hydrodynamics, the mechanics of solids, the equations of state for solids and gases in the case of very high and medium pressures, and the dynamical strength of solids. These various elements make it possible to draw up a system of equations which define completely the changes with time of the shock-wave produced in the ground by the explosion. (authors) [French] Apres une description de la phenomenologie des explosions souterraines, on expose les lois fondamentales regissant la propagation dans le sol de l'energie degagee par l'explosion. L'expose comprend des developpements sur l'hydrodynamique, la mecanique des solides, les equations d'etat des solides et des gaz, aux tres fortes et moyennes pressions, et sur la resistance dynamique des solides. Ces differents elements permettent d'ecrire un systeme d'equations qui definissent completement l'evolution dans le temps de l'onde de choc emise dans le sol par l'explosion. (auteurs)

  18. Maintenance des équipements de transport pour l'installation des cryo-aimants dans le tunnel LHC

    CERN Document Server

    Chevalley, JM

    2005-01-01

    Le transport et l’installation de quelque 1800 cryo-aimants dans le tunnel LHC seront réalisés à l’aide d’équipements de transport et de manutention de haute technologie spécialement développés par le groupe TS-IC. La section HM devra assurer la maintenance de toute cette chaîne d’équipements : le pont roulant pour la descente des cryo-aimants dans le tunnel LHC, les véhicules de transport spéciaux alimentés dans le tunnel par la gaine monorail et enfin les tables de transfert utilisées pour la mise en place finale des cryo-aimants sur leurs vérins. Dans ce cadre, plusieurs aspects seront développés dans ce document : la mise en place et l’organisation de la maintenance, l’analyse des modes de défaillance et de leur criticité (AMDEC), les différentes méthodes possibles pour la recherche et résolution des pannes, ainsi que le suivi du projet, et ce dans le but de fiabiliser et d†™assurer le bon fonctionnement de t...

  19. Status of safety at Areva group facilities. 2007 annual report; Areva, etat de surete des installations nucleaires. Rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.

  20. Dismantling of nuclear facilities: the industrial know-how; Demantelement des installations nucleaires: les voies de la maitrise industrielle

    Energy Technology Data Exchange (ETDEWEB)

    Lellament, R. [Societe Francaise d' Energie Nucleaire (SFEN), Groupe de Reflexion Energie/Environnement, 75 - Paris (France)

    2004-11-01

    Numerous nuclear facilities in laboratories or research reactors have been decommissioned and dismantled over the 2 last decades throughout the world. The valuable feedback experience has allowed nuclear industry to design, upgrade and test specific techniques for dismantling. These techniques are efficient although they have been validated on a reduced number of nuclear power plants. In France only 3 power units have been dismantled: Chinon A1, A2 and Brennilis (EL4) and they are not representative of the real park of EDF'reactors. 6 PWR-type reactors have already been dismantled in the Usa. The results of a survey concerning 26 countries shows that the dismantling cost is around 320 dollars/kWe, it represents 15% of the construction cost which is far from being excessive as it is often read in the media. The dismantling costs can be broken into: - de-construction (25-55%), - wastes from dismantling (17-43%), - security and monitoring (8-13%), - site reclamation (5-13%), and - engineering and project management (5-24%). (A.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-02-15

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

  2. Installation of cooling floors at the ``La Fayette`` shopping mall; Inbetriebnahme des Kuehldeckensystems im ``La Fayette``

    Energy Technology Data Exchange (ETDEWEB)

    Ostermann, M.; Schulte, M.

    1997-02-01

    The ``La Fayette`` shopping mall on the Friedrichstrasse in central Berlin was inaugurated in February 1996. Apart from the shopping center, the building has 7 upper storeys with offices which are served by a ventilation system and a system of cooling floors. The building and its installations are described in some detail. (orig.) [Deutsch] Das Gebaeude Galerie `La Fayette` entstand im Zentrum Berlins an der Friedrichstrasse und wurde Ende Februar 1996 eroeffnet. Ausserhalb des Kaufhausbereichs dieser Galerie befinden sich in den sieben Obergeschossen Buerobereiche, die durch eine Lueftungsanlage und ein Kuehldeckensystem versorgt werden. Die Anlage wird in diesem Beitrag naeher beschrieben. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

  6. Élaboration et gestion des plans d'installation de la machine LHC

    CERN Document Server

    Corso, Jean Pierre

    2005-01-01

    Remplir 27 km de l’étroit tunnel du LEP avec plusieurs milliers d’équipements est le défi posé par le LHC et à relever par les techniciens et ingénieurs du CERN. Le LEP avait initié ce concept avec un outil nommé LEGO ; Le LHC a encore franchi une étape avec DMU (Digital Mock-Up), en tirant profit de l’évolution significative des outils informatiques (langages de programmation et logiciels). Utilisé comme interface entre une base de données Oracle® regroupant toutes les informations sur chaque équipement et les modèles 3D standard correspondants issus d’Euclid®, DMU a étendu, depuis, son champ d’application en permettant dorénavant de générer automatiquement tous les plans d’installation des 514 demi cellules de la Machine. Les évolutions futures de la configuration du LHC nous conduiront à modifier ou déplacer les équipements en place et à en insérer de nouveaux. Ceux-ci seront introduits dans la base de données avant de pouvoir être restitués via DMU sous forme de pl...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Ryabukhina, Yu. S.

    1963-11-15

    . On a etudie le comportement de deux alliages eutectiques de l'indium en presence de certains materiaux de construction; la premiere installation a ndium-gallium est entree en service au debut de 1960. Des travaux ulterieurs ont permis d'equiper le reacteur IRT de l'Academie des sciences de Georgie d'une boucle modele permettant d'obtenir dans le.canal d'irradiation une activite maximum equivalent a environ 100 g de radium, et d'installer une boucle d'essai a indium-gallium-etain dans le canal du reacteur IRT appartenant a l'Institut de l'energie atomique de l'Academie des sciences de l'URSS. Enfin, en 1962, une boucle a indium - gallium - etain a ete mise en service dans le reacteur IRT de l'Academie des sciences de Lituanie, en vue d'executer des irradiations a une echelle semi-industrielle. Son activite maximum atteignait, dans le dispositif d'irradiation, un niveau equivalent a 30 000 g de radium. Le memoire se compose des quatre parties suivantes: 1. ''Calcul des boucles d'irradiation''; les auteurs generalisent les resultats des travaux sur les methodes de calcul des boucles d'irradiation. 2. ''Modele d'une boucle d'irradiation a indium-gallium pour le reacteur IRT-2000 de Tbilisi''; les auteurs decrivent le fonctionnement de la boucle. 3. ''Boucle d'irradiation a indium-gallium-etain du reacteur nucleaire IRT de l'Academie des sciences de Lituanie''; les auteurs decrivent le fonctionnement de la boucle. 4. des boucles d'irradiation''; les auteurs decrivent des experiences, donnent des schemas et indiquent les calculs sur la base desquels il devient possible-de construire des boucles a manganese solide et des boucles utilisant des alliages liquides d'indium. (author) [Spanish] Desde 1957 se vienen realizando en la Union Sovietica estudios sobre la construccion de circuitos de irradiacion. Se idearon metodos de calculo de tales sistemas y se averiguaron las posibilidades que ofrecen los distintos portadores gamma. En

  9. Economic study of an installation for uranium isotope separation by gaseous diffusion; Etude economique d'une installation de separation des isotopes de l'uranium par diffusion gazeuse

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    This report describes the major problems which arise in the choice of characteristics required in a gaseous diffusion installation for the separation of uranium isotopes. This choice depends largely on economic evaluations, and also on considerations of simplicity. The choice of working pressures and of the characteristics of the membrane are described, as are the possible alternatives regarding the structure of the stages and the problems of control. (author) [French] Ce rapport decrit les problemes majeurs qui se posent dans le choix des caracteristiques d'une installation de diffusion gazeuse destinee a la separation des isotopes de l'uranium. Ce choix depend en grande partie d'evaluations economiques et repose egalement sur des considerations de simplicite. On decrit ainsi le choix des pressions d'operation, celui des caracteristiques de la barriere, les alternatives possibles concernant la structure des etages et les problemes de regulation. (auteur)

  10. Basis of conception for emergency plans of fuel cycle installations; Bases de conception des plans particuliers d`intervention des installations du cycle du combustible

    Energy Technology Data Exchange (ETDEWEB)

    Charles, T.; Mercier, J.P. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Dept. d`Evaluation de Surete; Rzepka, J.P.; Dubiau, P.; Jouve, A.C. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Dept. de Protection de l`Environnement et des Installations

    1994-12-31

    In this text we give the principles on which the fuel cycle installations emergency plans are based. The bases are the inventory of toxic and radioactive materials contained in the installation, the credible accident and the source term, the atmospheric diffusion. On these terms the risk for population is evaluated and relocation or confinement of population is taken.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-11-15

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

  12. The Management of Nuclear Materials in a Research Establishment; Gestion des Matieres Nucleaires dans un Centre de Recherche; Uchet yadernykh materialov v nauchno-issledovatel'skom uchrezhdenii; Administracion de Sustancias Nucleares en un Centro de Investigaciones

    Energy Technology Data Exchange (ETDEWEB)

    Wright, W. J.; Hocking, D. R. [Australian Atomic Energy Commission Research Establishment, Lucas Heights, NSW (Australia)

    1966-02-15

    The functions of a nuclear materials management scheme are reviewed in relation to the activities of research establishments. Since these activities are normally non-repetitive, there is little opportunity to establish statistical quality and quantity control. The risks of an error in the material accounts must therefore be established from relatively few analytical measurements and the implications of this are discussed. Similar arguments are applied to illustrate the difficulties of quality control on suppliers when a large variety of materials are being purchased in small quantities. (author) [French] Les auteurs examinent le role d'un systeme de gestion des matieres nucleaires applique aux activites des centres de recherche. Comme ces activites ne sont normalement pas appelees a se repeter, il n'est guere possible d'organiser un controle statistique quantitatif et qualitatif. Il faut donc determiner les possibilites d'erreurs dans la comptabilite matieres en s'appuyant sur un nombre relativement restreint de mesures analytiques et les auteurs examinent les conclusions a tirer de cette situation. Ils recourent a une argumentation analogue pour illustrer les difficultes inherentes au controle de la qualite des matieres livrees par les fournisseurs lorsqu'il doit porter sur une grande diversite de matieres en petites quantites. (author) [Spanish] Los autores examinan el funcionamiento de un sistema de administracion de materiales nucleares en relacion con las actividades de los centros de investigaciones. Como estas actividades son por lo comun muy diversas, hay pocas oportunidades de establecer un control estadistico de la calidad y la cantidad. Por ello es necesario determinar los riesgos de error en la contabilidad de los materiales partiendo de un numero relativamente reducido de mediciones analiticas; en la memoria se examinan las consecuencias de este hecho. Los autores aplican razonamientos analogos para poner de manifiesto las dificultades con que, en el

  13. Behaviour of semiconductor nuclear-particle detectors; Comportement des semi-conducteurs comme detecteurs de particules nucleaires; Povedenie detektorov yadernykh chastits na poluprovodnikakh; Propiedades de los detectores de particulas nucleares a base de semiconductores

    Energy Technology Data Exchange (ETDEWEB)

    Walter, F J; Dabbs, J W.T.; Roberts, L D [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-04-15

    . Matched expansion-coefficient fabrication techniques which have been successfully used to make detectors up to 8 cm{sup 2} in active area are also described. (author) [French] Les auteurs ont fait des etudes theoriques et experimentales sur le comportement des semi-conducteurs comme detecteurs de particules nucleaires a des temperatures allant de 0,2{sup o} K a 300{sup o} K. Ils presentent un modele theorique simple du comportement du detecteur qui correspond au comportement observe pour toute une gamme de valeurs des parametres. Ils examinent quelle est l'importance de la purete du semi-conducteur et de la tension de polarisation en ce qui concerne l'amplitude de l'impulsion, le temps de montee de l'impulsion et la surface du detecteur. Des etudes empiriques sur le bruit et la resolution en energie montrent que, pour des particules alpha, les plus petites largeurs de crete observees sont tres nettement plus importantes que les largeurs que l'on avait prevues en tenant compte du bruit d'origine electrique provenant du detecteur et de l'amplificateur. A 77{sup o}K, on a releve pour un detecteur a barriere de surface au silicium, d'une surface de 40 mm{sup 2}, des intensites de bruit equivalant a {<=} 3 keV (largeur totale a mi-hauteur du maximum). Les semi-conducteurs presentent un a l'egard des fragments de fission. On a tout lieu de penser que ce defaut n'est pas du a une . Si des champs electriques insuffisants pour assurer une complete sont la cause de ce defaut, le gradient de champ necessaire (a la surface) est superieur a 3 {center_dot} 10{sup 4} V/cm dans le cas de fragments de fission contre 2 {center_dot} 10{sup 3} V/cm dans le cas de particules alpha de Ge et de Si. Des etudes detaillees sur le temps de montee des impulsions au niveau de l'amplificateur ont montre que pour des substances de grande resistivite le temps de relaxation dielectrique et la resistance propres aux substances de base non appauvries peuvent

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-05

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

  15. Comparative Studies of Chemical Effects following Nuclear Reactions and Transformations on Metal Organic Phenyl Compounds; Etudes Comparatives des Effets Chimiques Induits par les Reactions et les Transformations Nucleaires sur des Composes Phenylmetalliques; 0421 0420 0410 0414 ; Estudios Comparativos de los Efectos Quimicos de las Reacciones y Transformaciones Nucleares en Compuestos Fenil-Organometalicos

    Energy Technology Data Exchange (ETDEWEB)

    Merz, E.; Riedel, H. J. [Kernforschungsanlage, Juelich, Federal Republic of Germany (Germany)

    1965-04-15

    molecule by the nuclear recoil and the resulting excitation. The hypothesis is put forward that the kind and quantity of certain new radioactive species produced in connection with nuclear events is less a function of the nature and concentration of primary recoil fragments than are the ions, radicals and lattice defects imparted to the irradiated materials by secondary recoil effects (elastic and inelastic interactions) , including the peculiar influence of oxygen. (author) [French] Les auteurs ont etudie les effets chimiques provoques par les atomes chaud de recul resultant des reactions nucleaires dans les solides et dans les liquides en se fondant sur une vaste comparaison des produits des processus (n,{gamma}) et (n,2n) dans les composes phenyles du germanium, de l'etain, du plomb, de l'arsenic et de l'antimoine. En outre, ils ont compare les produits de recul radioactifs formes apres capture K dans le tetraphenyl- germanium-{sup 68}Ge avec les resultats du processus (n,{gamma}) dans le triphenylgalliumet du processus (n,p) sur le tetraphenylgermanium. Enfin, ils ont etudie la transition {beta}{sup -} dans laquelle {sup 77}Ge est remplace par {sup 77}As dans le compose. En appliquant differentes methodes de separation, par exemple la chromatographie d'adsorption sur alumine, l'echange d'ions et l'electrophorese, ils ont separe les divers produits de recul radioactifs et determine les rendements individuels. Ils ont constate que, dans les reactions nucleaires, les composes des metaux cites ayant des coordinats identiques forment pratiquement les memes classes.de produits de recul. Toutefois, pour la distribution des rendements, il y a des differences caracteristiques entre la reaction (n,{gamma}) et la reaction (n,2n). L'influence sur les rendements est a peine perceptible lorsque les irradiations ont lieu dans des liquides ou des solutions. Mais les differences trouvees pour les nouveaux composes formes par des transformations nucleaires sont frappantes, en ce qui

  16. The System for Controlling Source and Special Nuclear Material at the Eurochemic Reprocessing Plant; Systeme de Controle des Matieres Nucleaires Brutes et Speciales a l'Usine de Traitement D'Eurochemic; Sistema kontrolya nad iskhodnym i spetsial'nym yadernym materialom na zavode evrokhimicheskoj kompanii po regeneratsii yadernogo topliva; Control de Materiales Nucleares Basicos y de Materiales Fisionables Especiales en la Planta de Regeneracion de la Eurochemic

    Energy Technology Data Exchange (ETDEWEB)

    Frenzel, W.; Schueller, W. [EUROCHEMIC, MOL (Belgium)

    1966-02-15

    Eurochemic is constructing a reprocessing plant near Mol (Belgium). The main characteristics of the plant and the different process steps are summarized. To maintain proper control of source and special nuclear material, the facilities of the company are divided into material balance areas. All transfers into and out of these areas are determined. Depending on their significance for the overall material balance, different precision requirements have been established according to a scale of significance which is briefly discussed. To adjust the book balance, physical inventories are periodically performed. The corresponding inventory procedures are outlined. The books used for nuclear materials accounting and the principles of the accounting system are summarized. (author) [French] La societe Eurochemic fait actuellement construire une usine de traitement chimique pres de Mol (Belgique). L'auteur indique succinctement les principales caracteristiques de l'usine et les differentes etapes du traitement. Pour assurer un controle correct des matieres nucleaires brutes et speciales, les installations d'Eurochemic sont divisees en secteurs de mesures. Tous les transferts entre ces secteurs de mesure sont determines quantitativement. Les mesures sont faites avec des degres de precision differents qui ont ete fixes en fonction de leur importance pour le bilan matieres general; les auteurs examinent brievement les criteres appliques a cette fin. Pour verifier le bilan, on procede periodiquement a des inventaires materiels. La facon dont sont menes ces inventaires est exposee dans ses grandes lignes. Les auteurs indiquent les livres utilises pour la comptabilite des matieres nucleaires et resument les principes du systeme comptable. (author) [Spanish] La compania Eurochemic esta construyendo una planta de regeneracion en Mol (Belgica). Los autores resumen las principales caracteristicas de la instalacion, y las distintas fases del proceso industrial. Para mantener un control

  17. Improvement of the greenhouse effect accounting of the waste storage installations; Ameliorer le bilan effet de serre des installations de stockage des dechets

    Energy Technology Data Exchange (ETDEWEB)

    Couturier, Ch.

    2003-07-01

    The wastes storage installations are responsible of 3 to 4 % of the greenhouse gases emissions in France and Europe. In spite of the decrease since ten years of the emissions hopeful the gas collect on the main sites, it is still possible to improve the greenhouse gases emission in the wastes disposals. The possible measures are presented: the bio-reactor, the improvement of the gas extraction systems, the choice of exploitation modes to limit the fill in times, the biogas valorization. (A.L.B.)

  18. Health physics problems in the context of the development of industrial uses of nuclear energy; Les problemes de radioprotection devant le developpement de l'utilisation industrielle de l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    fate of radioactive ions in the hydrosphere may be determined. - experiments and studies linked with the possibilities for disposal a underground storage of wastes. All these studies cover a complementary field, that of radioprotection, which forms the necessary link between nuclear safety proper, which concerns the actual operation of nuclear installations and medical supervision which directly concerns the health of the individual and the population. At the same time each one of the Health Physics disciplines possesses an independence which increases their efficiency on the safety level. (authors) [French] Le developpement de l'utilisation industrielle de l'energie nucleaire a mis l'accent sur la necessite de promouvoir une doctrine rationnelle et coherente en matiere de securite des installations atomiques et plus particulierement en matiere de securite des sites nucleaires. Le but principal de la securite est de diminuer, voire d'annuler les risques d'irradiation ou de contamination des travailleurs et de la population, consecutifs au fonctionnement normal ou accidentel des installations. La securite est obtenue par la mise en oeuvre d'un ensemble complexe de moyens. Parmi ces moyens les auteurs considerent essentiellement ceux qui presentent une certaine independance a l'egard du type d'installation: moyens d'alerte et de mesure et leur mise en oeuvre - preparation psychologique et technique des individus - evaluation de la capacite d'un site a absorber les rejets radioactifs sans dommage pour la population. Il est clair en effet que les consequences d'un accident sont diminuees par l'augmentation de la valeur des moyens de surveillance, de mesure et d'alerte, l'elevation du niveau technique et l'entrainement du personnel, l'education de la population. Ceci est particulierement vrai aupres d'une installation nucleaire ou l'etude des dangers presente un caractere abstrait et

  19. Health physics problems in the context of the development of industrial uses of nuclear energy; Les problemes de radioprotection devant le developpement de l'utilisation industrielle de l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    fate of radioactive ions in the hydrosphere may be determined. - experiments and studies linked with the possibilities for disposal a underground storage of wastes. All these studies cover a complementary field, that of radioprotection, which forms the necessary link between nuclear safety proper, which concerns the actual operation of nuclear installations and medical supervision which directly concerns the health of the individual and the population. At the same time each one of the Health Physics disciplines possesses an independence which increases their efficiency on the safety level. (authors) [French] Le developpement de l'utilisation industrielle de l'energie nucleaire a mis l'accent sur la necessite de promouvoir une doctrine rationnelle et coherente en matiere de securite des installations atomiques et plus particulierement en matiere de securite des sites nucleaires. Le but principal de la securite est de diminuer, voire d'annuler les risques d'irradiation ou de contamination des travailleurs et de la population, consecutifs au fonctionnement normal ou accidentel des installations. La securite est obtenue par la mise en oeuvre d'un ensemble complexe de moyens. Parmi ces moyens les auteurs considerent essentiellement ceux qui presentent une certaine independance a l'egard du type d'installation: moyens d'alerte et de mesure et leur mise en oeuvre - preparation psychologique et technique des individus - evaluation de la capacite d'un site a absorber les rejets radioactifs sans dommage pour la population. Il est clair en effet que les consequences d'un accident sont diminuees par l'augmentation de la valeur des moyens de surveillance, de mesure et d'alerte, l'elevation du niveau technique et l'entrainement du personnel, l'education de la population. Ceci est particulierement vrai aupres d'une installation nucleaire ou l'etude des dangers presente un caractere abstrait et ou les moyens technologiques de protection sont multiples et complexes. Les etudes de

  20. The origin of cholesterol in chyle demonstrated by nuclear indicator methods; Origines du cholesterol du chyle mises en evidence par la methode des indicateurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Vyas, M

    1962-07-01

    In order to obtain information about the mechanism of the intestinal absorption of cholesterol, rats having a lymphatic abdominal fistula are used. The animals receive either 4-{sup 14}C- cholesterol subcutaneously or orally, or the 1-{sup 14}C acetate. The study of the specific radio-activities of the cholesterol in chyle, in serum, in the lining, and in the intestinal contents makes it possible to define the roles played by the transfer cholesterol from the serum, by the cholesterol synthesised intestinally, and by the absorption cholesterol, in the formations of the lymph and of the chylomicrons. A new theory is proposed for the mechanism of cholesterol absorption. (author) [French] Pour obtenir des renseignements concernant le mecanisme de l'absorption intestinale du cholesterol, on utilise des rats porteurs d'une fistule lymphatique abdominale. Les animaux recoivent soit du cholesterol 4-{sup 14}C par voie sous-cutanee ou par voie orale, soit de l'acetate 1-{sup 14}C. L'etude des radioactivites specifiques du cholesterol du chyle, du serum, de la paroi et du contenu intestinal permet de preciser les roles joues par le cholesterol de transfert d'origine serique, par le cholesterol de synthese intestinale et par le cholesterol d'absorption, dans la formation de la lymphe et des chylomicrons. Une theorie nouvelle concernant le mecanisme de l'absorption du cholesterol est proposee. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

  2. Contribution to the study of molecular movements in cyclohexane by electron spin resonance and electron-nuclear double resonance using a radical probe; Contribution a l'etude des mouvements moleculaires dans le cyclohexane par resonance paramagnetique electronique et double resonance electronique-nucleaire a l'aide d'une sonde radicalaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Solutions of stable free radicals of the nitroxide type have been studied as a function of temperature. In the plastic or globular state, the cyclohexane molecules have rapid rotational and diffusional movements. They transmit this movement to dissolved free radicals. Conversely, measurements by electron spin resonance of the absolute movement of the radicals, and by electron nuclear double resonance of their movement relative to the cyclohexane molecules give very precise methods for local analyses of the movement present in the cyclohexane matrix. The principle of these techniques makes up the 'radical probe method'. (author) [French] Des solutions de radicaux libres stables, du type nitroxyde dans le cyclohexane ont ete etudiees, en fonction de la temperature. Les molecules de cyclohexane, dans l'etat plastique ou globulaire, sont animees de mouvements rapides de rotation sur elles-memes et de diffusion. Elles transmettent leur mobilite aux radicaux libres dissous. Reciproquement, la mesure du mouvement absolu des radicaux, a l'aide de la resonance paramagnetique electronique, et celle du mouvement relatif des radicaux et des molecules de cyclohexane par double resonance electronique-nucleaire, constituent des methodes tres precises pour analyser localement les mouvements presents dans la matrice de cyclohexane. Ce principe et ces techniques constituent la 'methode de la sonde radicalaire'. (auteur)

  3. Contribution to the study of molecular movements in cyclohexane by electron spin resonance and electron-nuclear double resonance using a radical probe; Contribution a l'etude des mouvements moleculaires dans le cyclohexane par resonance paramagnetique electronique et double resonance electronique-nucleaire a l'aide d'une sonde radicalaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Solutions of stable free radicals of the nitroxide type have been studied as a function of temperature. In the plastic or globular state, the cyclohexane molecules have rapid rotational and diffusional movements. They transmit this movement to dissolved free radicals. Conversely, measurements by electron spin resonance of the absolute movement of the radicals, and by electron nuclear double resonance of their movement relative to the cyclohexane molecules give very precise methods for local analyses of the movement present in the cyclohexane matrix. The principle of these techniques makes up the 'radical probe method'. (author) [French] Des solutions de radicaux libres stables, du type nitroxyde dans le cyclohexane ont ete etudiees, en fonction de la temperature. Les molecules de cyclohexane, dans l'etat plastique ou globulaire, sont animees de mouvements rapides de rotation sur elles-memes et de diffusion. Elles transmettent leur mobilite aux radicaux libres dissous. Reciproquement, la mesure du mouvement absolu des radicaux, a l'aide de la resonance paramagnetique electronique, et celle du mouvement relatif des radicaux et des molecules de cyclohexane par double resonance electronique-nucleaire, constituent des methodes tres precises pour analyser localement les mouvements presents dans la matrice de cyclohexane. Ce principe et ces techniques constituent la 'methode de la sonde radicalaire'. (auteur)

  4. Modélisation, simulation et contrôle des installations cryogéniques du CERN

    CERN Document Server

    Bradu, Benjamin; Gayet, P

    2010-01-01

    Cette thèse présente le développement d'un simulateur de processus cryogéniques de grande taille appliqué aux installations cryogéniques de l'accélérateur de particules LHC (Large Hadron Collider) au CERN (Organisation Européenne pour la Recherche Nucléaire). Ce simulateur est basé sur une approche de modélisation orientée objet où chaque équipement (échangeur, turbine, compresseur, etc.) est représenté à partir d'un ensemble d'équations physiques algébro-différentielles. L'architecture de contrôle du CERN est également simulée en intégrant le contrôle réalisé par des automates programmables (PLC) avec le système de supervision. Ce simulateur à été développé pour servir différents desseins comme l'entraînement des opérateurs, la vérification des programmes automates (virtual commissioning) et l'optimisation des stratégies de contrôle. Le système cryogénique d'un détecteur de particules (CMS) a d'abord été simulé pour valider les modèles, puis un liquéfacteur d'...

  5. Validity of the electrical model representation of the effects of nuclear magnetic resonance (1961); Validite de la representation par modele electrique des effets de resonance magnetique nucleaire (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    When studying the behaviour of a magnetic resonance transducer formed by the association of an electrical network and of a set of nuclear spins, it is possible to bring about a representation that is analytically equivalent by means of an entirely electrical model, available for transients as well as steady-state. A detailed study of the validity conditions justifies its use in most cases. Also proposed is a linearity criterion of Bloch's equations in transient state that is simply the prolongation of the well-known condition of non-saturation in the steady-state. (author) [French] L'etude du comportement d'un transducteur a resonance magnetique forme de l'association d'un reseau electrique et d'un ensemble de noyaux dotes de spin, montre qu'il est possible d'en deduire une representation analytiquement equivalente au moyen d'un modele entierement electrique utilisable pour un regime transitoire aussi bien que pour un regime permanent. Une etude detaillee des conditions de validite permet d'en justifier l'emploi dans la majorite des cas. On propose enfin un critere de linearite des equations de Bloch en regime transitoire, qui constitue un prolongement de la condition connue de non-saturation en regime stationnaire. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-10-01

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

  8. L'évolution des messages publicitaires des entreprises financières installées en Equateur

    Directory of Open Access Journals (Sweden)

    1993-01-01

    Full Text Available L'analyse des messages publicitaires insérés dans la presse écrite et télévisée par les institutions financières de 1960 à 1991 permet d'approcher l'influence socio-culturelle de ce secteur de l'économie sur les modes de vie des strates aisées et moyennes de la population équatorienne à partir de l'exemple quiténien. Si le message a vu son support évoluer depuis trois décennies (dessin dans les années soixante, photographie durant les années soixante- dix puis images de synthèse au cours des années quatre- vingt, son image projetée se caractérise par une relative continuité thématique. Toutefois, il semble que les campagnes publicitaires financières délaissent progressivement les éléments importés et intègrent (« récupèrent » ? des caractères régionaux ou nationaux. Enfin, si dans les années soixante le système financier avait recours à un langage spécifique, il s'oriente aujourd'hui vers l'utilisation de symboles et d'éléments écrits ou visuels qui sont tout à fait intégrés à la mondialisation de la communication. LA EVOLUCIÓN DE LOS ANUNCIOS PUBLICITARIOS DE LAS EMPRESAS FINANCIERAS RADICADAS EN EL ECUADOR: UN INDICADOR DE LA MUNDIALIZACIÓN DE LA COMUNICACIÓN (1960- 1991. El análisis de los anuncios publicitarios que transmitieron las instituciones financieras por la prensa (diarios y televisión desde 1960 hasta 1991 permite enfocar la influencia sociocultural de esta área de la economía sobre los modos de vida de las categorías pudientes y medianas de la población ecuatoriana a partir del ejemplo quiteño. Si el soporte del mensaje ha cambiado rápidamente desde tres décadas (dibujo en los años sesenta, fotografía durante los años setenta e imágenes producidas a partir de computadora en el transcurso de los años ochenta, su imagen proyectada se caracteriza por una relativa continuidad temática. Sin embargo, las campañas publicitarias financieras dejan paulatinamente de lado los

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

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

  10. Contribution to the study of deformed heavy nuclei by means of nuclear reactions; Contribution a l'etude des noyaux lourds deformes au moyen de reactions nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-06-01

    The experimental results obtained in the study of the (d,p) reactions, at E{sub d} = 12 MeV, on the three even-even deformed nuclei {sup 170}Yb, {sup 172}Yb and {sup 174}Yb have been analysed in terms of DWBA calculations. The spectroscopic information relative to the odd final nuclei have been compared with the predictions of the collective model and of the Nilsson's model. The effect of various parameters used in the DWBA analysis (form factors, optical wave functions) has been carefully studied. The observed differences between the three final nuclei are qualitatively reproduced in the experimental study of resonances, seen in excitation functions of elastically and inelastically scattered protons on the same target nuclei, and corresponding to analogue states in the three nuclei {sup 171}Lu, {sup 173}Lu and {sup 175}Lu. (author) [French] Les resultats experimentaux de l'etude des reactions (d.p) a E{sub d} = 12 MeV, sur les noyaux deformes pairs-pairs {sup 170}Yb, {sup 172}Yb et {sup 174}Yb ont ete interpretes dans le cadre de l'approximation de Born des ondes deformees. Les informations spectroscopiques relatives aux noyaux impairs finals ont ete comparees aux predictions du modele collectif et du modele de Nilsson, apres avoir examine avec soin l'influence des differents parametres (facteurs de forme, fonctions d'onde 'optiques') utilises lors de l'analyse. Les differences observees entre les trois noyaux finals sont qualitativement reproduites par les resultats experimentaux de l'etude de resonances dans les fonctions d'excitation de diffusion elastique et inelastique de protons sur les memes noyaux-cibles, lors de la recherche d'etats analogues dans les noyaux {sup 171}Lu, {sup 173}Lu et {sup 175}Lu. (auteur)

  11. The use of tracers in the study of the ionic permeability of the nerve; Utilisation des indicateurs nucleaires dans l'etude de la permeabilite ionique du nerf

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    The use of the radioactive tracers {sup 24}Na and {sup 42}K, and the electrophysiological fine study carried out on the plant Cephalopods nervous cells have made it possible, during ten years, to study the relationships between the electrical phenomena observed during the propagation of the nervous impulse and the ionic movements which occur at the cell membrane between the intra- and extra-cellular media. In the state of rest, the nerve fibres present a certain permeability towards sodium and potassium, a permeability which allows the renewal, from the extra-cellular medium, of the cations contained in the cytoplasm. At the moment of the passage of the nervous impulse, it is possible to demonstrate a temporary increase in the permeability towards the sodium which causes the entry of Na{sup +} ions into the nerve fibre, whilst, a few milliseconds later, the increase in the potassium permeability causes the departure of an equivalent quantity of K{sup +} ions. A recovery phase follows the passage of the nervous impulse, during which the original ionic conditions are re-established. If the potassium movements can be considered as passive, the expulsion of Na{sup +} requires, on the part of the cell, the use of a part of the metabolic energy. (author) [French] L'utilisation des indicateurs radioactifs {sup 24}Na et {sup 42}K, et l'etude electrophysiologique fine realisee sur des cellules nerveuses geantes de Cephalopodes a permis, depuis une dizaine d'annees, d'etudier les rapports entre les phenomenes electriques observes lors de la propagation de l'influx nerveux et les mouvements ioniques qui s'effectuent au niveau de la membrane cellulaire entre milieux intracellulaire et extracellulaire. A l'etat de repos, les fibres nerveuses possedent pour le sodium et le potassium, une permeabilite qui permet le renouvellement, a partir du milieu extracellulaire des cations contenus dans le cytoplasme. Au moment du passage de l'influx nerveux, on peut mettre en evidence une

  12. Modélisation des installations de chauffage à eau chaude. Les économies d’énergie apportées par la mise en place des pompes à vitesse variable

    Directory of Open Access Journals (Sweden)

    Mirela Slavu

    2007-01-01

    Full Text Available L’objectif visé dans cette étude est la définition et la validation des modèles de simulation hydraulique et thermique des installations de chauffage à eau, bitube, à circulation forcée, avec des radiateurs équipés de robinets thermostatiques. Dans l’environnement du logiciel de simulation TRNSYS, le modèle de simulation de l’installation de chauffage, couplé à un modèle représentatif d’un bâtiment multizone, est ensuite utilisé pour évaluer les économies d’énergie apportées par la mise en place des pompes à vitesse variable. L’étude simulée du fonctionnement et des performances est réalisée pour une installation de chauffage d’un petit bâtiment tertiaire qui aboitte des bureaux. Les simulations sont effectuées dans l’ensemble de la saison de chauffage à l’aide de fichiers météorologiques au pas horaire. L’analyse porte principalement sur les économies d’énergie apportées par la mise en place d’une pompe à vitesse variable avec les deux types de réglage (H=const. et H -- proportionnelle.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

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

  14. The evaluation of the nuclear facilities safety at the CEA from 1999 to 2001; Le bilan de la surete des installations nucleaires du CEA du 1999 a 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-11-01

    The aim of this document is the presentation of an evaluation of the problems and the safety methods in the concerned period. The first chapter presents the nuclear safety in the CEA. The second chapter is devoted to the organization and the quality for the safety: liabilities, audits, relations with the safety authorities and with the public. The chapters three and four deal respectively with the methodological and technical abilities supporting the exploitation teams and with the nuclear safety projects. The last chapter presents the experiments and events from 1999 to 2001. (A.L.B.)

  15. Theme day: corrosion and surface treatments in nuclear facilities. Proceedings; Journee Thematique: Corrosion et Traitements de surface dans les Installations Nucleaires. Recueil des presentations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    This document brings together the available presentations given at the theme day organized by the Bourgogne Nuclear Pole on the topic of corrosion and surface treatments in nuclear facilities. Eleven presentations (slides) are compiled in this document: 1 - Introduction - PNB centre of competitiveness and R and D activities (A. Mantovan, PNB); 2 - Corrosion damage (M. Foucault, Areva NP - Centre Technique Le Creusot); 3 - Corrosion mechanisms (R. Oltra, UB-ICB); 4 - Examples of expertise management (C. Duret-Thual, Institut de la corrosion/Corrosion Institute); 5 - General framework of surface treatments (C. Nouveau, ENSAM Cluny Paris Tech); 6 - Surfaces et interfaces characterisation - Part A (C. Langlade, Y. Gachon, UTBM and HEF); 7 - Surfaces et interfaces characterisation - Part B (C. Langlade, Y. Gachon, UTBM and HEF); 8 - Ion beam surface treatment (Y. Le Guellec, Quertech Ingenierie); 9 - Impact surface treatment (G. Saout, Sonats); 10 - Metal oxides Characterisation by US laser (R. Oltra, UB-ICB); 11 - Detection and Characterisation of intergranular corrosion (Y. Kernin, Stephane Bourgois, Areva Intercontrole)

  16. Information note about the protection of nuclear facilities against aircraft crashes; Note d'information sur la protection des installations nucleaires contre les chutes d'avions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight < 5.7 t), the military aircraft, and the commercial aircraft (w > 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

  17. Testing on air cleaning systems: Testing of the components in-place tests; Controle des installations d'epuration de l'air essais de conformite des elements: Tests in situ

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    The reliability of air cleaning systems is dependent on testing they are submitted to. Although in-place tests are the most important as they act as final tests upon achieved plants, component tests are necessary too. They allow detection of defective units before they are installed, partition of unit defects from mounting defects and they are more sensitive. For similar reasons, material teats are most useful. The various tests are described, about aerosol filters for one part, iodine trap for the other. The checked features are: materials nature, units sizes, efficiency, air resistance, flammability, humidity resistance, temperature resistance, adsorbent friability, etc... On iodine trapping systems, small check traps, working by-pass with the main trap are periodically subjected to efficiency test. This control allow to cut down the in-place tests frequency, particularly when poisoning from organic vapours is to be feared. (authors) [French] La surete de fonctionnement des installations d'epuratition de l'air esf fonction des controles auxquels ces installations sont soumises. Si les tests in situ sont les plus importants puisqu'ils constituent le controle final de l'installation terminee, les essais de conformite des elements constitutifs sont egalement necessaires. Ils permettent l'elimination d'elements defectueux avant leur mise en place, la discrimination des defauts du montage de ceux de l'element et sont en outre plus sensibles. De meme, le controle des materiaux constitutifs de l'element s'avere fort utile. On decrit les differents controles, d'une part, pour les fittres a aerosols, d'autre part, pour les pieges a iode. Les caracteristiques verifiees sont: nature des materiaux, dimenesions des elements, efficacite, perte de charge, resistance mecanique, inflammabilite, tenue a l'humidite, tenue a la temperature, resistance au detassement des pieges a iode, friabilite du materiau adsorbant, etc... En ce qui concerne les installations de piegeage d

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The study of defects created in solids by irradiation is of considerable fundamental and practical interest. Low temperature irradiation allows defects to be obtained in their simplest 'primary' state, not being then annihilated or rearranged by thermal motion. In-pile irradiation at low temperature raises a number of technical problems connected to 1) the necessary refrigeration power which may be considerable, 2) chemical processes which may occur under irradiation, 3) the lack of space in a reactor. Furthermore the necessity that all the irradiation and subsequent measurements be done without reheating the samples demands continuous and reliable working of the irradiation device and its being designed so as to permit removal of the samples in the cold condition or their measurement and controlled annealing 'in situ'. The way in which these problems have been solved in Grenoble for irradiation devices at 78 deg. K, 28 deg. K and 4 deg. K in the swimming-pool reactors Melusine and Siloe is described. Some operation results are given about the liquid nitrogen rig, called mark A, which has worked for several years in Melusine. In particular certain observations about chemical reactions which may occur in impure liquid nitrogen under radiation are made. The liquid nitrogen rig, called mark B, which has just been installed in the Siloe reactor, is described with some detail. The essential features of this apparatus are that irradiation can be performed in higher fluxes with it than with the former one, and that its operation is made much easier by a design which allows the samples to be introduced and removed without any disconnection of the apparatus. A liquid hydrogen loop, which has worked for one year in the Melusine reactor, is then analysed. An entirely closed hydrogen refrigerating circuit provides the coldness to the irradiation enclosure, which contains neon. Owing to this solution, the samples may be recovered in the cold condition without hydrogen being

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-05-01

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

  1. Measurement of neutrinos released in nuclear reactors through the Borexino experiment; Mesure des neutrinos de reacteurs nucleaires dans l'experience Borexino

    Energy Technology Data Exchange (ETDEWEB)

    Dadoun, O

    2003-06-01

    The main goal of the Borexino experiment is to measure in real time the solar neutrino flux from the beryllium (Be{sup 7}) line at 862 keV. Beyond this pioneer low energy neutrino detection, Borexino will be able to measure solar neutrinos above the MeV, (B{sup 8} neutrinos and pep neutrinos), nuclear reactor neutrinos (with an average energy of 3 MeV) and the supernova neutrinos (their spectrum goes up to some ten MeV). In this work I mainly focus on the study of the nuclear reactors neutrinos. This field has recently been enriched by the results of the KamLAND experiment, which have greatly improved the determination of the neutrino oscillation parameters. In order to measure these events which are above the MeV, the Borexino collaboration entrusted the PCC group at College de France, with the tasks of developing a fast digit system running at 400 MHz: the FADC cards. The PCC group designed the FADC cards and completed them at the beginning of 2002. The first cards which were introduced in the main electronic acquisition unit allowed us to control their functioning and that of the acquisition software. FADC cards were also installed in the Borexino prototype, CTF. The data are analysed in order to determine a limit to the expected background noise of Borexino in measuring the nuclear reactor neutrinos. (author)

  2. Reducing the electricity consumption of small ventilation installations; Reduktion des Elektrizitaetsverbrauchs von Klein-Lueftungsanlagen - Schlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Furter, R.; Casartelli, E.; Lang, M.

    2010-03-15

    This final report for the Swiss Federal Office of Energy (SFOE) takes a look at how the electricity consumption of small ventilation installations can be reduced. Residential ventilation systems - also known as comfort ventilation systems - have to fulfil demands placed on energy efficiency, comfort and hygiene. The results of exemplary measurements of the electrical power consumption that have been made in order to estimate the current situation of ventilation systems and of air handling units in apartments and single family houses are presented and discussed. Air networks were simulated at nominal air flow with different pressure losses for nine different ventilation units. The most important conclusion of this work is quoted as being that the internal pressure losses of the ventilation units have to be reduced and the design recommendation for the air network has to be reconsidered. Also the authors are of the opinion that hygiene requirements must be more rigorously respected.

  3. Meeting around industrial sites; Concertation autour des sites d'installations industrielles

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, Th. [Centre d' etude sur l' Evaluation de la Protection dans le domaine Nucleaire (CEPN), 92 - Fontenay aux Roses (France); Sene, M. [Groupement de Scientifiques pour l' Information sur l' Energie Nucleaire, 91 - Orsay (France); Melguen, M. [Electricite de France (EDF), 75 - Paris (France); Saint-Raymond, Ph. [Direction Generale de la Surete Nucleaire et de la Radioprotection, 75 - Paris (France); Oudiz, A. [Institut de Radioprotection et de Surete Nucleaire, 92 - Fontenay-aux-Roses (France); Brie, J. [Charente Nature (France); Schmitt, P. [CLS de Fessenheim, 68 (France); Verot, Y [Atofina, 92 -Paris la Defense (France); Quintin, Ch. [DRIRE Rhone Alpes, 69 (France); Dubuis, Th. [Secretariat Permanent pour la Prevention des Pollutions Industrielles, 59 - Dunkerque (France); Adelfa, J.S.; Hocquet, M.P. [CLCV, France (France); Gheerardyn, P. [MEDEF Cote d' Opale (France); Villers, S. [EDA, France (France); Modrzejewski, F. [DRIRE Nord-Pas-de-Calais (France); Gadbois, S.; Heriard-Dubreuil, G. [MUTADIS, 75 - Paris (France); Geismar, N.; Eimer, M. [CLI de Saint-Laurent (France); Andre, S. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France); Vindimian, E. [Institut National de l' Environnement Industriel et des Risques, 60 - Verneuil en Halatte (INERIS) (France); Remond-Gouilloud, M. [Universite Paris-Sorbonne, 75 (France)

    2005-07-01

    Following the research work on the ' stakes in the social dialogue around the follow-up of the nuclear industrial installations ' engaged by the I.R.S.N. in 2000, a seminar was organized on January 21. and 22., 2003 in Ville d Avray. This seminar gathered personalities of different origins (administration, institutional experts, operators, associations, Local Commissions of Information, elected representatives) to discuss and enrich the conclusions of the research work and elaborate collectively a contribution to the current remarks in France on the public debate and the processes of dialogue. The present report establishes the acts of this seminar and redraws all the discussions between the participants. (N.C.)

  4. Challenges for the nuclear safety of the deregulation of electricity markets; Defis pour la surete nucleaire de la dereglementation des marches de l'electricite

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    Eurosafe 2000 was organised around two round tables on the first day and four seminars on the second day. The first round table dealt with general aspects of deregulation including the economic constraints and the special challenges arising during transition from regulated to deregulated structures. The second round table focussed on technical and organisational safety issues which are directly or indirectly related to the changes introduced by deregulation. The four seminars hold in order to provide opportunities for comparing experiences and learning about recent activities of IPSN, GRS and their partners in the European Union and Eastern Europe: Seminar 1 (Nuclear installation safety, assessment and analysis): assessment of the flooding incident at the Blayais nuclear power plant; PSA data base, comparison of the French and German approach; assessment of the Balakovo fire probabilistic study and elaboration of a guide for reviewing fire PSA; comprehensive technical assessment of an advanced German PWR by PSA - objectives and main results; PSA approach for the safety assessment of low-power and shutdown states; correlation of initiating events with the PSA level-2 results; safety assessment for fission products tests in the Phebus reactor; use of NPP simulators for applied human factor studies; assessment of the 'deterministic realistic method' applied to large LOCA analysis; assessment of the feasibility of an improvement programme enabling operation of units 3 and 4 of Kozloduy nuclear power plant. Seminar 2 (nuclear installation safety, research): PHEBUS 2K project on severe accidents; current status of the COCOSYS development; fission product modeling in ASTEC; Euratom Framework Programme (FP) research in reactor safety: main achievements of FP- 4 (1994-1998), some preliminary results of FP-5 (1998-2002) and prospects for beyond 2002; development of coupled systems of 3D neutronics and fluid-dynamic system codes and their application for safety analyses

  5. Challenges for the nuclear safety of the deregulation of electricity markets; Defis pour la surete nucleaire de la dereglementation des marches de l'electricite

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    Eurosafe 2000 was organised around two round tables on the first day and four seminars on the second day. The first round table dealt with general aspects of deregulation including the economic constraints and the special challenges arising during transition from regulated to deregulated structures. The second round table focussed on technical and organisational safety issues which are directly or indirectly related to the changes introduced by deregulation. The four seminars hold in order to provide opportunities for comparing experiences and learning about recent activities of IPSN, GRS and their partners in the European Union and Eastern Europe: Seminar 1 (Nuclear installation safety, assessment and analysis): assessment of the flooding incident at the Blayais nuclear power plant; PSA data base, comparison of the French and German approach; assessment of the Balakovo fire probabilistic study and elaboration of a guide for reviewing fire PSA; comprehensive technical assessment of an advanced German PWR by PSA - objectives and main results; PSA approach for the safety assessment of low-power and shutdown states; correlation of initiating events with the PSA level-2 results; safety assessment for fission products tests in the Phebus reactor; use of NPP simulators for applied human factor studies; assessment of the 'deterministic realistic method' applied to large LOCA analysis; assessment of the feasibility of an improvement programme enabling operation of units 3 and 4 of Kozloduy nuclear power plant. Seminar 2 (nuclear installation safety, research): PHEBUS 2K project on severe accidents; current status of the COCOSYS development; fission product modeling in ASTEC; Euratom Framework Programme (FP) research in reactor safety: main achievements of FP- 4 (1994-1998), some preliminary results of FP-5 (1998-2002) and prospects for beyond 2002; development of coupled systems of 3D neutronics and fluid-dynamic system codes and their application for safety

  6. Contribution to the experimental survey of the nuclear isomerism. Application of the deferred coincidences method to research and to the survey of metastable states of short period; Contribution a l'etude experimentale de l'isomerie nucleaire. Application de la methode des coincidences differees a la recherche et a l'etude d'etats metastables de periode courte

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-06-15

    Various methods of the physics brought many informations on the nuclear elements which one can arrange some ponderable quantities, what is the case of the steady elements and some, unsteady elements, as most of natural radioelements. On the other hand, elements of shorter life duration, and notably those that are carried to an excited state, are more badly known, and one can get information to their consideration that by the mediator of the properties of the transitions that they undergo, when they give birth has best-known nuclear cash: among these transitions represent the isomeric transitions. The goal of this work is the survey of the isomeric transitions from metastable states of short period, included in the domain of the microsecond to some milliseconds. The method of the deferred coincidences has been put to the point and applied in this goal while using the advantages of the selectors to several channels, under two main aspects where the device to several channels was either a selector of time, either a selector of amplitudes. This method served to study the working of Geiger-Muller counter and to measure with precision the period of {sup 181}Ta{sup *} in of the varied experimental conditions. The adopted value is 17,2 {+-}0,2 {mu}s. This work also found an immediate practical application to the setting in evidence of very weak quantities of hafnium in zirconium, of which it constitutes a tenacious and difficult impurity to analyze by the ordinary ways. (M.B.) [French] Les diverses methodes de la physique ont apporte de nombreux renseignements sur les especes nucleaires dont on peut disposer en quantites ponderables, ce qui est le cas des especes stables et de certaines especes instables, comme la plupart des radioelements naturels. Par contre, les noyaux de duree de vie plus courte, et notamment ceux qui sont portes a un etat excite, sont plus mal connus, et on ne peut obtenir de renseignements a leur egard que par l'intermediaire des proprietes des

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  8. Coordination des installations et survey dans les zones experimentales impératifs de collaboration et de flexibilité

    CERN Document Server

    Gayde, JC; CERN. Geneva. TS Department

    2005-01-01

    La section TS/SU-EM fournit les informations géométriques de formes, dimensions et positions des infrastructures des cavernes et des détecteurs des expériences LHC. Elle intervient à toutes les étapes de construction et ses opérations sont dépendantes des autres chantiers, des entreprises en particulier, et de la configuration changeante des lieux. Les travaux de TS/SU-EM dans les cavernes LHC font donc partie des multiples tâches que TS/LEA a pour mandat de coordonner et gérer. Bien que défini et planifié, le moment exact des interventions est souvent connu sous des délais courts, la méthodologie et les ressources devant alors être adaptées et prêtes au moment décidé. De plus, la section intervient souvent pour des opérations de contrôle de dernière minute par définition non programmées. Une communication permanente et directe entre SU et LEA a été établie pour assurer les échanges indispensables au bon déroulement du projet. Ses formes et moyens seront présentés ici.

  9. Reduction des effectifs ou licenciements

    CERN Multimedia

    Maiani, Luciano

    2002-01-01

    "Vous faites un amalgame entre la reduction en cours des effectifs du CERN (organisation europeenne pour la recherche nucleaire) et les economies que le laboratoire doit realiser dans les cinq ans a venir pour financer le projet de grand collisionneur de hadrons (Le Monde du 4 septembre)" (1/2 page).

  10. The United States Atomic Energy Commission Programme of Nuclear Materials Management; Le Programme de Gestion des Matieres Nucleaires Applique par L'USAEC; Programma komissii po atomnoj ehnergii ssha v oblasti obrashcheniya s yadernymi materialami; El Programa de Administracion de Materiales Nucleares de la Comision de Energia Atomica de los Estados Unidos

    Energy Technology Data Exchange (ETDEWEB)

    George, D. E. [United States Atomic Energy Commission, Washington, DC (United States)

    1966-02-15

    Nuclear materials management as conceived by the US Atomic Energy Commission is defined and its development traced from 1943 to the present time. The general programme is outlined and its principal features discussed. Emphasis is placed on administration of those portions of the USAEC programme which pertain to the development and maintenance of quantity data, the establishment of internal controls and the evaluation of performance. The current techniques whereby transfer data are recorded and processed within the USAEC are discussed in some detail, as are the techniques for presentation of material balance reports which periodically summarize the transactions and the results of operations. The techniques used by the USAEC to ascertain the effectiveness of the nuclear materials management programmes of its operating contractors are also discussed. In addition to material being held by contractors which operate USAEC-owned plants and laboratories, there are large quantities of special nuclear material held under a wide variety of financial and administrative arrangements, e.g. under lease, private ownership, under contract with the USAEC where the user is financially liable for losses, as well as those where the risk of losses is taken by the USAEC. This divergence of circumstances causes significant variation in the emphasis and approach used by the AEC and this variation is noted. A brief summary of unresolved problem areas concludes the presentation. (author) [French] L'auteur definit la gestion des matieres nucleaires telle qu'elle est concue par l'USAEC et decrit son evolution depuis 1943 jusqu'a nos jours. Il expose le programme general et discute ses principales caracteristiques. Le memoire souligne les aspects administratifs des parties du programme qui ont trait a la preparation et la tenue a jour des donnees relatives aux quantites, a l'application de controles internes et a l'evaluation de l'efficacite des mesures prises. L'auteur commente en detail la

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

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

  12. Modelisation des effets physico-techniques pour la conception des ...

    African Journals Online (AJOL)

    automatisation dans les installations industrielles a besoin d'une régulation automatique des commandes des processus technologiques pour lesquelles certaines contraintes sont à relever compte tenu des exigences des innovations scientifiques de ...

  13. Nuclear wastes management; Gestion des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document is the proceedings of the debate that took place at the French Senate on April 13, 2005 about the long-term French policy of radioactive wastes management. The different points tackled during the debate concern: the 3 axes of research of the 1991 law, the public acceptance about the implementation of repositories, the regional economic impact, the cost and financing, the lack of experience feedback, the reversibility or irreversibility of the storage, the share of nuclear energy in the sustainable development policy, the European Pressurized Reactor (EPR) project, the privatization of Electricite de France (EdF) etc. (J.S.)

  14. Legal and Administrative Problems of Controlling the Disposal of Nuclear Wastes in the Sea; Problemes Juridiques et Administratifs Poses par le Controle de l'Elimination des Dechets Nucleaires dans la Mer; 041f 0420 041e 0414 ; Problemas Juridicos y Administrativos que Plantea el Control de la Evacuacion de Desechos Nucleares En El Mar

    Energy Technology Data Exchange (ETDEWEB)

    Hydeman, Lee M.; Berman, William H. [Atomic Energy Research Project, University of Michigan Law School (United States)

    1960-07-01

    The basic purpose of the paper is to present some approaches to multinational control of the sea disposal of nuclear wastes, considering both the type of international .control which may be appropriate and the means for accomplishing such control. First, the authors give a brief description of the kind of control which appears to be necessary in protecting public health against the hazards of the disposal of wastes in the sea. The second part consists of a general analysis of the legal problems posed by nuclear wastes. Emphasis is placed on the authority of coastal states to impose unilateral control on the disposal of wastes by other nations if such disposal might adversely affect their interests. The authors inquire into the adequacy of legal remedies as well as the possible rule of law regarding the prevention of damage from waste disposal and the apportionment of liability in the event that such damage does occur. The third part is an analysis of how other problems of control have been handled, both unilaterally and multilaterally. The final part consists of an inquiry into various means of internationally controlling the sea disposal of nuclear wastes. The role of existing international bodies in the maintenance of continuing administrative control at the international level is mentioned. (author) [French] Le but essentiel du memoire est d'exposer diverses facons d'envisager le probleme du controle multinational de l'evacuation des dechets nucleaires dans l'eau de mer, en examinant a la fois le type de controle international approprie et les moyens de le mettre en oeuvre. La premiere partie contiendra une description succincte du genre de controle qui semble necessaire pour la protection de la sante publique contre les effets de l'evacuation des dechets dans la mer. La deuxieme partie consistera en une analyse generale des problemes juridiques poses par. l'elimination des dechets nucleaires. Les auteurs traiteront particulierement du droit des Etats riverains

  15. IRSN press briefing on the issue 'Fukushima, one year after': Situation of Fukushima Dai-ichi nuclear installations; Accident of the Fukushima Dai-ichi: briefing on the situation in February 2012; The Fukushima 1 accident one year after: assessment of environmental consequences in Japan; assessment of consequences of the Fukushima accident on the environment in Japan, one year after; Health consequences of the Fukushima Dai-ichi: situation briefing in February 2012; Point presse de l'IRSN sur le theme 'Fukushima, un an apres': Situation des installations nucleaires de Fukushima Dai-ichi; Accident survenu a la centrale de Fukushima Dai-Ichi Point de la situation en fevrier 2012; L'accident de Fukushima 1 an apres: bilan des consequences environnementales au Japon; bilan des consequences de l'accident de Fukushima sur l'environnement au Japon, un an apres l'accident; Les consequences sanitaires de l'accident de Fukushima Dai-ichi: point de situation en fevrier 2012

    Energy Technology Data Exchange (ETDEWEB)

    Charles, T.; Jourdain, Jean-Rene

    2012-02-28

    This document gathers reports and Power Point presentations (with maps, data tables and graphs) dealing with the Fukushima accident, one year after its occurrence. Different issues are addressed: the status of the nuclear installations, the situation of the installations and of the environment, assessments, measurements and investigations on the effects and consequences of the accident (radioactive releases and fallouts) on the ground and marine environment and on public health

  16. Installation for the study of heat transfer with high flux density; Installation d'etude de transmission de chaleur a densite de flux elevee

    Energy Technology Data Exchange (ETDEWEB)

    Robin, M; Schwab, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    As a result of their very low vapor pressure, metals with a low fusion point (sodium, sodium-potassium alloys, etc.) can be used at high temperature, as heating fluids, in installations whose internal pressure is close to atmospheric pressure. Owing to the very high convection coefficients which can be reached with these fluids and to the large temperature differences utilizable, it is possible to produce through the exchange surfaces considerable heat flux densities, of the order of those which exist through the canning of fuel elements in nuclear reactors. The installation described allowed a flux density of more than 200 W/cm{sup 2} to be obtained, the heating fluid being a Na-K alloy (containing 56 per cent by weight of potassium) brought to a temperature around 550 deg. C. (author) [French] Par suite de leur tres faible pression de vapeur, les metaux a bas point de fusion (sodium, alliages sodium-potassium, etc.) peuvent etre utilises a haute temperature, comme fluides de chauffage, dans des installations dont la pression interne est voisine de la pression atmospherique. Grace aux coefficients de convection tres eleves que ces fluides permettent d'atteindre et aux importantes differences de temperature utilisables, il est possible de produire, a travers les surfaces d'echange, des densites de flux de chaleur considerables, de l'ordre de celles qui existent a travers les gaines des elements combustibles des reacteurs nucleaires. L'installation decrite a permis l'obtention d'une densite de flux de plus, de 200 W/cm{sup 2}, le fluide chauffant etant de l'alliage Na-K (a 56 pour cent en poids de potassium) porte a une temperature voisine de 550 deg. C. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-07-01

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

  18. Poultry farming buildings. Natural gas heating. Guidebook of installation rules; Batiments d`elevage avicole. Chauffage au gaz. Guide des regles d`installation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The technical and economical performances of a poultry farm are greatly influenced by the mastery of ambient temperature during the first days of husbandry. The natural gas space heating installation must answer these requirements and also respect all safety rules concerning the personnel and the animals. In order to answer the questions of poultry farming professionals, the technical association of the natural gas industry (ATG) in France and the Groupama insurance company have redefined the new version of this brochure which integrates the recent technological advances and defines the minimum quality and safety rules required to achieve a natural gas heating installation. The different topics presented are: the gas supply (aerial fixed reservoirs), the general distribution panel (location, command systems, regulation systems for LPG installations, electrical equipments), the distribution pipes (general supply, indoor pipes, flexible pipes, pipe fittings), the heating systems (power, choice, power supply, fastening, air renewal), the check and sign and the start-up of the installation, the periodical control and maintenance operations. (J.S.)

  19. L'amélioration du milieu urbain et la réinstallation sont des moyens ...

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

    18 févr. 2015 ... Quelle est l'efficacité des efforts déployés en Afrique du Sud pour améliorer ses centres urbains, modifier ses environnements urbains et espaces publics, donner des services aux victimes de violence et faire participer directement les collectivités touchées par la violence aux mesures de réduction de la ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  1. Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-06-15

    An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

  2. Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-06-15

    An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

  3. Days of dismantling activities of installations and rehabilitation of contaminated sites in France; Demantelement des installations et rehabilitation de sites contamines

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The objective of these days, organized by the section environment of the French society of radiation protection, is to present a panorama of the activities of nuclear installations dismantling and contaminated sites rehabilitation in France, by leaning in the same time on practical cases and by stating the French rule and the national and international recommendations on the subject. These days have also for object to approach the stakes associated with the sectors of waste management and the materials generated by these activities and in a more general way, the stakes to come for the different actors of the dismantling and the rehabilitation. (N.C.)

  4. Biological Dosimetry Methods Employed at the Boris Kidric Institute of Nuclear Sciences; Application de Quelques Methodes Particulieres de Dosimetrie Biologique a l'Institut des Sciences Nucleaires Boris Kidric

    Energy Technology Data Exchange (ETDEWEB)

    Aleksic, B.; Veljkovic, D.; Djordjevic, O.; Djukic, Z. [Institut des Sciences Nucleaires Boris Kidric, Belgrade, Yugoslavia (Serbia)

    1971-06-15

    In addition to the more usual methods, the following methods are used at the Boris Kidric Institute of Nuclear Sciences in the medical supervision of occupationally exposed staff: analysis of bi nucleated lymphocytes and chromosome aberrations; physical examination (for example, determination of the pain sensitivity threshold, adaptation to pain, discrimination of sensitivity); capillaroscopy. These methods are described briefly and their practical application discussed. (author) [French] Outre les methodes habituelles, on a utilise a l'Institut Boris Kidric, pour le controle medical des travailleurs professionnellement exposes, des methodes d'analyse des lymphocytes binuclees et des aberrations chromosomiques, ainsi que des methodes d'examen physique telles que la determination du seuil de sensibilite douloureuse, de l'adaptation a la douleur et de la discrimination de la sensibilite, et la capillaroscopie. Ces methodes sont brievement decrites et leurs applications pratiques discutees. (author)

  5. Statistical pulses generator. Application to nuclear instrumentation (1962); Generateur d'impulsions aleatoires. Application a l'instrumentation nucleaire (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    This report describes a random pulses generator adapted to nuclear instrumentation. After a short survey on the statistical nature of electronic signals, the different ways for generating pulses with a Poisson's time-distribution are studied. The final generator built from a gaseous thyratron in a magnetic field is then described. Several tests are indicated : counting-rate stability, Pearson's criterion, distribution of time-intervals. Applications of the generator in 'whole testing' of nuclear instrumentation are then indicated for sealers, dead time measurements, time analyzers. In this application, pulse-height spectrums have been made by Poissonian sampling of a recurrent or random low-frequency signal. (author) [French] Cette etude decrit un generateur d'impulsions aleatoires et ses applications a l'instrumentation nucleaire. Apres un bref rappel sur la nature statistique des signaux en electronique nucleaire, sont passes en revue les principaux moyens d'obtenir des impulsions distribuees en temps suivant une loi de Poisson. Le generateur utilisant un thyratron a gaz dans un champ magnetique est ensuite decrit; diverses methodes de test sont appliquees (stabilite du taux de comptage, criterium de Pearson, spectre des intervalles ds temps). Les applications du generateur a l'electronique nucleaire dans le domaine des 'essais globaux' sont indiques: test des echelles de comptage et mesure des temps morts, test des analyseurs en temps apres division du taux de comptage par une puissance de deux, test des analyseurs multicanaux en amplitude. Pour cette derniere application, on a realise des spectres d'amplitudes suivant une loi connue, par echantillonnage poissonien d'un signal basse frequence recurrent ou aleatoire. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-10-01

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

  7. Prevention of the causes and consequences of a criticality accident - measures adopted in France; Prevention des causes et des consequences d'un accident de criticite - solutions adoptees en France

    Energy Technology Data Exchange (ETDEWEB)

    Fruchard, Y.; Lavie, J.M

    1966-07-01

    The question of safety in regard to criticality accident risks has two aspects: prevention of the cause and limitation of the consequences. These two aspects are closely connected. The effort devoted to prevention of the causes depends on the seriousness of the possible human psychologic and economic consequences of the accident. The criticality accidents which have occurred in the nuclear industry, though few in number, do reveal the imperfect nature of the techniques adopted to prevent the causes, and also constitute the only available realistic basis for evaluating the consequences and developing measures to limit them. The authors give a analysis of the known causes and consequences of past criticality accidents and on this basis make a number of comments concerning: the validity of traditional safety criteria, the probability of accidents for different types of operations, characteristic accidents which can serve as models, and the extent of possible radiological consequences. The measures adopted in France to limit the consequences of a possible criticality accident under the headings: location, design and lay-out of the installations, accident detection, and dosimetry for the exposed personnel, are briefly described after a short account of the criteria used in deciding on them. (author) [French] La surete relative aux risques d'accidents de criticite presente deux aspects: la prevention des causes et les parades aux consequences. Ces deux aspects sont tres lies. L'effort consenti a la prevention des causes decoule de l'importance des consequences humaines economiques et psychologiques possibles d'un eventuel accident. Les accidents de criticite survenus dans l'industrie nucleaire, malgre leur rarete, d'une part devoilent les imperfections des techniques de prevention des causes, d'autre part constituent la seule base realiste disponible d'evaluation des consequences et de mise au point des parades a ces consequences

  8. Prevention of the causes and consequences of a criticality accident - measures adopted in France; Prevention des causes et des consequences d'un accident de criticite - solutions adoptees en France

    Energy Technology Data Exchange (ETDEWEB)

    Fruchard, Y; Lavie, J M

    1966-07-01

    The question of safety in regard to criticality accident risks has two aspects: prevention of the cause and limitation of the consequences. These two aspects are closely connected. The effort devoted to prevention of the causes depends on the seriousness of the possible human psychologic and economic consequences of the accident. The criticality accidents which have occurred in the nuclear industry, though few in number, do reveal the imperfect nature of the techniques adopted to prevent the causes, and also constitute the only available realistic basis for evaluating the consequences and developing measures to limit them. The authors give a analysis of the known causes and consequences of past criticality accidents and on this basis make a number of comments concerning: the validity of traditional safety criteria, the probability of accidents for different types of operations, characteristic accidents which can serve as models, and the extent of possible radiological consequences. The measures adopted in France to limit the consequences of a possible criticality accident under the headings: location, design and lay-out of the installations, accident detection, and dosimetry for the exposed personnel, are briefly described after a short account of the criteria used in deciding on them. (author) [French] La surete relative aux risques d'accidents de criticite presente deux aspects: la prevention des causes et les parades aux consequences. Ces deux aspects sont tres lies. L'effort consenti a la prevention des causes decoule de l'importance des consequences humaines economiques et psychologiques possibles d'un eventuel accident. Les accidents de criticite survenus dans l'industrie nucleaire, malgre leur rarete, d'une part devoilent les imperfections des techniques de prevention des causes, d'autre part constituent la seule base realiste disponible d'evaluation des consequences et de mise au point des parades a ces consequences. Les auteurs presentent une analyse des

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-02-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  12. Dresses problems arising from hot-plant operation and their solution (1961); Les problemes vestimentaires poses par l'exploitation des installations actives et leurs solutions (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    acceleree en periode d'incidents doivent etre traites comme le linge des centres hospitaliers. Le lavage du linge par le procede allemand du contre-courant (systeme Sulzman) se revele un procede precieux par les cadences rapides qu'il permet et, surtout, par sa faible production d'effluents liquides. Le nettoyage a sec est une technique d'avenir qui s'avere encore plus economique. Dans une laverie active, le controle des vetements traites du point de vue de la contamination residuaire peut constituer un serieux goulet d'etranglement a la production du linge propre s'il n'est pas solutionne par l'utilisation de machines automatiques a cadence rapide. Le risque encouru par le personnel d'exploitation est uniquement la contamination de l'atmosphere et des surfaces. A ce titre, l'installation doit etre traitee comme une zone active dans laquelle sont manipules journellement quelques dizaines de millicuries d'emetteurs dangereux et quelques microcuries de plutonium. (auteurs)

  13. Dresses problems arising from hot-plant operation and their solution (1961); Les problemes vestimentaires poses par l'exploitation des installations actives et leurs solutions (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    renouveles a cadence acceleree en periode d'incidents doivent etre traites comme le linge des centres hospitaliers. Le lavage du linge par le procede allemand du contre-courant (systeme Sulzman) se revele un procede precieux par les cadences rapides qu'il permet et, surtout, par sa faible production d'effluents liquides. Le nettoyage a sec est une technique d'avenir qui s'avere encore plus economique. Dans une laverie active, le controle des vetements traites du point de vue de la contamination residuaire peut constituer un serieux goulet d'etranglement a la production du linge propre s'il n'est pas solutionne par l'utilisation de machines automatiques a cadence rapide. Le risque encouru par le personnel d'exploitation est uniquement la contamination de l'atmosphere et des surfaces. A ce titre, l'installation doit etre traitee comme une zone active dans laquelle sont manipules journellement quelques dizaines de millicuries d'emetteurs dangereux et quelques microcuries de plutonium. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-09-14

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

  16. FAWA - Field-analysis of Heat-pump Installations - Proceedings; Tagungsband zur 11. Tagung des Forschungsprogramms Umgebungswaerme, Waerme-Kraft-Kopplung, Kaelte des Bundesamts fuer Energie (BFE)

    Energy Technology Data Exchange (ETDEWEB)

    Rognon, F.

    2004-07-01

    These proceedings of the 11th conference organised by the Swiss Federal Office of Energy's Research Programme on Ambient Heat, Combined Heat and Power and Refrigeration present 6 papers on heat-pump topics. These include two papers concerning the results obtained from the FAWA project - a unique study of over 230 heat pump installations in operation in the field that was started in 1996 to assess the success of Swiss heat-pump promotion activities. The activities of the Swiss Heat-pump Testing Centre are dealt with and the potential for cost reductions through the optimal choice of system - done according to the motto 'small and simple is beautiful' - is reviewed. A further contribution deals with the question of the heat-pump customer being the 'king'. The role of installers and fitters acting as the instances who choose which system is to be used is looked at in a further contribution. A list of useful addresses completes the proceedings.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

  18. Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants; Limitations de l'Efficacite de la Detection des Defauts par Essais Non Destructifs de Tubes de Bouilleurs pour Centrales Nucleaires; Predely ehffektivnosti nedestruktivnoj defektoskopii trub parogeneratorov yadernykh ehlektrostantsij; Limites para Distinguir los Defectos en el Ensayo No Destructivo de Tubo para Generadores de Vapor Destinados a Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlmann, A.; Adamsky, F. -J. [Technischer Ueberwachungs-Verein Reinland e.V., Cologne (Germany)

    1965-10-15

    In the Federal Republic of Germany there are nuclear reactors under construction with steam generators inside the reactor pressure-vessel. As a result design repairs of steam- generator tubes are very difficult and cause large shut-down times of the nuclear-power plant. It is known that numerous troubles in operating conventional power plants are results of steam-generator tube damages. Because of the high total costs of these reactors it. is necessary to construct the steam generators especially in such a manner that the load factor of the power plant is as high as possible. The Technischer Ueberwachungs-Verein Rheinland was charged to supervise and to test fabrication and construction of the steam generators to see that this part of the plant was as free of defects as possible. The experience gained during this work is of interest for manufacture and construction of steam generators for nuclear-power plants in general. This paper deals with the efficiency limits of non-destructive testing steam-generator tubes. The following tests performed will be discussed in detail: (a) Automatic ultrasonic testing of the straight tubes in the production facility; (b) Combined ultrasonic and radiographic testing of the bent tubes and tube weldings; (c) Other non-destructive tests. (author) [French] En Allemagne, on construit actuellement des generatrices nucleaires dans lesquelles les bouilleurs sont installes a l'interieur du caisson etanche du reacteur. Il s'ensuit que les reparations des tubes des bouilleurs sont tres difficiles et provoquent de longs arrets des centrales nucleaires. On sait que de nombreuses perturbations du fonctionnement des centrales classiques sont dues a des dommages dans les tubes des bouilleurs. C'est en grande partie en raison du prix de revient eleve de ces reacteurs qu'il est necessaire de construire les bouilleurs notamment de sorte que le facteur d'utilisation de la centrale soit aussi eleve que possible. C'est le ' Technischer Ueberwachungs

  19. Extraction liquide-liquide des sels minéraux. Approximation analytique des isothermes de partage. Application au calcul sur ordinateur d'une installation Liquid-Liquid Extraction of Mineral Salts. Analytical Approximation of Partition Isotherms. Application to the Computer Designing of an Installation

    Directory of Open Access Journals (Sweden)

    Chaid M. T.

    2006-11-01

    Full Text Available Cet article comporte deux parties -dans la première on a calculé les isothermes de partage en partant des considérations thermodynamiques basées sur les travaux de Guggenheim. Les résultats ne sont bons que dans le cas des solutions idéales. On a donc simulé les isothermes par des fonctions analytiques. Celles-ci permettent de représenter convenablement tous les faisceaux d'isothermes quelles que soient l'acidité de la solution aqueuse et les concentrations dans les deux phases; - la deuxième partie est réservée au calcul d'une installation complète d'extraction avec colonne de récupération; le calcul, mené sur ordinateur, utilise les fonctions analytiques précédentes et permet d'obtenir les débits et les concentrations à chaque plateau. This article contains two parts: - the first part discusses the calculating of partition isotherms using thermodynamic considerations based on research by Guggenheim. The results are good only in the case of ideal solutions. Therefore, isotherms were simulated by ànalyticfunctionswhich are suitable for representing all isotherm bundles no matter what the acidity of the aqueous solution and the concentrations in both phases moy be. - the second part 'deals' with designing a complete extraction installation with a recovery column. Computerized designing makes use of the preceding analytic functions and enables flowrates and concentrations ta be determined at each plate.

  20. Geothermal probes and heat pump installation at the Gerzensee training centre; EWS-WP des Studienzentrums Gerzensee/BE

    Energy Technology Data Exchange (ETDEWEB)

    Kuhn, P.

    2004-07-01

    This preliminary report for the Swiss Federal Office of Energy (SFOE) presents the results of a refurbishment project at the Swiss National Bank's training centre in Gerzensee, Switzerland. Eight air-water heat pumps with a total heating capacity of 180 kW were replaced by two ground-coupled heat pumps, each with a heating capacity of 120 kW. The geothermal probes are additionally used for free-cooling during the summer season. An oil-fired boiler used for meeting peak-load and back-up purposes, was also replaced for reasons of higher energy efficiency. Both investments and running costs of the heating system are presented along with details on expenses for electrical installations and building adaptations. The improvements in energy-saving, when compared with the former air-water heat pump system, are impressive: Total energy consumption for space heating, hot water and for ventilation systems was lowered by around 54%. The oil consumption has been reduced from 34,800 to 6,600 litres/year, which corresponds to a reduction of 81%. Also, electrical power consumption by the heat pump installation was lowered by around 8%. Figures are given on the proportion of heating supplied by the heat-pump system that now covers 90.6% of total demand.

  1. La durabilité des géosynthétiques dans les installations de stockage de déchets : le projet Durageos DURAGEOS. Durability of geosynthetics used in landfills

    Directory of Open Access Journals (Sweden)

    FARCAS, Fabienne ; PONS, Carlos ; BOUCHEZ, Théodore ; MAZÉAS, Laurent ; MÉRY, Jacques ; TOUZE-FOLTZ, Nathalie ; DURRIEU, Claude ; FAYOLLE, Bruno ; RICHAUD, Emmanuel ; LANOË, Marie ; MARTINS, Jean ; PIERSON, Patrick ; SALDI, Fethi

    2012-08-01

    Full Text Available Les géosynthétiques sont de plus en plus utilisés pour renforcer les barrières d'étanchéité des installations de stockage des déchets non dangereux. Afin de réduire l'impact environnemental des installations, les utilisateurs de ces matériaux ont donc besoin de guides et de recommandations sur leur mise en œuvre délicate, mais également d'estimations sur leur durée de vie. Cet article nous présente les moyens mis en œuvre par le projet Durageos pour mieux connaître et prédire les processus de vieillissement des géomembranes en polyéthylène haute densité et des géosynthétiques bentonitiques.The DURAGEOS project studies geosynthetics (HDPE geomembranes and GCLs ageing mechanisms under combined action of mechanical stresses, microorganisms and/or oxygen in connection with mass transfer. Physico-chemical and mechanical features of model and commercial geosynthetics aged in laboratory allow the development of a kinetic model of prediction of the lifetime coupled to a model of mass transfer. The models will be validated by geosynthetics sampled on landfill sites. Ecotoxicological risks and environmental external costs of transfers are to be assessed.

  2. Nuclear biological studies in France; Les etudes de biologie nucleaires en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

  3. Nuclear biological studies in France; Les etudes de biologie nucleaires en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

  4. Canadian Food Irradiation Facilities; Installations Canadiennes d'Irradiation des Aliments; Kanadskie ustanovki dlya oblucheniya pishchevykh produktov; Instalaciones de Irradiacion de Alimentos en el Canada

    Energy Technology Data Exchange (ETDEWEB)

    Warland, H. M.F.; MacQueen, K. F. [Atomic Energy of Canada Ltd., Commercial Products, Ottawa (Canada)

    1966-11-15

    '(AECL) a entrepris en 1956 des travaux sur l'irradiation des pommes de terre en utilisant comme source des barreaux de combustible epuise. En 1958, l'AECL a concu et fabrique le premier appareil Gammacell 220, qui est un irradiateur complet, et l'on n'a plus utilise que du cobalt-60 pour l'execution du programme d'irradiation des aliments. En 1960, la premiere autorisation du service de controle des produits alimentaires et pharmaceutiques a ete obtenue pour les pommes de terre. La phase suivante consistait a montrer aux producteurs et distributeurs de pommes de terre que le cobalt-60 est un instrument sans danger, simple et sur, et que l'irradiation entrave la germination. En 1961 l'AECL a concu et fabrique un irradiateur mobile afin d'executer le programme de demonstration. L'irradiateur a ete monte sur une remorque routiere entierement equipee et, au cours de la saison 1961/1962, 500 tonnes de pommes de terre ont ete irradiees en divers endroits du Canada oriental. En 1965, l'AECL a concu et construit le premier irradiateur commercial de denrees alimentaires pour la compagnie Newfield Products Ltd. Pendant l'execution du programme d'irradiation des pommes.de terre, l'AECL a lance des programmes communs avec des laboratoires canadiens de recherche sur les produits alimentaires, en utilisant d'autres appareils Gammacell. En 1960, l'AECL a construit une installation d'irradiation en casemate dans son etablissement d'Ottawa pour l'irradiation d'articles plus volumineux tels que des quartiers de porcs et des regimes de bananes. Au cours de l'annee 1963, l'irradiateur mobile, qui avait deja montre son utilite, a ete modifie en vue d'elargir ses applications: l'intensite de la source a ete augmentee et il a ete equipe d'un dispositif de refroidissement des produits; en outre, la remorque a ete climatisee. Ainsi transforme, il a ete utilise en Californie pour l'irradiation d'une grande variete de fruits a la station du Departement de l'agriculture des Etats-Unis, a Fresno. Le

  5. Re-enrichment of depleted uranium by passage through a gaseous diffusion installation; Reenrichissement de l'uranium appauvri par passage dans une installation de diffusion gazeuse

    Energy Technology Data Exchange (ETDEWEB)

    Lagrange, P; Billous, O [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The reader will find in this paper an economic study of the re-utilization of depleted uranium from nuclear reactors, whether its content be above or under natural proportions. Re-utilization is possible either through bringing the depleted product up to its initial content of {sup 235}U by mixture with a richer concentrate, or else by passing it through a gaseous diffusion plant. The economic area of such re-utilization depends on a number of considerations. We give a general study of it, with reference to some typical gaseous diffusion facilities. (author)Fren. [French] Ce rapport examine au point de vue economique la reutilisation de l'uranium appauvri provenant des reacteurs nucleaires, qu'il soit indifferemment en dessus ou en dessous de la teneur naturelle. Cette reutilisation peut se faire soit en ramenant le produit a sa teneur initiale en isotope 235 par un melange convenable avec un concentre plus riche, soit en le faisant passer dans une usine de Diffusion Gazeuse. La zone de rentabilite de cette reutilisation depend de diverses conditions economiques. Elle est etudiee ci-dessous d'une maniere generale, puis en se referant a des installations-type de diffusion gazeuse. (auteur)

  6. Problems presented by the filtration and sampling of aerosols in the atomic energy programme; Problemes poses par la filtration et le prelevement des aerosols dans le cadre de l'energie atomique

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    The maximum permissible limits for radioactive aerosols are much lower than those for aerosols encountered in the non-nuclear industries. These limits depend on numerous factors such as: nature of the radiation, half-life, etc. The radioactive aerosols can be prepared by various methods. The filtering of the air in high activity laboratories or in plutonium treatment factories necessitates an installation consisting of: - aspiration filters, - extraction filters of very high efficiency (those used for {alpha} emitter cells: designed to be replaced without incurring contamination risks; those used for {gamma} emitter cells: designed to be replaced by remote control). The filtering in nuclear reactors is also effectuated by filter papers: - the G1 reactor with open circuit: the air coolant is entirely filtered at the entry and on leaving; - the G2, G3 and EDF1 reactors with closed circuits: filtering under pressure of a small portion of the coolant gas. (author) [French] Les limites maxima permises des aerosols radioactifs sont beaucoup plus faibles que celles des aerosols rencontres dans l'industrie classique. Elles dependent de nombreux facteurs tel que: nature du rayonnement, periode radioactive, etc... La formation des aerosols radioactifs est de nature diverse. La filtration des laboratoires de haute activite, ou d'usines d'elaboration de plutonium conduit a des types d'installations comportant: - des filtres d'aspiration; - des filtres d'extraction a rendement extremement eleve (type pour cellules emettrices {alpha} concu pour etre change sans risque de contamination, type pour cellules emettrices {gamma}: concu pour etre change a distance) La filtration des reacteurs nucleaires sont egalement effectuee par des papiers filtres: - reacteur G1 a circuit ouvert: air de refroidissement totalement filtre a l'aspiration et a l'extraction; - reacteurs G2, G3, EDF1: a circuit ferme: filtration sous pression d'une faible partie du gaz de refroidissement. (auteur)

  7. Nuclear study of Melusine; Etude nucleaire de Melusine

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    In this report are reviewed - with respect to starting of experiments - the main nuclear characteristics of a 20 per cent enriched uranium lattice, with light water as moderator and reflector. The reactor is to operate at 1 MW. 1) Study of various critical masses. 2) Control. Effectiveness of cadmium. Control rods and of a stainless steel regulating rod. 3) Study of the effect on reactivity of disturbances in the core center. 4) Study of xenon and samarium poisoning. 5) Temperature factor. 6) Heat exchanges in a fuel element. (author) [French] On etudie, dans ce rapport, les principales proprietes nucleaires d'un reseau a uranium enrichi (20 pour cent), dont le moderateur et le reflecteur sont l'eau legere en vue des experiences de demarrage. Ce reacteur devra fonctionner a 1 MW. 1) Etude de diverses masses critiques. 2) Controle. Efficacite des barres de controle en cadmium et d'une barre de reglage en acier inoxydable. 3) Etude de l'effet sur la reactivite de perturbation au centre du coeur. 4) Etude de l'empoisonnement xenon et samarium. 5) Coefficient de temperature. 6) Echanges thermiques dans un element. (auteur)

  8. A treatment station for solid radio-active waste at the Saclay nuclear research centre (1962); Station de traitement des dechets radioactifs solides au centre d'etudes nucleaires de Saclay (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    The waste from an atomic centre is very varied in nature, in form, and in activity, going from weakly contaminated laboratory waste to objects actuated in a pile and strongly radioactive. After one year's working of a pilot plant, a factory has been built, in which solide waste is treated and then conditioned in concrete blocks. The present communication describes the treatment and conditioning techniques in this factory which uses to a maximum remotely controlled operation. (authors) [French] Les dechets d'un Centre Atomique sont de natures, de forme et d'activites extremement variees, allant des dechets de laboratoires faiblement contamines, aux dispositifs actives en pile et fortement radioactifs. Apres l'exploitation pendant un an d'une unite pilote, une usine a ete construite dans laquelle les dechets solides sont traites, puis conditionnes en bloc de beton. La presente communication a pour objet la description des techniques de traitement et de conditionnement dans cette usine ou les operations sont au maximum commandees automatiquement et a distance. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

  10. A mathematical model for cost of maritime transport. Application to competitiveness of nuclear vessels; Modele mathematique du cout de transport maritime application a la competitivite du navire nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Dorval, C [Commissariat a l' Energie Atomique, 75 - Paris (France)

    1966-05-01

    In studying the competitiveness of a nuclear merchant vessel, economic assessments in terms of figures were discarded in favor of a simplified model, which gives a clearer idea of the mechanism of the comparison between alternative vessels and the particular influence of each parameter. An expression is formulated for the unit cost per ton carried over a given distance as a function of the variables (speed and deadweight tonnage) and is used to determine the optima for conventional and nuclear vessels. To represent the freight market involved in the optimization studies, and thus in the competitiveness computation, two cases are taken into account: the tonnage to be carried annually is limited, and the tonnage to be carried annually is not limited. In both cases the optima are calculated and compared for a conventional and a nuclear vessel. Competitiveness curves are plotted as a function of the ratios of nuclear and conventional fuel costs and nuclear and conventional marginal power costs. These curves express the limiting values of the above two ratios for which the transport costs of the nuclear and conventional vessels are equal. The competitiveness curves vary considerably according to the hypothesis adopted for the freight market and the limit of tonnage carried annually. (author) [French] Pour etudier la competitivite du navire marchand nucleaire, plutot que de nous livrer a des evaluations economiques chiffrees, discutables dans l'etat actuel des etudes, nous utilisons un modele simplifie permettant de mieux saisir le mecanisme de la comparaison des navires et l'influence particuliere de chaque parametre. Nous etablissons une expression du cout unitaire de la tonne transportee sur un parcours donne en fonction des variables vitesse et port en lourd. Et nous l'utilisons pour determiner les optima des navires classiques et nucleaires. Pour representer le marche du fret qui intervient dans les etudes d'optimisation, et donc dans la recherche de la

  11. French research in the field of nuclear agronomy; Les recherches francaises en agronomie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Guerin De Montgareuil, P. [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    , industrial firms, university laboratories scientific institutes. The role of the Commissariat a l'Energie Atomique is defined: on the one hand it supplies information and support, and on the other hand it takes charge of specifically nuclear aspects of the work. Its part in the field has recently found expression in the creation, within the Biology Department, of a Radio-agronomy Section; its objective are described,, as well as the, means placed att its disposal at the Centre d'etudes Nucleaires, Cadarache. (author) [French] On propose un bilan des travaux les plus significatifs effectues en France depuis la deuxieme conference internationale en matiere d'agronomie nucleaire et qui vont d'une recherche apparemment desinteressee a l'application la plus directe. Une telle differenciation recouvre de moins en moins, au fur et a mesure de l'evolution des programmes, la distinction qui est faite dans l'expose entre l'action biologique des rayonnements et les autres emplois des techniques nucleaires. C'est ainsi que les recherches do radiogenetique agricole sont poursuivies dans deux directions: d'un point de vue theorique et methodologique avec l'etude comparative de l'action des divers types de rayonnements, l'influence du debit de dose et de la temperature, l'action des agents mutagenes chimiques, la production de chimeres sous irradiation gamma; et d'autre part, sous un aspect pratique aboutissant a la creation de varietes nouvelles plus resistantes ou plus precoces (riz, mil, arachide). Les problemes de destruction des insectes (eradication) et de conservation des denrees sous irradiation se trouvent egalement abordes par des voies et avec des objectifs tres divers. A la demarche globale representee par une irradiation pure et simple (grains humides, pommes de terre...) sont parfois associees des etudes souvent originales, d'ordre biochimique ou microbiologique (par exemple: alteration de l

  12. French research in the field of nuclear agronomy; Les recherches francaises en agronomie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Guerin De Montgareuil, P [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    , industrial firms, university laboratories scientific institutes. The role of the Commissariat a l'Energie Atomique is defined: on the one hand it supplies information and support, and on the other hand it takes charge of specifically nuclear aspects of the work. Its part in the field has recently found expression in the creation, within the Biology Department, of a Radio-agronomy Section; its objective are described,, as well as the, means placed att its disposal at the Centre d'etudes Nucleaires, Cadarache. (author) [French] On propose un bilan des travaux les plus significatifs effectues en France depuis la deuxieme conference internationale en matiere d'agronomie nucleaire et qui vont d'une recherche apparemment desinteressee a l'application la plus directe. Une telle differenciation recouvre de moins en moins, au fur et a mesure de l'evolution des programmes, la distinction qui est faite dans l'expose entre l'action biologique des rayonnements et les autres emplois des techniques nucleaires. C'est ainsi que les recherches do radiogenetique agricole sont poursuivies dans deux directions: d'un point de vue theorique et methodologique avec l'etude comparative de l'action des divers types de rayonnements, l'influence du debit de dose et de la temperature, l'action des agents mutagenes chimiques, la production de chimeres sous irradiation gamma; et d'autre part, sous un aspect pratique aboutissant a la creation de varietes nouvelles plus resistantes ou plus precoces (riz, mil, arachide). Les problemes de destruction des insectes (eradication) et de conservation des denrees sous irradiation se trouvent egalement abordes par des voies et avec des objectifs tres divers. A la demarche globale representee par une irradiation pure et simple (grains humides, pommes de terre...) sont parfois associees des etudes souvent originales, d'ordre biochimique ou microbiologique (par exemple: alteration de l'amidon, metabolisme glucidique des tubercules irradies, radioresistance des levures

  13. Methods for determining thermal stresses values. Some examples relating to nuclear reactors; Methodes de determination des contraintes thermiques. Quelques exemples d'application aux reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, J; Gautier, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Peres, A [Israel Institute of Technology, Dept. of Nuclear Science Technion (Israel)

    1958-07-01

    As modern techniques develop more elaborate machines, and make their way towards higher and higher temperatures and pressures, the thermal stresses become a matter of major importance in the design of mechanical structures. In the first part of this paper, the authors examine the problem from a theoretical standpoint, and try to evaluate the aptitude and limitation of mathematical techniques to attain the quantitative values of thermal stresses. This paper deals mainly with the experimental methods to measure thermal stresses. The authors show some examples relating to nuclear reactors. (author)Fren. [French] Au fur et a mesure que la technique moderne developpe des machines plus poussees et s'oriente vers des temperatures et des pressions toujours plus elevees, les contraintes thermiques deviennent un facteur d'importance capitale dans le calcul des structures mecaniques. Les auteurs examinent d'abord l'aspect theorique du probleme, ainsi que l'aptitude et les limites du calcul pour exprimer quantitativement la valeur des contraintes thermiques. Les auteurs exposent principalement, ensuite, les methodes experimentales qui permettent de mesurer ces contraintes, et illustrent cet expose de quelques exemples relatifs aux installations nucleaires. (auteur)

  14. Radioactivity and radioprotection: the every day life in a nuclear installation. Press tour at CEA/GRENOBLE 18 november 1999; Radioactivite et radioprotection: la vie quotidienne dans une installation nucleaire. Voyage de presse au Centre CEA/CADARACHE 18 novembre 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    In the framework of the public information, this paper gives a general information on the radioactivity and the radioprotection at the CEA/Cadarache center. A first part is devoted to a presentation of the radioactivity with definitions and radiation effects on the human being and the environment. An other part presents the radioprotection activities and regulations. The last part deals with specific activities of the CEA/Cadarache: the CASCAD installations for spent fuels storage, the LECA Laboratory for the Examination of Active Fuels and a dismantling installation for big irradiated objects. Historical aspects of the CEA/Cadarache are also provided. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Desgranges, L.

    2006-12-15

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

  16. Determination of the cross-sections of some nuclear reactions occurring as a result of cosmic radiation (1963); Determination des sections efficaces de quelques reactions nucleaires intervenant dans les effets ou rayonnement cosmique (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-06-15

    The high energy reactions studied during this research are reactions liable to occur as a result of cosmic radiation. On the one hand the reaction {sup 16}O(p, 3p){sup 14}C was studied and its cross-section measured between 65 MeV and 2.7 GeV; a value of 2.3 mb {+-} 0.5 was found. These values have mode it possible to forecast measurable quantities of carbon-14 in meteorites and also to measure them. On the other hand the reactions {sup 12}C({sup 16}O...), {sup 12}C({sup 14}N...) and {sup 12}C({sup 12}C...) have been studied and an attempt has been made to explain the mechanism of these reactions. (author) [French] Les reactions a hautes energies qui ont ete etudiees au court de ce travail sont des reactions susceptibles de se produire sous l'effet du rayonnement cosmique. Il s'agit d'une part de la reaction {sup 16}O(p, 3p){sup 14}C dont on a mesure la section efficoce egale a 2,3 mb {+-} 0,5 entre 65 MeV et 2,7 GeV. Ces valeurs ont permis de prevoir des quantites mesurables de carbone 14 dans les meteorites et par suite de les determiner. D'autre part les reaction {sup 12}C({sup 16}O...), {sup 12}C({sup 14}N...) et {sup 12}C({sup 12}C...) ont ete etudiees et on a tente d'expliquer le mecanisme de ces reactions. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

  18. The Radioisotopic Determination of Diffusion Coefficients and Currents in Natural Waters. Surface Collection of Radioactive Fall-Out on a Large Alpine Lake; Determination par detection nucleaire des coefficients de diffusion et des courants dans les eaux naturelles. Evolution de la surface de collection d'un grand lac alpin pour les retombees radioactives; Opredelenie koehffitsienta diffuzii i skorosti techeniya estestvennykh vod pri pomoshchi yadernogo detektirovaniya. Ehvolyutsiya poverkhnosti sbora radioaktivnykh osadkov na bol'shom al'pijskom ozere; Determinacion por deteccion nuclear de los coeficientes de difusion y de las corrientes en las aguas naturales evolucion de la superficie de captacion de un gran lago alpino para las precipitaciones radiactivas

    Energy Technology Data Exchange (ETDEWEB)

    Chesselet, R.; Nordemann, D. [Service d' Electronique Physique, Centre d' Etudes Nucleaires de Saclay (France); Dussart, B. [Centre de Recherches Hydrobiologiques, CNRS, Gif-sur-Yvette (France)

    1963-08-15

    'un coefficient de diffusion pour l'emetteur utilise et a la mesure eventuelle de la vitesse du courant au point ou la mesure est effectuee (dans le cas decrit, le lac Leman). Dans une seconde etape, en correlation avec une etude de geophysique concernant le probleme general des retombees radioactives, les auteurs ont utilise l'apport des retombees radioactives ayant pour origine les essais nucleaires atmospheriques (octobre 1961-janvier 1962). Des mesures de la radioactivite ont ete effectuees chaque jour sur des prelevements d'eau du lac Leman a des profondeurs de 0 m, 10 m, 20 m et sur un collecteur de retombees atmospheriques seches et humides. Malgre la complexite du regime des apports en fonction du temps, l'interpretation des diagrammes obtenus peut contribuer a resoudre le probleme du devenir des produits radioactifs dans les conditions de diffusion et de courants rencontrees. L'utilisation de la diffusion de produits radioactifs en tres faibles quantites et des differentes techniques de detection nucleaires a haute sensibilite actuellement disponibles peut conduire a une meilleure connaissance de la diffusion in situ et du mouvement des masses d'eaux naturelles. (author) [Spanish] En una primera etapa, los autores ha i provecado la difusion in situ de un emisor radiactivo, el sodio-22 en forma de Na{sup +}, de actividad muy baja (inferior al milicurie). La aplicacion de las leyes de la difusion a este caso facilita el calculo de la velocidad de difusion de la ''nube radiactiva''. Por consiguiente, el registro en funcion del tiempo de las actividades medidas con dos detectores gamma dispuestos de modo conveniente permite asignar un coeficiente de difusion ai emisor empleado y, eventualmente, evaluar la velocidad de la corriente en el punto en que se efectua la medicion (en el caso descrito, el lago Leman). En una segunda etapa, en relacion con un estudio geofisico del problema general de las precipitaciones radiactivas, los autores utilizaron la aportacion de las

  19. Associative memories in nuclear physics; Les memoires associatives en physique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Blanca, E; Carriere, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    Experiments in nuclear physics involve the use of large size 'memories'. After showing the difficulties arising from the use of such memories, the authors give the principles of the various programming methods which make it possible to operate the memories associatively thus benefiting from a reduction in size and better operational conditions. They attempt to estimate the shape and dimensions of an associative memory with cable connections which could be designed specially for nuclear research, contrary to those actually in service. (authors) [French] Les experiences de physique nucleaire necessitent l'emploi de 'memoires' de grandes dimensions. Apres avoir montre les inconvenients que presente l'utilisation de telles memoires, les auteurs exposent les principes des diverses methodes de programmation qui permettent d'assurer un fonctionnement des memoires sur le mode associatif donc une reduction de leurs dimensions et un meilleur usage. Ils tentent d'evaluer le format d'une memoire associative cablee qui, contrairement a celles qui existent actuellement, serait prevue specialement pour l'experimentation nucleaire. (auteurs)

  20. Information note about the protection of nuclear facilities against aircraft crashes; Note d'information sur la protection des installations nucleaires contre les chutes d'avions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight < 5.7 t), the military aircraft, and the commercial aircraft (w > 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

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

  2. Nuclear geophysics in prospecting for ore and coal deposits; Geophysique nucleaire et prospection des gisements de charbon et autres mineraux; Yadernaya geofizika pri razvedke rudnykh i ugol'nykh mestorozhdenij; Geofisica nuclear u prospeccion de yacimientos de carbon y otros minerales

    Energy Technology Data Exchange (ETDEWEB)

    Bulashevich, Yu P; Voskobojnikov, G M; Muzyukin, L V

    1962-01-15

    eliminated by inverse probes. These neutron methods, and similarly neutron-activation logging, have also been applied at deposits of copper, manganese, aluminium and various other ores. Continuous-activation logging is appropriate where the occurring radioisotope has a suitable half-life. It is then possible to determine the optimum logging conditions (rate, length of probe, etc.) theoretically. Neutron recording during photo-neutron logging makes it possible to distinguish ore bodies containing beryllium, and to estimate the beryllium content from 0.001% upwards. Experience is confirming the effectiveness and economic expediency of nuclear geophysical methods in prospecting for ore and coal deposits. (author) [French] Les methodes de geophysique nucleaire s'emploient surtout pour l'exploration des gisements de charbon et autres mineraux par radiosondage. Dans le cas des gisements de charbon et d'autres mineraux de l'Union sovietique, les types suivants de prospection par sondage radioactif ou nucleaire (SR) trouvent une large application pratique : determination de la densite ou sondage gamma-gamma (S.G.G.) avec le {sup 60}cO comme source de rayonnements, sondage gamma-gamma selectif (S.G.G.S.) avec une source de rayonnements mous du type {sup 75}Se, sondage neutronsneutrons (S.N.N.) et sondage gamma-neutrons (S.G.N.) avec une source de neutrons Po-Be, sondage par activation - surtout par activation continue - avec emploi de la meme source, et sondage photo-neutronique avec l'emetteur gamma {sup 124}Sb. L'objet essentiel du S.R., dans les gisements de minerais, est de reconnaitre les differentes couches de minerais que l'on rencontre dans le trou de sonde, ce qui reduit le temps d'analyse, ainsi que d'evaluer approximativement, sur place, la teneur en elements utiles. Dans les gisements de charbon, le S.R. permet de determiner la profondeur, l'importance et la structure des veines. Les methodes dites S.G.G. et S.G.G.S. sont fondees sur l'enregistrement du rayonnement gamma

  3. Production of artificial radioelements; Production des radioelements artificiels

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The techniques used in the production of artificial radioelements are described, with special emphasis on the following points: - nuclear reactions and use of reactors; - chemical separation methods and methods for enriching the activity of preparations; - protection of personnel and handling methods. (author) [French] On decrit l'ensemble des techniques utilisees dans la fabrication des radioelements artificiels en insistant notamment sur les points suivants: - reactions nucleaires et utilisation des reacteurs; - methodes de separations chimiques et methodes d'enrichissement d'activite des preparations; - protection du personnel et methodes de manipulation. (auteur)

  4. Construction of an apparatus for nuclear orientation measurements at low temperatures. Application to neodymium-cobalt alloy; Realisation d'un appareil pour des mesures d'orientation nucleaire a basse temperature. Application a l'alliage neodyme-cobalt

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-10-01

    We describe experiments along which has been studied the anisotropy of {gamma} radiations emitted by oriented nuclei. We have used the great hyperfine fields acting on nuclei in ferromagnetic metals so as to produce alignment at low temperature. By irradiation we obtained a few cobalt 60 nuclei in our samples which were then cooled down to 0,01 K. The anisotropic rate of the 1,33 MeV {gamma} radiation was measured in function of the sample temperature, using as thermometer the anisotropy of {gamma} radiation emitted by cobalt 60 nuclei in a cobalt single crystal. Cobalt 60 was lined up in a cobalt nickel alloy (40% Ni). The hyperfine field at the cobalt was measured compared to the effective field in metallic cobalt: Heff(Co Ni)/Heff(Co metal) = 0.71 {+-} 0.12. These results are in good agreement with specific heat measurements made previously. Cobalt 60 has been polarised in a neodymium-cobalt alloy (NdCo{sub 5}). The field at the cobalt in NdCo{sub 5} has been measured compared to the field in metallic cobalt and taking the non-saturation into account we found 165000 oersteds < Heff(NdCo{sub 5}) < 220000 oersteds. (author) [French] Nous decrivons des experiences au cours desquelles nous avons etudie l'anisotropie de rayonnements {gamma} emis par des noyaux orientes. Nous avons utilise les grands champs hyperfins agissant sur las noyaux dans les metaux ferromagnetiques pour produire l'alignement a basse temperature. Par irradiation nous avons obtenu quelques noyaux de cobalt 60 dans nos echantillons qui furent ensuite refroidis a 0,01 K. Le degre d'anisotropie du rayonnement {gamma} de 1,33 MeV fut mesure en fonction de la temperature de l'echantillon en utilisant l'anisotropie du rayonnement {gamma} de noyaux de cobalt 60 dans un monocristal de cobalt metallique utilise comme thermometre. Le cobalt 60 a ete aligne dans un alliage de cobalt-nickel (40% Ni). Le champ hyperfin au niveau du cobalt a ete mesure par rapport au champ effectif dans le cobalt metallique

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-04-15

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

  6. The Problems of Controlling Defects in the Materials Used for the First Czechoslovak Nuclear-Power Station; Problemes de Controle des Defauts dans les Materiaux Utilises a la Premiere Centrale Nucleaire de Tchecoslovaquie; Problemy defektoskopicheskogo kontrolya stroitel'nykh materialov reaktora pervoj chekhoslovatskoj atomnoj ehlektrostantsii; Problemas de Control de Defectos en los Materiales Utilizados en la Primera Central Nuclear de Checoslovaquia

    Energy Technology Data Exchange (ETDEWEB)

    Radislav, Filipp [Zavody Im.V.I. Lenina, Pl' zen, Czechoslovakia (Czech Republic)

    1965-09-15

    cassettes. In radiographing thick welds, betatrons of Czechoslovak manufacture are used. The paper describes the methods used for testing and the results obtained and compares the Czechoslovak 15-MeV betatron with the Siemens' betatron. (author) [French] Le memoire donne une description succincte de la cuve du reacteur de la premiere centrale nucleaire de Tchecoslovaquie. En raison des specifications rigoureuses auxquelles doivent repondre les methodes de construction et d'assemblage de la cuve du reacteur, en acier inoxydable faiblement allie de grande epaisseur (650 mm), il a fallu elaborer une methode de controle non destructif du materiau de base et des soudures, fondes sur l'emploi de ' temoins ' . Pour controler la qualite du materiau de base et des sourdures, on utilise essentiellement des ultrasons puises et une sonde. Le memoire decrit les methodes d'essais et l'evaluation des donnees au cours de l'examen du materiau de base, ainsi que le procede qui permet de verifier la qualite des soudures electriques a scorie, des soudures en atmosphere de gaz carbonique et des soudures a l'arc faites a la main. Le controle des plaques forgees et laminees se fait au moyen d'un dispositif automatique de defectoscopie qui a ete mis au point en Tchecoslovaquie. Ce dispositif se compose de deux parties: un mecanisme mobile et un detecteur a ultrasons du type U1D-A2, de fabrication tchecoslovaque. Il comprend plusieurs elements inedits. On a compense l'effet de la distance sur l'ampleur du signal declenche par un defaut de maniere que cette ampleur reste constante. On a compense aussi l'effet du aux irregularites de la liaison acoustique, les impulsions etant communiquees a un dispositif d'enregistrement a distance. L'importance du defaut est evalue a l'aide d'unattenuateur. On metau point un dispositif automatique pour controler une surface cylindrique verticale. Les soudures d'assemblage circulaire doivent etre verifiees a une temperature elevee. Dans les usines V. I. Lenine de

  7. Conference introductory keynote: Radioactive waste management and the future of nuclear energy; Elements essentiels de la conference: Gestion des dechets radioactifs et l'avenir de l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Waeterloos, Christian [Directorate General Energy and Transport, Nuclear Safety and Safeguards, European Commission, Rue de la Loi 200, 1049 Brussels (Belgium)

    2004-07-01

    Nuclear power contribution to the electricity consumption in the European Union amounts up to one third. Eight members states are nuclear electricity producers. These states make use of 143 nuclear plants. After extension of the Union 11 states will operate a total number of 163 nuclear reactors while the energy market could rest almost unchanged. On long term five members states declared a moratorium on new NPP construction while other states decided their nuclear reactors to be shut down at the end of their lifetime. A single state decided to construct a new reactor while others are hesitant. European Union's public opinion is not against nuclear power, on condition of safeguarding the nuclear installations, of non-proliferation of nuclear materials and of a secure and safe radioactive waste management. The speaker addresses the following topics: - The status of nuclear power; - The nuclear safety issue; - The directive 'Safety of nuclear installations'; - The directive 'Radioactive waste management'; - International cooperation. Summarizing, the author underlines as major target, the nuclear safety legislation proposals of The European Commission to ensure an extreme rigorous observance of nuclear protection throughout extended Union, in strict compliance with all international pertinent regulations. Application of this community legislation will enable European nuclear industry to evolve within a stable juridical frame. At the same time, by guaranteeing a sustainable high level nuclear safety the growth of a free and healthy concurrence in a deeply mutant electricity market will be enhanced. The debate on competence of the Community on nuclear safety matters was ceased as ordered by the EU Justice Court in December 2002. Indeed, the Court clearly uttered that Community has normative competence to be exerted. Hiding behind juridical arguments to avoid Union concern within a community frame in handling nuclear safety matters would be

  8. Magnetic resonance studies of solid polymers; Etude des polymeres solides par resonance magnetique

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    This paper is a review of the application of nuclear magnetic resonance (NMR) to solid polymers. In the first, theoretical part, the elements of the theory of NMR, which are necessary for the study of the properties of solid polymers are discussed: the moments method, nuclear relaxation and the distribution of correlation times. In the second part the experimental results are presented. (author) [French] Cette etude est une recherche bibliographique sur l'application de la resonance magnetique nucleaire (RMN) aux polymeres solides. Dans la premiere partie theorique on discute les elements de la theorie de RMN, necessaires pour l'etude des proprietes des polymeres solides: la methode des moments, la relaxation nucleaire et la distribution des temps de correlation. La deuxieme partie presente les resultats des experiences. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1956-07-01

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

  10. Contribution to the study of several chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses; Contribution a l'etude de quelques nuisances chimiques au centre d'etudes nucleaires de Fontenay-aux-Roses

    Energy Technology Data Exchange (ETDEWEB)

    Megemont, C; Grau, C [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-10-01

    From the checking of 2750 index cards of hazards, the study relates the distribution of the chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses. Those concerning the greatest number of agents in the Centre are classified according to the categories corresponding to the different conditions of working. Thus, the most important are put forward. Then, the authors rapidly make a review of hazards which may have some special interest because they appear more specific of the nuclear energy or because they are the most frequently noted on the index cards of hazards. The case of the tributylphosphate is studied more precisely. (authors) [French] A partir de l'examen de 2750 fiches de nuisances, l'etude porte sur la repartition des nuisances chimiques au Centre d'Etudes Nucleaires de Fontenay-aux-Roses. Celles qui concernent le plus grand nombre d'agents du Centre sont classees selon les categories correspondant aux differentes conditions de travail. Les plus importantes d'entre elles sont ainsi mises en evidence. | Les auteurs passent ensuite en revue, rapidement, les nuisances qui peuvent presenter un interet particulier soit parce qu'elles semblent plus specifiques de l'Energie Nucleaire, soit parce qu'on les rencontre le plus frequemment sur les fiches de nuisances. Le cas du tributylphosphate est envisage de facon plus detaillee. (auteurs)

  11. Awareness of households to the development of wind energy sites - Reporting on a survey; Receptivite des menages au developpement des sites eoliens. Rapport d'enquete

    Energy Technology Data Exchange (ETDEWEB)

    Voisard, M.

    2000-07-01

    This report for the Swiss Federal Office of Energy presents in tables and diagrams the results of a survey involving 421 households in Switzerland, about their awareness to energy issues and, in particular, to all what regards wind energy and wind power plants. Globally, 80% of the persons asked for their opinion believe that electric power demand will continue to increase. 66% of them are in favour of increased use of renewable energy sources and would consequently agree with a 10% more expensive end-user energy price. 89% of the persons taking part to the survey approve the installation of wind energy farms in Switzerland. Moreover, statistics indicates that the households living in regions already equipped with wind farms are significantly more favorable to the creation of new wind energy sites than those not living in these regions. By the end of the day, it turns out that the main reasons for accepting wind energy are environmental concerns as well as the fear of being obliged to use nuclear power. [French] Ce rapport presente par des graphiques et des tableaux le resultat d'un sondage d'opinion aupres de 421 menages en Suisse, sur la sensibilite du public aux problemes de l'energie et plus particulierement sur sa perception de tout ce qui concerne l'energie du vent et son exploitation par l'implantation d'eoliennes. Globalement, 80% des menages pensent que la demande d'energie electrique va poursuivre sa croissance. 66% d'entre eux sont favorables au developpement des energies renouvelables et prets a accepter en consequence une augmentation du prix de l'energie allant jusqu'a 10%. 89% des personnes interrogees sont favorables au developpement des eoliennes en Suisse. De plus, la statistique montre de maniere significative que les menages des regions dans lesquelles sont deja implantes des sites eoliens sont plus favorables au developpement des eoliennes que les autres. Finalement, le respect de l

  12. Awareness of households to the development of wind energy sites - Reporting on a survey; Receptivite des menages au developpement des sites eoliens. Rapport d'enquete

    Energy Technology Data Exchange (ETDEWEB)

    Voisard, M

    2000-07-01

    This report for the Swiss Federal Office of Energy presents in tables and diagrams the results of a survey involving 421 households in Switzerland, about their awareness to energy issues and, in particular, to all what regards wind energy and wind power plants. Globally, 80% of the persons asked for their opinion believe that electric power demand will continue to increase. 66% of them are in favour of increased use of renewable energy sources and would consequently agree with a 10% more expensive end-user energy price. 89% of the persons taking part to the survey approve the installation of wind energy farms in Switzerland. Moreover, statistics indicates that the households living in regions already equipped with wind farms are significantly more favorable to the creation of new wind energy sites than those not living in these regions. By the end of the day, it turns out that the main reasons for accepting wind energy are environmental concerns as well as the fear of being obliged to use nuclear power. [French] Ce rapport presente par des graphiques et des tableaux le resultat d'un sondage d'opinion aupres de 421 menages en Suisse, sur la sensibilite du public aux problemes de l'energie et plus particulierement sur sa perception de tout ce qui concerne l'energie du vent et son exploitation par l'implantation d'eoliennes. Globalement, 80% des menages pensent que la demande d'energie electrique va poursuivre sa croissance. 66% d'entre eux sont favorables au developpement des energies renouvelables et prets a accepter en consequence une augmentation du prix de l'energie allant jusqu'a 10%. 89% des personnes interrogees sont favorables au developpement des eoliennes en Suisse. De plus, la statistique montre de maniere significative que les menages des regions dans lesquelles sont deja implantes des sites eoliens sont plus favorables au developpement des eoliennes que les autres. Finalement, le respect de l'environnement et la crainte d'avoir a recourir a l

  13. Regulations concerning the cooking installations using the natural gas in the bakeries and the cake shops of the shopping Centers; Reglementation des installations de cuisson au gaz naturel en boulangerie-patisserie dans les centres commerciaux

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-05-01

    This brochure presents the regulation relative to the cooking installations using the natural gas in bakeries and cake shops of the shopping Centers. Following the general regulation context, the guide presents the ovens which can be installed and the associated technical restraints. The necessary conditions for the buildings, the gas alimentation, the natural gas pipelines in the buildings and the installations conditions are also presented. Finally the guide presents the maintenance facilities obligations. (A.L.B.)

  14. Application d'une équation d'état à la simulation du comportement thermodynamique des fluides dans les gisements et dans les installations de surface Application of an Equation of State to Simulating the Thermodynamic Behaviour of Fluids in Reservoirs and Surface Installations

    Directory of Open Access Journals (Sweden)

    Jain C.

    2006-11-01

    Full Text Available La connaissance des propriétés thermodynamiques des fluides pétroliers, en particulier des masses volumiques et des coefficients d'équilibre liquide-vapeur, intervient à divers stades de la production : primaire, secondaire par in-jection de gaz (C02 ou hydrocarbures miscibles, vapeur d'eau, séparation, réseau de collecte et de transport. L'ampleur du domaine de pression et de température à l'intérieur duquel on a besoin de connaître les propriétés des huiles et des gaz à condensat, et le fait que la compo-sition d'ensemble des mélanges diphasiques ne cesse de varier au cours de leur déplacement soit dans les gisements, soit dans les installations d'exploitation, rendent mani-feste l'intérêt de pouvoir calculer ces propriétés, en évi-tant d'avoir recours à des travaux de laboratoire beaucoup trop importants. Pour résoudre ces problèmes, une nouvelle équation d'état appelée Redlich-Kwong Développée (RKD a été mise au point. Au cours de cet exposé, nous verrons que cette équation restitue les enveloppes diphasiques de l'équilibre liquide-vapeur avec une qualité au moins égale à celles des méthodes de Soave et de Peng-Robinson qui jouissent actuellement d'une grande notoriété. L'avantage de ce modèle sur ces dernières méthodes est l'évaluation simultanée des propriétés volumétriques des phases en présence avec une bonne précision, ce qui est d'une grande utilité pour l'application de ce modèle aux problèmes industriels. Knowing the thermodynamic properties of petroleum fluids, and in particular the density and liquid-vapor equilibrium coefficients, is important at different stages of production, i. e. primary production, secondary production by gas flooding (CO2 or miscible hydrocarbons, steam, separation, gathering network and transportation. The pressure and temperature range within which the oil and gas-condensate properties must be known coupled with the fact that the overall composition of

  15. Part 1: The detection of criticality accidents in the Commissariat a l'Energie Atomique. Part 2: The Burst Slug Detection; 1. partie: la detection des accidents de criticite au Commissariat a l'Energie Atomique. 2. partie.: la detection des ruptures de gaines

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    of the plant. The techniques developed during this programme can be subsequently adapted to easily solve problems of detection in other types of reactor. The main characteristics of the evolution of the various installations constructed or under construction is reflected in the continuous progress towards greater automation and the use of detectors working under higher and higher temperatures and pressures. Succeeding to the reactor G3 whose BSD installation was already highly automatic, the EDF reactors at Chinon use digital computers especially meant for BSD data processing. In the planned reactor EL 4, the BSD measurements will be processed with all the other control measurements in a centralized computer unit. The progressive pressure increase of the cooling gas (15 bars in G3, 25 bars in the Chinon reactors, 60 bars in EL 4) has required the development of electric precipitations able to separate and measure the fission products in the carbonic gas at temperatures reaching 300 C and under pressures as high as 60 bars. In spite of the severe conditions of utilisation, the various devices developed offer all the guarantees of safety and long life expectancy required for their use on BSD installations. (authors) [French] Dans toute installation ou est manipulee de la matiere fissile en quantite potentiellement superieure a la masse critique, existe, quelles que soient les precautions prises, un risque permanent d'excursion nucleaire accidentelle, pouvant entrainer une irradiation grave du personnel. La detection immediate suivie d'une evacuation rapide limite considerablement les risques d'irradiation dus aux produits de fission ou a la reaction nucleaire elle-meme si elle se poursuit. Les phenomenes physiques qui accompagnent une excursion nucleaire, demeurant insuffisants pour suivre l'alarme et pouvant preter a confusion, la necessite d'un appareillage approprie de la detection des accidents de criticite s'impose donc. Compte-tenu des caracteristiques des

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

    International Nuclear Information System (INIS)

    Debiesse, J.

    1958-01-01

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

  17. Control of risks: comparative evaluation between the different kind of approach in industrial area. Relative focalization to nuclear and chemical sectors. Phase two; Maitrise des risques: evaluation comparative des modes d`approche dans les secteurs industriels. Focalisation relative aux secteurs nucleaires et chimiques. Deuxieme phase

    Energy Technology Data Exchange (ETDEWEB)

    Brenot, J; El Jammal, M H

    1997-12-31

    The research made here for the Ministry of Environment, aims the probabilistic approach, to examine its differences with the determinist approach in the frame of risk management, and to know if the both approaches are inducted by the nature of dangers, the quality of data, the theoretical knowledge or the kind of problem to mange ( monitoring of installations, functioning agreements, and so on). The nuclear activities, the chemical installations and the transports of dangerous materials illustrate the present purpose. (N.C.)

  18. Control of risks: comparative evaluation between the different kind of approach in industrial area. Relative focalization to nuclear and chemical sectors. Phase two; Maitrise des risques: evaluation comparative des modes d`approche dans les secteurs industriels. Focalisation relative aux secteurs nucleaires et chimiques. Deuxieme phase

    Energy Technology Data Exchange (ETDEWEB)

    Brenot, J.; El Jammal, M.H

    1996-12-31

    The research made here for the Ministry of Environment, aims the probabilistic approach, to examine its differences with the determinist approach in the frame of risk management, and to know if the both approaches are inducted by the nature of dangers, the quality of data, the theoretical knowledge or the kind of problem to mange ( monitoring of installations, functioning agreements, and so on). The nuclear activities, the chemical installations and the transports of dangerous materials illustrate the present purpose. (N.C.)

  19. A comprehensive survey of nuclear reactions; Panorama des reactions nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Cugnon, J. [Liege Univ., IFPA, AGO Dept. (Belgium)

    2007-07-01

    The various mechanisms of nuclear reactions are surveyed and classified in different regimes, based on the notions of coherent mechanisms and hard versus soft processes. The emphasis is put on the concepts at the basis of the understanding of these regimes and on the elements of nuclear structure which are involved in these different regimes, as well as the on the possibility of extracting this information. Due to lack of space and for pedagogical reasons, the discussion is limited to nucleon-induced and light-ion-induced reactions. However, a few remarks are given concerning some specific probes, such as weakly bound projectiles or neutron-rich nuclei. (author)

  20. Nuclear waste management; La gestion des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Nifenecker, H.

    2008-07-01

    The author gives an overview of the main issues related to the use of nuclear energy: the management and the environmental impact of wastes. After having outlined the different radiological consequences of different radionuclides, he proposes an approximate assessment of waste production which may depend on reactor technology, and which needs a distinction between low level, intermediate level, and high level wastes. He discusses the differences between primary energies and final energies, and how to consider nuclear energy and its wastes within this classification. Then, considering the deep geological storage, he describes how contamination may occur and the risks for the population as well as for the environment. After having evoked the use of breeder reactors and its separation-transmutation issues, the author briefly comments the nuclear waste financing issue

  1. Nuclear molecular imaging of paragangliomas; Imagerie moleculaire nucleaire des paragangliomes

    Energy Technology Data Exchange (ETDEWEB)

    Taieb, D.; Tessonnier, L.; Mundler, O. [Service central de biophysique et de medecine nucleaire, CHU de la Timone, 13 - Marseille (France)

    2010-08-15

    Paragangliomas (PGL) are relatively rare neural crest tumors originating in the adrenal medulla (usually called pheochromocytoma), chemoreceptors (i.e., carotid and aortic bodies) or autonomic ganglia. These tumors are highly vascular, usually benign and slow-growing. PGL may occur as sporadic or familial entities, the latter mostly in association with germline mutations of the succinate dehydrogenase (SDH) B, SDHC, SDHD, SDH5, von Hippel-Lindau (VHL), ret proto-oncogene (RET), neurofibromatosis 1 (NF1) (von Recklinghausen's disease), prolyl hydroxylase domain protein 2 (PHD2) genes and TMEM127. Molecular nuclear imaging has a central role in characterization of PGL and include: somatostatin receptor imaging ({sup 111}In, {sup 68}Ga), MIBG scintigraphy ({sup 131}I, {sup 123}I), {sup 18}F-dihydroxy-phenylalanine ({sup 18}F-DOPA) positron emission tomography (PET), and {sup 18}F-deoxyglucose ({sup 18}F-FDG) PET. The choice of the tracer is not yet fully established but the work-up of familial forms often require the combination of multiple approaches. (authors)

  2. The processing and management of wastes from atomic reactors; Nouvelles installations industrielles du C.E.A. pour le traitement des dechets radioactifs liquides et solides

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The policy concerning radioactive wastes studied by all Atomic Centres has led to various procedures which, while apparently numerous, come under a few standard headings. Whether the wastes are in the liquid or solid state their management depends on their physical and chemical nature. The procedure adopted is governed by three general principles: - determination of the most economical means possible of storage and processing by volume reduction; - conversion to a solid compact form; - complete acceptance of the accepted standards at all places and all times. In this communication all the standard solutions adopted and used by the various Centres of the Commissariat a l'Energie Atomique will be examined bearing in mind the preceding remarks. Particular mention will be made of the following: - For liquids, physical, chemical and physico-chemical processing - For solids, decontamination, volume reduction and long-term conditioning techniques. The different procedures for collecting and storing solid wastes before and after processing are also discussed. The paper ends with a brief review of the studies, both technical and economic, being pursued on this subject. (authors) [French] La gestion des dechets etudies par tous les Centres Atomiques a donne lieu a des solutions qui - bien que nombreuses en apparence - se ramenent a quelques solutions types, peu nombreuses. Qu'il s'agisse de dechets solides ou liquides, la nature physique et chimique des dechets conditionne leur mode de gestion. Celle-ci procede de trois principes generaux: - recherche du mode de stockage et de traitement aussi economique que possible par reduction de volume; - mise sous forme compacte solide; - garantie du respect des normes en tous lieux et en tous temps. Dans cette communication, nous examinons toutes les solutions types, compte tenu des remarques precedentes, qui ont ete adoptees et sont utilisees par les differents Centres du Commissariat a l'Energie Atomique. Nous rappelons en

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

  4. Fire prevention in industrial installations presenting a risk for man and environment (ICPE); La prevention des incendies dans les ICPE: une exigence d'amelioration permanente

    Energy Technology Data Exchange (ETDEWEB)

    Moche, L. [Ministere de l' Amenagement du Territoire et de l' Environnement, Direction de la Prevention des Pollutions et des Risques, 75 - Paris (France)

    2000-09-01

    The most likely accident in industrial installations is fire. 59 out of 100 accidents reported in 1999 describe a fire outbreak, the fire is either the initiating cause of the accident or the form into which the event eventually evolves. This article briefly describes the why and the wherefore of French regulations on fire prevention in installations presenting a risk for man and environment. The French system is based on the responsibility of the plant operator and on the result of inspections performed by authorities to check the conformity of the installation with current regulations. (A.C.)

  5. The Use of the Moessbauer Effect in Investigating the Chemical Effects of Nuclear Transmutations in Oxygenous Compounds of Manganese and Tin; Utilisation de l'Effet Moessbauer pour l'Etude des Effets Chimiques des Transformations Nucleaires dans les Composes de Manganese et d'Etain; 0418 0421 0421 041b 0415 0414 ; Empleo del Efecto Moessbauer para Investigar las Transformaciones Nucleares de Compuestos Oxigenados de Estano y de Manganeso

    Energy Technology Data Exchange (ETDEWEB)

    Nesmejanov, An. N.; Babeshkin, A. M.; Kosev, N. P.; Bekker, A. A.; Lebedev, V. A. [Moskovskij Gosudarstvennyj Universitet Im. M.V. Lomonosova, Moskva, SSSR (Russian Federation)

    1965-04-15

    auteurs ont etudie les formes de stabilisation des atomes de recul de 56 Mn des solutions et des echantillons solides irradies de permanganate, ainsi que celles des atomes de recul de {sup 119m}Sn dans l'oxyde et le bioxyde d'etain. Les echantillons de permanganate ont ete irradies dans un bloc de paraffine a l'aide d'une source au polonium-beryllium donnant un flux de neutrons de 10{sup 7} a 10{sup 8} n/cm{sup 2} * s. Les atomes chauds de {sup 56}Mn qui se forment peuvent avoir les valences +7, +4 et inferieures. Les echantillons (SnO et SnO{sub 2}), exposes dans un reacteur a un flux de 2,2 * 10{sup 13} n/cm{sup 2} * s pendant 1800 h, ont ete directement utilises pour la preparation de sources destinees a l'etude de l'absorption par resonance des phonons dans une installation fonctionnant a vitesse constante. Des composes d'etain correspondants ont ete employes comme absorbeurs. On n'a constate la presence d'atomes {sup 119m}Sn de recul qu'a l'etat tetravalent. Sur la base des donnees obtenues, les auteurs examinent le mecanisme de stabilisation des atomes de recul. (author) [Spanish] Los metodos utilizados corrientemente para estudiar el estado quimico de los atomos de retroceso, esto es, aquellos asociados a los cambios de fase (analisis quimico, cromatografia, electroforesis), lo mismo que el recocido, solo permiten conocer indirectamente el mecanismo de estabilizacion de los atomos calientes. Cuando el analisis se efectua por el metodo de absorcion por resonancia de los cuantos gamma sin retroceso, no se introduce en la muestra ninguna modificacion capaz de influir en las formas de estabilizacion, incluso si la estabilidad no es muy grande. Los autores investigaron las formas de estabilizacion de los atomos de retroceso del {sup 56}Mn en soluciones y muestras solidas de permanganato irradiadas, y las de los atomos de retroceso del {sup 119m}Sn en oxido estannico y estannoso. Las muestras del permanganato se irradiaron en un bloque de parafina con un flujo de 10{sup

  6. Organization and methodology applied to the control of commissioning tests to guarantee safe operation of nuclear units; Organisation et methodologie appliquees au controle des essais de mise en service pour assurer la surete de fonctionnement des tranches electronucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Clausner, J P; Jorel, M

    1990-12-01

    This paper describes the activities of the Safety Analysis Department (DAS), which provides technical support for the French safety authorities in the specific context of analysis and control of startup test programme quality at each of the different stages of the programme. These activities combine to ensure that the objective of the startup tests is reached, in particular that the functions of each safety-related system are guaranteed in all operating configurations, that the performance levels of all components in the system comply with design criteria and that defects revealed during previous tests have been dealt with correctly. The special case of French nuclear facilities, linked to unit standardization, has made it possible to acquire a large amount of experience with the startup of the 900 MWe units and has illustrated the importance of defining a startup test programme. In 1981, a working group, comprising operating organization and safety authority representatives, studied the lessons which had to be learned from 900 MWe unit startup and the improvements which could be made and taken into account in the 1300 MWe unit startup programme. To illustrate the approach adopted by the DAS, we go on to describe the lessons learned from startup of the first 1300 MWe (P4) units. (author) [French] Au sein de l'Institut de Protection et de Surete Nucleaire (IPSN), le Departement d'Analyse de Surete (DAS) constitue le support technique du Service Central de Surete des Installations Nucleaires (SCSIN) qui est l'autorite de surete francaise. A ce titre, il evalue les programmes d'essais de demarrage et emet un avis sur le traitement des problemes survenus au cours des essais. Pour ce faire, le DAS assure l'analyse du programme d'essais depuis l'elaboration des documents jusqu'a la montee du reacteur a sa puissance nominale. L'evaluation du DAS commence par une analyse approfondie des programmes de principe d'essais (PPE) qui sont etablis par Electricite de France (EDF

  7. Recommendations for the lighting of sporting facilities. 5. edition; Recommandations relatives a l'eclairage des installations sportives. 5. edition

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-01-01

    Natural and artificial lighting is an important factor of comfort, pleasure and safety in sporting facilities and influences the construction costs but also the frequenting of installations. The duration of use of installations and the profitability of investments are directly linked with the prolongation of visiting hours for competition, training and leisure purposes. This book presents, first, the common recommendations and principles for the lighting of sporting facilities in general. The particular recommendations relative to some specific activities are considered in a second part (golf, ski, bowls, pelota, skate-board, hippodromes etc..). (J.S.)

  8. Reports by the Parliamentary Office for scientific and technological assessments. Thursday, May 5, 2011. Post-accidental management of nuclear crisis; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 5 mai 2011. Gestion post-accidentelle des crises nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-05-15

    The first part addresses the preparedness of the post-accidental management in France. Representatives of control agencies and of nuclear installation operators are asked how they prepare and plan the worst scenario, what is purely hypothetical and what comes from return on experience, how knowledge and practices of other hazardous situations (notably in the chemical industry) can be useful for the nuclear sector. The second part addresses the commitment of French and foreign stakeholders in the management of a post-accidental situation: role and intervention of associations, French participation at the international level and international cooperation in the preparation to the management of a post-accidental situation

  9. Du désir d’île à l’installation, les circulations migratoires des Métropolitains à la Martinique

    Directory of Open Access Journals (Sweden)

    Michel Desse

    2008-09-01

    Full Text Available Le lien entre migration et Antilles françaises est souvent traité en termes d’émigration insulaire vers l’Hexagone. En effet, les flux les plus nombreux correspondent encore à ce mouvement centripète qui s’explique par une situation sociale tendue du fait de l’inadaptation entre l’offre de travail et les jeunes adultes en trop grand nombre. Pourtant les mobilités venant de Métropole existent avec le retour des Antillais au pays. Les Antilles attirent aussi les Métropolitains. La tertiairisation de l’économie, les investissements des grandes sociétés françaises ainsi que les dernières lois de défiscalisation ou celles concernant la création d’entreprises semblent favorisent le mouvement. L’article se propose d’analyser les moteurs de ces nouvelles formes de circulation migratoire entre la France métropolitaine et la Martinique, ainsi que l’insertion économique et les territorialités spécifiques des nouveaux acteurs.The migration-West Indies nexus is often dealt with in terms of insular emigration towards Metropolitan France. Indeed, most of the flows are still characterised by a centripetal move that can be accounted for by the hiatus between job supply and the demographic importance of the youth. Nonetheless, Metropolitan-origin mobility exist with West Indian return migration as well as Metropolitan French migration. The boom of the service economy, investments from large French firms and recent advantageous fiscal laws favour this pattern. The article seeks to analyse the new driving forces behind the circular movement between Metropolitan France and Martinique, as well as the economic insertion and the specific territorialities of the new actors.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    1. Introduction: the present paper is devoted to analog simulation of problems related to nuclear reactors other than the simulation of the kinetic equations which is well known. 2. Thermodynamic problems: various problems relative to temperature evolution in a reactor, in a pipe, in an exchanger, in a turbine, are studied, and simulation techniques used by earlier authors are critically reviewed. 3. Pipe simulators: it is shown that this problem can be solved by the use of specialized simulators which will be described and analysed. 4. Rotating machine simulators: the particular aspect of rotating machine calculations introducing frequent use of diagrams is emphasized. A simulator requiring both digital and analogue methods is described. 5. The study of a nuclear power station: as an example it is proposed to discuss problems a rising in connection with the preceding elements (a, b, c, d) when simulating the behaviour of large nuclear plants. The part played by ordinary computing elements for the simulation of the different servomechanism transfer functions is considered and process of regulation is outlined. 6. Conclusion: the necessity of the use of high quality simulators and computers is underlined and the accuracy of the solutions is discussed. (author)Fren. [French] 1. Cinetique des reacteurs: la simulation des equations cinetiques d'un reacteur nucleaire ne pose desormais plus de probleme. II est donc possible de faire le point des differentes applications de la technique analogique dans ce domaine. 2. Les problemes thermodynamiques: on discute les differents problemes poses par l'evolution des temperatures dans un reacteur, dans une tuyauterie, dans un echangeur, dans une turbine, et on passe en revue les techniques de simulation proposees jusqu'a ce jour. 3s simulateurs de tuyauteries: on montre comment les differents problemes poses ci-dessus peuvent etre resolus, pour une classe tres vaste de reacteurs par l'emploi de simulateurs speciaux que l

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

  12. Prevention of the Causes and Consequences of Criticality Accidents: Measures Adopted in France; Prevention des Causes et des Consequences d'un Accident de Criticite: Solutions Adoptees en France

    Energy Technology Data Exchange (ETDEWEB)

    Fruchard, Y.; Lavie, J. -M. [Commissariat a l' Energie Atomique, Paris (France)

    1966-05-15

    et psychologique. Les accidents de criticite survenus dans l'industrie nucleaire, malgre leur rarete, devoilent les imperfections des techniques de prevention, et constituent la seule base realiste disponible en vue de l'evaluation des consequences et de la mise au point de mesures de protection. Les auteurs presentent une analyse des causes et des consequences connues des accidents de criticite survenus et en degagent un certain nombre d'observations: sur la validite des criteres traditionnels de surete, la probabilite que des accidents se produisent suivant la nature des operations, les accidents caracteristiques susceptibles de servir de modele, et l'ampleur des consequences radiologiques possibles. Les solutions adoptees en France pour limiter les consequences d'un eventuel accident de criticite (situation, conception et amenagement des installations; detection des accidents; dosimetrie pour le personnel expose) sont brievement decrites apres un rapide expose des principes ayant preside a leur choix. L'incidence economique du choix et de l'homogeneite des mesures de protection est examinee eu egard a leur fiabilite. (author)

  13. Risk Analysis of Flare Flame-out Condition in a Gas Process Facility Analyse des risques des conditions d’extinction de torche au sein d’une installation de traitement de gaz

    Directory of Open Access Journals (Sweden)

    Zadakbar O.

    2011-02-01

    Full Text Available Flaring is a common method of disposal of flammable waste gases in the downstream industries. Flare flame out (flame lift-off or blow-outs often occurs causing toxic vapors to discharge. The toxic gases released may have hazardous effects on the surrounding environment. To study the effect of inhalation exposure of these toxic gases on human health, the four steps of the EPA (Environmental Protection Agency framework with the field data to quantify the cancer and non-cancer health risks are integrated in this paper. As a part of exposure assessment, gas dispersion modeling using AERMOD and UDM-PHAST is applied in two different conditions of normal flaring and flare flame out during a particular climate condition in Khangiran region. Recommendations to avoid flare flame out conditions are also presented here. Le torchage est un procédé courant d’élimination des gaz résiduaires inflammables dans les industries de traitement. L’extinction de la torche (par décollage ou soufflage de flamme provoque souvent une émission de vapeurs toxiques. Ces gaz toxiques libérés peuvent présenter des effets dangereux sur le milieu environnant. Pour étudier l’effet d’une exposition par inhalation de ces gaz toxiques sur la santé, cet article croise les quatre étapes de la démarche de l’EPA (Environmental Protection Agency, Agence de protection de l’environnement avec les données d’exploitation afin de quantifier le risque sanitaire cancérologique et non cancérologique. Dans le cadre de l’estimation d’exposition, une modélisation de dispersion des gaz utilisant AERMOD et UDM-PHAST est évaluée dans deux configurations différentes de torchage normal et d’extinction de torche à l’occasion de conditions climatiques particulières dans la région du Khangiran. L’article propose également des recommandations destinées à éviter les conditions d’une extinction de flamme de torche.

  14. Wind power installations in Switzerland - Guidelines for the analysis of environmental impact; Eoliennes en Suisse. Guide pour l'analyse des effets sur l'environnement

    Energy Technology Data Exchange (ETDEWEB)

    Ott, W.; Kaufmann, Y.; Steiner, P. [Econcept AG, Zuerich (Switzerland); Gilgen, K.; Sartoris, A. [IRAP-HSR, Institut fuer Raumentwicklung an der Hochschule fuer Technik Rapperswil, Rapperswil (Switzerland)

    2008-07-01

    This report published by the Swiss Federal Office of Energy (SFOE) provides guidelines concerning the impact of the construction of wind-energy installations on the environment in Switzerland. The report aims to ascertain the relevant environmental aspects of the construction of such wind turbines. If no relevant restrictions apply, the acceptance of such wind power installations is said to increase. The guidelines also recommend a standardised course of action and provide sources of information for investors that are necessary for successful planning. The results which can be obtained by using these guidelines can be used to compile a short-form report for cantonal environment protection agencies. An appendix contains an example of the structure of such a report.

  15. Caractérisation de la perméabilité des couches constituant la barrière passive des installations de stockage de déchets non dangereux Permeability characterization of the geological barrier of non dangerous landfill sites

    Directory of Open Access Journals (Sweden)

    Mouthier B.

    2012-09-01

    Full Text Available Pour obtenir son autorisation d’exploiter, une Installation de Stockage de Déchets Non Dangereux (ISDND doit justifier réglementairement sa favorabilité géologique. Le « Guide de bonnes pratiques pour les reconnaissances géologiques » de l’AFNOR fournit les critères d’aptitude du site à recevoir une ISDND et les moyens à mettre en œuvre, dont ceux qui concernent la perméabilité des couches géologiques qui protègent le milieu naturel. La mesure de la perméabilité in situ, en forage, des matériaux peu à très peu perméables des deux couches de la barrière de sécurité passive, est une opération délicate qui nécessite une mise en œuvre soignée respectant les normes appropriées, choisies en fonction des gammes de perméabilité attendues. Plusieurs types d’essai en forage sont présentés. In order to get administrative authorization, a non dangerous waste landfill site (ISDND, must justify a favourable geological context, which follows the AFNOR “Guide de bonnes pratiques pour les reconnaissances géologiques ». Criteria and technical means are described among which the in situ and lab permeability determination processes. The low and very low permeability coefficient to be measured within the deep argillaceous formations of a landfill site, is a delicate operation which must be representative and accurate. Depending the permeability range, several norms are proposed.

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

    Directory of Open Access Journals (Sweden)

    Morillon R.

    2006-11-01

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

  17. Mobilising the market potential of biogas installations in Switzerland; Mobilisierung des Marktpotenzials von Biogasanlagen in der Schweiz. Vorstudie: Synthese des vorhandenen Wissens zu Hemmnissen und Foerderfaktoren landwirtschaftlicher und gewerblichindustrieller Biogasanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Umbach-Daniel, A.; Ruetter, H.

    2004-07-01

    This final report for the Swiss Federal Office of Energy (SFOE) presents the results of a preliminary study that aimed to provide a synthesis of all available knowledge on obstacles to the construction of agricultural and commercial/industrial biogas installations and promotional factors. Social, political and cultural factors are examined that can promote or hinder the introduction of the technology and comparison is made to the introduction of organic farming methods in agriculture. In particular, an 'adoption/diffusion' model is looked at. A second part of the report deals with the economic findings and deals with the economic viability of biogas installations and the investments and costs involved. Here, too, economic factors that promote or hinder the use of biogas are examined. Finally, the various players and factors influencing the Swiss biogas scene are looked at and the findings of the study are summarised.

  18. Presentation of the health impact evaluation study of atmospheric emissions of a major coal combustion installation; Mise a jour de l'etude d'evaluation de l'impact sur la sante des rejets atmospheriques des tranches charbon d'une grande installation de combustion

    Energy Technology Data Exchange (ETDEWEB)

    Bonnard, R

    2004-12-15

    In the framework of a working group on the major installations, a study has been realized on a today coal combustion installation. The direct risk by inhalation and the risks bond to indirect exposure of atmospheric releases were analyzed. The calculation method is explained and the uncertainties are discussed to present the results. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Charmasson, S

    1998-07-01

    Man-made radionuclides released into the marine environment by the installations from the nuclear fuel cycle are used as tracers of various bio-geochemical processes. Several installations belonging to the whole nuclear fuel cycle, except the uranium mining, are set up on the Rhone River Banks. The sea disposal of low and intermediate level radioactive waste has never been authorized in the Mediterranean sea but several sites have been used in the North-East especially in abyssal waters. Radionuclides released by the Rhone river installations are used in order to study the dynamics of the Rhone inputs into the Mediterranean Sea. In the river, freshwater samples reflect quite accurately the discharge composition with a predominance of {sup 106}Ru, a radionuclide mostly released by the spent nuclear fuel reprocessing plant in Marcoule. Conversely, at the Rhone mouth, in the sediment compartment {sup 106}Ru yields to caesium isotopes ({sup 134}Cs and {sup 137}Cs) in importance. As these two isotopes demonstrate very different half-lives (30,2 and 2,1 years respectively), the temporal evolution of their ratio acts as a chronometer enabled to date sediment accumulation near the river mouth. Mean accumulation rates greater than 35 cm y{sup -1} have been determined in the pro-deltaic zone near the Roustan buoys over the period 1983-1991. Accumulation rates decrease rapidly with distance from the mouth and therefore most of the {sup 137}Cs inventory in this part of the Gulf of Lions is limited to the pro-deltaic area. A first study about the part the different {sup 137}Cs sources in the Mediterranean Sea play in this inventory has been carried out. Direct (atmospheric) and indirect (fluviatile) inputs due to fallout from both past nuclear tests and the Chernobyl accident could contribute to this inventory at the highest to 40 % while the industrial releases could contribute at the lowest to 60 %. The last site used for the dumping of low and intermediate level radioactive

  20. Production of nuclear graphite in France; Production de graphite nucleaire en France

    Energy Technology Data Exchange (ETDEWEB)

    Legendre, P; Mondet, L [Societe Pechiney, 74 - Chedde (France); Arragon, Ph; Cornuault, P; Gueron, J; Hering, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The graphite intended for the construction of the reactors is obtained by the usual process: confection of a cake from coke of oil and tar, cooked (in a electric oven) then the product of cook is graphitized, also by electric heating. The use of the air transportation and the control of conditions cooking and graphitization have permitted to increase the nuclear graphite production as well as to better control their physical and mechanical properties and to reduce to the minimum the unwanted stains. (M.B.) [French] Le graphite destine a la construction des reacteurs est obtenu par le procede usuel: confection d'une pate a partir de coke de petrole et de brai, cuisson de cette pate (au four electrique) puis graphitation du produit cuit, egalement par chauffage electrique. L'usage du transport pneumatique et le controle des conditions cuisson et de graphitation ont permit d'augmenter la production de graphite nucleaire ainsi que de mieux controler ses proprietes physiques et mecaniques et de reduire au minimum les souillures accidentelles. (M.B.)

  1. Report by the AERES on the unit: Unit of researches on neutron transport and radioactivity confinement in nuclear installations under the supervision of the establishments and bodies: IRSN; Rapport de l'AERES sur l'unite: Unite de recherches en neutronique et confinement de la radioactivite dans les installations nucleaires sous tutelle des etablissements et organismes: IRSN

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    This report is a kind of audit report on a research laboratory whose activity is organized in three departments: neutron transport and criticality (themes: numerical methods, maths and statistics related to the simulation of neutral particle propagation, nuclear data, uncertainty propagation and bias estimation, code qualification and associated experimental programs, neutron transport in reactors and fuel cycle, criticality accidents), radionuclide transfer in radioactive waste disposals (site identification strategy, hydro-mechanical phenomena affecting storage performance, physical-chemical evolution factors, storage modelling), and metrology and confinement of radioactive gases and aerosols. The authors discuss an assessment of the unit activities in terms of strengths and opportunities, aspects to be improved and recommendations, productions and publications. A more detailed assessment is presented for each department in terms of scientific quality, influence and attractiveness (awards, recruitment capacity, capacity to obtain financing and to tender, participation to international programs), strategy and governance, and project

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

  5. Regulation imposed to nuclear facility operators for the elaboration of 'waste studies' and 'waste statuses'; Reglementation imposee aux exploitants d'installations nucleaires pour l'elaboration ''des etudes dechets'' et ''des bilans dechets''

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-04

    This decision from the French authority of nuclear safety (ASN) aims at validating the new versions of the guidebook for the elaboration of 'waste studies' for nuclear facilities and of the specifications for the elaboration of 'waste statuses' for nuclear facilities. This paper includes two documents. The first one is a guidebook devoted to nuclear facility operators which fixes the rules of production of waste studies according to the articles 20 to 26 of the inter-ministry by-law from December 31, 1999 (waste zoning conditions and ASN's control modalities). The second document concerns the specifications for the establishment of annual waste statuses according to article 27 of the inter-ministry by-law from December 31, 1999 (rational management of nuclear wastes). (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-04-15

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

  7. Radiopharmaceutical projects of CNESTEN (Centre National de l'Energie, des Sciences et des Techniques Nucleaires)

    International Nuclear Information System (INIS)

    2000-01-01

    In nuclear medicine, the prescriptions of isotopic investigations are increasing because they can provide early information about morphological anomalies and permit,so to avoid long and onerous treatments. Until now, Morocco imports the radiopharmaceuticals in spite of the difficulties related to administrative procedures. To facilitate these procedures CNESTEN has launched a project which involves the following activities: - Import and distribution of needed radiopharmaceuticals; - development and production of new radiopharmaceutical kits in cooperation with scientific partners. Priority is given to the most prescribed radiopharmaceuticals. Many kits have been produced with manufacturing protocol modifications aiming to improve and optimize the production processes. The quality of the obtained products is tested and their biodistribution kinetics are studied. (F.M.)

  8. Installing Omeka

    Directory of Open Access Journals (Sweden)

    Jonathan Reeve

    2016-07-01

    Full Text Available Omeka.net is a useful service for Omeka beginners, but there are a few reasons why you might want to install your own copy of Omeka. Reasons include: * Upgrades. By installing Omeka yourself, you can use the latest versions of Omeka as soon as they’re released, without having to wait for Omeka.net to upgrade their system. * Plugins and themes. You can install any plugin or theme you want, without being restricted to those provided by Omeka.net. * Customizations. You can buy a custom domain name, and customize your code to achieve your desired functionality. * Control. You have control over your own backups, and you can update the server yourself so that its security is always up-to-date. * Price. There are many low-cost Virtual Private Servers (VPSs now, some of which cost only $5 per month. * Storage. Many shared hosting providers now offer unlimited storage. This is useful if you have a large media library. In this tutorial, we’ll be entering a few commands on the command line. This tutorial assumes no prior knowledge of the command line, but if you want a concise primer, consult the Programming Historian introduction to BASH. There are other ways of installing Omeka, of course, some using exclusively GUI tools. Some hosting providers even offer “one-click installs” via their control panels. Many of those methods, however, will install older versions of Omeka which are then harder to upgrade and maintain. The method outlined below may not be the easiest way to install Omeka, but it will give you some good practice with using the command line, which is a skill that will be useful if you want to manually upgrade your install, or manually install other web frameworks. (For example, this installation method is very similar to WordPress’s “Five-Minute Install”. There are four steps to this process, and it should take about an hour.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  10. Nuclear developments at the international inter govern mental level (1961); Developpements nucleaires sur le plan international intergouvernemental (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    The United Nations organisation and nuclear energy rose simultaneously, in 1945, to occupy an important place in the public eye. The spiritual succession of the League of Nations which had foundered during the war was taken up by the new organisation which sought to implant its political ideal in a more tangible reality, so that it might thereby be inspired by concrete and substantial objectives. This is one of the reasons for the existence of the dozen specialized agencies created by the family of the United Nations and dealing with Health, Culture, Agriculture, Finance, etc. Nuclear energy is one of these techniques. Becoming suddenly an important power factor and exploiting for itself the prestige of Science, it became the favorite domain for the growth of this new spirit, as much in its universal form in 1945 as in its more regional form which it was later to adopt. The achievements are numerous and of varying importance; they deserve te be studied carefully. (author) [French] L'organisation des Nations Unies et le nucleaire ont ete places simultanement, en 1945, au premier plan de la scene mondiale. La Societe des Nations ayant sombre pendant la guerre, son heritage spirituel fut recueilli par la nouvelle organisation qui chercha a enraciner son ideal politique dans une realite plus materielle, de facon a y puiser une nourriture concrete et substantielle. C'est une des raisons d'existence de la douzaine d'institutions specialisees gravitant dans la famille des Nations Unies et s'occupant de Sante, de Culture, d'Agriculture, de Finances, etc. Le nucleaire est l'une de ces techniques. Devenu soudainement un facteur primordial de puissance, Cristallisant a son benefice le prestige de la Science, c'etait un terrain de predilection pour le developpement du nouvel esprit, aussi bien sous la forme universelle de 1945, que sous les formes regionales qui ont vu le jour ensuite. Les travaux realises que nombreux, d'importance tres inegale. Ils meritent qu'on les examine

  11. Nuclear developments at the international inter govern mental level (1961); Developpements nucleaires sur le plan international intergouvernemental (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    The United Nations organisation and nuclear energy rose simultaneously, in 1945, to occupy an important place in the public eye. The spiritual succession of the League of Nations which had foundered during the war was taken up by the new organisation which sought to implant its political ideal in a more tangible reality, so that it might thereby be inspired by concrete and substantial objectives. This is one of the reasons for the existence of the dozen specialized agencies created by the family of the United Nations and dealing with Health, Culture, Agriculture, Finance, etc. Nuclear energy is one of these techniques. Becoming suddenly an important power factor and exploiting for itself the prestige of Science, it became the favorite domain for the growth of this new spirit, as much in its universal form in 1945 as in its more regional form which it was later to adopt. The achievements are numerous and of varying importance; they deserve te be studied carefully. (author) [French] L'organisation des Nations Unies et le nucleaire ont ete places simultanement, en 1945, au premier plan de la scene mondiale. La Societe des Nations ayant sombre pendant la guerre, son heritage spirituel fut recueilli par la nouvelle organisation qui chercha a enraciner son ideal politique dans une realite plus materielle, de facon a y puiser une nourriture concrete et substantielle. C'est une des raisons d'existence de la douzaine d'institutions specialisees gravitant dans la famille des Nations Unies et s'occupant de Sante, de Culture, d'Agriculture, de Finances, etc. Le nucleaire est l'une de ces techniques. Devenu soudainement un facteur primordial de puissance, Cristallisant a son benefice le prestige de la Science, c'etait un terrain de predilection pour le developpement du nouvel esprit, aussi bien sous la forme universelle de 1945, que sous les formes regionales qui ont vu le jour ensuite. Les travaux realises que nombreux, d

  12. Radioisotopes in sedimentology; Emploi des radioelements en sedimentologie

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, G [CEA, Centre d' etudes Nucleaires de Saclay (France)

    1967-05-15

    precipitation of sediment as a function of the physico-chemical characteristics of the water-bod y, and measurements of sediment density by means of back-scattering gauges. (author) [French] Les radioelements en sedimentologie trouvent emploi principalement dans deux grandes voies: l'etude de la dynamique des sediments en milieu fluvial et maritime et la mesure en continu de la quantite de sediments en suspension dans un milieu donne; ces deux questions sont examinees en detail et l'auteur decrit brievement quelques exemples d'autres applications n'entrant pas dans ces domaines. -Dynamique des sediments. Apres avoir rappele le principe de base de cette etude (injection dans le courant d'un sediment marque ou d'un simulateur suivie de la detection dans le temps du deplacement de l'activite), l'auteur fournit une liste aussi exhaustive que possible des problemes susceptibles d'etre resolus par l'emploi d'une telle technique. Ils sont essentiellement de deux types: 1) Les problemes lies au genie civil fluvial ou maritime: en mer, engravement de passes d'acces et de bassines, formation de bancs ou de barres, choix des points de rejet de sediments dragues, implantation de ports, protection des cotes, etc.; en riviere, orientation des prises d'eau des centrales hydroelectriques ou nucleaires, repercussion d'ouvrages sur le transport solide, installation de barrages, protection des berges, installation d'epis, comblement des lacs, etc. Dans les deux cas, mer et riviere, transport d'effluents et surtout tarage des modeles reduits. La bibliographie jointe comprend surtout des references relativement recentes et tient compte des travaux des groupes de chercheurs qui etudient actuellement le sujet. 2) Les problemes lies a la recherche fondamentale ou appliquee essentiellement mise en oeuvre par les universites et les centres de recherches: etude du quaternaire d'une region determinee, sedimentologie pure, recherche de grands courants de transports sedimentaires, confirmation ou

  13. Thermal energy of nuclear origin produced in non-fissile materials (1962); Energie calorifique d'origine nucleaire degagee dans les materiaux non fissiles (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Naudet, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Millies, P; Berger, J [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1962-07-01

    A first part is devoted to the description of the interaction phenomena between elementary particles and material that may be observed during the irradiation process in a nuclear reactor: nuclear reactions due to neutrons, production of gamma rays and absorption of those gamma rays through various processes. In a second part the phenomena producing calorific energy in irradiated material are quantitatively examined. In the third part results are summed up in a formulary. The fourth part presents tables and figures giving to the reader all the numerical values necessary for practical calculations. (authors) [French] Une premiere partie est consacree a l'examen des principaux phenomenes d'interaction des particules avec la matiere qui interviennent lors d'une irradiation dans un reacteur: reactions nucleaires dues aux neutrons, production des rayons gamma et absorption de ces derniers par les divers processus. Une deuxieme partie etudie quantitativement les phenomenes qui conduisent a l'apparition d'energie calorifique dans le materiau irradie. En troisieme partie, un formulaire resume les resultats etablis. Dans une quatrieme partie, des tableaux et des courbes fournissent a l'experimentateur toutes les valeurs numeriques necessaires aux calculs pratiques. (auteurs)

  14. Installation Art

    DEFF Research Database (Denmark)

    Petersen, Anne Ring

    Despite its large and growing popularity – to say nothing of its near-ubiquity in the world’s art scenes and international exhibitions of contemporary art –installation art remains a form whose artistic vocabulary and conceptual basis have rarely been subjected to thorough critical examination....... In Installation Art: Between Image and Stage, Anne Ring Petersen aims to change that. She begins by exploring how installation art developed into an interdisciplinary genre in the 1960s, and how its intertwining of the visual and the performative has acted as a catalyst for the generation of new artistic...... phenomena. It investigates how it became one of today’s most widely used art forms, increasingly expanding into consumer, popular and urban cultures, where installation’s often spectacular appearance ensures that it meets contemporary demands for sense-provoking and immersive cultural experiences. The main...

  15. Installation Art

    DEFF Research Database (Denmark)

    Petersen, Anne Ring

    . In Installation Art: Between Image and Stage, Anne Ring Petersen aims to change that. She begins by exploring how installation art developed into an interdisciplinary genre in the 1960s, and how its intertwining of the visual and the performative has acted as a catalyst for the generation of new artistic......Despite its large and growing popularity – to say nothing of its near-ubiquity in the world’s art scenes and international exhibitions of contemporary art –installation art remains a form whose artistic vocabulary and conceptual basis have rarely been subjected to thorough critical examination...... phenomena. It investigates how it became one of today’s most widely used art forms, increasingly expanding into consumer, popular and urban cultures, where installation’s often spectacular appearance ensures that it meets contemporary demands for sense-provoking and immersive cultural experiences. The main...

  16. Border installations

    International Nuclear Information System (INIS)

    Lenaerts, Koen

    1988-01-01

    Border installations cover all nuclear plants located near the border with a neighbouring state. However, the actual distance depends on the context. The distance can vary considerably. Also the prohibition on siting near a heavily populated area also defines the actual distance variably. The distance criteria may be modified by other factors of topography, prevailing climate and so on. Various examples which illustrate the problems are given. For example, the Creys-Melville nuclear power plant is 80km from Geneva and the Cattonam installation is 12km from the French border with Luxembourg and Germany. The Cattenom case is explained and the legal position within the European Institutions is discussed. The French licensing procedures for nuclear power stations are described with special reference to the Cattenom power plant. Border installations are discussed in the context of European Community Law and Public International Law. (U.K.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

  18. The diode pump: its application to nuclear particle counting and to the detection of rapid neutronic power excursions in atomic piles (1962); La pompe a diodes, son application au comptage de particules nucleaires et a la detection des excursions rapides de puissance neutronique d'une pile atomique (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-05-15

    This work deals in particular with three applications of an electronic device whose principle is based on that of the diode pump. 1- Linear response circuit 2- Logarithmic response circuit 3- Detection of neutronic power excursions in atomic piles using a circuit or a combination of several circuits of the linear response type. Each of the applications has been studied theoretically and experimentally. Finally, the detection of rapid power excursions is extensively discussed with reference to the many methods available, emphasis being laid on the rapidity of the electronic response. (author) [French] Cet ouvrage traite plus particulierement de trois applications d'un dispositif electronique dont le principe de fonctionnement est base sur celui de la pompe a diodes. 1- Circuit a reponse lineaire 2- Circuit a reponse logarithmique 3- Detection des excursions de puissance neutronique d'une pile atomique a l'aide d'un circuit ou d'une association de plusieurs circuits a reponse lineaire. Chacune des applications fait l'objet d'une etude theorique et experimentale. Enfin, la detection des excursions rapides de puissance est tres largement discutee a travers plusieurs methodes, notamment sur la partie concernant la rapidite de reponse de l'electronique. (auteur)

  19. Fast neutron spectrometry and dosimetry; Spectrometrie et dosimetrie des neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    We have studied fast neutron spectrometry and dosimetry through the recoil protons they produce in hydrogenated samples. In spectrometric, we used nuclear emulsions, in dosimetric, we used polyethylene coated with zinc sulphide and placed before a photomultiplier. (author)Fren. [French] Nous avons etudie la spectrometrie et la dosimetrie des neutrons rapides en utilisant les protons de recul qu'ils produisent dans une matiere hydrogenee. En spectrometrie, nous avons employe des emulsions nucleaires, en dosimetrie, du polyethylene recouvert de sulfure de zinc place devant un photomultiplicateur. (auteur)

  20. Nuclear installations

    International Nuclear Information System (INIS)

    2001-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  1. Nuclear installations

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  2. Isomers chart; Table des isomeres

    Energy Technology Data Exchange (ETDEWEB)

    Dupont-Gautier, P; Chantelot, S; Moisson, N [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    The nuclear isomers are nuclides offering the same mass number and the same atomic number, but different energy levels. In the following chart the zero energy ground states are omitted and the metastable isomers, i.e. of non-zero energy, known and of measurable lifetime, are listed. The lower limit of this lifetime was set here to 0.1 x 10{sup -6} s. The various isomers were classified in increasing lifetimes. (authors) [French] Les isomeres nucleaires sont des nucleides presentant le meme nombre de masse et le meme numero atomique, mais des niveaux energetiques differents. Dans la table suivante, on a neglige les etats fondamentaux d'energie nulle et on a recense les isomeres metastables, c'est-a-dire d'energie non nulle, connus et de periode mesurable. La limite inferieure de cette periode a ete fixee ici a 0,1 x 10{sup -6} s. Les differents isomeres ont ete classes par periodes croissantes. (auteurs)

  3. Isomers chart; Table des isomeres

    Energy Technology Data Exchange (ETDEWEB)

    Dupont-Gautier, P.; Chantelot, S.; Moisson, N. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    The nuclear isomers are nuclides offering the same mass number and the same atomic number, but different energy levels. In the following chart the zero energy ground states are omitted and the metastable isomers, i.e. of non-zero energy, known and of measurable lifetime, are listed. The lower limit of this lifetime was set here to 0.1 x 10{sup -6} s. The various isomers were classified in increasing lifetimes. (authors) [French] Les isomeres nucleaires sont des nucleides presentant le meme nombre de masse et le meme numero atomique, mais des niveaux energetiques differents. Dans la table suivante, on a neglige les etats fondamentaux d'energie nulle et on a recense les isomeres metastables, c'est-a-dire d'energie non nulle, connus et de periode mesurable. La limite inferieure de cette periode a ete fixee ici a 0,1 x 10{sup -6} s. Les differents isomeres ont ete classes par periodes croissantes. (auteurs)

  4. Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants; Perspectives a long terme des couts de traitement de l'uranium naturel irradie. Tailles et localisations optimales des usines

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Oger, C; Vaumas, P de [Saint-Gobain Nucleaire, 92 - Courbevoie (France)

    1964-07-01

    processing plants are shown, different from those in part two. The indirect effect of these reprocessing programmes on the availability of plutonium, and therefore on the possibility.of undertaking plutonium burning reactor programmes, must be taken into account. (authors) [French] L'objet de cette communication est d'apporter une contribution a la solution du probleme du choix des tailles et des localisations optimales des usines de traitement des combustibles nucleaires irradies, associees a des programmes de puissance electrique installee. Dans une premiere partie, on etudie la structure des couts d'investissements et d'exploitation des usines de traitement de l'uranium naturel irradie, l'influence de la taille des usines sur ces couts et ces structures de couts. Au cout de traitement de l'uranium naturel irradie s'ajoute d'autre part le cout du transport des combustibles irradies des lieux de production aux sites des usines de traitement. La recherche du cout minimum pour la production d'un pays ou d'un ensemble de pays fait donc intervenir a la fois la taille et la localisation des usines. On indique les couts de transport previsibles pour l'uranium naturel irradie et la structure de ces couts (transport, assurance, couts et amortissement des containers). Dans une deuxieme partie, et pour differents echeanciers de combustibles irradies a traiter chaque annee, on determine les tailles et les localisations optimales des usines de traitement et la sensibilite de ces resultats, aux hypotheses de base concernant le cout du traitement, le cout du transport, l'annee de demarrage du programme d'usines, l'horizon choisi. - le probleme de nature combinatoire, assez complexe, est resolu par l'application des methodes de la programmation dynamique. - on montre que les methodes sont egalement applicables au probleme du choix des tailles et des localisations optimales des usines de traitement des elements du type MTR, associees aux programmes de reacteurs de recherche ainsi qu

  5. Relationship between the nuclear resonance of cobalt metal and its ferromagnetic properties; Relations entre la resonance nucleaire du cobalt metallique et ses proprietes ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-05-15

    resulte du couplage intense existant entre les noyaux et les electrons porteurs du magnetisme. Ces derniers excitent les noyaux et, dans les parois de Bloch, les soumettent a un champ radio-frequence bien plus intense que le champ RF applique. Les parametres de la resonance se determinent alors a partir du mouvement des parois, et dependent donc des constantes ferromagnetiques. La theorie permet de prevoir quantitativement certains effets particuliers, notamment par action d'un champ magnetique continu ou de la temperature. L'etude expeimentale a porte sur des poudres de cobalt et est en bon accord avec la theorie. Toutefois il faut tenir compte de l'effet de peau et reviser la theorie en consequence. Ceci permet d'expliquer certaines divergences observees, ainsi que l'influence de la taille des grains et celle du champ magnetique sur la forme de raie. Des renseignements originaux ont ete obtenus sur certaines proprietes purement ferromagnetiques du cobalt, en etudiant l'effet d'un champ magnetique et cette methode a pu etre appliquee a d'autres corps ferromagnetiques. En raison du caractere particulier de cette resonance nucleaire, qui se produit en l'absence de champ directeur et possede une importante largeur de raie, des spectrographes de type nouveau ont ete realises qui ont rendu possible des mesures precises de la forme de raie. La faible intensite des signaux obtenus dans certains cas a conduit a la mise au point d'une methode originale d'extraction dont la theorie et les applications pratiques sont donnees ici. L'ensemble de ces experiences fait apparaitre la resonance nucleaire comme un puissant moyen d'etude du ferromagnetique permettant de deceler des phenomenes microscopiques difficilement accessibles par les methodes classiques. (auteur)

  6. Relationship between the nuclear resonance of cobalt metal and its ferromagnetic properties; Relations entre la resonance nucleaire du cobalt metallique et ses proprietes ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-05-15

    couplage intense existant entre les noyaux et les electrons porteurs du magnetisme. Ces derniers excitent les noyaux et, dans les parois de Bloch, les soumettent a un champ radio-frequence bien plus intense que le champ RF applique. Les parametres de la resonance se determinent alors a partir du mouvement des parois, et dependent donc des constantes ferromagnetiques. La theorie permet de prevoir quantitativement certains effets particuliers, notamment par action d'un champ magnetique continu ou de la temperature. L'etude expeimentale a porte sur des poudres de cobalt et est en bon accord avec la theorie. Toutefois il faut tenir compte de l'effet de peau et reviser la theorie en consequence. Ceci permet d'expliquer certaines divergences observees, ainsi que l'influence de la taille des grains et celle du champ magnetique sur la forme de raie. Des renseignements originaux ont ete obtenus sur certaines proprietes purement ferromagnetiques du cobalt, en etudiant l'effet d'un champ magnetique et cette methode a pu etre appliquee a d'autres corps ferromagnetiques. En raison du caractere particulier de cette resonance nucleaire, qui se produit en l'absence de champ directeur et possede une importante largeur de raie, des spectrographes de type nouveau ont ete realises qui ont rendu possible des mesures precises de la forme de raie. La faible intensite des signaux obtenus dans certains cas a conduit a la mise au point d'une methode originale d'extraction dont la theorie et les applications pratiques sont donnees ici. L'ensemble de ces experiences fait apparaitre la resonance nucleaire comme un puissant moyen d'etude du ferromagnetique permettant de deceler des phenomenes microscopiques difficilement accessibles par les methodes classiques. (auteur)

  7. Detection of high energy gamma radiations with liquid rare gases as scintillators; Detection des rayonnements Gamma de grande energie avec les gaz rares liquides comme scintillateurs

    Energy Technology Data Exchange (ETDEWEB)

    Ho, Phan Xuan

    1965-11-25

    . Notre installation est encombrante a cause de la basse temperature utilisee et des soins necessaires pour conserver la purete du scintillateur, mais nous ne sommes theoriquement pas limite en volume. Nous nous sommes propose de realiser un scintillateur dans le but de detecter des gamma de haute energie a l'Accelerateur lineaire de 45 MeV de Saclay. L'appareillage que nous avons concu et realise peut egalement servir de moyen d'etude de la scintillation de tout autre gaz liquefie pour la detection des particules nucleaires. (auteur)

  8. On behalf of the commission of the National Defense and the armed forces, on the law project of finances for 2004 (no. 1093). Part 2. Defense - nuclear deterrence; Au nom de la commission de la defense nationale et des forces armees, sur le projet de loi de finances pour 2004 (no. 1093). Tome 2. Defense - dissuasion nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-10-01

    This analysis deals with the nuclear weapons situation in the world. It presents a new and coherent deterrence tool with an evolutive doctrine. It presents also the financial aspects of the problem and the dismantling of fissile materials production installations. It takes stock on the simulation program of nuclear weapons already engaged. (A.L.B.)

  9. Installations solaires photovoltaïques

    CERN Document Server

    2014-01-01

    Cet ouvrage présente les règles de conception et de mise en œuvre des installations photovoltaïques raccordées au réseau public de distribution à basse tension. Il s’applique aux bâtiments neufs et existants et concerne non seulement les petites installations résidentielles, d’une puissance de l’ordre de quelques kWc, mais aussi celles des bâtiments collectifs, tertiaires ou agricoles. Il traite successivement : - des fondamentaux de l'énergie solaire photovoltaïque (gisement solaire, principe de la conversion, composants d'une installation...) ; - du dimensionnement de l'installation (choix des matériels, règles de conception, estimation de l'énergie récupérable...) ; - de sa mise en oeuvre (travail en hauteur, habilitation électrique, mise en service, maintenance...) ; - des démarches administratives nécessaires (aides financières, accès au réseau de distribution, vente de l'électricité produite...).

  10. Transformations of highly enriched uranium into metal or oxide; Etudes des procedes de transformation des composes d'uranium a fort enrichissement isotopique

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    described successively, together with the studies which led to their development The civil engineering construction was begun in June 1962. The workshops are to start production in may 1964. (authors) [French] Les ateliers de traitement d'uranium enrichi de Cadarache ont pour but: d'une part, de transformer l'hexafluorure d'uranium en metal, ou en oxyde, et d'autre part, de recuperer l'uranium contenu dans les dechets divers produits lors des operations de transformation metallurgique. Les principes qui ont ete suivis pour la conception et la securite de ces ateliers sont exposes. La securite nucleaire est basee sur la geometrie des appareils de traitement. Pour mettre au point les procedes et la technologie de ces ateliers, de nombreuses etudes ont ete conduites depuis 1960, dont certaines ont abouti a des realisations originales. La transformation de l'hexafluorure d'uranium a fort enrichissement isotopique s'effectue, soit par injection en phase gazeuse dans l'ammoniaque, soit par un procede original de reduction directe en tetrafluorure d'uranium par l'hydrogene. La recuperation de l'uranium contenu dans les dechets metalliques d'uranium-zirconium s'operera par attaque par l'acide chlorhydrique, puis traitement du chlorure d'uranium par le fluor afin d'obtenir l'uranium sous forme d'hexafluorure. La recuperation de l'uranium contenu dans les dechets divers s'opere par un procede classique de raffinage: grillage des dechets metalliques, dissolution de l'oxyde obtenu dans l'acide nitrique, purification par solvant au tributyl-phosphate, precipitation a l'ammoniaque, calcination reduction fluoruration, calciothermie et traitement des scories. Deux ateliers separes fonctionnent suivant ce procede: l'un traite l'uranium d'un enrichissement isotopique inferieur ou egal a 3 p. 100, l'autre est reserve aux forts enrichissements. La mise en oeuvre, d'une maniere nucleairement sure, de chacune des etapes du procede a pose des problemes technologiques particuliers et a conduit a

  11. Purification by ion exchange resins of the heavy water of the reactors EL 1 and EL 2. A - the purifying process. Equipment and results; Purification par resines echangeuses d'ions de l'eau lourde des reacteurs EL1 et EL2. A - conduite de la purification. Installations et resultats

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J.; Roth, E. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    The heavy water was purified by tapping off part of the moderator over a mixed bed of anion and cation exchangers. The heavy water leaving the columns has a resistivity reaching several-meg-ohms, which allows the resistivity of the moderator to be maintained between 10{sup 5} and 10{sup 6} ohms/cm. Two methods of deuteration of the ion exchangers are described, as well as the heavy water recuperation from resins charged with radioactive products. The influence of the purity of the water on the radiolytic dissociation is investigated. An interpretation of the variations in pH and of the formation of hydrogen peroxide is given. In addition the report contains a general description of the EL1 and EL2 purification installations. (author) [French] L'epuration de l'eau lourde a ete effectuee en derivant une partie du moderateur sur un lit melange d'echangeurs d'anions et de cations. Les colonnes delivrent de l'eau lourde dont la resistivite atteint plusieurs megohms; ceci permet d'entretenir la resistivite du moderateur entre 10{sup 5} et 10{sup 6} ohms/cm. Deux procedes deuteriation des echangeurs d'ions sont decrits de meme que la recuperation de l'eau lourde partir des resines chargees de produits radioactifs. L'influence de la purete de l'eau sur sa dissociation radiolytique est etudiee. Une interpretation est donnee des variations de pH et de la formation d'eau oxygenee. Le rapport comprend en outre une description generale des installations d'epuration de EL1et EL2. (auteur)

  12. Purification by ion exchange resins of the heavy water of the reactors EL 1 and EL 2. A - the purifying process. Equipment and results; Purification par resines echangeuses d'ions de l'eau lourde des reacteurs EL1 et EL2. A - conduite de la purification. Installations et resultats

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J; Roth, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    The heavy water was purified by tapping off part of the moderator over a mixed bed of anion and cation exchangers. The heavy water leaving the columns has a resistivity reaching several-meg-ohms, which allows the resistivity of the moderator to be maintained between 10{sup 5} and 10{sup 6} ohms/cm. Two methods of deuteration of the ion exchangers are described, as well as the heavy water recuperation from resins charged with radioactive products. The influence of the purity of the water on the radiolytic dissociation is investigated. An interpretation of the variations in pH and of the formation of hydrogen peroxide is given. In addition the report contains a general description of the EL1 and EL2 purification installations. (author) [French] L'epuration de l'eau lourde a ete effectuee en derivant une partie du moderateur sur un lit melange d'echangeurs d'anions et de cations. Les colonnes delivrent de l'eau lourde dont la resistivite atteint plusieurs megohms; ceci permet d'entretenir la resistivite du moderateur entre 10{sup 5} et 10{sup 6} ohms/cm. Deux procedes deuteriation des echangeurs d'ions sont decrits de meme que la recuperation de l'eau lourde partir des resines chargees de produits radioactifs. L'influence de la purete de l'eau sur sa dissociation radiolytique est etudiee. Une interpretation est donnee des variations de pH et de la formation d'eau oxygenee. Le rapport comprend en outre une description generale des installations d'epuration de EL1et EL2. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    In the following report one can find first a short general view on the present situation of our knowledge concerning the nuclear fission process, namely on the nucleus going through the saddle-point. Then there are some aspects connected with the excitation energy of the fissioning nucleus. The measurements made at Saclay on the fast neutron fission cross-section of U{sup 233}, U{sup 235}, Pu{sup 239}, U{sup 238} are described at the beginning of this work. It appears that for U{sup 233} there is some characteristic shape modulation of the cross-section curve, in relation with the collective excited state of the deformed nucleus at the saddle-point. Good evidence of this is also given by the study of the relative fission rate with emission of long-range particles; it appears also that this ternary fission rate does not change substantially for neutron between thermal energy and 2 MeV, but that is very lower for the compound nucleus U{sup 239} than for even-even compound nuclei. At the end there are some experiments on the strong 4,5 MeV gamma-ray originated by slow neutron absorption in U{sup 235}. Time-of-flight device is used to establish that this 4,5 MeV gamma-ray seems mostly connected with radiative capture. (author) [French] Le present travail debute par un apercu de l'etat actuel de nos connaissances sur le processus de fission nucleaire, notamment sur le passage par le point-seuil. Puis sont evoques des aspects lies au niveau d'energie d'excitation auquel est porte le noyau qui subit la fission. Les mesures de sections efficaces de fission induite dans {sup 233}U, {sup 235}U, {sup 239}Pu et {sup 238}U par des neutrons rapides effectuees a Saclay sont decrites en premier lieu; elles font apparaitre pour {sup 233}U une ondulation caracteristique du role des etats collectifs d'excitation du noyau deforme au point-seuil. Des experiences sur la fission avec emission de particules de long parcours confirment cet aspect tout en demontrant que la frequence

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-10-15

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

  16. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states; Rapport sur le controle de la surete et de la securite des installations nucleaires. Deuxieme partie: la reconversion des stocks de plutonium militaire. L'utilisation des aides accordees aux pays d'Europe centrale et orientale et aux nouveaux etats independants

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

    This report deals with two different aspects of the safety and security of nuclear facilities. The first aspect concerns the reconversion of weapon grade plutonium stocks: the plutonium in excess, plutonium hazards and nuclear fuel potentialities, the US program, the Russian program, the actions of European countries (France, Germany), the intervention of other countries, the unanswered questions (political aspects, uncertainties), the solutions of the future (improvement of reactors, the helium-cooled high temperature reactor technology (gas-turbine modular helium reactor: GT-MHR), the Carlo Rubbia's project). The second aspect concerns the actions carried out by the European Union in favor of the civil nuclear facilities of central and eastern Europe: the European Union competencies through the Euratom treaty, the conclusions of the European audit office about the PHARE and TACIS nuclear programs, the status of committed actions, the coming planned actions, and the critical analysis of the policy adopted so far. (J.S.)

  17. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states; Rapport sur le controle de la surete et de la securite des installations nucleaires. Deuxieme partie: la reconversion des stocks de plutonium militaire. L'utilisation des aides accordees aux pays d'Europe centrale et orientale et aux nouveaux etats independants

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

    This report deals with two different aspects of the safety and security of nuclear facilities. The first aspect concerns the reconversion of weapon grade plutonium stocks: the plutonium in excess, plutonium hazards and nuclear fuel potentialities, the US program, the Russian program, the actions of European countries (France, Germany), the intervention of other countries, the unanswered questions (political aspects, uncertainties), the solutions of the future (improvement of reactors, the helium-cooled high temperature reactor technology (gas-turbine modular helium reactor: GT-MHR), the Carlo Rubbia's project). The second aspect concerns the actions carried out by the European Union in favor of the civil nuclear facilities of central and eastern Europe: the European Union competencies through the Euratom treaty, the conclusions of the European audit office about the PHARE and TACIS nuclear programs, the status of committed actions, the coming planned actions, and the critical analysis of the policy adopted so far. (J.S.)

  18. Commissioning Experience from the Agesta Nuclear Power Plant; Experience acquise lors des essais de mise en service de la centrale nucleaire d'Agesta; Opyt po vvedeniyu v ehkspluatatsiyu yadernoj ehnergeticheskoj ustanovki Agesta; Experiencia adquirida con la puesta en marcha de la central nucleoelectrica de Agesta

    Energy Technology Data Exchange (ETDEWEB)

    Rydell, N. [Aagesta Kraftvarmewerk, Farsta (Sweden)

    1963-10-15

    The Agesta Nuclear Power Plant is a pressurized heavy water reactor of the pressure vessel type, fuelled with natural uranium. It was commissioned with light water from December 1962 to May 1963. Observations of a more general interest were made during this commissioning essentially on the following topics; (a) cleanliness of primary circuit (b) valve operation (c) pressurization of the primary circuit (d) water leakage (e) refuelling machinery (f) containment testing. (author) [French] Il s'agit d'un reacteur a uranium naturel et a eau lourde pressurisee, du type a caisson sous pression. Les essais de mise en service ont ete faits avec de l'eau ordinaire, de decembre 1962 a mai 1963. La mise en service a permis de faire des observations d'interet general sur les sujets suivants: a) non-contamination du circuit primaire; b) fonctionnement des vannes; c) maintien sous pression du circuit primaire; d) fuites d'eau; e) appareils de chargement du combustible; f) essais d'isolement. (author) [Spanish] La central nucleoelectrica de Agesta posee un reactor de agua pesada del tipo de recipiente de presion, con combustible de uranio natural. Se mantuvo en funcionamiento con agua ligera entre diciembre de 1962 y mayo de 1963. Durante esta prueba, se efectuaron observaciones de interes mas general, relacionadas esencialmente con las siguientes cuestiones: a) limpieza del circuito primario; b) funcionamiento de las valvulas; c) presion del circuito primario; d) perdidas de agua; e) dosposiciones de reposicion del Combustible; f) ensayos de confinamiento. (author) [Russian] Yadernaya ehnergeticheskaya ustanovka Agesta predstavlyaet soboj tyazhelovodnyj reaktor pod davleniem, ispol'zuyushchij prirodnyj uran v kachestve topliva. Reaktor byl vveden v ehkspluatatsiyu na obychnoj vode v period s dekabrya 1962 goda po maj 1963 goda. Zamechaniya bolee obshchego kharaktera byli sdelany vo vremya ehkspluatatsii v osnovnom po sledukhshchim temam: a) chistota pervichnogo kontura; b

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  20. ETUDE DE LA DISTRIBUTION DES CATIONS ECHANGEABLES

    African Journals Online (AJOL)

    SEI Joseph

    programme d'installations minières pour l'exploitation de l'or et du manganèse, intéressant des emprises foncières importantes. ... pour maitriser les risques liés aux sols pollués, lesquels peuvent conduire à des effets négatifs sur le long terme Meusy, & Giorni .... kaolinite et de type bentonite industrielle (SFBD). Le pH des ...

  1. Radiological follow-up of the environment of the G.I.P. CYCERON of Caen - year 2005 - 2006 - assessment 2007; Suivi radiologique de l'environnement des installations du GIP CYCERON de Caen - annee 2005 - 2006 - bilan 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The present study answers at the request of the Inspection of the classified installations to see the operator of the G.I.P. Cyceron setting up a plan of environmental radiological surveillance around its installations and including, at a minimal level, the following data: Measures of radioactivity on representative biological indicators and measures of dose rate in the environment close to installations in functioning. Further to the radiological assessment of the terrestrial environment of the G.I.P. Cyceron installations realized at the end of 2003, within the framework of a project of the installations extension, the A.C.R.O. was again required for the implementation of this radiological surveillance for year 2005. The first purpose is to supply elements of appreciation about the impact of these installations on environment and persons. This evaluation participates in radiation protection and allows to make sure that the G.I.P. operator respects the required regulatory thresholds. (N.C.)

  2. Border installations

    International Nuclear Information System (INIS)

    Lenaerts, K.

    1988-01-01

    This chapter highlights the legal problems raised by the concept of a border installation. Using the Cattenom nuclear power plant as an example, the author describes the different stages of the legal conflict raised by construction of the plant and analyses the relationship between French administrative law and some provisions of the Euratom Treaty. Based on the Treaty, the Community institutions have adopted directives to strengthen inter-State co-operation and consultation between neighbouring countries. He observes that these principles of co-operation, consultation and vigilance already exist in public international law; however, international case law has not yet made it possible to establish the strict liability of the constructing state in case of a nuclear accident (NEA) [fr

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

  5. Special equipment for processing can-rupture measurements; Equipement specialise de traitement des mesures de rupture de gaines

    Energy Technology Data Exchange (ETDEWEB)

    Kaiser, J.; Phalippou, J.; Dumont, D.; Viellard, R. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    installees sur des reacteurs nucleaires utilisent dans la partie du traitement des mesures en totalite ou en partie un calculateur numerique. La fiabilite du systeme est limitee par celle du calculateur, celui-ci representant un point commun pour tout le traitement DRG. Pour satisfaire aux exigences de la securite de fonctionnement il faudrait envisager dans certains cas de doubler le calculateur. L'utilisation d'un calculateur necessite comme interface entre l'equipement de detection et lui-meme des echelles fonctionnant en integrateur pour les impulsions sortant du detecteur. En ajoutant un certain nombre de circuits a ces echelles on est capable d'effectuer le travail demande actuellement au calculateur, en ce qui concerne le calcul. Ce raisonnement nous a conduit a une solution dite ''decentralisee'' en realisant des equipements specialises au niveau du prospecteur meme. Nous croyons que cette solution represente, en dehors de l'aspect de fiabilite, surtout un interet economique. Dans notre solution, le point commun dans le traitement d'information se situe maintenant non plus au niveau d'elaboration du resultat comme dans le cas du calculateur, mais a un niveau plus bas, dans l'impression des resultats. Meme dans le cas d'une defaillance du point commun, les resultats sont elabores, affiches et compares aux seuils d'alarme. Dans le cas d'une panne d'un equipement specialise les resultats de ce prospecteur ne sont plus disponibles, les autres restent en fonction. Il semble que cette solution represente un degre de fiabilite meilleur que la solution utilisant les calculateurs universels. L'utilisation d'une technique a tiroir interchangeable (MULTIBLOC) permet un remplacement rapide de l'equipement specialise en panne. L'emploi systematique des circuits integres (TTL) assure une fiabilite accrue de l'equipement. (auteur)

  6. Nuclear facilities: repair and replacement technologies; Installations nucleaires: technologies de reparation et de remplacement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The oldest operating reactors are more than 35 years old and are now facing major maintenance operations. The first replacement of a pressurizer took place in autumn 2005 at the St-Lucie plant (Usa) while steam generators have been currently replaced since 1983. Nuclear industry has to adapt to this new market by proposing innovative technological solutions in the reactor maintenance field. This document gathers the 9 papers presented at the conference. The main improvements concern repair works on internal components of PWR-type reactors, the replacement of major components of the primary coolant circuit and surface treatments to limit the propagation of damages. The first paper shows that adequate design and feedback experience are good assets to manage the ageing of a nuclear unit. Another paper shows that a new repair method of a relief valve can avoid its replacement. (A.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  8. Report by the parliamentary mission of nuclear safety, the place and future of the sector - Intermediary report: the nuclear safety; Office parlementaire d'evaluation des choix scientifiques et technologiques. Rapport de la mission parlementaire sur la securite nucleaire, la place de la filiere et son avenir

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    Notably based on visits, meetings and auditions, this report first discusses the management of nuclear safety in France and stresses how rigorous it is. It comments how the different types of risks (natural, industrial, human) are taken into account, how safety is physically present (protection barriers, warehousing, operator training) and monitored, how this organisation is always improved as far as monitoring, information and preparedness to crisis are concerned. Then, the authors present the main orientations for the strengthening of safety: by taking new major risks into account, by anticipating possible situations (for installations, for matters of civil security, for population information and sensitization), and by investing on the issue of safety (in a financial way as well as in an organisational way, or by investing on research)

  9. Report by the AERES on the unit: Department of Nuclear Technology under the supervision of the establishments and bodies: Atomic Energy Commission (CEA); Rapport de l'AERES sur l'unite: Departement de Technologie Nucleaire sous tutelle des etablissements et organismes: Commissariat a l'Energie Atomique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-02-15

    This report is a kind of audit report on a research laboratory, the DTN (Department of Nuclear Technology) which comprises four departments: technology of industrial reactors, advanced technologies and processes, transfer modelling and nuclear measurements, thermal-hydraulic and technological studies. The authors discuss an assessment of the whole unit activities in terms of strengths and opportunities, aspects to be improved, risks and recommendations, productions and publications, scientific quality, influence and attractiveness (awards, recruitment capacity, capacity to obtain financing and to tender, participation to international programs), strategy and governance, and project. The same discussion is proposed for the different research themes: design of nuclear installation circuits and components, thermal-hydraulic and severe accidents, instrumentation for nuclear measurements and process control, transfers in reactors and in the environment

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  11. The Why and How of Nuclear Accident Dosimetry; Dosimetrie en cas d'Accident Nucleaire: Raison d'Etre et Modalites; 041e 0411 041e 0421 041d 041e 0412 0414 ; Dosimetria en Casos de Accidente Nuclear: Justificacion y Modalidades

    Energy Technology Data Exchange (ETDEWEB)

    Vallario, E. J.; Wasson, H. R. [United States Atomic Energy Commission, Washington, DC (United States)

    1965-06-15

    The objective of an effective nuclear accident dosimetry programme is to ensure that a means is provided for estimating the gamma neutron dose from a nuclear accident. In this connection, the limitation of the film badge is discussed, in addition to certain accident experiences which demonstrate the need for an effective accident dosimetry programme at facilities having a potential for nuclear accidents. Certain basic parameters should be considered in the development of an effective nuclear accident dosimetry programme. These are (a) a method for screening personnel involved in nuclear accidents, (b) a fixed system (primary unit) capable of determining first collision dose within some established degree of accuracy at its point of location, (c) the need for ''secondary units'', and (d) the need for a device worn by personnel which would afford spectrum and flux information to assist in dose extrapolation from the fixed unit to the location of man. The neutron component of the system should permit flux and spectral information in order to arrive at appropriate quality factors in the dose estimation. Accuracies should be established based upon the current state of the art. The gamma -ray component of the system should permit measuring gamma radiation within the biological area of interest, i. e. from 10 to 10{sup 3}r. Consideration for the number, placement and ease of recovery of accident units are indeed an integral part of an effective system of accident dosimetry. These considerations should enable reasonable data collection across the entire fission spectrum. (author) [French] L'objet d'un programme efficace de dosimetrie en cas d'accident nucleaire est d'evaluer la dose de rayons gamma et de neutrons emise lors d'un acccident nucleaire. Le memoire examine les limitations des dosimetres a film et expose les circonstances accompagnant certains accidents, lesquelles demontrent la necessite de prevoir un programme efficace de dosimetrie dans les installations ou

  12. Contraintes organisationnelles et gestion des risques en milieu ouvert : l’activité des monteurs installateurs de structures de fête Organizational constraints and risk management in an open environment: the activity of festival equipment erectors and installers Exigencias organizacionales y gestión del riesgo en lugares abiertos : La actividad de los montadores instaladores de estructuras de fiestas foráneas

    Directory of Open Access Journals (Sweden)

    Valérie Zara-Meylan

    2006-05-01

    Full Text Available Dans cet article, nous analysons l’activité des monteurs installateurs de structures de fête, agents d’une collectivité territoriale dans une grande ville. L’objectif est de mettre en évidence, dans ce type de système ouvert, les contraintes organisationnelles dues à la multiplicité des niveaux de décision et des réseaux d’acteurs ayant chacun leurs objectifs spécifiques. Ces contraintes ont un coût pour les opérateurs, en particulier en ce qui concerne les risques encourus.Après avoir montré les limites de la gestion verticale des risques, les régulations individuelles et collectives mises en place dans les équipes dans le but de gérer les risques sont analysées du point de vue de l’articulation des rôles des anciens et des novices dans le processus d’action, dans plusieurs situations.La méthodologie employée associe à l’analyse in situ des questionnaires et des tableaux de bord. Elle permet de mettre en évidence des situations critiques occasionnées par les interventions de multiples acteurs, en amont des chantiers et sur les sites. Ces intervenants perturbent la gestion horizontale des risques assurée par les anciens, les conduisant à faire des compromis, souvent au détriment de leur santé.In this article, we analyze the work activity of festival equipment erectors and installers in a large city local authority. The purpose is to identify, in this type of open system, the organizational constraints caused by the many decision levels and networks of actors with their own specific objectives. These constraints have a cost for the operators, especially in terms of occupational risks.After showing the limitations of " vertical " risk management, the individual and collective regulations that are implemented in the teams in order to manage the risks are analyzed from the standpoint of the articulation of older workers’ and novices’ roles in the action process, in several situations.The methodology

  13. Contribution to the study of nuclear structure using neutron total cross-section measurements between 400 and 1200 keV: isolated resonances and intermediate structure; Contribution a l'etude de la structure nucleaire par des mesures de sections efficaces neutroniques entre 400 keV et 1200 keV. Resonances isolees et structure intermediaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-06-15

    The neutron total cross sections have been measured over the energy range 400 keV - 1200 keV for fluorine, aluminium, silicon, phosphorus, vanadium, chromium, manganese, iron, nickel, cobalt and lead with an energy spread of 3 keV. The neutrons were produced by the T (p,n) {sup 3}He reaction, the proton beam was supplied by a 2 MeV Van de Graaff. The structure in {sup 56}Fe has been studied in a more detailed way by measuring six angular distributions in the above range and the elastic scattering excitation curves at four angles. The measurements have made it possible to show the existence of the compound nucleus, as well as the presence of an intermediate structure in certain nuclei. (author) [French] Nous avons mesure les sections efficaces totales neutroniques entre 400 keV et 1200 keV du fluor, de l'aluminium, du silicium, du phosphore, du vanadium, du chrome, du manganese, du fer, du nickel, du cobalt et du plomb avec une dispersion en energie de 3 keV. Les neutrons etaient produits a l'aide de la reaction T (p,n) {sup 3}He, les protons etant acceleres par un Van de Graaff 2 MeV. Nous presentons de plus quatre courbes d'excitation de la diffusion elastique des neutrons sur le fer ainsi que six distributions angulaires. Ces mesures ont permis de mettre en evidence un certain nombres de resonances du noyau compose, ainsi que la presence d'une structure intermediaire dans. certains noyaux. (auteur)

  14. Differential measurement of the earth's magnetic field by nuclear magnetic resonance; Mesure differentielle du champ magnetique terrestre par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    MNR transducers using proton dynamic polarisation allows to convert into a phase measurement any variation of the earth magnetic field. There exist several versions of the instrument corresponding to various models of MNR transducers, which the author analyses in detail, devoting an important place to influence of their alignment with respect to the earth's magnetic field. The sensibility obtained is of one hundredth of a gamma over a bandwidth of (0-0,1 Hz). - This instrument is designed for measuring field gradients in airborne magnetic surveying, for detecting nearly magnetic anomalies, and for distinguishing between nearly and distant magnetic phenomena. (author) [French] L'emploi de capteurs, bases sur la resonance magnetique nucleaire des protons en presence de polarisation dynamique, permet de traduire une difference de champ magnetique terrestre en une mesure de phase. L'appareil existe sous plusieurs versions avec des capteurs de modeles differents dont l'auteur fait une analyse detaillee en accordant une part importante a l'influence de l'orientation des capteurs par rapport au champ magnetique terrestre. La sensibilite est de 1/100 {gamma} pour une bande passante de (0 - 0,1 Hz). Cet appareil s'applique a la mesure du gradient en prospection magnetique aeroportee, a la detection d'anomalies magnetiques proches, a la differentiation d'effets magnetiques proches et lointains. (auteur)

  15. The Manhattan project; Nucleaire - Le Projet Manhattan

    Energy Technology Data Exchange (ETDEWEB)

    Alexieff, A.

    2010-07-15

    The author reports the history of the Manhattan project which was launched in 1942 with the objective of building an A bomb at any price and as soon as possible. This lead to the fabrication of two types of bomb, one using uranium in gun mode, and the other using plutonium in implosion mode. The author recalls the creation of different scientific and nuclear institutions, the development of several installations (Los Alamos, Hanford, Oak Ridge). He outlines the project secrecy (President Truman did not know anything about it when he became president), and recalls the final tests, the bombing of Hiroshima and Nagasaki, and the last moment of the Manhattan Project after the end of the war. In conclusion, he notices that this nuclear era allowed a direct confrontation to be avoided despite the several crises which occurred during about two decades after the war

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

  17. 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)

  18. ''1995/2010: site drainage and nuclear facilities dismantling program'' result 2001; ''1995/2010: programme d'assainissement du site et de demantelement des installations nucleaire'' bilan 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    A drainage and dismantling planing with the corresponding wastes management, has been decided for the CEA of Fontenay aux roses, in 1995. It will end in 2010. This document presents the main evolutions occurred since october 2000. (A.L.B.)

  19. Study of the impact of radionuclides discharges from nuclear industry in the northern Cotentin area on the oyster Crassostrea gigas: expression of cellular stress molecular markers; Etude de l'impact des radionucleides rejetes par les installations nucleaires du Nord Cotentin sur l'huitre creuse Crassostrea gigas: analyse de l'expression de marqueurs moleculaires de stress

    Energy Technology Data Exchange (ETDEWEB)

    Farcy, E

    2006-11-15

    This thesis explores the potential radiological impact of radionuclide discharges from the nuclear industry on the Pacific oyster, Crassostrea gigas. One of the major goals of this research was to identify markers that could be used to monitor the effects of low-level chronic irradiation. We decided to focalize on the expression of stress-induced genes involved in the regulation of cellular stress, focusing on transcription. First, homology cloning was used to identify four new cDNAs encoding stress markers. Then data collected at various sites enabled to evidence that mRNA levels for each of the genes of interest naturally vary to a significant degree, based on individual differences and seasonal factors. Comparing oysters from exposed sites with those from a reference site located on the Atlantic coast did not suggest any relationship between mRNA levels changes and the oysters exposure to liquid radioactive waste from the A.R.E.V.A. reprocessing plant. In the environment, we found that those radionuclide releases resulted in a very small increase in radioactivity in oysters, especially compared with their natural radioactivity. In the laboratory, by exposing the oysters to higher radionuclide concentrations than those found in the environment, we were able to identify two genes as potential candidates for studying the effects of chronic exposure to low doses of ionizing radiations in the oyster: genes encoding MT and MXR. We confirmed that transcriptional induction of these two genes occurs in response to high doses of acute irradiation. Finally, the comparison between environmental results and the laboratory results underlined the complementarity of these two approaches. In particular, it revealed that seasonal variations in mRNA levels probably have a significant effect on the stress response. (author)

  20. Administrative Arrangement between the Atomic Energy Control Board of Canada and le Service central de surete des installations nucleaires du Ministere de l'industrie et de l'amenagement du territoire de la Republique francaise for the exchange of technical information and cooperation in the regulation of nuclear safety (10 May 1990)

    International Nuclear Information System (INIS)

    1990-01-01

    The Arrangement which entered into force on the date of its signature and remains in effect for five years, provides for exchange of information between both agencies on the regulation of nuclear facilities and intervention measures in cases of emergency. This includes information on regulatory procedures for the safety of designated nuclear facilities, notification of important events, such as serious operating incidents, reactor shutdowns ordered by the regulatory authorities, etc. (NEA) [fr

  1. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 23, 2011, 6:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 23 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 23, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  2. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 22, 2011, 6:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 22 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 22, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  3. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 24, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 24 mars 2011 a 08 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 24, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  4. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 29, 2011, 12:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 29 mars 2011 a 12h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 29, 2011, at 12:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  5. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 21, 2011, 3:00 PM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 21 mars 2011 a 15 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 21, 2011, at 3:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  6. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 25, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 25 mars a 08h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 25, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  7. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 26, 2011, 10:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 26 mars 2011 a 10h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 26, 2011, at 10:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  8. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 28, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 28 mars 2011 a 08h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 28, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  9. Decree no. 2002-447 of the 27 march 2002 authorizing the Normandy society of preserve and sterilization to realize definitive shutdowns and dismantling operations of the nuclear installation no. 152 situated on the territory of Osmanville (Calvados); Decret no. 2002-447 du 27 mars 2002 autorisant le Societe normande de conserve et sterilisation a proceder aux operations de mise a l'arret definitif et de demantelement de l'installation nucleaire de base no. 152 situee sur le territoire de la commune d'Osmanville (Calvados)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The decree presents the shutdown preliminary obligations, the installation quality, the prevention of radioactivity dissemination risk, the workers protection, the wastes management, the fire prevention. (A.L.B.)

  10. The magnetic diffusion of neutrons; La diffusion magnetique des neutrons

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    The purpose of this report is to examine briefly the diffusion of neutrons by substances, particularly by crystals containing permanent atomic or ionic magnetic moments. In other words we shall deal with ferromagnetic, antiferromagnetic, ferrimagnetic or paramagnetic crystals, but first it is necessary to touch on nuclear diffusion of neutrons. We shall start with the interaction of the neutron with a single diffusion centre; the results will then be applied to the magnetic interactions of the neutron with the satellite electrons of the atom; finally we shall discuss the diffusion of neutrons by crystals. (author) [French] Le but de ce rapport est d'examiner, brievement, la diffusion des neutrons par les substances, et surtout, par des cristaux qui contiennent des moments magnetiques atomiques ou ioniques permanents. C'est-a-dire que nous nous interesserons aux cristaux ferromagnetiques, antiferromagnetiques, ferrimagnetiques ou paramagnetiques; il nous faut cependant rappeler d'abord la diffusion nucleaire des neutrons. Nous commencerons par l'interaction du neutron avec un seul centre diffuseur; puis les resultats seront appliques aux interactions magnetiques du neutron avec les electrons satellites de l'atome; enfin nous discuterons la diffusion des neutrons par les cristaux. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

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

  12. Nuclear raw materials; Matieres premieres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1970-01-15

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

  13. Nucleaire et Energies Nr 65 - March 2015

    International Nuclear Information System (INIS)

    Lenail, Bernard; Ducroux, Guy; Seyve, Claude; Simonnet, Jacques; Justin, Francois; Salanave, Jean-Luc; Raisonnier, Daniele

    2015-03-01

    After a first brief article about the difficult situation faced by Areva, and an article about the Japanese situation four years after the Fukushima accident and the progressive restarting of reactors, an article proposes an overview of recent evolutions and events in the energy sector: the sharp decrease of oil prices and its consequences for Total and the European Union. Three articles concern nuclear activities: recent events in the mining and fuel fabrication sectors (perspectives, restructuring in the USA, contracts for Areva and EDF), overview of the situation of reactors (with perspective for the installed power by 2050, unclear perspectives in France, projects in the UK in Hinkley Point, Moorside, and Wylfa, situation in Belgium, Hungary and Russia, contracts for Areva and EDF, situation in Taiwan, India, South Korea, Japan, USA, South Africa), overview of activities and events related to the back-end of the fuel cycle and to decommissioning in different countries (recycling activities in France, decommissioning in France and in the UK, warehousing in France and Germany, a new warehousing system to be approved in the USA, events related to storage activities). An article discusses issues related to the lifetime of French nuclear reactors, and another one discusses the identification of electric power costs and ways to compare them. A last article briefly discusses some terminological confusion between energy and electricity, and between produced energy and available power

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

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

  16. Facilities for Waste Management at Chalk River, Canada; Les Installations d'Elimination et d'Utilisation des Dechets a Chalk River, Canada; 041e 0411 041e 0420 0423 0414 041e 0412 ; Instalaciones Utilizadas para el Provechamiento y Evacuacion de Desechos Radiactivos en Chalk River, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Mawson, C. A.; Russell, A. E. [Environmental Research Branch, Atomic Energy of Canada Ltd. (Canada)

    1960-07-01

    The waste disposal areas used by the Atomic Energy of Canada Limited are situated in a rock basin filled with glacial till and sand, draining into the Ottawa River. Low-activity liquid effluent is run into pits in the sand, which are filled with small rocks to prevent contact of liquid with the air. Medium- level liquid is mixed with cement in drums which are stacked and totally enclosed in concrete trenches; medium-level solids are buried in concrete-lined trenches; high-level solids are placed in holes lined with steel or concrete piping. Special facilities are provided for organic liquids and bottled wastes. Details will be given of the structural work and procedures, with an outline of the results of environmental monitoring. (author) [French] Les zones d'elimination utilisees par l'Atomic Energy of Canada Limited sont situees dans un bassin rocheux, rempli de blocs erratiques et'de sable, dont les eaux s'ecoulent dans la riviere Ottawa. Les effluents liquides de faible activite sont verses dans des puits creuses dans le sable, qui sont ensuite remplis de petites pierres pour prevenir le contact du liquide avec l'air. Les dechets liquides d'activite moyenne sont melanges a du ciment dans des barils qui sont entasses et completement enfermes dans des tranchees betonnees; les dechets solides d'activite moyenne sont enfouis dans des tranchees bordees de beton; les dechets solides de haute activite sont places dans des trous bordes de conduites d'acier ou de ciment. Des installations speciales sont prevues pour les liquides organiques et les dechets enfermes dans des recipients en forme de bouteilles. Le memoire expose en detail les travaux d'amenagement et les methodes suivies; il donne un apercu des resultats du controle du milieu ambiant. (author) [Spanish] Las zonas utilizadas por la Atomic Energy of Canada Limited para la evacuacion de desechos radiactivos estan situadas en una cuenca rocosa recubierta de limo y arena del periodo glacial, que desemboca en el

  17. Statistics on the production and the use of the artificial radioelements in France; Statistiques sur la production et l'emploi des radioelements artificiels en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The CEA is, in France, the unique producer of artificial radioelements for public uses. These products have been provided to the users since 1949. They include until now only radioelements formed in nuclear reactors. The following aspects of use in France of the artificial radioelements will be described: - Consumption of the artificial radioelements in France, - French production and import, - Teaching and study of applications. (M.B.) [French] Le Commissariat a l'Energie Atomique est, en Franoe, le seul producteur de radioelements artificiels pour l'utilisation publique. Ces produits ont ete fournis aux utilisateurs des 1949. Ils ne comprennent jusqu'a present que des radioelements formes dans des reacteurs nucleaires. Les aspects suivants de l'utilisation en France des radioelements artificiels seront decrits: onsommation des radioelements artificiels en France, Production francaise et importation, - Enseignement et etudes d'applications. (M.B.)

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

    International Nuclear Information System (INIS)

    Kottmann, G.

    2012-01-01

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

  19. Installation for analytic chemistry under irradiation; Installation de chimie analytique sous rayonnement

    Energy Technology Data Exchange (ETDEWEB)

    Fradin, J; Azoeuf, P; Guillon, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1966-07-01

    An installation has been set up for carrying out manipulations and chemical analyses on radioactive products. It is completely remote-controlled and is of linear shape, 15 metres long; it is made up of three zones: - an active zone containing the apparatus, - a rear zone giving access to the active zone, - a forward zone independent of the two others and completely protected from which the remote-control of the apparatus is effected. The whole assembly has been designed so that each apparatus corresponding to an analytical technique is set up in a sealed enclosure. The sealed enclosures are interconnected by a conveyor. After three years operation, a critical review is now made of the installation. (authors) [French] L'installation a ete realisee pour effectuer des manipulations et des analyses chimiques sur des produits radioactifs. Elle est totalement telecommandee et se presente sous une forme lineaire de 15 metres de longueur et comporte trois zones: - une zone active d'appareillage, - une zone arriere d'intervention, - une zone avant independante des deux premieres et totalement protegee, ou s'operent les telecommandes de l'appareillage. L'ensemble a ete concu de facon a ce que chaque appareillage correspondant a une technique d'analyse soit implante dans une enceinte etanche. Les enceintes etanches sont reliees entre elles par un convoyeur. Apres trois annees de fonctionnement nous faisons le bilan et les critiques de l'installation. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

  1. Damage caused to houses and equipment by underground nuclear explosions; Degats dus aux explosions nucleaires souterraines sur les habitations et les equipements

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    A description is given of the damaged caused to various structures, buildings, houses, mechanical equipment and electrical equipment by underground nuclear explosions in granite. For each type of equipment or building are given the limiting distances for a given degree of damage. These distances have been related to a parameter characterizing the movement of the medium; it is thus possible to generalize the results obtained in granite, for different media. The problem of estimating the damage caused at a greater distance from the explosion is considered. (authors) [French] Les degats sur diverses structures, constructions, habitations, equipements mecaniques et materiels electriques provoques par des explosions nucleaires souterraines dans le granite sont decrits. On a indique pour chaque type de materiel ou de construction, les distances limites correspondant a un degre de gravite de dommage observe. Ces distances ont ete reliees a un parametre caracterisant le mouvement du milieu, permettant ainsi de generaliser les resultats obtenus dans le granite, a differents milieux. Le probleme de la prevision des degats en zone lointaine a ete aborde. (auteurs)

  2. Radioactive Waste Facilities at the Australian Atomic Energy Commission Research Establishment; Installations pour le Traitement des Dechets Radioactifs au Centre de Recherche de la Commission Australienne a l'Energie Atomique; 0423 0421 0422 0414 ; Dispositivos para Evacuacion de Desechos Radiactivos en el Centro de Investigaciones de la Australian Atomic Energy Commission

    Energy Technology Data Exchange (ETDEWEB)

    Berglin, C. L.W.; Keher, L. H.; Miles, G. L.; Wilson, A. R.W. [Australian Atomic Energy Commission Research Establishment, Lucas Heights, Sydney, NSW (Australia)

    1960-07-01

    This paper describes the facilities,which are being provided for the collection, treatment and disposal of radioactive wastes at Lucas Heights in relation to the estimated arisings. Low-activity effluent is divided into three types: (a) Sewage; (b) Trades waste, arising from reactor cooling tower blow-down and engineering workshops and other inactive areas; and (c) Effluent arising from laboratories and other active areas. The effluent treatment plant for the latter type of effluent consists essentially of mixing and alkali dosing tanks, a sludge-blanket clarifier (using a calcium- iron-phosphate process) and holding tanks. Methods of concentrating the sludge and of secondary treatment are at present being investigated and are discussed. The discharge formula and the expected dilution obtained in the Woronora river are discussed, together with a dilution experiment carried out in the tidal waters. It is proposed to bury all low-activity solid waste after baling where appropriate and the choice and location of the disposal area is discussed. A facility for the storage and disposal of highly active solid waste is discussed. It is proposed to evaporate and store the medium- and high-activity liquid waste. Details are given of the capital and operating costs of the Effluent Treatment Plant and other waste handling facilities. (author) [French] Le memoire decrit les installations que le Centre de Lucas Heights cree a l'heure actuelle, eu egard au developpement envisage'en matiere de rassemblement, de traitement et d'elimination des dechets radioactifs. Les' effluents de faible activite se divisent en trois categories: a) Eaux d'egout; b) Dechets industriels provenant de la tour de refroidissement du reacteur, des ateliers et d'autres zones non-actives; c) Effluents provenant des laboratoires et d'autres zones actives. L'usine affectee au traitement du dernier type d'effluents se compose essentiellement de malaxeurs, de bacs de dosage d'alcalis, d'un clarificateur d

  3. Radiological assessment of terrestrial environment of facilities of G.I.P. CYCERON from Caen - year 2003; Bilan radiologique de l'environnement terrestre des installations du GIP CYCERON de Caen - annee 2003

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Concerning the gamma emitters, the only analysis on soils put in evidence the presence of cesium-137 ({sup 137}Cs), that does not come from the cyclotron functioning but from past man action as the Chernobylsk accident and the nuclear weapon tests in atmosphere. Independently of the functioning of the installation, we observe an increase of the ambient gamma radiation only near radioactive waste storage. It results of the storage of the former cyclotron elements. The induced increase is moderated because at 5 meters the values do not exceed the background noise. In relation with the functioning of the installation an increase of the ambient gamma radiation is noticed. Two causes are to considered: the release of radionuclides in atmosphere with gaseous effluents and the radiance of radiation sources inside the building. After the stopping of the installation (48 h at least), no increase of gamma radiation is observed. About the neutrons monitoring, the measures made during the cyclotron functioning, highlight the lack of significant overexposure around the blockhouse at the level of man, a very net increase of the ambient neutron radiation (about 20 times the background noise) exclusively on the roof of the blockhouse. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  7. Radio-protection problems presented by iodine isotopes in nuclear fuel chemical treatment plants (1962); Les problemes de radioprotection poses par les isotopes de l'iode dans les installations de traitement chimique des combustibles (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Bouzigues, H; Scheidhauer, J; Messainguiral, L [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1962-07-01

    The origin of radio-iodine and the conditions in which it is liberated are given. The authors review the question of the risks associated with the presence of this radioelement In the atmosphere. Finally a method is proposed for the trapping and rapid measuring of the iodine in the vapour form, applicable to radioprotection. (authors) [French] L'origine et les conditions de liberation du radioiode sont exposees. Les auteurs font le point de la question des risques associes a la presence de ce radioelement dans l'atmosphere. Enfin, une methode de piegeage et de mesure rapide de l'iode a l'etat de vapeur applicable a la radioprotection, est proposee. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

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

  9. Contribution to the study of the evolution of radiation induced He in Be O; Etudes sur l'evolution de l'helium produit par reactions nucleaires dans l'oxyde de beryllium

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-11-15

    The purpose of this work in-pile investigation of He formed by (n, 2n) and (n, {alpha}) nuclear reactions, released from irradiated BeO, in the temperature range 1000 - 1350 deg. C. The experimental results show that, for an instantaneous neutron fast flux of 10{sup 13} n cm{sup -2} sec{sup -1}, an equilibrium is attempted, after several days, for a part lower than 20 per cent of the quantity of He formed, theoretically calculated from the neutron cross sections of nuclear reactions, and from the analytical form of the neutron fast flux, releases from the solid. The validity of the values of calculated helium and the gas chromatographic analytical method are also verified by dissolution of the BeO pellets in cryolite. A new fast neutron flux measuring method may be so defined. The discussion of the experimental results enables to establish that the processus of He release is characterized by two phenomena: the first one which controls the release of He atoms out of the solid and the second which reveals a capture processus, connected to the irradiation and probably due to the vacancies induced in the lattice. (author) [French] On etudie en pile le degagement de l'helium forme par reactions nucleaires (n, 2 n) et (n, {alpha}) dans l'oxyde de beryllium irradie entre 1000 et 1350 deg. C. Les resultats experimentaux montrant que, pour un flux rapide instantane de 10{sup 13} n{sub r} cm{sup -2} s{sup -1}, on aboutit, au bout de quelques jours, a un etat d'equilibre pour lequel une partie, inferieure a 20 pour cent de la quantite d'helium forme, calculee theoriquement a partir des sections efficaces des reactions nucleaires et de la forme analytique du flux rapide, s'echappe du solide. On verifie egalement par dissolution des echantillons de BeO dans la cryolithe la validite du calcul de l'helium et de la methode de dosage par chromatographie en phase gazeuse. On peut ainsi definir une methode nouvelle de mesure des flux rapides. La discussion des resultats experimentaux

  10. Contribution to the study of the evolution of radiation induced He in Be O; Etudes sur l'evolution de l'helium produit par reactions nucleaires dans l'oxyde de beryllium

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-11-15

    The purpose of this work in-pile investigation of He formed by (n, 2n) and (n, {alpha}) nuclear reactions, released from irradiated BeO, in the temperature range 1000 - 1350 deg. C. The experimental results show that, for an instantaneous neutron fast flux of 10{sup 13} n cm{sup -2} sec{sup -1}, an equilibrium is attempted, after several days, for a part lower than 20 per cent of the quantity of He formed, theoretically calculated from the neutron cross sections of nuclear reactions, and from the analytical form of the neutron fast flux, releases from the solid. The validity of the values of calculated helium and the gas chromatographic analytical method are also verified by dissolution of the BeO pellets in cryolite. A new fast neutron flux measuring method may be so defined. The discussion of the experimental results enables to establish that the processus of He release is characterized by two phenomena: the first one which controls the release of He atoms out of the solid and the second which reveals a capture processus, connected to the irradiation and probably due to the vacancies induced in the lattice. (author) [French] On etudie en pile le degagement de l'helium forme par reactions nucleaires (n, 2 n) et (n, {alpha}) dans l'oxyde de beryllium irradie entre 1000 et 1350 deg. C. Les resultats experimentaux montrant que, pour un flux rapide instantane de 10{sup 13} n{sub r} cm{sup -2} s{sup -1}, on aboutit, au bout de quelques jours, a un etat d'equilibre pour lequel une partie, inferieure a 20 pour cent de la quantite d'helium forme, calculee theoriquement a partir des sections efficaces des reactions nucleaires et de la forme analytique du flux rapide, s'echappe du solide. On verifie egalement par dissolution des echantillons de BeO dans la cryolithe la validite du calcul de l'helium et de la methode de dosage par chromatographie en phase gazeuse. On peut ainsi definir une methode nouvelle de mesure des flux rapides. La

  11. New purchase conditions by EDF, of the electrical power produced by the energy valorization installations of domestic wastes and assimilated; Nouvelles conditions d'achat par EDF de l'electricite produite par les installations de valorisation energetique des dechets managers et assimiles

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

    The State Secretary for the Industry, C. Pierret, approved the new purchase conditions by EDF, concerning the electric power, produced by the installations of domestic wastes energy valorization. This action is in agreement with the energy policy. The purchase conditions are presented and commented. (A.L.B.)

  12. Systematic study of the use of electrical fields for improving heat exchange in boiling liquids; Etude systematique de l'utilisation de champs electriques pour l'amelioration des echanges thermiques dans des liquides bouillants

    Energy Technology Data Exchange (ETDEWEB)

    Bochirol, L; Bonjour, E; Lagnier, R; Verdier, J; Weil, L [Commissariat a l' Energie Atomique, Grenoble (France).Centre d' Etudes Nucleaires

    1961-07-01

    We have studied, at the boiling point, for liquids with various electrical properties (hexane, benzene, trichloroethylene, demineralized water, acetone, methyl-ethyl-ketone, etc...) the effect of the application of electric fields on the exchange coefficients and on the maximum dissipative powers before calefaction. We have given the mechanism of the significant improvements obtained (multiplication by a factor of 2 to 10): - in the natural convection zone by showing the role played by the dielectric properties of the liquids under study; - in the zone of nuclear boiling by analysis of the forces acting on the boiling nuclei. Finally we give some experimental results concerning measurements made under pressure until local boiling occurred: they show the possibility of some interesting applications of the method. (author) [French] On a etudie, a l'ebullition, sur des liquides de caracteristiques electriques diverses (hexane, benzene, trichlorethylene, eau demineralisee, acetone, methylethylcetone, etc...) les effets de l'application de champs electriques sur les coefficients d'echanges et les puissances maximales dissipables avant calefaction. On a precise le mecanisme des ameliorations importantes obtenues (multiplication par un facteur 2 a 10): - dans la zone de convection naturelle en mettant en evidence le role des caracteristiques dielectriques des liquides etudies; - dans la zone d'ebullition nucleaire par analyse des forces mises en jeu sur les noyaux d'ebullition. On donne enfin des resultats experimentaux sur des mesures effectuees sous pression jusqu'a l'ebullition locale: ils illustrent des possibilites d'applications interessantes du procede. (auteur)

  13. Preliminary study for the revitalisation of the 'Duersteller' small hydropower installation in Wetzikon, Switzerland; Vorstudie Kleinwasserkraftwerk J. Duersteler and Co AG Wetzikon ZH. Revitalisierungsvorhaben des Kraftwerkes mit seinen 80-jaehrigen Francis-Doppelturbinen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This report for the Swiss Federal Office of Energy (SFOE) discusses the possibility of revitalising an 80-year-old, small industrial hydropower plant fitted with twin Francis turbines. The present situation and the condition of the turbines and their associated water channels are described and the hydrological data of the Aabach stream is presented. Details are given on the presently installed technical apparatus and the legal and ownership situation. Environmental and historical aspects are discussed. The economics of the proposed revitalisation project are discussed and possible restrictions that could be enforced by the authorities are looked at. The report is concluded with recommendations for further action.

  14. Comparison of the Economic Aspects of the Treatment and Storage of Fission Products from Installations Processing Irradiated Natural Uranium; Aspects Economiques Compares du Traitement et du Stockage des Produits de Fission Issus des Usines de Traitement de l'Uranium Naturel Irradie; Sravnitel'nye ehkonomicheskie aspekty obrabotki i khraneniya produktov deleniya, poluchaemykh na zavodakh po pererabotke obluchennogo prirodnogo urana; Aspectos Economicos Comparados del Tratamiento y del Almacenamiento de los Productos de Fision que Salen de las Plantas de Tratamiento de Uranio Natural Irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L.; Lesur, P.; Giraud, R. [Commissariat a l' Energie Atomique, Paris (France); Wanlin, J. [Societe Saint-Gobain Techniques Nouvelles, Paris (France)

    1966-02-15

    The paper summarizes the main policies adopted for the management of fission product effluents and briefly describes the essential technical features of the stainless steel storage installations (in acid medium) used in France, giving a breakdown of the costs involved. The dependence of these costs on the activity of the solutions stored and on their heat release is shown. The second part of the paper discusses the cost of storage in terms of feasible tank size. The optimum size for such tanks and the rate at which they are placed in service are determined in relation to the characteristics of the fission products to be stored and to the respective capacities of the installations for processing irradiated natural uranium. It is shown that although storage costs depend on the assumptions made regarding the useful life of installations, rates of interest and operating costs, optimum policy decisions (as to size and rate of entry into service) are independent of these assumptions, being determined solely by the variation in the cost of tanks, according to size. These are the factors which enter into the optimized cost of storing these effluents indefinitely. In the third part, this method of indefinite storage is compared with other possibilities of fission product management, e.g. vitrification and separation of Cs and Sr. The paper discusses the economics of the various methods and summarizes some possible long-term solutions. (author) [French] Apres avoir rappele les principales politiques de gestion le plus souvent envisagees pour les produits de fission, le memoire decrit sommairement les caracteristiques techniques essentielles des installations de stockage en acier inoxydable (en milieu acide) utilisees en France et la structure des couts de ces installations. U montre la sensibilite de ces couts a l'activite des solutions stockees et a leur degagement de chaleur. Dans une deuxieme partie, les auteurs examinent leur cout de stockage, selon la taille des

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

    CERN Document Server

    Margueron, J

    2001-01-01

    We study the elementary interactions between neutrinos and dense matter in a proroneutron star. Equations of state obtained with different nuclear effective interactions (skyrme, Gogny, relativistic Lagrangians) are first discussed.Then we characterize their stability in spin and isospin. We derive magnetic susceptibilities for all isospin asymmetry values as a function of Landau parameters G^{tau tau'}_0 (where tau, tau' = proton or neutron)We calculate nthe pure neutron matter response functions with and withoutcharge exchange, describing nuclear correlations in both approaches : non-relativistic and relativistic. At the end we calculate neutrino mean free paths for neutral current and charged current reactions.Comparisons between relativistic and non-relativistic approaches allow us to identify relativistic effects in nuclear matter at densities as low as twice the saturation density.RPA correlations make the medium more transparent to neutrinos compared to free Fermi gas.

  16. Institut National des Sciences et Techniques Nucleaires. From academic to vocational: specificity and vision

    Energy Technology Data Exchange (ETDEWEB)

    Turpin, Laurent [Institut National des Sciences et Techniques Nucleaires - INSTN, CEA-Saclay (France)

    2008-07-01

    - What is INSTN?: Teaching and training service of CEA; Capability of awarding degrees; Stand-alone: only specialty degrees; Partnership with universities and Engineer schools: master degrees; Professional training operator for CEA and for SMEs. - Corner stones for the next future (5-10 years): increasing the capability in nuclear training (Nuclear skills for nuclear engineers (reactor physics,...), factor 3-4, Nuclear skills for non-nuclear engineers (civil works, project management,...), All stakeholders have to do more (Academics on basic knowledge (have to prepare to a wide range of positions), Specialty institutes on specialized knowledge (before the job and on the job), Internal programs on proprietary programs), optimizing the resources (No false hope: more training means higher costs but does not mean nuclear companies will lay golden eggs; Availability of teaching resource and capability of internship tutoring could be bottlenecks; Trained/graduate production must match actual human resources needs). - A strategy for INSTN: Academic partnerships, to implement nuclear modules within training programs; With companies, a stakeholder-shareholder joint venture model for postgraduate training; Open to European and offshore cooperation.

  17. Probing nuclear structure with nucleons; Sonder la structure nucleaire avec des nucleons

    Energy Technology Data Exchange (ETDEWEB)

    Bauge, E. [CEA Bruyeres-le-Chatel, Service de Physique Nucl aire, 91 (France)

    2007-07-01

    The goal of this lecture is to show how nucleon scattering can be used to probe the structure of target nuclei, and how nucleon scattering observables can be interpreted in terms of nuclear structure using microscopic optical potentials. After a brief overview of the specificities of nucleon-nucleus scattering, and a quick reminder on scattering theory, the main part of this lecture is devoted to the construction of optical potentials in which the target nuclei structure information is folded with an effective interaction. Several examples of such microscopic optical model potentials are given. (author)

  18. Nuclear wastes: status and perspectives; Les Dechets nucleaires: etat des lieux et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Barre, B.; Bazile, F.; Bonin, B.; Marvy, A.; Ouzounian, G.; Wizsenfeld, B.

    2011-07-01

    Radioactive wastes are considered by the large public as a problem which mortgages the future of nuclear industry. Today, the main principles of radioactive wastes management are defined: separation, conditioning, storage and disposal are the main elements of a strategy allowing to protect the man and the environment from the impacts of the inevitable ultimate wastes. In a period of debate concerning the future of these wastes, this book aims at supplying to the public the elements which will allow him to build his own opinion about this hot topic. (J.S.)

  19. Dictionary of nuclear sciences and techniques; Dictionnaire des sciences et techniques nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Bigot, B.; Santarini, G. [CEA Saclay (HC), 91 - Gif-sur-Yvette (France)

    2008-07-01

    This reference book has been totally reworked in its fourth edition, in order to answer the needs of the numerous sectors of activity concerned by nuclear sciences and technologies: radiation protection, cancerology, neurology and pharmacology in the medical sector, power generation and more generally energy production, micro-electronics, quality control and on-line analysis in many industrial sectors, patrimony preservation, food safety, environmental and paleo-climate studies in relation with climate prospective, etc. This complete overview of the nuclear world integrates the regulatory aspects, necessary to shade light on it, and many other technological innovations. Elaborated with harmonization, clarification and exhaustiveness concerns, this dictionary is the result of a large consensus among the French-speaking nuclear community. It includes some 4800 entries with more than 250 color illustrations and an English-French glossary. Its aim is to offer to everyone a precise vocabulary, fully shared by everybody and necessary for exchanges and debates clarity. (J.S.)

  20. Declassification and restoration of nuclear sites; Declassement et restauration des sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Noynaert, L; Rahier, A; Deboodt, P; Massaut, V

    1998-09-01

    The report describes the legal and technical aspects of the declassification and restoration of nuclear sites. This involves a number of technical and administrative operations. Different declassification strategies are discussed. The evaluation of the risks and impact on the environment are discussed as well as research and development needs, costs and possible sources for funding.

  1. Links between nuclear medicine and radiopharmacy; Structuration des liens entre medecine nucleaire et radiopharmacie

    Energy Technology Data Exchange (ETDEWEB)

    Pelegrin, M. [Inserm, U896, CRLC Val-d' Aurelle-Paul-Lamarque, institut de recherche en cancerologie de Montpellier (IRCM), universite Montpellier 1, 34 - Montpellier (France); Francois-Joubert, A. [Service de medecine nucleaire, centre hospitalier de Chambery, 73 - Chambery (France); Chassel, M.L. [Radiopharmacie, service de pharmacie, centre hospitalier de Chambery, 73 - Chambrry (France); Desruet, M.D. [Service de radiopharmacie et service pharmaceutique, clinique universitaire de medecine nucleaire, CHU de Grenoble, 38 - Grenoble (France); Bolot, C. [Service de radiopharmacie, service pharmaceutique, centre de medecine nucleaire, groupement hospitalier Est, 69 - Bron (France); Lao, S. [Service de radiopharmacie, medecine nucleaire, hopital de l' Archet, 06 - Nice (France)

    2010-11-15

    Radiopharmaceuticals are nowadays under the responsibility of the radio-pharmacist because of their medicinal product status. Radiopharmacy belongs to the hospital pharmacy department, nevertheless, interactions with nuclear medicine department are important: rooms are included or located near nuclear medicine departments in order to respect radiation protection rules, more over staff, a part of the material and some activities are shared between the two departments. Consequently, it seems essential to formalize links between the radiopharmacy and the nuclear medicine department, setting the goals to avoid conflicts and to ensure patients' security. Modalities chosen for this formalization will depend on the establishment's organization. (authors)

  2. The technological prospective of non nuclear channels; La prospective technologique des filieres non nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Claverie, M.; Clement, D.; Girard, C

    2000-07-15

    This prospective study concerns the electric power demand in 2050. It examines the three non nuclear sectors of production: the natural gas combined cycle power plants, the wind turbines among the renewable energies and the cogeneration electric power - heat in the ternary and building sector. The necessity of the network adaptation to the european competition and the decentralized production of electric power will suppose new investments of transport and storage. (A.L.B.)

  3. Licence prolongations of US nuclear power plants; Les prolongations de licence des centrales nucleaires americaines

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-04-01

    Licences of US nuclear reactors were initially attributed for a 40 years duration. However, the vast majority of the reactors can benefit of a licence prolongation for a period of 20 years maximum. This article recalls first the procedure to follow for the licence prolongation demands (safety analysis, components aging, environmental impact statement), and then it makes a status of the accepted prolongations, of the demands under examination, and of the demands that should be presented in the next 5 years. (J.S.)

  4. Particles identification using nuclear emulsion in OPERA; Identification des particules par les emulsions nucleaires dans OPERA

    Energy Technology Data Exchange (ETDEWEB)

    Manai, K

    2007-10-15

    The Opera experiment will try to confirm the {nu}{sub {mu}} {yields} {nu}{sub {tau}} oscillations by the appearance of the {nu}{sub {tau}} in a pure {nu}{sub {mu}} beam. Indeed, a neutrino beam almost pure is produced at CERN (CNGS Beam) and sent to the Opera detector. The detector is composed of two muons spectrometers and a target formed by walls of bricks. Each brick is an alternation of lead plates and emulsions. This modular structure allows to reconstruct the kink topology of the {tau} lepton decay with a high spatial resolution. The great challenge of the Opera experiment is to detect the {nu}{sub {tau}} interactions with the less uncertainty. To reduce this uncertainty it is essential to identify with the greatest efficiency any background event not including a tau particle. My work permits to reduce background. My principal contribution concerns the selection development, the reconstruction and the muons identification at low energy. This work is based on the setting of variables related to the deposit energy and the multiple scattering. Previously, only deposit energy was used in the analyses of pion/muon separation. This study allows doubling the muon identification efficiency at low energy. This leads to increase the background events rejection in Opera and to decrease the contamination by 30%. I also studied the nuclear emulsions capacity to identify charged particles through the analysis of a test beam carried out by the Nagoya group. This test contains protons and pions with different energies. My work proves that the European scan system gives comparable results with those obtained by the Japanese scan system. (author)

  5. Institut National des Sciences et Techniques Nucleaires. From academic to vocational: specificity and vision

    International Nuclear Information System (INIS)

    Turpin, Laurent

    2008-01-01

    - What is INSTN?: Teaching and training service of CEA; Capability of awarding degrees; Stand-alone: only specialty degrees; Partnership with universities and Engineer schools: master degrees; Professional training operator for CEA and for SMEs. - Corner stones for the next future (5-10 years): increasing the capability in nuclear training (Nuclear skills for nuclear engineers (reactor physics,...), factor 3-4, Nuclear skills for non-nuclear engineers (civil works, project management,...), All stakeholders have to do more (Academics on basic knowledge (have to prepare to a wide range of positions), Specialty institutes on specialized knowledge (before the job and on the job), Internal programs on proprietary programs), optimizing the resources (No false hope: more training means higher costs but does not mean nuclear companies will lay golden eggs; Availability of teaching resource and capability of internship tutoring could be bottlenecks; Trained/graduate production must match actual human resources needs). - A strategy for INSTN: Academic partnerships, to implement nuclear modules within training programs; With companies, a stakeholder-shareholder joint venture model for postgraduate training; Open to European and offshore cooperation

  6. Nuclear tests: the late indemnification of victims; Essais nucleaire: l'indemnisation tardive des victimes

    Energy Technology Data Exchange (ETDEWEB)

    Charbonneau, S. [Bordeaux-1 Univ., 33 (France)

    2010-04-15

    The author briefly recalls the historical context of the creation of the CEA and outlines the silence and denial about the radioactive contamination of military personnel during the nuclear tests performed in the Algerian Sahara and in Polynesia. He also outlines the continuous action of the association of veterans and victims of these nuclear tests which gathered proofs of health consequences. He comments the content and scope of application of laws which have been lately adopted (in 2010) to acknowledge these facts and indemnify the victims

  7. Nuclear risks perception and information; Perception des risques nucleaires et information

    Energy Technology Data Exchange (ETDEWEB)

    Brenot, J; Bonnefous, S; Hubert, P

    1994-12-31

    In this text we present the studies made by the IPSN (Institute of Protection and Nuclear Safety) on the nuclear risks perception by the public and we compare this perception of risks with other industries.

  8. Technical and Economic Problems Associated with the Development of Methods of Processing and Using Radioactive Waste; Problemes techniques et economiques lies au developpement des methodes de traitement et d'utilisation des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L; Sauteron, J; Oger, C [Commissariat a l' Energie Atomique, Fontenay-Aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    The paper briefly reviews the various techniques used in processing the radioactive wastes which unavoidably result from the generation of electric power from nuclear sources. The paper goes on to define the relative importance, in nuclear fuel cycles, of the problem raised by these wastes. Emphasis is placed on the economic influence of management policies on the cost of power generation, and hence on the relative position of nuclear energy. A substantial percentage of these wastes can be economically utilized. Attention is drawn to the major technical and economic features of the industry which will come into being as a result of this utilization. The major uses anticipated are discussed: radiation sources, heat sources, auxiliary power generation. The paper concludes that satisfactory solutions have already been found to these problems, and describes possible improvements. (author) [French] La communication rappelle d'abord succinctement les differentes techniques de traitement des dechets radioactifs resultant necessairement de la production d'electricite d'origine nucleaire. On situe ensuite l'importance du probleme pose par ces residus dans le cycle du combustible nucleaire. On fait ressortir l'influence economique du choix des methodes de gestion sur le cout de production de l'energie, et par consequent sur la place devolue a l'energie nucleaire. Une part importante de ces dechets peut faire l'objet d'une utilisation rentable de l'industrie qui naitra de cette utilisation. Les principales applications envisagees sont evoquees: sources d'irradiation, sources chauffantes, generateurs auxiliaires d'energie. On conclut que d'ores et deja des solutions satisfaisantes ont ete apportees a ces problemes, et l'on decrit les perspectives d'amelioration concevables. (auteur)

  9. The struggle of the veterans of the French nuclear tests; La lutte des veterans des essais nucleaires francais

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The question debated in this article concerns the demand of compensation and recognition of the impact on their health of nuclear tests. The military personnel that worked during nuclear tests in French Polynesia and the Sahara sites, but also the inhabitants of the atolls of Moruroa and Fangataufa equally in French Polynesia. An observatory of the veterans health has been created in order to improve the medical management of military personnel and former military personnel. An association 'Moruroa e tatou' contains the Polynesian former workers of the Nuclear tests of the Pacific and the association A.V.E.N. contains the veterans of nuclear tests. numerous examples are detailed. The question is tackled too for the consequences on health of the British nuclear tests, in Australia, Christmas Islands, and New Zealand. (N.C.)

  10. Technical, economic, environmental and social follow-up of innovating farm-based small methanization plants: BIOGAZ PLUS - Report after a 12-month follow-up; Installation: EARL Guilbaud - Report after a 15-month follow-up; Installation: GAEC Des Buissons - Report after a 12-month follow-up

    International Nuclear Information System (INIS)

    Lalanne, Mathieu; Cordelier, Marine; Pouech, Philippe; Thual, Julien; Bastide, Guillaume; Faure, Benoit; Faure, Jean-Marie; Bousquet, Dominique; El Habti, Audrey; L'Heriau, Germain; Guianvarch, David; Farcy, Alexandre; Banville, Sandrine; Chauvin, Damien; Frederic, Sylvain; Haumont, Francois; Guilbaud, Gerard; Leroux, Yannick; Tronc, Jean-Sebastien; Menard, Anthony

    2015-08-01

    This document contains three follow-up reports, each concerning a small farm-based methanization unit. For each one, the report proposes a technical description (operation, provisional exploitation assessment, process principle and implementation, installed instrumentation), describes the status of production (noticed dysfunctions and identified causes, returns on experience), an operation assessment after 12 or 15 months in terms of biological performance (composition of input mixture, methane generation potential, organic load) and energetic performance (biogas, electric, thermal and energetic assessments), an assessment of environmental and social performance (time spent, energy efficiency, greenhouse gas assessment, integration of the installation within the farm, risk and pollution assessment), an economic assessment in terms of investment, of operating statements and of indicators of financial profitability. Results of composition measurements performed on input materials and digestates are provided

  11. Determination of electromagnetic modes in oversized corrugated waveguides on the electron cyclotron resonance heating installation at the tokamak Tore Supra; Determination de modes electromagnetiques de guides d'ondes corrugues surdimensionnes sur l'installation de chauffage des electrons de tokamak Tore Supra

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, L

    2001-03-09

    Electron cyclotron resonance heating (ECRH) in the Tore Supra tokamak constitutes an important step in the research aimed at obtaining thermonuclear fusion reactions. Electron heating is achieved by transmitting an electromagnetic wave from the oscillators (gyrotrons) to the plasma via the fundamental mode, propagating in oversized corrugated waveguides. Maximizing the proportion of the gyrotron power coupled to the fundamental waveguide mode is essential for the good functioning of the transmission line and for maximizing the effect on the plasma. This thesis gives all necessary tools for finding the proportion of the fundamental mode and all other modes present in passive components and at the output of the gyrotron as installed in the Tore Supra ECRH plant. This characterisation is based on obtaining amplitude and phase diagrams of the electric field on a plane transverse to the propagation axis. The most difficult part of obtaining these diagrams is measuring the phase which, despite the very short wavelength, is measured directly at low power levels. At high power levels the phase is numerically reconstructed from amplitude measurements for gyrotron characterisation. A complete theoretical study of the phase reconstruction code is given including its validation with theoretical diagrams. This study allows the realisation of a modal characterisation unit electromagnetic for measurement of radiated beams and usable in each part of the ECRH installation. At the end, the complete modal characterisation is given at low level for a mode converter and also at high level for the first series gyrotron installed at TORE SUPRA. (author)

  12. Migration, pauvreté rurale et gestion communautaire des ressources ...

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

    La migration, les déplacements et les réinstallations forcées sont loin d'être des phénomènes nouveaux au Cambodge. Après des années d'agitation et de troubles de l'ordre civil, et en raison de la croissance rapide de la population et du développement agricole, la plupart des terres irriguées et inondables au Cambodge ...

  13. L'incidence des pesticides sur les producteurs de pommes de terre ...

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

    27 janv. 2011 ... L'incidence des pesticides sur les producteurs de pommes de terre de l'Équateur ... L'entreposage des pesticides dans les bâtiments de ferme, des installations .... (les pesticides) : L'intoxication par les pesticides en Équateur.

  14. Proposition of resolution aiming at the creation of an inquiry commission relative to the safety of the french nuclear installations and the protection of inhabitants face to the risks of radioactive contaminations coming to uranium leakages or any other product used in the nuclear power plants and the radioactive waste storage facilities; Proposition de resolution tendant a la creation d'une commission d'enquete relative a la securite des installations electro-nucleaires francaises et la protection des habitants face aux risques de contaminations radioactives dues aux fuites d'uranium ou de tout autre produit utilise dans les centrales nucleaires et les installations de stockage de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This commission will have for mission to establish the facts relative to the Tricastin accident and the previous pollutions around this site; to appreciate the delay, the transparency and the public information modalities, both by the company and by the authorities; to establish a systematic and precise statement of the radioactive contaminations on the sites and around the french nuclear facilities ( included the waste storage sites); to measure the ecological damages on the ecosystems and the sanitary risks for the populations; to evaluate the prevention programmes management and the safety of these facilities; to identify the dysfunctions of the french nuclear sector and give propositions to improve the safety of these facilities. (N.C.)

  15. Report on the behalf of the Foreign Affairs, Defence and Armed Forces Commission on the bill project authorizing the ratification of the treaty between the French Republic, the United-Kingdom of Great-Britain and Northern Ireland related to common hydrodynamic and radiographic installations; Rapport fait au nom de la commission des affaires etrangeres, de la defense et des forces armees (1) sur le projet de loi autorisant la ratification du traite entre la Republique francaise et le Royaume-Uni de Grande Bretagne et d'Irlande du nord relatif a des installations radiographiques et hydrodynamiques communes

    Energy Technology Data Exchange (ETDEWEB)

    Pintat, X.

    2011-07-01

    After a presentation of the main directions defined during the London summit for the French-British defence cooperation (convergence of interests and ambitions, cooperation in the operational, capacity, technological and industrial areas), this report more precisely presents and discusses the cooperation perspectives in the military nuclear field (deterrence by the French and British nuclear weapons, the experimentation as a field of cooperation, cooperation modalities with a common installation and a common technological development centre). These perspectives encompass experimentation installations aimed at the simulation of nuclear weapons. Then, it details the content of the treaty related to common hydrodynamic and radiographic installations: characteristics of the EPURE and TDC installations, financing conditions, and some other issues

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

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

  17. Les risques industriels et le prix des logements

    DEFF Research Database (Denmark)

    Grislain-Letrémy, Céline; Katossky, Arthur

    2013-01-01

    Le prix des logements peut diminuer du fait de la proximité d’installations industrielles. Cet effet dépend de la perception du risque par les riverains et est donc potentiellement modifié par des événements changeant la perception du risque, tels que les plans de prévention des risques technolog......Le prix des logements peut diminuer du fait de la proximité d’installations industrielles. Cet effet dépend de la perception du risque par les riverains et est donc potentiellement modifié par des événements changeant la perception du risque, tels que les plans de prévention des risques...... proximité d’installations industrielles dans les agglomérations françaises de Bordeaux, Dunkerque et Rouen. La méthode des prix hédoniques permet d’estimer l’effet de la proximité des usines sur les prix des logements. Les résultats suggèrent que les écarts de prix ne sont modifiés ni par les incidents...

  18. Nuclear Installations Act 1965

    International Nuclear Information System (INIS)

    1965-01-01

    This Act governs all activities related to nuclear installations in the United Kingdom. It provides for the licensing procedure for nuclear installations, the duties of licensees, the competent authorities and carriers of nuclear material in respect of nuclear occurrences, as well as for the system of third party liability and compensation for nuclear damage. The Act repeals the Nuclear Installations (Licensing and Insurance) Act 1959 and the Nuclear Installations (Amendment Act) 1965 except for its Section 17(2). (NEA) [fr

  19. Installation report - Lidar

    DEFF Research Database (Denmark)

    Georgieva Yankova, Ginka; Villanueva, Héctor

    The report describes the installation, configuration and data transfer for the ground-based lidar. The unit is provided by a customer but is installed and operated by DTU while in this project.......The report describes the installation, configuration and data transfer for the ground-based lidar. The unit is provided by a customer but is installed and operated by DTU while in this project....

  20. The Upgraded Plasma Focus Installation > - The Installation >

    International Nuclear Information System (INIS)

    Krokhin, O.N.; Nikulin, V.Ya.; Babenko, B.A.; Gorbunov, D.N.; Gurei, A.E.; Kalachev, N.V.; Kozlova, T.A.; Malafeev, Yu.S.; Polukhin, S.N.; Sychev, A.A.; Tikhomirov, A.A.; Tsybenko, S.P.; Volobuev, I.V.

    1999-01-01

    The paper presents the upgraded plasma focus installation > - the installation > and some preliminary experimental results. The total energy stored in capacity bank is now 400 kJ, current - 5 MA with the rise time 3.5 μs. The investigation is targeted on the study of near electrode processes and its influence on plasma dynamics in a special operating regime of Filippov type PF - Hard X-ray regime. (author)

  1. State of the art of methods for the elimination of nitrogen in small and medium-sized agricultural biogas installations - Final report; Etat de l'art des methodes (rentables) pour l'elimination, la concentration ou la transformation de l'azote pour les installations de biogaz agricoles de taille petite/moyenne - Rapport final

    Energy Technology Data Exchange (ETDEWEB)

    Bakx, T.; Membrez, Y.; Mottet, A. [Erep SA, Aclens (Switzerland); Joss, A.; Boehler, M. [EAWAG, Duebendorf (Switzerland)

    2009-09-15

    This final report for the Swiss Federal Office of Energy (SFOE) reports on research work done on the elimination, concentration or transformation of nitrogen in small and medium-sized agricultural biogas installations. The goal of the project - the conception of a state of the art on existing, economically feasible technologies or processes to treat the nitrogen produced in anaerobic digestion - is discussed. Typical Swiss small/medium size agricultural biogas plants with an electrical power of around 100 kW from its combined heat and power generation (CHP) unit are examined. A reference installation is discussed which treats cow slurry, organic restaurant waste, used vegetable oils, bakery wastes, coffee grounds, and cereal wastes. A literature research is described which was conducted to find information regarding available treatment techniques for slurry and digestate treatment. Information from Switzerland, France, Belgium, the Netherlands, Germany and Austria was used. Various techniques are examined including a screw-press separator, a centrifuge, membrane filtration, air stripping with acid wash, air stripping with catalytic combustion, evaporation, band dryer, precipitation, composting and biological treatment. The economic analysis and the comparison between techniques are quoted as being coarse as they are based on numerous assumptions.

  2. SOL-PAC: Integrated solar heating and heat pump systems for refurbished buildings - Performance analysis; SOL-PAC: analyse des performances du couplage d'une pompe a chaleur avec une installation solaire thermique pour la renovation - Rapport final

    Energy Technology Data Exchange (ETDEWEB)

    Citherlet, C.; Bony, J.; Nguyen, B.

    2008-07-01

    The purpose of this study is to evaluate the energetic and economic performances of various types of brine/water heat pumps coupled with a fan coil fitted with solar collectors. Different indicators such as the annual coefficient of performance or the electricity consumption have been compared between the different analysed systems. The optimization of the energy control system and energy storage was investigated in order to reduce the operation time of the fan coil. This study has been performed using the TRNSYS computerized simulation package. The icing of the fan coil as well as its defrosting cycles could not been taken into account within the framework of this project, because of a lack of a numerical model. At current electricity prices, the most economical solution remains the heat pump without solar collectors. However, from an energy point of view, the annual overall coefficient of performance of the installation may be improved by 15 to 36%, depending on the climate, thanks to the coupling with solar collectors. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-03-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-09-09

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-12-03

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

  6. Contrôle des Circuits Auxiliaires des PFW (arrêt machines 2002/2003)

    CERN Document Server

    Ottaviani, J

    2003-01-01

    Les PFW sont des nappes polaires installées sur les pôles des aimants du PS. Elles sont au nombre de 4 par unité d aimant et constituées d un circuit principal (dans lequel circule le courant désiré selon le cycle magnétique utilisé) et de circuits auxiliaires. Les circuits auxiliaires sont des enroulements de correction (boucles de tour et pick-up brasés sur les enroulements). Pendant la variation du champ magnétique de l aimant PS, on utilise des tensions induites dans ces circuits auxiliaires pour corriger les erreurs de champ dues aux courants de Foucault dans la chambre à vide. Chaque année, pendant l arrêt machine, on vérifie si les caractéristiques des circuits auxiliaires correspondent aux normes (mesures des résistances des boucles de tours, résistances entre pick-up et isolation des circuits) afin de faire un suivi. Les 404 PFW sont ainsi vérifiées. Dans cette note, on ne relèvera que les PFW ayant des défauts (valeurs hors tolérances, boucles ouvertes ou en court-circuit, déf...

  7. Règle d'installation vidéosurveillance

    CERN Document Server

    2011-01-01

    Ce référentiel définit les exigences techniques minimales applicables aux systèmes de vidéosurveillance, avec des caméras implantées à l’intérieur ou l’extérieur. Il donne des recommandations pour concevoir, installer et maintenir des systèmes de vidéosurveillance dans des applications de sécurité. Pour une vidéosurveillance efficace, on pourra appliquer la méthodologie proposée : comment réaliser l’analyse de risque ? Quel rôle attribuer au système de vidéosurveillance ? quel système mettre en place, avec quelles fonctions et quelles caractéristiques techniques ? comment réaliser l’installation ? comment assurer la maintenance du système ? Cette nouvelle édition a notamment pour objectifs de : compléter les rôles de la vidéosurveillance (gestion d'activité) ; clarifier la définition des objectifs de prise de vue ; inclure l'utilisation d'une cible normalisée pour la réception de l'installation ; mettre à disposition un outil d'aide pour les petits systèmes ;...

  8. Some results on the fluorescence of gases excited by high-energy charged particles; Quelques resultats concernant la fluorescence de gaz excites par des particules chargees de grande energie

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The essential characteristics of rare gases for use as scintillators are as follows: a very brief period of luminescence, generally less than 10{sup -8} s; a linear response as a function of the energy lost by the nuclear particle in the gas, even in the case of strongly ionising particles (fission fragments). In the gaseous or condensed state therefore, they are of great interest in nuclear physics. (author) [French] Les caracteristiques essentielles des gaz rares en tant que scintillateurs sont: une duree de luminescence tres breve, inferieure a 10{sup -8} s en general; une reponse lineaire en fonction de l'energie perdue par la particule nucleaire dans le gaz, meme dans le cas de particules fortement ionisantes (fragments de fission). A l'etat gazeux ou condense, ils presentent donc un grand interet en physique nucleaire. (auteur)

  9. Contribution to the Study of Nuclear Magnetic Resonance in Ferromagnets; Contribution a l'etude de la resonance nucleaire dans les corps ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Properties of nuclear magnetic resonance in the field acting on the nucleus in a ferromagnet were studied. Nuclei were {sup 57}Fe in iron and yttrium iron garnet. Static properties of resonance (frequency, line-width, dipolar structure) were investigated and compared with magnetic behavior and magnetic structure of the materials. Relaxation in garnet points out importance of long range fluctuations induced by impurities in a ferromagnetic lattice. (author) [French] Nous avons etudie les proprietes de la resonance nucleaire dans le champ existant a remplacement d'un noyau dans un corps ferromagnetique (champ local). Les noyaux etaient ceux de {sup 57}Fe dans le fer et dans le grenat d'yttrium et de fer. Les proprietes statiques de la resonance (frequence de resonance, largeur de la raie, structures dues a l'interaction dipolaire) ont ete etudiees et reliees aux caracteristiques magnetiques et a la structure de ces corps. La relaxation dans le grenat a mis en evidence les fluctuations a longue distance induites par des impuretes dans un reseau ferromagnetique. (auteur)

  10. Contribution to the Study of Nuclear Magnetic Resonance in Ferromagnets; Contribution a l'etude de la resonance nucleaire dans les corps ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Properties of nuclear magnetic resonance in the field acting on the nucleus in a ferromagnet were studied. Nuclei were {sup 57}Fe in iron and yttrium iron garnet. Static properties of resonance (frequency, line-width, dipolar structure) were investigated and compared with magnetic behavior and magnetic structure of the materials. Relaxation in garnet points out importance of long range fluctuations induced by impurities in a ferromagnetic lattice. (author) [French] Nous avons etudie les proprietes de la resonance nucleaire dans le champ existant a remplacement d'un noyau dans un corps ferromagnetique (champ local). Les noyaux etaient ceux de {sup 57}Fe dans le fer et dans le grenat d'yttrium et de fer. Les proprietes statiques de la resonance (frequence de resonance, largeur de la raie, structures dues a l'interaction dipolaire) ont ete etudiees et reliees aux caracteristiques magnetiques et a la structure de ces corps. La relaxation dans le grenat a mis en evidence les fluctuations a longue distance induites par des impuretes dans un reseau ferromagnetique. (auteur)

  11. Construction of a differential thermal analysis installation; Realisation d'une installation d'analyse thermique differentielle

    Energy Technology Data Exchange (ETDEWEB)

    Branche, G; Chantret, F [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    The authors are indicating the characteristics of a D.T.A. installation they built. Experimental rooms, ovens, thermal regulation, recording methods are thoroughly described, with outlining of the requirements to obtain a high sensitivity. Numerous D.T.A. curves relating to argillaceous substances, bituminous shales, and uraniferous compounds are given. (author) [French] Les auteurs donnent les caracteristiques de l'installation d'Analyse Thermique Differentielle qu'ils ont construits. Ils decrivent en detail les chambres d'experiences, les fours, la regulation thermique, l'enregistrement, en insistant sur les conditions necessaires pour obtenir une sensibilite elevee. Ils donnent de nombreuses courbes differentielles relatives des produits argileux, des schistes bitumineux et des composes uraniferes. (auteur)

  12. LHC installation planning

    CERN Document Server

    Weisz, S

    2005-01-01

    installation of the general services, the installation of the cryogenic line (QRL), the installation of the machine elements and the hardware commissioning. While the installation of the general services is now almost finished (see presentation by Katy Foraz and Serge Grillot), several problems and delays with the QRL made it unavoidable to revise the installation strategy and to schedule a number tasks in parallel. A new compressed installation planning has been issued, that fulfils the strategic objectives and allows starting new activities with minimal delays in sectors 7-8 and 8-1. However, the shortcuts that are introduced increase the level of risk that we will have to face and the coordination of such a large and complex variety of simultaneous activities makes the project even more challenging. The document will describe how the input from the different equipment groups is taken into account by the master schedule planning team with respect to equipment availability and production as well as logistics...

  13. A future for nuclear sites beyond their service life. Nuclear site value development; Un avenir pour les sites nucleaires en fin de cycle. Valorisation des sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites in built-up areas. AREVA is currently working on a site value development program on two industrial sites in Annecy and Veurey, near Grenoble. Dating back to 1955 and 1957, the sites were created for the manufacture and precision machining of uranium metal. The number of clean-up and dismantling projects is set to rise steadily in the years ahead and site value development will unquestionably become a new nuclear activity in its own right. AREVA is developing the corresponding competencies and expertise: new professions are springing up (value development project manager, scenario and feedback manager, operational dismantling methods manager, flushing operator, etc.) and a dedicated theoretical and practical training program is being put together. Once a nuclear site has been shut down, the long-term dismantling and value development operations make a considerable contribution to the local economy. Site rehabilitation is an environmental necessity and improves nuclear's image in the eyes of the public. As new nuclear projects get off the ground, developing the value of disused sites will free up space for future projects and make a valuable contribution to the nuclear revival.

  14. Electrical installation calculations basic

    CERN Document Server

    Kitcher, Christopher

    2013-01-01

    All the essential calculations required for basic electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practice. A step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3Fo

  15. Electrical installation calculations advanced

    CERN Document Server

    Kitcher, Christopher

    2013-01-01

    All the essential calculations required for advanced electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practiceA step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3For apprentices and electrical installatio

  16. Electrical installations and regulations

    CERN Document Server

    Whitfield, J F

    1966-01-01

    Electrical Installations and Regulations focuses on the regulations that apply to electrical installations and the reasons for them. Topics covered range from electrical science to alternating and direct current supplies, as well as equipment for providing protection against excess current. Cables, wiring systems, and final subcircuits are also considered, along with earthing, discharge lighting, and testing and inspection.Comprised of 12 chapters, this book begins with an overview of electrical installation work, traits of a good electrician, and the regulations governing installations. The r

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  18. Spectra theory for nuclei with closed shells (1962); Theorie des spectres des noyaux a couches completes (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    second approximation which alone leads to a region of optimum agreement identical for both carbon and oxygen. An excellent general agreement is obtained with the known spectra of these two nuclei. The importance of higher order terms in the calculation of the 3{sup -} and 5{sup -} collective states for calcium 40 is demonstrated; furthermore it is possible to explain these levels only by the second approximation. Certain forecasts are made using the effective forces thus found. (author) [French] On applique une theorie unifiee des spectres des noyaux a couches completes, fondee sur les excitations elementaires particule-trou de ces systemes, a l'etude du carbone 12, de l'oxygene i6 et du calcium.40. Deux approximations sont utilisees. La premiere consiste a diagonaliser l'interaction residuelle a deux corps dans un sous-espace limite de configurations a une particule et un trou. Sa validite repose sur l'energie importante exigee pour l'excitation d'une paire particule-trou. La seconde approximation consiste a resommer la sous-serie infinie des diagrammes particule-trou. Elle est equivalente a la methode de Hartree-Fock dependante du temps ou a la methode des Quasi-Bosons. Son domaine de validite, dans le cas nucleaire, n'est pas bien compris. Les diagrammes sommes sont preponderants a la limite des fortes densites, alors que la densite nucleaire est de l'ordre de l'unite. La violation des Principe de Pauli, dans cette approximation, n'est justifiee que si le nombre de paires excitees est petit par rapport au nombre d'etats de particule disponibles; or, dans les noyaux legers les degenerescences des couches sont petites. Neanmoins cette approximation qui postule l'existence d'un champ nucleaire moyen, lentement variable dans le temps par rapport aux periodes des nucleons a le merite d'etre self-consistante, de donner des etats propres orthogonaux a l'etat non physique du centre de masse et d'ameliorer le calcul des regles de somme. Pour determiner et limiter le role de la

  19. Nuclear program of Iran. Towards de-escalation of a nuclear crisis. Advisory letter; Nucleair programma van Iran. Naar de-escalatie van een nucleaire crisis. Briefadvies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-15

    The Dutch government, partly at the request of the House of Representatives (Second Chamber), the AIV asked to give an opinion about the position of Iran in the region and the role of the nuclear program of Iran in the geopolitical relations, in view of the most recent developments [Dutch] De Nederlandse regering heeft, mede op verzoek van de Tweede Kamer der Staten-Generaal, de AIV gevraagd advies uit te brengen over de positie van Iran in de regio en de rol van het nucleaire programma van Iran in de geopolitieke verhoudingen hierin, mede gelet op de meest recente ontwikkelingen.

  20. Food Irradiation Research and Pilot Facilities in Operation or Planned in India; Recherches sur l'irradiation des Denrees Alimentaires et Installations Pilotes en Service ou a l'Etude en Inde; Izuchenie oblucheniya pishchevykh produktov' i dejstvuyushchie'i zaplanirovannye opytnye ustanovki v Indii; Irradiacion de Alimentos en la India: Investigaciones y Plantas Piloto en Servicio o en Proyecto

    Energy Technology Data Exchange (ETDEWEB)

    Kumta, U. S.; Sreenivasan, A. [Atomic Energy Establishment Trombay, Bombay (India)

    1966-11-15

    temperature ambiante (25-28 Degree-Sign C). Differents aspects de ce procede ont ete etudies, en particulier la dose de rayonnements admissible, l'effet concomitant de l'acide sorbique, les ameliorations de la qualite des produits au moyen d'autres traitements physiques et chimiques et le type d'emballage. En combinant l'irradiation a faibles doses (0,1 et 0,2 Mrad) et l'utilisation d'emballages enduits d'acide sorbique, il est possible de retarder d'environ 20 jours, a la temperature ambiante, l'apparition dans les fromages de moisissures et d'alterations de la saveur par oxydation. On a etudie les effets nuisibles des rayonnements sur les proteines du poisson en vue de determiner notamment le degre de scission et d'aggregation, l'effet de dedoublement et la mobilite electrophoretique. L'utilisation des rayonnements pour la desinsection des cereales et la prolongation de la duree de conservation du pain a donne des resultats encourageants. On etudie les effets de l'irradiation sur les composants et les qualites nutritives du ble. Le memoire decrit les installations d'irradiation en service et a l'etude. Le laboratoire d'irradiation et de traitement des'denrees alimentaires, qui sera bientot termine, contiendra un irradiateur au cobalt-60 pour produits empaquetes (100 000 Ci), un irradiateur portatif au cobalt-60 pour cereales (28 000 Ci) et des installations annexes de laboratoire pour l'analyse, la recherche et le traitement. L'irradiateur pour produits empaquetes doit avoir une capacite de 45 kg/h sous 0,5 Mrad et l'irradiateur portatif pourra traiter 225 kg de cereales a l'heure, sous 15 krad. (author) [Spanish] Se ha estudiado el empleo de las radiaciones gamma de una fuente de cobalto-60 para: a) retrasar la maduracion de ciertas frutas tropicales; b) esterilizar frutas y verduras, en combinacion con un tratamiento termico moderado; c) prolongar el periodo de almacenamiento de frutas semidesecadas; d) inhibir la germinacion de patatas y cebollas. Se han evaluado las

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-10-15

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

  3. Illicit operation of industrial plant subject to licensing, or of other installations within the purview of the German Federal Emission Control Act (BImSchG), which have been shut down for protection against hazards (section 327, subsection 2, No. 1 Penal Code (StGB)); Das unerlaubte Betreiben von genehmigungsbeduerftigen Anlagen oder sonstigen Anlagen im Sinne des Bundes-Immissionsschutzgesetzes, deren Betrieb zum Schutz vor Gefahren untersagt worden ist (Paragraph 327 Abs.2 Nr.1 StGB)

    Energy Technology Data Exchange (ETDEWEB)

    Ocker, A.

    1995-12-31

    The 18th act of 28 March 1980 for amendment of the German Criminal Code (StGB) incorporated the provisions governing the criminal offence of illicit operation of installations subject to licensing into the StGB. These provisions have until then been forming part of the BImSchG (Federal Act on Emission Control). The study in hand presents a discussion of section 327, subsection 2, No. 1 StGB, because this provision represents a fundamental type of an administration accessory criminal offence and thus is suitable to be taken as a basis for an analysis of the scope of problems covered by the StGB, but having an effect on and being interlaced with offences governed by other acts and legal provisions. The study addresses inter alia items such as the object of legal protection defined by this section of the StGB, the provisions defining the licensability of a non-licensed installation in operation, and the consequences of defective decisions under administrative law on the applicability of criminal law provisions. The specific aspects of section 327 StGB, which are of a dominantly administrative nature, are discussed, in particular those referring to the definition of the term ``industrial installation`` as defined by the BImSchG. [Deutsch] Durch das 18. Strafrechtsaenderungsgesetz vom 28.3.1980 wurde der Straftatbestand des unerlaubten Betreibens von Anlagen, die einer Genehmigung nach dem Bundesimmissionsschutzgesetz beduerfen, aus dem BImSchG in das Kernstrafrecht ueberfuehrt. Die vorliegende Untersuchung versucht eine eingehendere Auseinandersetzung mit Para. 327 Abs. 2 Nr. 1 StGB, weil diese Vorschrift als ein Grundtypus der verwaltungsakzessorischen Straftatbestaende die Gelegenheiit zur vertieften Diskussion von umfassenderen strafrechtlichen Problemkreisen gibt. Angesprochen sind insoweit vor allem die Frage des geschuetzten Rechtsgutes der Norm, der Behandlung der materiellen Genehmigungsfaehigkeit eines ungenehmigten Anlagenbetriebs sowie der Auswirkungen von

  4. ANALYSE DES PERCEPTIONS LOCALES ET DES FACTEURS ...

    African Journals Online (AJOL)

    AISA

    1Faculté des Sciences Agronomiques (FSA), Université d'Abomey-Calavi (UAC), 01 BP 526 Cotonou Bénin. Email : cgbemavo@yahoo.fr. 2Institut National des Recherches Agricoles du Bénin, Centre de Recherches Agricoles d'Agonkanmey (CRA-A),. Laboratoire des Sciences du Sol, Eau et Environnement (LSSEE).

  5. Project of law authorizing the approval of the agreement between the government of the French republic and the government of the Russian federation relative to the civil liability by way of nuclear damage owing to the supply of materials from the French republic devoted to nuclear facilities in the Russian federation; Projet de loi autorisant l'approbation de l'accord entre le gouvernement de la republique francaise et le gouvernement de la federation de Russie relatif a la responsabilite civile au titre de dommages nucleaires du fait de fournitures en provenance de la republique francaise destinees a des installations nucleaires en federation de Russie

    Energy Technology Data Exchange (ETDEWEB)

    Raffarin, J.P.; Villepin, D. de

    2002-07-01

    An agreement between France and Russia was signed on June 20, 2000 about the civil liability of Russia because of the supply of French material devoted to Russian nuclear facilities. This agreement was necessary because Russia do not belong to any of the two big international civil liability systems relative to nuclear energy, i.e. the Paris convention from July 29, 1960 (in the OECD framework) and the Vienna convention from May 21, 1963 (in the IAEA framework). This agreement offers a protection to the French nuclear suppliers against any damage claims in the case of a nuclear accident occurring on the Russian federation territory. This project of law aims at approving this agreement. (J.S.)

  6. Installation for producing sealed radioactive sources; Installation de fabrication de sources radioactives scellees

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [French] Cette installation a ete concue et realisee pour effectuer des fabrications de sources scellees d'elements de fission: caesium 137 - strontium 90 - promethium 147 - ruthenium 106 - cerium 144 en particulier. L'installation est composee de cellules etanches et protegees, chacune d'elles etant affectee a une fabrication particuliere. La securite et la surete de fonctionnement de l'ensemble sont parmi les elements principaux qui ont guide l'etude. Le rapport decrit l'installation et plus particulierement l'appareillage utilise ainsi que les divers controles et commandes. Le bilan de fonctionnement apres 6 ans d'exploitation sert de conclusion. (auteurs)

  7. Installation for producing sealed radioactive sources; Installation de fabrication de sources radioactives scellees

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [French] Cette installation a ete concue et realisee pour effectuer des fabrications de sources scellees d'elements de fission: caesium 137 - strontium 90 - promethium 147 - ruthenium 106 - cerium 144 en particulier. L'installation est composee de cellules etanches et protegees, chacune d'elles etant affectee a une fabrication particuliere. La securite et la surete de fonctionnement de l'ensemble sont parmi les elements principaux qui ont guide l'etude. Le rapport decrit l'installation et plus particulierement l'appareillage utilise ainsi que les divers controles et commandes. Le bilan de fonctionnement apres 6 ans d'exploitation sert de conclusion. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-10-15

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

  9. Organisation des travaux ST-CV

    CERN Document Server

    Martel, C; CERN. Geneva. ST Division

    2003-01-01

    Débutée il y a deux ans, la phase de construction des installations de refroidissement du LHC a atteint en 2003 son apogée. De nombreux autres projets sont également gérés par le groupe dans divers secteurs du laboratoire. La spécificité du groupe est de réaliser des installations complexes impliquant des spécificités diverses telles qu’aéraulique, hydraulique, électrique, etc. Pour faire face à ces demandes la section travaux du groupe ST CV a adopté une structure capable de réaliser ces divers projets avec un minimum de personnel. La première partie de ce document décrit l’organisation de la section travaux ST CV. Dans une deuxième partie, les auteurs dressent un état des lieux des chantiers par projet en décrivant plus particulièrement les activités dans les domaines du traitement d’air et de refroidissement par eau.

  10. Detection of contamination of the respiratory tracts by autoradiography of sputum (1963); Recherche de contaminations des voies respiratoires par l'autoradiographie des crachats (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Andre, M; Hugot, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-07-01

    The sputum collected in the morning immediately after awakening is dissolved in mineral acids and then evaporated on a stainless steel plate. It is placed in contact with a nuclear emulsion plate and the number of traces appearing after 24 hrs, 48 hrs and 7 days exposure is counted. The conditions of exposure, development, and result interpretation are defined. (authors) [French] Le crachat recueilli le matin aussitot apres le reveil est mineralise puis evapore sur une plaque d'acier inoxydable. On met en contact avec une plaque d'emulsion nucleaire et on compte le nombre de traces apparues apres 24 h, 48 h et 7 jours d'exposition. Les conditions d'exposition, de developpement et l'interpretation des resultats sont definies. (auteurs)

  11. 3D Projection Installations

    DEFF Research Database (Denmark)

    Halskov, Kim; Johansen, Stine Liv; Bach Mikkelsen, Michelle

    2014-01-01

    Three-dimensional projection installations are particular kinds of augmented spaces in which a digital 3-D model is projected onto a physical three-dimensional object, thereby fusing the digital content and the physical object. Based on interaction design research and media studies, this article ...... Fingerplan to Loop City, is a 3-D projection installation presenting the history and future of city planning for the Copenhagen area in Denmark. The installation was presented as part of the 12th Architecture Biennale in Venice in 2010....

  12. TESLA accelerator installation

    International Nuclear Information System (INIS)

    Neskovic, N.; Ostojic, R.; Susini, A.; Milinkovic, Lj.; Ciric, D.; Dobrosavljevic, A.; Brajuskovic, B.; Cirkovic, S.; Bojovic, B.; Josipovic, M.

    1992-01-01

    The TESLA accelerator Installation is described. Its main parts are the VINCY Cyclotron, the multiply charged heavy-ion mVINIS Ion Source, and the negative light-ion pVINIS Ion Source. The Installation should be the principal installation of a regional center for basic and applied research in nuclear physics, atomic physics, surface physics and solid state physics, for production of radioisotopes, for research and therapy in nuclear medicine. The first extraction of the ion beam from the Cyclotron is planned for 1995. (R.P.) 3 refs.; 1 fig

  13. Very high temperature measurements: Applications to nuclear reactor safety tests; Mesures des tres hautes temperatures: Applications a des essais de surete des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Parga, Clemente-Jose

    2013-09-27

    This PhD dissertation focuses on the improvement of very high temperature thermometry (1100 deg. C to 2480 deg. C), with special emphasis on the application to the field of nuclear reactor safety and severe accident research. Two main projects were undertaken to achieve this objective: - The development, testing and transposition of high-temperature fixed point (HTFP) metal-carbon eutectic cells, from metrology laboratory precision (±0.001 deg. C) to applied research with a reasonable degradation of uncertainties (±3-5 deg. C). - The corrosion study and metallurgical characterization of Type-C thermocouple (service temp. 2300 deg. C) prospective sheath material was undertaken to extend the survivability of TCs used for molten metallic/oxide corium thermometry (below 2000 deg. C)

  14. Construction, fabrication, and installation

    International Nuclear Information System (INIS)

    1992-05-01

    This standard specifies the construction, fabrication, and installation requirements that apply to concrete containment structures of a containment system designated as class containment components, parts and appurtenances for nuclear power plants

  15. Visiting the SPS installation

    CERN Multimedia

    1975-01-01

    ...., Guenther Loehr, Hans Horisberger walk along the SPS tunnel: here, on the right, an absorber block of 22 tons for beam dumping in the external beam lines. The chariot serves for the installation of the block.

  16. Biggest semiconductor installed

    CERN Multimedia

    2008-01-01

    Scientists and technicians at the European Laboratory for Particle Physics, commonly known by its French acronym CERN (Centre Europen pour la Recherche Nuclaire), have completed the installation of the largest semiconductor silicon detector.

  17. Sizewell 'B' cable installation

    International Nuclear Information System (INIS)

    Gemmell, D.R.

    1992-01-01

    N G Bailey and Co. Ltd., UK were awarded the contract for the procurement, manufacture, works testing, works finishing, supply, delivery, off-loading, storage, installation, site finishing, preservation, setting to work and site testing of the following; the main cable installation throughout the Station including the addition of the Radioactive Waste Building, earthing and lightning protection installation, cable supporting steelwork and carriers and glanding and termination of cables. The cabling installation comprises power distribution, control and instrumentation cabling including all the associated cabling accessories, terminal boxes and similar components. The way that the contract was set-up, awarded and is now being carried out is described. Planning and industrial relations have been key features of the contract. (Author)

  18. A heat pump coupled to geothermal probes for heating and cooling of a small to medium sized enterprise; Pompe a chaleur sur sondes geothermiques pour chauffer et refroidir une PME. Installation de chauffage et de climatisation des bureaux et des ateliers de l'entreprise Roger Seematter SA a St-Legier

    Energy Technology Data Exchange (ETDEWEB)

    Luthi, M.; Seematter, R. [Roger Seematter SA, St-Legier/Vevey (Switzerland)

    2004-07-01

    The new building of Roger Seematter SA near Vevey, southwestern Switzerland, contains workshops and offices having a useful floor area of about 1100 m{sup 2}. Space heating and cooling is provided by a reversible water-water heat pump coupled to vertical geothermal probes. The estimated heating power amounts to 27-30 kW, the estimated cooling power during summer 21 kW. Three vertical geothermal probes of 150 meters length are used as heat source in winter and are also used for recharging the ground in summer. The energy efficiency of the installation was monitored from October 2002 to June 2004 yielding a coefficient of performance of the heat pump lying between 3.7 and 3.9, and a coefficient of performance for the whole system of 3.2 to 3.4. The investment cost for the whole system amounts to CHF 193'000, the investment for a conventional heating system with an oil-fired boiler would have been CHF 105'000.

  19. Results of concentration measurements of artificial radioactive aerosols in the lower atmosphere; Resultats des mesures de concentration, dans la basse atmosphere, des aerosols radioactifs artificiels

    Energy Technology Data Exchange (ETDEWEB)

    Ardouin, B; Jehanno, C; Labeyrie, J; Lambert, G; Tanaevsky, O; Vassy, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-07-01

    This report gives the results of the measurements of artificial gross-{beta}-radioactivity in aerosols in the lower atmosphere; these measurements have been made by the Electronic Physics Service of the Electronic Department, and by the Atmospheric Physics Laboratory of the Paris Science Faculty. The measurements were begun in September 1956 and were continued in an increasing number of stations both in France and in the rest of the world. The present report deals with the period up to the end of august 1961, that is up to the end of the nuclear moratorium. After recalling the constitution and the properties of radioactive aerosols present in the atmosphere, the authors describe the measurement methods, estimate their accuracy and discuss various aspects of the results. (authors) [French] Ce rapport contient les resultats des mesures de radioactivite {beta} globale d'origine artificielle des aerosols dans la basse atmosphere, effectuees conjointement par le Service d'Electronique Physique du Departement d'Electronique et le Laboratoire de Physique de l'Atmosphere de la Faculte des Sciences de Paris. Les mesures ont commence en septembre 1956 et ont ete poursuivies dans un nombre croissant de stations, tant en France que dans le reste du monde. Le present rapport s'arrete a la fin aout 1961, c'est-a-dire au moment de la reprise des essais nucleaires. Apres avoir rappele la constitution et les proprietes des aerosols radioactifs presents dans l'atmosphere, les auteurs indiquent les methodes de mesure utilisees, evaluent leur precision et discutent les differents aspects des resultats de leurs mesures. (auteurs)

  20. Étude et mise en pratique d'un service autour des produits

    OpenAIRE

    Anthony Peguet

    2013-01-01

    Depuis une vingtaine d'années, nous assistons à une démocratisation des services dans les entreprises industrielles. De nombreux types de services autour des produits sont ainsi mis en place : installation de matériels, assistance, formations, etc. Un des objectifs principal de la mise en place de ces différents services est l'augmentation de l'attachement des clients à l'entreprise. Cette fidélité permet d'engendrer des profits directement et indirectement. Directement par l'augmentation du ...

  1. The control of nuclear sector; Le controle du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The Asn is loaded with the control of the nuclear safety and the radiation protection in France: it provides this control, in the name of the state, to protect the workers, the patients, the public and the environment of the risks in relation with nuclear activities. The control is the core business of Asn. Asn so checks the nuclear basic installations (I.N.B.), since their conception until their dismantling, the pressure equipment specially conceived for these installations, the management of the radioactive waste as well as the transport of radioactive substances. Asn also checks all the industrial and research installations as well as the hospitals where are used ionizing radiations. It is a more recent profession there, because dating the reform of the control of the nuclear power of 2002, which constitutes that of the radiation protection. The first responsibility of the activities at risks falls to the one who begins them. This principle applies to all the sectors checked by Asn: an industrialist is responsible for the safety of the nuclear installations which he exploits, a doctor is responsible for the use of the ionizing radiations which he uses. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-10

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

  3. Model of purchase contract of the electric power produced by installations which valorize the domestic wastes or equivalent, at the exception of the installations using biogas, and subjected to the electric power purchase obligation. Established in the application of the article 5 from the decree of the 10 may 2001 and approved by the ministry charged with the electric power; Modele de contrat d'achat de l'energie electrique produite par les installations qui valorisent des dechets menagers ou assimiles, a l'exception des installations utilisant du biogaz, et beneficiant l'obligation d'achat d'electricite. Etablie en application de l'article 5 du decret du 10 mai 2001 et approuve par le Ministre charge de l'electricite

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The text of the contract is provided presenting the general conditions and specific conditions adapted to the installation characteristics of the electric power producer: contract object, connecting to the public network, producer installation, reciprocal agreements, measure and control of the energy and power, tariffs periods, price of the bought energy, taxes, payments, contract management, validity, suspension modification or avoidance of the contract. (A.L.B.)

  4. Study of the first collective levels of the even-even nuclei between masses 182 and 206; Etude des premiers niveaux collectifs des noyaux pairs-pairs entre les masses 182 et 206

    Energy Technology Data Exchange (ETDEWEB)

    Barloutaud, R; Leveque, A; Lehmann, P; Quidort, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    The reduced probabilities of deexcitation of the first two 2 + levels of {sup 184}W, {sup 186}W, {sup 188}Os, {sup 190}Os, {sup 192}Os and {sup 194}Pt have been deduced from coulombic excitation experiments on these nuclei.The results are included in a chart of the properties of the first two 2 + levels of even-even nuclei situated between masses 182 and 206. The variation of these properties as a function of nuclear distortion is compared with the various theoretical predictions concerning vibration levels. (author) [French] Les probabilites reduites de desexcitation des deux premiers niveaux 2 + de {sup 184}W, {sup 186}W, {sup 188}Os, {sup 190}Os, {sup 192}Os and {sup 194}Pt ont ete deduites des experiences d'excitation coulombienne de ces noyaux. Les resultats sont inseres dans une systematique des proprietes des deux premiers niveaux 2 + des noyaux pairs-pairs situes entre les masses 182 et 206. La variation de ces proprietes en fonction de la deformation nucleaire est comparee aux diverses predictions theoriques concernant les niveaux de vibration. (auteur)

  5. Capping off installation

    CERN Multimedia

    2006-01-01

    Installation of the cathode strip chambers for the muon system on the CMS positive endcap has been completed. Technicians install one of the last muon system cathode strip chambers on the CMS positive endcap. Like successfully putting together the pieces of a giant puzzle, installation of the muon system cathode strip chambers on one of the CMS endcaps has been completed. Total installation of the cathode strip chambers (CSC) is now 91 percent complete; only one ring of chambers needs to be mounted on the remaining endcap to finish installation of the entire system. To guarantee a good fit for the 468 total endcap muon system CSCs, physicists and engineers from the collaboration spent about 10 years carefully planning the design. The endcap muon system's cables, boxes, pipes and other parts were designed and integrated using a 3D computerized model. 'It took a long time to do all the computer modelling, but in the long run it saved us an enormous amount of time because it meant that everything fit together,...

  6. Origin of elements of the Uranium-235 family observed in the Ellez river near the EL-4 experimental nuclear reactor in dismantling (Monts d'Arree- Finistere department); Origine des elements de la famille de l'uranium-235 observes dans la riviere Ellez a proximite du reacteur nucleaire experimental EL4 en cours de demantelement (Mont d'Arree - departement du Finistere). Resultats et premiers constats annee 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    In a previous study which concerned the catchment basin of the harbour of Brest, the A.C.R.O. put in evidence a marking by artificial radioelements around the power plant of Brennilis which can be imputed without ambiguities to the nuclear installation. It also put in evidence abnormalities concerning the natural radioactivity which justifies this new study. In the area of the Monts d'Arree, actinium 227 ({sup 227}Ac), non born by its ascendents which are {sup 235}U and {sup 231}Pa is observed. This phenomenon is characterized by mass activities superior to these ones of {sup 235}U and able to reach these ones of {sup 238}U. Its presence corresponds with the drainage of the Ellez river since the former channel of radioactive effluents releases from the nuclear power plant EL-4 up to the reservoir Saint-Herblot situated 6 km downstream. The strongest values of radioactivity are registered near the disused power plant, at this place a relationship exists between the level of actinium 227 and this one of the artificial radioactivity as it exists a relationship with the decay products of radon exhaled from the subsoil ({sup 210}Pb). But its presence is not limited to a part of the Ellez river, it is equally observed in terrestrial medium, in places in priori not influenced by the direct liquid effluents of the power plant. This place is situated at more than 4 km and without any connection with the Ellez waters. At this stage of the study, it is not possible to answer with certainty the question of the origin of this phenomenon. A new reorientation is considered indispensable to clarify definitively the origin of this unknown phenomenon in the scientific publications and the environmental monitoring. (N.C.)

  7. variabilite des productions et des revenus des exploitations

    African Journals Online (AJOL)

    3Centre de coopération internationale en recherche agronomique pour le développement (CIRAD), UMR Innovation,. Montpellier, France. Doubangolo COULIBALY, Email kone_b@yahoo.fr. RESUME. La durabilité des systèmes de production à base de coton dans un contexte de variabilité des prix aux producteurs et de ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

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

  9. Ventilation of radioactive enclosures; Ventilation des enceintes radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Caminade, F; Laurent, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    Mechanical, physical and chemical manipulations on radioactive products must be carried out in properly ventilated enclosed places. The air extracted can only be discharged into the atmosphere after a correct filtration. The power of the ventilation systems is a function of the dimensions and purpose of the enclosure? The choice of types of filter is determined by the physical state and chemical nature of the radioactive materials to be manipulated. This study deals with the individual equipment of small installations: glove boxes, manipulation boxes with outside control and, if necessary, production chambers (maximum useful volume: 5 m{sup 3}). The performances of three types of 'ventilators', and the modifications provided by the addition of filters, are measured and compared. (author) [French] Les manipulations oceaniques, physiques et chimiques sur des produits radioactifs doivent s'effectuer dans des enceintes convenablement ventilees. L'air extrait ne peut etre rejete dans l'atmosphere qu'apres une filtration correcte. La puissance des installations de ventilation est fonction des dimensions de l'enceinte et de son utilisation. Le choix des types de filtres est determine par l'etat physique et la nature ehimique des corps radioactifs manipules. Notre etude porte sur l'equipement individuel d'installations de petites dimensions: boites a gants, boites a pinces et, a la rigueur, enceintes de production (volume maximum utilisable 5 m{sup 3}). Nous mesurons et comparons les performances de trois types de 'ventilateurs' et les modifications apportees par l'adjonction de filtres. (auteur)

  10. Python Introduction and Installation

    Directory of Open Access Journals (Sweden)

    William J. Turkel

    2012-07-01

    Full Text Available This first lesson in our section on dealing with Online Sources is designed to get you and your computer set up to start programming. We will focus on installing the relevant software – all free and reputable – and finally we will help you to get your toes wet with some simple programming that provides immediate results. In this opening module you will install the Python programming language, the Beautiful Soup HTML/XML parser, and a text editor. Screencaps provided here come from Komodo Edit, but you can use any text editor capable of working with Python. Here’s a list of other options: Python Editors. Once everything is installed, you will write your first programs, “Hello World” in Python and HTML.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-10-15

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

  12. Python Introduction and Installation

    OpenAIRE

    William J. Turkel; Adam Crymble

    2012-01-01

    This first lesson in our section on dealing with Online Sources is designed to get you and your computer set up to start programming. We will focus on installing the relevant software – all free and reputable – and finally we will help you to get your toes wet with some simple programming that provides immediate results. In this opening module you will install the Python programming language, the Beautiful Soup HTML/XML parser, and a text editor. Screencaps provided here come from Komodo ...

  13. Logistics of LEP installation

    International Nuclear Information System (INIS)

    Genier, C.; Capper, S.

    1988-01-01

    The size of the LEP project, coupled with the tight construction schedules, calls for organized planning, logistics, monitoring and control. This is being carried out at present using tools such as ORACLE the Relational Database Management System, running on a VAX cluster for data storage and transfer, micro-computers for on-site follow-up, and PC's running Professional ORACLE, DOS and XENIX linked to a communications network to receive data feedback concerning transport and handling means. Following over 2 years of installations, this paper presents the methods used for the logistics of installation and their results

  14. Electrical installations technology

    CERN Document Server

    Whitfield, J F

    1968-01-01

    Electrical Installations Technology covers the syllabus of the City and Guilds of London Institute course No. 51, the "Electricians B Certificate”. This book is composed of 15 chapters that deal with basic electrical science and electrical installations. The introductory chapters discuss the fundamentals and basic electrical principles, including the concept of mechanics, heat, magnetic fields, electric currents, power, and energy. These chapters also explore the atomic theory of electric current and the electric circuit, conductors, and insulators. The subsequent chapter focuses on the chemis

  15. Field installation and maintenance

    International Nuclear Information System (INIS)

    Prebble, R.E.

    1981-01-01

    The use of a neutron moisture meter for the determination of the water content of soil necessitates the installation of an access tube down which the probe can be lowered. Errors in neutron count rate will be introduced if water enters the air gap between a loose fitting tube and the soil. Errors may also be caused by changes in the soil structure resulting from the techniques for soil removal and from driving the access hole. Access tube materials and dimensions, methods of installation and maintenance of the site are discussed

  16. Contrôle des circuits auxiliaires des P.F.W. (arret machine 2004/2006)

    CERN Document Server

    Ottaviani, J

    2005-01-01

    Les PFW sont des nappes polaires installées sur les pôles des aimants du PS. Elles sont au nombre de 4 par unité d’aimant et constituées d’un circuit principal (dans lequel circule le courant désiré selon le cycle magnétique utilisé) et de circuits auxiliaires. Les circuits auxiliaires sont des enroulements de correction (boucles de tour et “pick-up” brasés sur les enroulements principaux). Pendant la variation du champ magnétique de l’aimant PS, on utilise des tensions induites dans ces circuits auxiliaires pour corriger les erreurs de champ dues aux pertes par courants de Foucault dans la chambre à vide. Chaque année, pendant l’arrêt machine, on vérifie si les caractéristiques des circuits auxiliaires correspondent aux normes (mesures des résistances des boucles de tours, résistances entre “pick-up” et isolation des circuits) afin de faire un suivi. Les 404 PFW sont ainsi vérifiées. Dans cette note, on ne relèvera que les PFW ayant des défauts (valeurs hors tolérances, ...

  17. Contrôle des Circuits Auxiliaires des P.F.W. (arrêt machine 2003/2004)

    CERN Document Server

    Ottaviani, J

    2004-01-01

    Les PFW sont des nappes polaires installées sur les pôles des aimants du PS. Elles sont au nombre de 4 par unité d'aimant et constituées d'un circuit principal (dans lequel circule le courant désiré selon le cycle magnétique utilisé) et des circuits auxiliaires. Les circuits auxiliaires sont des enroulements de correction (boucles de tour et "pick-up" brasés sur les enroulements principaux). Pendant la variation du champ magnétique del'aimant PS, on utilise des tensions induites dans ces circuits auxiliaires pour corriger les erreurs de champ dues aux pertes par courants de Foucault dans la chambre à vide. Chaque année, pendant l'arrêt machine, on vérifie si les caractéristiques des circuits auxiliaires correspondent aux normes (mesures de résistances des boucles de tours, résistances entre "pick-up" et isolation des circuits) afin de faire un suivi. Les 404 PFW sont ainsi vérifiées. Dans cette note, on ne relèvera que les PFW ayant des défauts (valeurs hors tolérances, boucles ouvertes ...

  18. Storing and evacuation of solid radioactive waste (1960); Stockage et evacuation des dechets radioactifs solides (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The object of this paper is to present the plans under consideration for the final destination of solid radioactive wastes. 1) It is first of all necessary to provide in each centre an organised temporary storage dump. Several types of temporary dumps are suitable and can coexist in the same area; on the ground, in buildings; in basements. 2) Definitive storage. To accomplish a definitive storage arrangement it is necessary, as a function of the activity and the conditioning of the wastes, to define: - the site and the means of transport considered both inside and outside nuclear centres. The solution adopted depends on the above imperatives, and plans for definitive storage on the ground, under ground and in the sea are examined successively. Economic considerations play a large part in the decision reached. (author) [French] La presente communication a pour objet les solutions envisagees pour une destination finale des dechets radioactifs solide. 1) Il est tout d'abord necessaire de prevoir, dans chaque centre, un stockage provisoire organise. Plusieurs types de stockage previsoire peuvent convenir et coexister sur une meme aire; stockage sur le sol; stockage en batiment; stockage en sous-sol. 2) Stockage definitif. La realisation d'un stockage definitif rend necessaire, en fonction de l'activite et du conditionnement des dechets, la definition: - du site et des modes de transports envisages a l'interieur et a l'exterieur des Centres Nucleaires. Le choix des solutions decoule des imperatifs ci-dessus et on examine successivement le stockage definitif, - sur le sol; dans le sous-sol; en mer. Les considerations d'ordre economique constituent un facteur important dans le choix de la solution. (auteur)

  19. Vers des chaînes d'approvisionnement durables et éthiques ...

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

    Les personnes les plus vulnérables ont tendance à être des travailleurs à domicile dépendants, et la majorité d'entre elles sont des femmes qui travaillent dans des installations externes, souvent à partir de leur propre foyer. En tant que « travailleurs à domicile », ces personnes sont moins susceptibles d'être reconnues en ...

  20. Report on the safety of wind turbines installations; Rapport sur la securite des installations eoliennes

    Energy Technology Data Exchange (ETDEWEB)

    Guillet, R.; Leteurtrois, J.P.

    2004-07-01

    This report aims to study the regulatory framework governing the safety of wind turbines and proposes improvement actions. It concerns the wind turbines risk assessment, the technical bases of the wind turbines safety, the regulation relative to the safety and possible evolutions. (A.L.B.)

  1. Installation of the ITER committee industry. Participants guide; Installation du Comite industrie ITER. Dossier des participants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    ITER is an international project to design and build an experimental fusion reactor based on the tokamak concept. This guide presents the ITER project and objectives and the associated organizations in France, the recommendations and actions for ITER, the industrial mobilization, the industrial committee and its members, technological sheets for the enterprises and the statistical document of the SESSI. (A.L.B.)

  2. Expertise concerning the request by the ZWILAG Intermediate Storage Wuerenlingen AG for delivery of the operation licence for the conditioning installation as well as for the burning and melting installation of the central intermediate storage facility for radioactive wastes in Wuerenlingen; Gutachten zum Gesuch der ZWILAG Zwischenlager Wuerenlingen AG um Erteilung der Betriebsbewilligung fuer die Konditionierungsanlage sowie fuer die Verbrennungs- und Schmelzanlage des Zentralen Zwischenlagers fuer radioaktive Abfaelle in Wuerenlingen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-08-15

    On December 15, 1997, the Central Intermediate Storage Facility for radioactive materials (ZWILAG) delivered a request to the Swiss Federal Council for an operational licence for the conditioning installation and the incineration and melting installation at the Central Intermediate Storage Facility (ZZL). For the whole project, the general licence was granted on June 23, 1993. The construction of the whole installation as well as the operation in the storage halls with reception, hot cell and transhipment station were licensed on August 12, 1999. The Federal Agency for the Safety of Nuclear Installations (HSK) examined the request documentation of ZWILAG from the point of view of nuclear safety and radiation protection. The results of the examination are contained in this report. In general, the examination leads to a positive decision. During the realisation process many project adaptations have brought improvements to the installation as far as radiation protection and the treatment of wastes are concerned. HSK requests from a former licensing process were taken into account by ZWILAG. The present examination contains many remarks and requests that the HSK considers necessary. The most important remarks are issued as special references as far as they do not appear as proposals in the licence obligations. In general, the reference form was chosen when the fulfilment of the request can be guarantied by HSK within the framework of a release process. Several references inform ZWILAG of problems for which HSK wishes to receive the results of extended inquiries or where HSK will assist in testing or demonstrations. Other references concern requests for plant documentation. Further, calculations of radioactive material release during normal operation is considered as being necessary. Based on its examination, HSK concludes that the conditions are fulfilled for the safe operation of the conditioning installation and of the incineration and melting installation as long as

  3. The study of neutron transport by oscillation method; Etude du transport des neutrons par la methode de modulation

    Energy Technology Data Exchange (ETDEWEB)

    Raievski, V

    1959-07-01

    The oscillation method is of very general use for studying the behavior of thermal neutrons in media. The main experiments are described and a general theory of them is given. This theory, which is presented in the first part, is established using the two-group approximation which has proved its efficiency in the case of thermal neutron piles. The validity of the two-group approximation is recalled. This allows definition of the meaning of the parameters used in the theory and which are measured in these experiments. The experiments carried out by this method are described, especially those performed at the Centre d'Etudes Nucleaires de Saclay where the method has been extensively used. These experiments are interpreted by means of the general theory given previously. In this way, the identity of parameters measured by this method and those given by the theory is proved. This is particularly conclusive is the case of the mean life of neutrons in a pile. (author) [French] La methode de modulation est un procede tres general d'etude des proprietes neutroniques des milieux contenant des neutrons thermiques. Le present rapport a pour but de decrire les principales de ces experiences et d'en donner une theorie generale. Cette theorie, exposee dans la premiere partie, est etablie dons le cadre de l'approximation a deux groupes de vitesse qui a prouve son efficacite dons le cas des piles a neutrons thermiques. Le domaine de validite de l'approximation a deux groupes est rappele au debut, ce qui permet de definir avec precision la signification des parametres qui entrent dons la theorie et qui font l'objet de ces mesures. La deuxieme partie decrit les experiences realisees, en particulier celles effectuees au Centre d'Etudes Nucleaires de Saclay ou la methode a ete considerablement developpee. Ces experiences sont interpretees dans le cadre de la theorie generale exposee precedemment. On prouve ainsi l'identite des parametres mesures par cette methode et de ceux figurant

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  5. Nuclear Installations Act 1969

    International Nuclear Information System (INIS)

    1969-01-01

    The purpose of this Act is to amend the Nuclear Installations Act 1965 to bring it into full compliance with the international conventions on nuclear third party liability to which the United Kingdom is a Signatory, namely, the Paris Convention, the Brussels Supplementary Convention and the Vienna Convention. (NEA) [fr

  6. Terre des hommes

    CERN Multimedia

    Staff Association

    2012-01-01

    Transformez votre téléphone portable en geste de solidarité ! Collecte du 12 au 23 novembre 2012   Faites un geste simple et utile en déposant vos téléphones portables inutilisés dans les urnes installées dans les trois restaurants du CERN. En Suisse, une personne change tous les 12 à 18 mois de téléphone portable. La plupart de nos vieux appareils sont simplement laissés à l’abandon avec comme seule fonction de parer une éventuelle panne à venir. On  estime ainsi que 8 millions de portables sont inutilisés, alors qu'entre 30 et 50% peuvent être réutilisés. L'action Solidarcomm leur offre une deuxième vie ! Terre des Hommes Suisse, dans le cadre de la campagne Solidarcomm, collecte et valorise vos téléphones inutilis&...

  7. Civili, langue des Baloango

    DEFF Research Database (Denmark)

    Mavoungou, Paul Achille; Ndinga-Koumba-Binza, Hugues Steve

    , Congo, Angola, etc.) issus de la décolonisation. Il présente de façon succincte quelques phénomènes historiques, phonologiques, morphosyntaxiques, homonymiques et analogiques de la langue. Des faits sémantiques des emprunts linguistiques y sont également décrits dans le cadre des changements...

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

    Energy Technology Data Exchange (ETDEWEB)

    Poggioli, Jean Renaud

    1984-03-02

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

  9. Report realized on behalf of the Foreign Affairs Commission, of Defense and Armed Forces on the law project allowing the agreement approbation between the French Republic Government and the Russian Federal Government relative to the civil liability concerning the nuclear damages occurring from goods supplying to nuclear facilities in Russian Federation and becoming from the French Republic; Rapport fait au nom de la commission des affaires etrangeres, de la defense et des forces armees sur le projet de loi autorisant l'approbation de l'accord entre le Gouvernement de la Republique francaise et le Gouvernement de la Federation de Russie relatif a la responsabilite civile au titre de dommages nucleaires du fait de fournitures en provenance de la Republique francaise destinees a des installations nucleaires en Federation de Russie

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The first part presents the international civil liability system in the nuclear domain and details then the 20 june 2000 agreement. It presents also the main aspects of the french-russian cooperation in the nuclear domain. (A.L.B.)

  10. installations involontaires : étude transnationale sur les inégalités ...

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

    installations involontaires : étude transnationale sur les inégalités et la pauvreté urbaines. Il se produit des déplacements involontaires de populations en milieu urbain lorsque des gens sont forcés de partir de chez eux, que ce soit à cause d'un projet de développement, d'un conflit ou d'une catastrophe naturelle.

  11. The latest electrical installation (I)

    International Nuclear Information System (INIS)

    Won, Jong Su

    1976-04-01

    This book deals with the latest electrical installation. The contents of this book are construction electrical installation, regulations related electrical installation, foundation and principle of wiring, main line feeder, lighting installation, power of wiring, main line feeder, lighting installation, power installation, method to read structure drawing for electrical construct drawing electric lamp wiring diagram, working drawing, material and tools and method of construction of electrical installation on types of wiring construction, metallic conduit, rigid poly-vinyl conduit wiring, bus duct work, cable work and insulation out of metal lathed.

  12. Des racines et des ailes

    Directory of Open Access Journals (Sweden)

    Stéphanie Vincent-Geslin

    2012-05-01

    Full Text Available Les mobilités pendulaires semblent être en augmentation en Europe depuis une dizaine d’années. Cette croissance du temps passé à se déplacer amène à remettre en question la conjecture de Zahavi et apparaît relativement inexplicable en regard du paradigme classique de l’acteur rationnel traditionnellement utilisé dans le champ des transports. Si, dans la littérature, les temps de déplacements sont principalement expliqués par le contexte résidentiel, la forme urbaine et le travail, ce cadre explicatif ne dit rien des processus de décision eux-mêmes qui amènent aux pendularités intensives.À partir d’une enquête qualitative menée auprès de pendulaires français, suisses et belges, cette contribution propose d’analyser les arbitrages et les éléments déterminants des processus de la grande pendularité. Les mobilités quotidiennes pendulaires apparaissent comme le résultat de compromis entre activité professionnelle, attachement résidentiel et choix de vie et prennent ainsi la forme de stratégies de conciliation entre vie privée et vie professionnelle. Ces mobilités spatiales permettent alors paradoxalement la préservation des ancrages résidentiels, sociaux et familiaux.Roots and wings. Long-distance commuting patterns, or how to conciliate professional and personal lifeLong-distance commuting patterns appear to be increasing in Europe over the last ten years. These raising mobility patterns lead to reappraise the Zahavi conjecture and appear largely inexplicable by the classical rational actor paradigm traditionally used in transportation research. In literature, commuting is mainly explained by residential contexts, urban forms and job. Nevertheless this theoretical frame says little about the decision-making processes themselves. Based on a qualitative survey conducted in three European countries - France, Belgium and Switzerland – among a population of high commuters, this paper proposes an analysis of

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    reacteurs en montrant ce qu'a ete jusqu'a present leur utilisation, et comment certaines modifications ont permis de les adapter a l'evolution des programmes. Ils precisent egalement les raisons qui ont conduit a l'elaboration du projet de la nouvelle pile OSIRIS, La pile ZOE, la plus ancienne du CEA, est en service au Centre de Fontenay-aux-Roses depuis 1948. Elle est principalement utilisee pour les mesures de section efficace d'absorption du graphite, et pour diverses irradiations de courte duree ne necessitant que des flux peu eleves. La Pile EL2, en service depuis 1952, a permis les premieres etudes liees au refroidissement par gaz. Elle a ete tres utilisee pour la production des radioisotopes et pour de nombreuses experiences de physique, de metallurgie et de physico-chimie - le vieillissement de certaines parties du reacteur a conduit a decider l'arret prochain de cette installation. La Pile EL. 3 a ete tres utilisee pour les experiences de physique et pour l'etude des combustibles. L'adoption d'une nouvelle structure pour le coeur (solution 'Cristal de neige') va permettre d'accroitre considerablement les possibilites de la pile pour les irradiations en neutrons rapides. La pile TRITON-I, piscine de 2 MW, est surtout utilisee pour les irradiations en neutrons rapides et en gamma. Certaines modifications, actuellement en cours, permettront d'accroitre la puissance du reacteur jusqu'a 4 ou 5 MW. Dans un compartiment voisin de TRITON-I est implantee la Pile TRITON-II, de meme structure generale, mais dont la puissance maximum est de 100 kW. TRITON-II est utilisee exclusivement pour les etudes de protections. MELUSINE, pile piscine de 2 MW est en fonctionnement au Centre d'Etudes Nucleaires de Grenoble depuis 1959. Elle a permis l'execution d'un programme important concernant surtout la physique du solide, l'etude fondamentale de combustibles refractaires et de graphites speciaux, et l'etude du comportement des liquides organiques sous radiations. Les installations de

  14. Industrial uses of radioelements in France; Utilisation industrielle des radioelements en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The birth of a nuclear industry has permitted the use of radioelements in an increasing number of domains. Currently, the majority of radioelements applications in industrial problematic are essentially on nondestructive control and on problems of static electricity, as well as in a least way for the use of the intense radiation sources, on agronomic problems, for hydrology or chemical analyses. In order to promote the industrial applications, The CEA took to this purpose several sets of decisions: 1 - institution of teachings and collaboration; 2 - encourage the constructors of devices; 3 - creation of a help service to the users. (M.B.) [French] La naissance d'une industrie nucleaire a permit l'emploi des radioelements dans un nombre croissant de domaines. Actuellement, la majorite des applications industrielles de radioelements porte essentielement sur le controle non destructif et les problemes d'electricite statique, ainsi que dans une moindre mesure l'utilisation des rayonnements intenses, les problemes agronomiques, les questions d'hydrologie, les analyses chimiques. Afin de promouvoir les applications industrielles, Le Commissariat a l'Energie Atomique a pris a cet effet plusieurs series de mesures: 1- institution d'enseignements et de collaboration; 2- encouragement aux constructeurs d'appareils; 3- creation d'un service de consultation aux usagers. (M.B.)

  15. BROOKHAVEN: RHIC installation

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    This summer, the first superconducting magnet was installed in 3.8 kilometre tunnel for Brookhaven's RHIC heavy ion collider (October, page 31). Manufactured by Northrop Grumman's Electronics and System Integration Division, the magnet is the first of RHIC's 373 dipoles. In addition to the dipoles, Northrop Grumman will also provide 432 RHIC quadrupoles. The first quadrupole was delivered on 8 April, a month before the first dipole arrived for onsite testing prior to installation. RHIC will need 1,700 superconducting magnets - dipoles, quadrupoles, sextupoles and correcting magnets, 1,200 of which will be built by industry and the rest built at Brookhaven. The 300 sextupoles are being supplied by Everson Electric

  16. Entropy and Digital Installation

    Directory of Open Access Journals (Sweden)

    Susan Ballard

    2005-01-01

    Full Text Available This paper examines entropy as a process which introduces ideas of distributed materiality to digital installation. Beginning from an analysis of entropy as both force and probability measure within information theory and it’s extension in Ruldof Arnheim’s text ‘Entropy and Art” it develops an argument for the positive rather thannegative forces of entropy. The paper centres on a discussion of two recent works by New Zealand artists Ronnie van Hout (“On the Run”, Wellington City Gallery, NZ, 2004 and Alex Monteith (“Invisible Cities”, Physics Room Contemporary Art Space, Christchurch, NZ, 2004. Ballard suggests that entropy, rather than being a hindrance to understanding or a random chaotic force, discloses a necessary and material politics of noise present in digital installation.

  17. Installation Strategic Planning Guidebook

    Science.gov (United States)

    2012-05-01

    Installation natural resource concerns (for example, wetlands , number of endangered species, water use restrictions, encroachment on training lands...Koehler Publishing, 1994 7. Strategy Safari – A Guided Tour Through the Wilds of Strategic Management by Henry Mintzberg, Bruce Ahlstrand, and...T. (1987). NY: Knopf 36. Shaping Strategic Planning: Frogs, Dragons, Bees and Turkey Tails. Pfeiffer, J. W., Goodstein, L. D. & Nolan, T. M. (1989

  18. Installing the ALICE detector

    CERN Multimedia

    Maximilien Brice

    2006-01-01

    The huge iron yoke in the cavern at Point 2 in the LHC tunnel is prepared for the installation of the ALICE experiment. The yoke is being reused from the previous L3 experiment that was located at the same point during the LEP project from 1989 to 2000. ALICE will be inserted piece by piece into the cradle where it will be used to study collisions between two beams of lead ions.

  19. SNRIU nuclear installation modifications

    International Nuclear Information System (INIS)

    Goroshanskyi, Andrii

    2013-01-01

    Design stages of Nuclear Instalations (NI): NI design is performed in three stages: • Feasibility study: - Feasibility study is developed on the basis of the customer task for production facilities and linear facilities engineering and transport infrastructure that require detailed study of relevant decisions and identify options for and feasibility of construction. • Design: - The design is developed on the basis of design task, initial data and approved the previous stage under three-stage design. • Detailed documentation

  20. Safety of nuclear installations

    International Nuclear Information System (INIS)

    1991-01-01

    In accordance with the Nuclear Energy Act, a Licence may only be issued if the precautions required by the state of the art have been taken to prevent damage resulting from the construction and operation of the installation. The maximum admissible body doses in the area around the installation which must be observed in planning constructional and other technical protective measures to counter accidents in or at a nuclear power station (accident planning values, are established). According to the Radiological Protection Ordinance the Licensing Authority can consider these precautions to have been taken if, in designing the installation against accidents, the applicant has assumed the accidents which, according to the Safety Criteria and Guidelines for Nuclear Power Stations published in the Federal Register by the Federal Minister of the Interior after hearing the competent senior state authorities, must determine the design of a nuclear power station. On the basis of previous experience from safety analysis, assessment and operation of nuclear power stations, the accident guidelines published here define which accidents are determinative for the safety-related design of PWR power stations and what verification -particularly with regard to compliance with the accident planning values of the Radiological Protection Ordinance -must be provided by the applicant. (author)

  1. First ALICE detectors installed!

    CERN Multimedia

    2006-01-01

    Detectors to track down penetrating muon particles are the first to be placed in their final position in the ALICE cavern. The Alice muon spectrometer: in the foreground the trigger chamber is positioned in front of the muon wall, with the dipole magnet in the background. After the impressive transport of its dipole magnet, ALICE has begun to fill the spectrometer with detectors. In mid-July, the ALICE muon spectrometer team achieved important milestones with the installation of the trigger and the tracking chambers of the muon spectrometer. They are the first detectors to be installed in their final position in the cavern. All of the eight half planes of the RPCs (resistive plate chambers) have been installed in their final position behind the muon filter. The role of the trigger detector is to select events containing a muon pair coming, for instance, from the decay of J/ or Y resonances. The selection is made on the transverse momentum of the two individual muons. The internal parts of the RPCs, made o...

  2. New recording methods and electromechanical analysis; Nouvelles methodes d'enregistrement et de depouillement electromecanique des numerations de particules

    Energy Technology Data Exchange (ETDEWEB)

    Meunier, R.; Bonpas, M.; Legrand, J.P. [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires

    1954-07-01

    The measurement that the most often occurs in nuclear physics are of the numerations of pulses representing the transit of a particle in a detector that can be a Geiger counter, a photomultiplier or a pulse chamber. We studied and constructed an electromagnetic recorder who permits to get automatically and without calculation: 1) the activity of a radioelement according to the time; 2) the curve of decrease of a radioelement and its period; 3) any curves of growth or decrease; 4) the activity, at any instant, of a neutron detector; 5) the neutron densities ratios in several points by the method of the detectors. (M.B.) [French] Les mesures qui se presentent le plus souvent en physique nucleaire sont des numerations d'impulsions representant le passage d'une particule dans un detecteur qui peut etre un compteur de Geiger, un photomultiplicateur ou une chambre a impulsions. Nous avons etudie et construit un enregistreur electromagnetique qui permet d'obtenir automatiquement et sans calcul: 1) l'activite d'un radioelement en fonction du temps; 2) la courbe de decroissance d'un radioelement et sa periode; 3) des courbes quelconques de croissance ou de decroissance; 4) l'activite, rapportee a un instant quelconque, d'un detecteur de neutrons; 5) les rapports des densites de neutrons en plusieurs points par la methode des detecteurs. (M.B.)

  3. New recording methods and electromechanical analysis; Nouvelles methodes d'enregistrement et de depouillement electromecanique des numerations de particules

    Energy Technology Data Exchange (ETDEWEB)

    Meunier, R; Bonpas, M; Legrand, J P [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires

    1954-07-01

    The measurement that the most often occurs in nuclear physics are of the numerations of pulses representing the transit of a particle in a detector that can be a Geiger counter, a photomultiplier or a pulse chamber. We studied and constructed an electromagnetic recorder who permits to get automatically and without calculation: 1) the activity of a radioelement according to the time; 2) the curve of decrease of a radioelement and its period; 3) any curves of growth or decrease; 4) the activity, at any instant, of a neutron detector; 5) the neutron densities ratios in several points by the method of the detectors. (M.B.) [French] Les mesures qui se presentent le plus souvent en physique nucleaire sont des numerations d'impulsions representant le passage d'une particule dans un detecteur qui peut etre un compteur de Geiger, un photomultiplicateur ou une chambre a impulsions. Nous avons etudie et construit un enregistreur electromagnetique qui permet d'obtenir automatiquement et sans calcul: 1) l'activite d'un radioelement en fonction du temps; 2) la courbe de decroissance d'un radioelement et sa periode; 3) des courbes quelconques de croissance ou de decroissance; 4) l'activite, rapportee a un instant quelconque, d'un detecteur de neutrons; 5) les rapports des densites de neutrons en plusieurs points par la methode des detecteurs. (M.B.)

  4. Samus Toroid Installation Fixture

    Energy Technology Data Exchange (ETDEWEB)

    Stredde, H.; /Fermilab

    1990-06-27

    The SAMUS (Small Angle Muon System) toroids have been designed and fabricated in the USSR and delivered to D0 ready for installation into the D0 detector. These toroids will be installed into the aperture of the EF's (End Toroids). The aperture in the EF's is 72-inch vertically and 66-inch horizontally. The Samus toroid is 70-inch vertically by 64-inch horizontally by 66-inch long and weighs approximately 38 tons. The Samus toroid has a 20-inch by 20-inch aperture in the center and it is through this aperture that the lift fixture must fit. The toroid must be 'threaded' through the EF aperture. Further, the Samus toroid coils are wound about the vertical portion of the aperture and thus limit the area where a lift fixture can make contact and not damage the coils. The fixture is designed to lift along a surface adjacent to the coils, but with clearance to the coil and with contact to the upper steel block of the toroid. The lift and installation will be done with the 50 ton crane at DO. The fixture was tested by lifting the Samus Toroid 2-inch off the floor and holding the weight for 10 minutes. Deflection was as predicted by the design calculations. Enclosed are sketches of the fixture and it relation to both Toroids (Samus and EF), along with hand calculations and an Finite Element Analysis. The PEA work was done by Kay Weber of the Accelerator Engineering Department.

  5. En eaux troubles : accentuation des pressions climatiques et ...

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

    informatique font partie des nombreuses grandes sociétés qui se sont installées dans cette ville tentaculaire. Or, les 10 millions d'habitants de Bengaluru, la multitude d'industries concurrentes, de même que les exploitations ...

  6. Nuclear reactor installation

    International Nuclear Information System (INIS)

    Keller, W.

    1976-01-01

    A nuclear reactor installation includes a pressurized-water coolant reactor vessel and a concrete biological shield surrounding this vessel. The shield forms a space between it and the vessel large enough to permit rapid escape of the pressurized-water coolant therefrom in the event the vessel ruptures. Struts extend radially between the vessel and shield for a distance permitting normal radial thermal movement of the vessel, while containing the vessel in the event it ruptures, the struts being interspaced from each other to permit rapid escape of the pressurized-water coolant from the space between the shield and the vessel

  7. Decommissioning nuclear installations

    International Nuclear Information System (INIS)

    Dadoumont, J.

    2010-01-01

    When a nuclear installation is