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Sample records for chinone

  1. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chinon nuclear power plant (Indre-et-Loire, 37 (FR)): 4 PWR reactors in operation (Chinon B, INB 107 and 132), 3 partially dismantled graphite-gas reactors (Chinon A, INB 133, 153 and 161), a workshop for irradiated materials (AMI, INB 94), and an inter-regional fuel storage facility (MIR, INB 99). 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 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  2. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chinon nuclear power plant (Indre-et-Loire, 37 (FR)): 4 PWR reactors in operation (Chinon B, INB 107 and 132), 3 partially dismantled graphite-gas reactors (Chinon A, INB 133, 153 and 161), a workshop for irradiated materials (AMI, INB 94), and an inter-regional fuel storage facility (MIR, INB 99). 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.)

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

    Directory of Open Access Journals (Sweden)

    Bruno Dufaÿ

    2006-05-01

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

  4. A robot-automated work site for repair of the Chinon A3 reactor

    International Nuclear Information System (INIS)

    Raynal, A.

    1987-01-01

    In 1982, following degradation due to corrosion of low-carbon steel by carbon dioxide gas, the utility undertook to repair some of the support structures at Chinon A3. This involved consolidation and reinforcing thermocouples and gas monitor pipeworks supports. A welding process was selected and the use of robots became indispensable because of the large number of components to be replaced (200 per outage). Two robots, supplied with tool heads and replacement components from outside the reactor were used. The robots and their servers were coordinated by a central computer and monitored by a closed circuit television system. Each repair operation was performed after ''training'' on a full-scale mockup of the top of the reactor reconstructed from telemetry of the real reactor dimensions. Since becoming operational in June 1986, the robots have accumulated over 20 000 hours of operation and seventy parts have been welded to the reactor. A 3D CAD system has been adapted to simulate the robots and analyse long trajectories in order to reduce robot learning time [fr

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

    International Nuclear Information System (INIS)

    2011-01-01

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

  6. The ISIS operation: Robotics repair work on the CHINON A3 natural uranium, carbon dioxide cooled, graphite moderated reactor

    International Nuclear Information System (INIS)

    Hilmoine, R.M.E.

    1989-01-01

    After describing the upper internal support structures of the CHINON A3 reactor, the problems resulting from their degradation due to corrosion and to the difficulties of the ISIS operation are presented here. The repair method is as follows: all tools and repair parts reach the working area by the feeding-pipes drilled through the 7 m thick concrete vessel surrounding the reactor core; the robots handle into the reactor, the tool heads and the repair parts which are automatically positioned and welded around the corroded structure, thus restoring the support of measurement devices. The parts are either linked together or to the existing structure by means of 2 studs of 12 mm in diameter. The different phases to sort out a problem are: in-core topography, reconforming of the full-scale mock-up with the repair area, learning on this mock-up and in-core repair. The technical specificities of the robots used are the following: they have an 11 meter long, 0.22 meter across telescopic mast with jointed arms reaching a radius of 2.7 m. Then the useful load is 70 daN and the repeatability 0.1 mm. Different tool heads can be handled by the robot: telemeter and laser reconstruction: it allows to locate the in core points and to materialize them on the mock-up by a laser crossed-beams locating technique; scouring: it cleans the corroded parts of the structures before welding; welding: it allows the parts handling and the carried studs welding; screwing; tensile test: carried out when the stud welds are defective. A high level computerized control system is organized around a central unit which calculates the displacements of robots and synchronises the actions of different tools by communicating with several local units. A 100,000 hour designing, a 200,000 hour building and assembling and a 450,000 hour operating on working area were necessary to repair 15 out of the 102 corroded structures by fitting and welding 205 repair parts. 10 figs

  7. The Chinon nuclear power plant, at the service of a safe, competitive and CO2-free power generation in the heart of the Centre region

    International Nuclear Information System (INIS)

    2010-01-01

    In less than 20 years, Electricite de France (EDF) has built up a competitive park of 58 nuclear power plants, with no equivalent elsewhere, which represents an installed power of 63.1 GW (85% of EDF's power generation). Inside this nuclear park, the national power generation centre of Chinon comprises 4 production units of 900 MW each (3600 MW as a whole). The facility generated 19.03 billion kWh in 2009, i.e. 4.8% of the French national power generation. This brochure presents the life of the power plant under various aspects: power generation, safety priority and culture, maintenance investments, respect of the environment, long-term fuel and wastes management, local economical involvement, transparency and public information, key figures and dates. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  10. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  11. Nuclear safety and radiation protection report of Chinon nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  12. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  13. Theoretical and experimental studies on bellows type expansion joints behaviour of Chinon 3 primary coolant system

    International Nuclear Information System (INIS)

    Vrillon, B.; Jeanpierre, F.; Copin, A.; Gregoire, J.P.

    1975-01-01

    The vibration study of the bellows was performed in two stages. A series of vibration tests was performed on a real bellow joint. By comparing the experimental results with calculations using the finite elements method for revolution shells it was possible to qualify the representation of the waves and reinforcement rings. The resonant frequencies and modes were calculated for the various joints under reactor conditions. According to the excitation sources considered, the amplitude of the displacements and stresses can be determined from these characteristic modes. The corrugations are protected internally from the aerodynamic effects of the gas flow by an inner sleeve welded to the primary piping upstream and free downstream. The annular space between this sleeve and the corrugations forms a resonant volume liable to be excited by flow-induced pressure fluctuations. It was possible to calculate the characteristic resonance frequencies and modes of this gas column (air at normal temperature and pressure). A full-scale mock-up test under conditions corresponding to the calculation hypotheses gave experimental proof of the calculation results. Owing to the good correlation between the results of these two studies an attempt was made to calculate the acoustical behaviour of these cavities for nominal running conditions (temperature and pressure) as a function of the known excitation sources. The results obtained from all these tests show that the use of bellows type expansion joints on a primary reactor circuit offers the same guarantees of reliability and resistance as any other circuit component under pressure, as long as the strains they undergo remain within the limits specified by the regulations and nuclear codifications

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

    International Nuclear Information System (INIS)

    Boussard, C.

    1991-01-01

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

  15. EDF's dismantling experience

    International Nuclear Information System (INIS)

    Mira, J.J.

    1993-01-01

    The dismantling policy at EDF, taking into account technical, economical and socio-political factors, is presented. The various current realizations are reviewed and their dismantling solution discussed: Chinon A2, Chinon A1, Marcoule G1, G2, G3, Brennilis (EL4). Several dismantling projects are also described (Chinon A3, St-Laurent A1-A2, Chooz A). The various dismantling operations are presented and scheduled

  16. 78 FR 69302 - National Oil and Hazardous Substances Pollution Contingency Plan; National Priorities List...

    Science.gov (United States)

    2013-11-19

    ... County Great Park will be home to a world-class Olympic-style sports village and entertainment center, a... included Agua Chinon Wash, Bee Canyon Wash, Borrego Canyon Wash, and Marshburn Channel. Three of these drainages (Agua Chinon Wash, Bee Canyon Wash, and Borrego Canyon Wash) were continuations of natural washes...

  17. Earthquake of Saint-Hilaire-de-Voust (Vendee) from February 12, 2018 (3h08 TU), Magnitude = 4,8 (Local Magnitude - CEA)

    International Nuclear Information System (INIS)

    Cushing, Edward; Provost, Ludmila

    2018-01-01

    A 3.9-4.0 magnitude superficial earthquake occurred at Saint-Hilaire-de-Voust (Vendee, France) on February 12, 2018 (3h08 TU). This brief note reviews, first, the historical and present day seismicity of the Armorican region, and then analyses the earthquake impact on the closest nuclear facilities (Pouzauges industrial irradiation facility, Chinon and Civaux NPPs)

  18. The 'relics of Joan of Arc'

    DEFF Research Database (Denmark)

    Charlier, P.; Poupon, J.; Eb, A.

    2010-01-01

    Archaeological remains can provide concrete cases, making it possible to develop, refine or validate medico-legal techniques. In the case of the so-called 'Joan of Arc's relics' (a group of bone and archaeological remains known as the 'Bottle of Chinon'), 14 specialists analysed the samples such ...

  19. Tables of formulae for calculating the mechanics of stacks in gas-graphite reactors; Formulaire pour le calcul de la mecanique des empilements des reacteurs graphite-gaz

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1968-07-01

    This collection of formulae only gives, for nuclear graphite stacks. The mechanical effects due to the strains, thermal or not, of steel structures supporting or surrounding graphite blocks. Equations have been established by mean of experiments made at Chinon with large pile models. Thus, it is possible to calculate displacement, strain and stress in the EDF type stacks of horizontal triangular block lattice. (authors) [French] Le domaine de ce formulaire est strictement limite aux effets mecaniques, pour les empilements, des deformations, thermiques ou autres, des structures metalliques de soutien (aire - support et corset). On propose un ensemble de relations qui ont ete etablies a la suite des essais de CHINON sur des maquettes de grande taille. Ces relations permettent le calcul des mouvements, des deformations et des contraintes dans les empilements du type EDF, a reseau horizontal triangulaire regulier. (auteurs)

  20. Tables of formulae for calculating the mechanics of stacks in gas-graphite reactors

    International Nuclear Information System (INIS)

    1968-01-01

    This collection of formulae only gives, for nuclear graphite stacks. The mechanical effects due to the strains, thermal or not, of steel structures supporting or surrounding graphite blocks. Equations have been established by mean of experiments made at Chinon with large pile models. Thus, it is possible to calculate displacement, strain and stress in the EDF type stacks of horizontal triangular block lattice. (authors) [fr

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

    International Nuclear Information System (INIS)

    Berthion, Y.

    1986-10-01

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

  2. Experience of steam generator tube examination in the hot laboratory of EDF: analysis of recent events concerning the secondary side

    International Nuclear Information System (INIS)

    Thebault, Y.; Bouvier, O. de; Boccanfuso, M.; Coquio, N.; Barbe, V.; Molinie, E.

    2011-01-01

    Until 2010, more than 60 steam generator (SG) tubes have been removed and analysed in the EDF hot laboratory of CEIDRE/Chinon. This article is particularly related to three recent events that lead to the extraction of several tubes dedicated to laboratory destructive examinations. The first event that constitutes a first occurrence on the EDF Park, concerns the detection of a circumferential crack on the external surface of a tube located at tube support plate elevation. After this observation, several tubes have been extracted from Bugey 3 and Fessenheim 2 nuclear power plants with steam generators equipped with 600 MA bundle. The other two events concern the consequences of chemical cleaning of the tube bundle steam generators. The examples chosen are from Cruas 4 et Chinon B2 units whose tubes were extracted following non destructive testing performed immediately after or at the completion of cycle following the chemical cleaning. In the case of Cruas 4, Eddy Current Testing (ET) were performed for requalification of steam Generators after chemical cleaning. They allowed the detection of an indication located at the bottom of tube for a large number of tubes; the ET signal was similar to that corresponding to 'deposit' corrosion. Moreover, inspections of Chinon-B2 SGs at the end of the operation cycle following the chemical cleaning, showed the presence of conductor deposits at the bottom of some tubes. The first part of this document presents the major results of laboratory examinations of the pulled tubes of Bugey 3 and Fessenheim 2 and their analysis. Hypothesis concerning damage mechanisms of the tubes are also proposed. The second part of the paper relates the results of the laboratory examinations of the pulled tubes of Cruas 4 and Chinon B 2 after chemical cleaning and their analysis. (authors)

  3. Attempt of application of prefabrication techniques to nuclear engineering

    International Nuclear Information System (INIS)

    Frangi, Roger

    1981-01-01

    Prefabrication can apply to nuclear civil engineering for the execution of complicated or tall shuttering or casing work, requiring shoring that one would wish to simplify or suppress. This technique saves on work hours and improves quality and safety. A few examples carried out on the Saint-Laurent-des-Eaux and Chinon power stations are given as well as that which will be undertaken on the Belleville power station [fr

  4. An example of the use of robotics in French nuclear power plants the ISIS robot

    International Nuclear Information System (INIS)

    Seguy, J.; Thirion, H.

    1988-01-01

    The authors report how Robotics in French nuclear power plants (NPP) is used to solve maintenance problems. One of the most typical example of the use of robotics in French NPP is the ISIS robot. The first generation of this robot has performed the repair of corroded upper internal structures in Chinon A3 gaz cooled reactor. Two robots of this type have successfully welded more than 200 repair parts in the core without major failure during more than 12,000 hours

  5. Induced draught circular cooling tower

    International Nuclear Information System (INIS)

    Blanquet, J.C.

    1980-01-01

    Induced draught atmospheric cooling towers are described, to wit those in which the circulation is by power fans. This technique with fans grouped together in the centre enables a single tower to be used and provides an excellent integration of the steam wreath into the atmosphere. This type of cooling tower has been chosen for fitting out two 900 MW units of the Chinon power station in France [fr

  6. PWR fuel monitoring: recent progress with hot cells' examination equipment

    International Nuclear Information System (INIS)

    Chenebault, P.

    1989-01-01

    The 'hot' laboratories set up by the French Atomic Energy Authority (CEA) in its nuclear research centers at Saclay and Grenoble, and by the French Electricity Board (EDF) on the Chinon nuclear power station site, are used for dismantling and examining fuel rod assemblies irradiated in PWRs. This article is limited to a description of a number of new or totally updated items of equipment in these laboratories. Nuclear industry companies are also participating in the development of new examination techniques. As an example, the use of wave-guides for remote transmission of signals in a radioactive environment is described. 2 figs

  7. The Use of Prestressed Concrete Vessels in the French Power Reactor Programme

    International Nuclear Information System (INIS)

    Conte, F.; Dambrine, C.; Gaussot, D.

    1963-01-01

    This paper deals with the use of pre-stressed concrete for the G2 and G3 reactors at Marcoule and for the EDF3 reactor now under construction at Chinon. The first two reactors have been operating at power since 1959 and 1960 respectively. Messrs. Conte and Dambrine discuss the problems that arose during construction of the vessels for G2 and G3 and also deal with the experience gained in operation - experience which suggests that they are extremely safe- Work on the EDF3 vessel, begun at Chinon in the second half of 1961, is still under way and should be finished towards the end of 1963. Mr. Gaussot discusses the reasons for choosing this type of vessel, the results of calculations and mock-up tests, and the problems presented by the construction itself. A number of studies have been devoted to the future prospects of prestressed concrete structures for reactors. It would seem that working pressures could be increased, if desired, and, in any case, that dimensions could be considerably enlarged, thus offering the chance of integral-type solutions. (author) [fr

  8. Systematic monitoring of atmosphere radioactivity on the main French nuclear sites in 1961; Surveillance systematique de la radioactivite de l'atmosphere sur les principaux sites nucleaires francais en 1961

    Energy Technology Data Exchange (ETDEWEB)

    Doury, A.

    1963-07-01

    After having indicated the different stations, departments and bodies involved in the monitoring of radioactivity for radiation protection purposes (notably CEA, EDF, National Navy for their establishments in Saclay, Le Bouchet, Grenoble, Marcoule, Cadarache, Cherbourg, Chinon, Antony) and briefly described how this network operates, this report presents the measurement program which comprises measurements of global instantaneous radioactivity at the vicinity of the ground, measurements of long life radioactivity, the identification and dosing of long life radio-elements, and additional measurements. It presents sampling and measurement methods for these different measurements performed on different forms of radioactive elements (airborne dusts, gas, gamma and cosmic ambient radiation, precipitations). Results are discussed and presented under tabular and graphical forms.

  9. The gamma-irradiation of cyclites. Pt. 1

    International Nuclear Information System (INIS)

    Bancher, E.; Washuettl, J.; Schmidt, B.; Riederer, P.; Wurst, F.

    1975-01-01

    The investigation of radiolysis of irradiated cyclites in various foods is seriously hindered by the lack of data on the radiation chemistry of the chemical pure substances. Because of this reason basis investigations were carried out in aqueous solutions using various isomers and derivates of hexahydroxycyclohexane. For the qualitative and quantitative analysis of the radiolytic products thin layer chromatography was selected. With different TLC-methods the Rsub(f)-values of myo-inosite, myo-inosose (2), (I) epi-inosose, tetrahydroxy-p-chinon. d,1-myo-inosose-2-phenylosazon, d,1-xylo-4,5,6-trihydroxy-2-oxo-1.3 bis,phenylhydrazono-cyclohexan were qualitative determined. (T.G.)

  10. A.C.R.O. activity report 2006

    International Nuclear Information System (INIS)

    2006-01-01

    This association participated in different working groups: North Cotentin radioecology group, groups of expertise on the uranium mines of Limousin, executive committee for the management of the post accidental phase of a nuclear accident or a radiological emergency situation, radioactive waste management, radiological surveillance of the territory, radiation protection mission by the Asn, radiological surveillance of the environment of the Chinon nuclear power plant, study of the presence of 235 U around the site of Brennilis, study of the radioactive waste management at the Manche plant, radiological surveillance of the Cyceron cyclotron at Caen, Aurengo commission on the consequences in France of the Chernobylsk accident. Actions of information, regular publications, meeting with public are also a part of the work of this association. (N.C.)

  11. The Citizen Observatory of Radioactivity - Assessment of results - Measurement of gamma emitters. Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    This document proposes a set of tables containing different information and data regarding measurements of gamma radioactivity made during the first and second half-year of 2009 in different marine and water environments (algae, sands, sea water, molluscs, sediments, water mosses, vegetal) in different locations: a bay close to the AREVA plant in La Hague, different locations on the Normandy coast, around the AREVA plant in La Hague, waterways in Normandy and in other river near the Chinon and Civaux nuclear power stations. These tables contain information about the sampling (date, location, quantity, analysed fraction, and so on) and results of measurements of artificial (isotopes of cobalt, ruthenium-rhodium, silver, iodine, caesium, americium, europium) and natural (potassium, beryllium, lead, bismuth, etc.) radionuclides

  12. Assessment of the radiological inventory of EDF's graphite waste through an assimilation method

    International Nuclear Information System (INIS)

    Poncet, B.

    2014-01-01

    The definitive disposal of graphite from the decommissioned UNGG reactors (Chinon A3, Saint-Laurent A1, Saint-Laurent A2 and Bugey 1) has required a radiological inventory of the irradiated graphite. This study focuses on Cl 36 that is produced by neutron absorption on Cl 35 that was present initially in graphite as an impurity (about 80 mg/t of Cl initially in Bugey 1 graphite)). It appears that the changes of Cl 36 concentration along the height of a stack of graphite do neither fit the changes in the neutron flux nor the changes in the graphite temperature. This fact is explained by the high level of purity of the graphite and the nugget effect. Challenged by the absence of spatial correlation of the Cl 36 concentration, an EDF's team has developed an assimilation method based on comparisons between calculations and measurements in order to get a conservative inventory. (A.C.)

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

    Directory of Open Access Journals (Sweden)

    Alexis Sierra

    2010-05-01

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

  14. A.C.R.O. activity report 2006; A.C.R.O. rapport d'activite 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This association participated in different working groups: North Cotentin radioecology group, groups of expertise on the uranium mines of Limousin, executive committee for the management of the post accidental phase of a nuclear accident or a radiological emergency situation, radioactive waste management, radiological surveillance of the territory, radiation protection mission by the Asn, radiological surveillance of the environment of the Chinon nuclear power plant, study of the presence of {sup 235}U around the site of Brennilis, study of the radioactive waste management at the Manche plant, radiological surveillance of the Cyceron cyclotron at Caen, Aurengo commission on the consequences in France of the Chernobylsk accident. Actions of information, regular publications, meeting with public are also a part of the work of this association. (N.C.)

  15. Presentation of the GIE INTRA Group's operational means

    International Nuclear Information System (INIS)

    Cochard, A.

    2010-01-01

    Located on the Chinon nuclear power plant site, the Intra Group is an economic interest grouping which has been created by the three French nuclear operators (EDF, CEA, and COGEMA now AREVA) after the Chernobyl accident. Its missions are to possess permanently available means of intervention in case of severe accident or radiological situation, to be able to intervene at any time on the French territory, to develop a European network of expertise, and to build up an ability centre for robotic intervention in hostile environment. This document briefly presents its different available means: remotely controlled equipment (inside and outside equipment, public works equipment), and radiological characterization equipment. Other aspects are briefly evoked: organization, information transmission, exercises and interventions, international relationships, future trends

  16. The Isis operation: working in nuclear environment

    International Nuclear Information System (INIS)

    Hilmoine, R.

    1987-01-01

    After describing the upper internal support structures of the Chinon A3 reactor, difficulties of ISIS operation are presented. The different phases to sort out the problem are: in-core topography, conforming the full-scale mock-up to the repair area, learning on this mock-up and in-core reparation. Robots have a telescopic mast 11 m long, 0.22 m in diameter, completed by jointed arms reaching a radius of 2.7 m. The load carrying capacity is then 70 daN and the repeatability is 0.1 mm. Several tool heads are handled by the robot: telemeter and reconstruction, scouring, welding, screwing. A high level computerized control system is organized around central unit monitoring several local units. It allows automatic or semi-automatic working modes. Our experience in operation and possible improvements are described [fr

  17. ALARA and planning of interventions

    Energy Technology Data Exchange (ETDEWEB)

    Rocaboy, A. [Electricite de France, Avoine (France)

    1995-03-01

    The implementation of ALARA programs implies integration of radiation protection criterion at all stages of outage management. Within the framework of its ALARA policy, Electricide de France (EDF) has given an incentive to all of its nuclear power plants to develop {open_quotes}good practices{close_quotes} in this domain, and to exchange their experience by the way of a national feed back file. Among the developments in the field of outage organization, some plants have focused on the planning stage of activities because of its influence on the radiological conditions of interventions and on the good succession of tasks within the radiological controlled areas. This paper presents the experience of Chinon nuclear power plant. At Chinon, we are pursuing this goal through careful outage planning. We want the ALARA program during outages to be part of the overall maintenance task planning. This planning includes the provision of the availability of every safety-related component, and of the variations of water levels in hthereactor and steam generators to take advantage of the shield created by the water. We have developed a computerized data base with the exact position of all the components in the reactor building in order to avoid unnecessary interactions between different tasks performed in the same room. A common language between Operation and Maintenance had been established over the past years, using {open_quotes}Milestones and Corridors{close_quotes}. A real time dose rate counting system enables the Radiation Protection (RP) Department to do an accurate and efficient follow up during the outage for all the {open_quotes}ALARA{close_quotes} maintenance tasks.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  19. EDF decommissioning programme a global commitment to safety, environment and cost efficiency of nuclear energy

    International Nuclear Information System (INIS)

    Grenouillet, J.-J.

    2002-01-01

    EDF has 9 NPPs permanently shutdown and under decommissioning. EDF considers that if the nuclear option is to remain open, it is necessary to deal with increasing public concerns for environmental and waste management issues. Therefore EDF has decided to achieve total dismantling of all shutdown reactor in the next 25 years. The Decommissioning Program has been developed including 2 stages of activities. The first stage consists of: 1) Final dismantling of Brennilis in 2015; 2) A dismantling demonstration of a PWR reactor building (Chooz A) before starting replacing the population of PWRs currently in operation; 3) Final dismantling of reactor containment of a GCR (Bugey 1) as a first of its kind. The second stage includes: 1)Dismantling of following 5 GCR (Saint Laurent A1 and A2, Chinon A1, A2 and A3); 2) Final dismantling of Chooz A and Bugey 1 in 2025. The successful implementation relies on the simplification of the regulatory process; availability of treatment, conditioning and disposal facilities and effective nuclear industry. The main issue is availability of time and waste solutions such as opening of a Very Low Waste disposal in 2003 (130 000 tons); opening of a new disposal for graphite and radiferous wastes (17 000 tons) in 2010 and opening in 2007-2008 of a centralized interim storage (BANEDA) facility for long-lived Medium Level Wastes (500 tons including filters, control rods etc)Three investigations are to be carried out for high level radioactive waste before 2006

  20. Fiscal 1992 R and D project for next generation infrastructure technology. Report on results of R and D on photo-reactive material; 1992 nendo hikari hanno zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-03-01

    R and D was conducted with the purpose of establishing fundamental technologies concerning photo-reactive materials, which control molecular structures or polymerization through light beam behavior and which can be used for ultra-high density optical recording, high resolution display, optical switch, etc., with the fiscal 1992 results summarized. In the studies on photochromic materials, investigation was carried out on the possibility of 10 multiple recording and the fundamental features of aggregate forming photochromic compounds. In the studies on high temperature of photochemical hole burning (PHB) materials, a material was synthesized using ionic porphyrin derivatives as guest material and deuterated polyvinyl alcohol (PVA) and the like as host, with the evaluation made on the performance of multiple hole formation and storage. In addition, comparisons were made for example on the thermal properties of the PHB materials among the participating enterprises mutually. In the development of chinone PHB materials and research on the improvement of the multiplicity, as this being the final year, researches were done on such subjects as integration of element technologies, material evaluation technology and PHB-related studies, correlatively as the work of the final year. Research results were also reported on the development and systematizing technology of porphyrin-based PHB materials. (NEDO)

  1. French experience with electropolishing

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  2. Pulverulent deposits on fuel assemblies in primary circuit on 2 units at EDF (France)

    International Nuclear Information System (INIS)

    Zatla, A.; Piana, O.

    2015-01-01

    In march 2013, during the moving of some fuel assemblies in the fuel deactivation pool of two units nuclear power plants (Blayais 4 and Chinon B2 units), some fine and powdery deposits in suspension have been observed. In the two cases, the fuel has stayed in the deactivation pool during a long time (12 and 3 months), the units have started for the first time to inject Zinc in the primary circuit in the beginning of the precedent fuel cycle, and the units have operated an extended fuel cycle. EDF has performed analysis to evaluate the harmfulness of the particles and to investigate the mechanisms involved in this phenomenon. 3 conclusions can be drawn. First, the deposits are made up of usual corrosion products issued from the primary circuit components. Secondly, the chemical composition and the powdery characteristics of the deposits exclude nuclear safety risks. Thirdly, the atypical behaviour of the deposits could probably be linked with a modification of their structure due to a zinc effect. Because of the lack of new understanding elements, the extension of zinc injection to other NPP units has been broken off currently in France. EDF is studying the international experience feedback to identify the operating parameters of the nuclear power plant which might influent the phenomenon, and to evaluate if the deposits could enhance fuel cladding corrosion

  3. Examination of the SG tube fatigue cracking at Fessenheim unit no.2 of EDF

    International Nuclear Information System (INIS)

    Boccanfuso, M.; Lorthios, J.; Thebault, Y.; Bruyere, B.; Duisabeau, L.; Herms, E.

    2015-01-01

    In February 2008, a primary-to-secondary leak occurred at Fessenheim Unit No.2 on a steam generator. A circumferential fatigue crack was observed at the upper tube support plate level of the R12C62 tube although the stability ratio evaluation performed to take into account some prior international events, concluded that this tube had no risk of fluid-elastic instability. A new tube pull process was developed and performed by AREVA in 2011 just before the SG replacement. The extraction at the uppermost TSP elevation was a first occurrence in the French EDF PWR. Destructive examinations were carried out in the EDF hot laboratory of CEIDRE/Chinon in order to characterize damage mechanisms at the initiation and propagation stage. The document relates the major results of laboratory examinations leading us to exclude the fluid-elastic instability scenario as previously reported in North-Anna (1987) and Mihama (1991) tube rupture incidents. Results analysis with particular focus on the fracture surface description using Scanning Electron microscopy observations and metallurgical investigations provide new elements concerning the aggravating factors of fatigue damage. Fracture surface investigations reveal that the circumferential crack was due to high cycle fatigue with a very low stress intensity factor. Some aggravating factors like intergranular corrosion appeared to be critical for the fatigue cracking initiation stage. The deterioration was also largely promoted by the lack of tube support at the Anti-Vibration Bars

  4. PWSCC of steam generator divider plates in alloy 600: coupling field characterizations with R-D studies

    International Nuclear Information System (INIS)

    Couvant, T.; Vaillant, F.; Miloudi, S.; Deforge, D.; Thebault, Y.

    2011-01-01

    Some IGSCC (Intergranular Stress Corrosion Cracks) indications have been observed at the cold work surface of the hot side (325 C) of some divider plates of steam generators (SG) since 2002. Based on many in-service inspection campaigns (about 100 SG inspections), no evidence of propagation following the first detection has never been observed. In this context, crack propagation tests were carried out in EDF in order to evaluate the susceptibility to SCC of warm rolled plates made of Alloy 600 as a function of the degree of cold work. Some results recently obtained in the EDF Hot Laboratories on the decommissioned SG1 of Chinon B1 were coupled with calibrated crack propagation laws on cold worked materials. Results enlightened the restricted susceptibility to observe a significant crack depth over the steam generator lifetime. Along the most probable crack growth path, the maximal crack growth rate (CGR) was lower than 300 μm.cycle -1 and the CGR did not exceed 260 μm.cycle -1 as soon as the local plastic deformation was lower than 0.07. A laboratory SCC test on a specimen with a superficial cold worked layer confirmed the good resistance to SCC when the local plastic strain was lower than 0.07, in good agreement with the field experience. (authors)

  5. Foodstuff monitoring. To protect the consumer

    International Nuclear Information System (INIS)

    2013-01-01

    A set of articles describes the activities of the IRSN in the field of foodstuff monitoring about nuclear plants, in order to assess the exposure of population by food. Simulation codes have been developed to model the deposit of radionuclides on grass and their transfer to cows and milk, but also to local vegetable productions. In case of accidental release, it would be possible to forbid the consumption of some products. The IRSN performs a continuous monitoring of the environment at the local, regional and national levels. For each of these levels, a sampling plan is defined in terms of sampling location and frequency. These controls are different according to the region. The radiological quality of water is monitored and several actors are involved in this process (regional and national agencies, producers and distributors, laboratories). The case of the region of Chinon is more particularly addressed. Local production and consumption habits are studied for a better assessment of their health impact. Some projects are finally evoked: inclusion of children in food-habit survey, investigations in different regions, analysis of bottled waters, widening of the area for the study of post-accidental consequences

  6. Ultrasonic measurement of high burn-up fuel elastic properties

    International Nuclear Information System (INIS)

    Laux, D.; Despaux, G.; Augereau, F.; Attal, J.; Gatt, J.; Basini, V.

    2006-01-01

    The ultrasonic method developed for the evaluation of high burn-up fuel elastic properties is presented hereafter. The objective of the method is to provide data for fuel thermo-mechanical calculation codes in order to improve industrial nuclear fuel and materials or to design new reactor components. The need for data is especially crucial for high burn-up fuel modelling for which the fuel mechanical properties are essential and for which a wide range of experiments in MTR reactors and high burn-up commercial reactor fuel examinations have been included in programmes worldwide. To contribute to the acquisition of this knowledge the LAIN activity is developing in two directions. First one is development of an ultrasonic focused technique adapted to active materials study. This technique was used few years ago in the EdF laboratory in Chinon to assess the ageing of materials under irradiation. It is now used in a hot cell at ITU Karlsruhe to determine the elastic moduli of high burnup fuels from 0 to 110 GWd/tU. Some of this work is presented here. The second on going programme is related to the qualification of acoustic sensors in nuclear environments, which is of a great interest for all the methods, which work, in a hostile nuclear environment

  7. Dismantling of nuclear facilities: the industrial know-how

    International Nuclear Information System (INIS)

    Lellament, R.

    2004-01-01

    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.)

  8. 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.)

  9. Lessons learned from tubes pulled from French steam generators

    International Nuclear Information System (INIS)

    Berge, Ph.; Boursier, J.M.; Dallery, D.; De Keroulas, F.; Rouillon, Y.

    1998-01-01

    Since 1981, the Chinon Hot Laboratory has completed more than 380 metallurgical examinations of pulled French steam generator tubes. Electricite de France decided to perform such investigations from the very outset of the French nuclear program, in order to contribute to nuclear power plant safety. The main reasons for withdrawing tubes are to evaluate the degradation, to validate non destructive examination (NDE) techniques, to gain a better understanding of cracking phenomena, and to ensure that the criteria on which plugging operations are based remain conservative. Considerable experience has been accumulated in the field of primary water stress corrosion cracking (PWSCC), OD (secondary) side corrosion, leak and burst tests, and various tube plugging techniques. This paper focuses on the PWSCC phenomenon and on the secondary side corrosion process, and in particular, attempts to correlate French data from pulled tubes with the results of fundamental R and D studies. Finally, within the framework of the Nuclear Power Plant Safety and Maintenance Policy, all these results are discussed in terms of optimization of the field inspection of tube bundles and plugging criteria. (author)

  10. 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

  11. A.C.R.O. activity report 2001

    International Nuclear Information System (INIS)

    2001-01-01

    As regards the environmental protection, the A.C.R.O. maintained in 2001 its programs of surveillance around the main western nuclear installations of France. The radioecological surveillance of the site of Cogema La-Hague for the dismantling of the former pipe of release in sea was one of the key points of this action environmental surveillance. The two accidents of atmospheric release in may and october 2001 at Cogema La Hague have shown the interest of an association as A.C.R.O.. It is thank to the measure, by our laboratory, of repercussions on environment of these incidents that it has been possible to bring to light a dysfunction of the measurement system of the gaseous effluents released by the facility operator. To improve the public information, A.C.R.O. concerns its main efforts on the development of the consumer technical information available on-line via its web site and in its regular publication 'the nuclear chronicle'. Besides, the participation of the A.C.R.O. to the radioecology North Cotentin group (within the framework of the continuation of its mission) but also at various local commissions of information (C.L.I.) as well as at the superior council of the safety and nuclear information ( C.S.S.I.N.) stays an essential action. Concerning the environmental protection, the A.C.R.O. maintains its programs of surveillance around the nuclear facilities of La Hague and Chinon and continues the surveillance of the site of Cogema La hague as regards the new pipe of release in sea. Among the new commitments for 2000, the participation to the radioecology North Cotentin group in the framework of the continuation of its mission and the participation to the international intercomparison 'N.O.R.C.O. 2000' punctuated the year. (N.C.)

  12. Learning from EDF investigations on SG divider plates and vessel head nozzles. Evidence of prior deformation effect on stress corrosion cracking

    International Nuclear Information System (INIS)

    Deforge, D.; Duisabeau, L.; Miloudi, S.; Thebault, Y.; Couvant, T.; Vaillant, F.; Lemaire, E.

    2011-01-01

    Nickel Based alloys Stress Corrosion Cracking (SCC) has been a major concern for all the Nuclear Power Plants (NPP) utilities since the beginning of the seventies. At EDF, the nineties were marked by the occurrence of cracks on vessel head nozzles. These cracks were responsible for a leak at Bugey 3 vessel head, which was the precursor leading to the replacement of all vessel heads. From 2002, new cases of Stress Corrosion Cracking were reported on Steam Generator (SG) Divider Plates (SGDP) welded junctions. These cracks are periodically inspected inservice and reparations could be performed in case of a significant evolution of the phenomenon even if the safety issue is less relevant than for the vessel head nozzles. Both issues have led to an important non-destructive testing (NDT) program and to destructive investigations campaigns. NDT were performed on an exhaustive basis for all vessel head nozzles and for all the divider plates of 900 MWe plants. Destructive investigations were performed on more than 30 vessel head nozzles and on 6 divider plates. The last investigations were performed on samples from two decommissioned Steam Generators of Chinon B1 which present SCC cracks. In this paper, the main conclusions driven from the analysis of both NDT and destructive investigation results are reported and a comparison of the behaviours of divider plates and vessel head nozzles is given. Results give evidence that prior plastic deformation of the components before operation is fundamental for the further environmental behaviour of the material. Analysis of field experience based on parameters characteristics of prior deformation and parameters characteristics of material microstructure can be used to account for the components which are the most sensitive to SCC cracking. Some perspectives on SCC predictive models are also presented. (authors)

  13. Food surveys for assessing chemical and dosimetric impacts near industrial sites

    International Nuclear Information System (INIS)

    Parache, V.; Maurau, S.; Mercat, C.

    2011-01-01

    Estimating the ingestion of potentially contaminated foodstuffs around conventional and nuclear industrial sites requires data about the food practices and eating habits of the local residents, especially the consumption of locally- and home-produced food. The IRSN thus chose to conduct surveys about these practices in the vicinity of nuclear sites. Their methodology was based on previous surveys near nuclear sites. In 2004, in partnership with AREVA and BEGEAT, the French Institute for Radioprotection and Nuclear Safety studied the eating habits of the residents of Bollene, near the Tricastin plant (Rhone Valley), with the aim of improving the quantification of the plant's potential health impacts. Based on these studies and as part of the SENSIB project to characterize vulnerability to nuclear risks, we developed and tested a survey protocol during the summer 2008, around the Chinon nuclear plant, in collaboration with EDF. The protocol is currently being tested around the Marcoule nuclear plant, in collaboration with the CEA. The aim was to optimize the feasibility and the reproducibility of the approach, while losing none of the robustness of the results. The data obtained made it possible to evaluate daily food intake values for individuals and to assess the rates of consumption of locally-grown products for many food categories. The data showed the existence of local population groups with very high rates of locally-grown food consumption - over 90 % of certain food products. This comparative study thus shows the significant variability of eating habits in the French population and proposes a reproducible approach to evaluating realistic indicators of potentially risky dietary habits. (authors)

  14. Food surveys for assessing chemical and dosimetric impacts near industrial sites; Enquetes alimentaires pour l'evaluation des impacts chimiques et dosimetriques a proximite de sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Parache, V.; Maurau, S.; Mercat, C.

    2011-03-15

    Estimating the ingestion of potentially contaminated foodstuffs around conventional and nuclear industrial sites requires data about the food practices and eating habits of the local residents, especially the consumption of locally- and home-produced food. The IRSN thus chose to conduct surveys about these practices in the vicinity of nuclear sites. Their methodology was based on previous surveys near nuclear sites. In 2004, in partnership with AREVA and BEGEAT, the French Institute for Radioprotection and Nuclear Safety studied the eating habits of the residents of Bollene, near the Tricastin plant (Rhone Valley), with the aim of improving the quantification of the plant's potential health impacts. Based on these studies and as part of the SENSIB project to characterize vulnerability to nuclear risks, we developed and tested a survey protocol during the summer 2008, around the Chinon nuclear plant, in collaboration with EDF. The protocol is currently being tested around the Marcoule nuclear plant, in collaboration with the CEA. The aim was to optimize the feasibility and the reproducibility of the approach, while losing none of the robustness of the results. The data obtained made it possible to evaluate daily food intake values for individuals and to assess the rates of consumption of locally-grown products for many food categories. The data showed the existence of local population groups with very high rates of locally-grown food consumption - over 90 % of certain food products. This comparative study thus shows the significant variability of eating habits in the French population and proposes a reproducible approach to evaluating realistic indicators of potentially risky dietary habits. (authors)

  15. The safety approach in the operation of EDF power plants

    International Nuclear Information System (INIS)

    Bertron, L.; Mira, J.J.

    1988-01-01

    To get a view on what is involved in maintaining a high level of safety in the operation of EdF nuclear power plants, it may be recalled that in 1987, 76 % of the EdF production was nuclear. The nuclear plants include thirty-four standard PWR 900 plants, fourteen PWR 1300 plants, the 305 MW SENA PWR, the four 500 MW GCR: CHINON A3 plant, St-LAURENT A1 (390 MW), A2 (450 MW) and BUGEY 1 (540 MW), the 233 MW PHENIX fast breeder reactor and the CREYS-MALVILLE 1200 MW fast breeder reactor, now being prepared for a new startup after the 1987 incident. So the importance of a safe operation of this investment is considerable for EdF, which is the designer, owner, industrial architect and operator. According to the French regulations, EdF is responsible for the safe operation of its power plants. A considerable human component is also at stake, as the safe operation of plants implies all the personnel to varying degrees. There are 15,000 such employees, all of whom have to be trained, competent and motivated. The operation of this system for 340 reactor-years has to-date resulted in no incident of any significant impact on the environment. Right from the start, safety in operation has always been an essential and clearly stated priority. Among other lessons the Three-Mile Island and Chernobyl accidents have reinforced the conviction that the human factors, the man-machine interface, and the safety culture were determining elements. With forty-eigh PWR plants in service, the problem is to maintain safe operation of a system now running at cruising speed, but also including some units (particularly the GCRs) that must be prepared for decommissioning. In addition EDF has to demonstrate the safe operations of CREYS MALVILLE, fast breeder reactor

  16. Thimble vibration analysis and monitoring on 1300 and 900 MW reactors using accelerometers and in core neutron noise

    International Nuclear Information System (INIS)

    Trenty, A.; Puyal, C.; Vincent, C.; Baeyens, R.; Messainguiral-Bruynooghe, C.; Lagarde, G.

    1988-01-01

    The axial flow along the thimbles of the in core instrumentation induces vibration and shocks against their guides in the vessel, producing wear and even leakage, either on the thimbles, or on the instrumentation tube of the fuel assemblies. In order to characterize the phenomenon and help to reduce or suppress vibration of the thimbles, two methods have been developed and applied to French and Belgian reactors. The first one consists of an analysis of the shocks perceived on the thimbles tubes by accelerometers; this analysis, based on the study of statistical distribution (amplitude, impulse rate of shocks...) has allowed to choose among the different solutions proposed to solve the problem; this choice has been confirmed by direct wear measurements made later. The second method is based on spectral and time analysis of the fluctuating signals from in core neutron chambers. The correlation appears clearly between shocks and fluctuations. An estimation of the thimble model shape in the instrumentation tube of the assembly, has been made. These two analysis methods have been widely applied during start-up of the first eight 1300 MW reactors: they have contributed to solve the problem and to increase the availability of these plants. On the 900 MW reactors, where the problem is less severe, the approach has been to study the mechanical behaviour of one new plant, Chinon B3: all in core guide tubes have been equipped with accelerometers and an on line monitoring system directly transmits to Chatou the parameters of shocks, in order to define an acoustic parameter able to characterize wear, and so, to define a new type of maintenance for the thimbles. The first results are presented. (author)

  17. The annual report for 1985

    International Nuclear Information System (INIS)

    1986-07-01

    Nuclear power: 1. The total installed nuclear power-generating capacity in the world increased by 13.77% during 1985, reaching 250 GW(e) by the end of the year. Nuclear power plants accounted for 15% of the world's electricity generation in 1985, at the end of which there were 374 nuclear power plants in operation; 32 new plants came on line during the year. 2. There was still no general upturn in the ordering of nuclear power plants, and construction work started on only six new plants. However, vigorous nuclear power programmes continued in a number of Member States - notably France, Japan and the East European Member States belonging to CMEA. At the same time, five developing countries (China, Egypt, the Republic of Korea, Turkey and Yugoslavia) issued bid invitations or were negotiating contracts for nuclear power plants. Two new plants came on line in developing countries, one in India and one in the Republic of Korea. 3. Last year was the first year since 1973 without any cancellations of nuclear power plant orders or suspensions of plant construction. 4. Three nuclear power plants (El-4 and Chinon-A2 in France and VAK Kahl in the Federal Republic of Germany) were permanently shut down at what was judged to be the end of their economically useful lifetimes. 5. In contrast with the uncertainties about the current nuclear power programmes in some countries, the development of advanced nuclear systems was highlighted in 1985 by three major events: by the start-up of the 1200 MW(e) Super Phenix in France; by the start-up of the THTR-300 prototype high-temperature reactor in the Federal Republic of Germany; and by the start-up of India's fast breeder test reactor. 6. The Agency's efforts to help strengthen nuclear power planning in developing Member States continued, through advisory missions, training courses and guidebooks. Issues relating to the financing of nuclear power programmes were discussed at a seminar where the participants concluded that the Agency

  18. Cost of transporting irradiated fuels and maintenance costs of a chemical treatment plant for irradiated fuels

    International Nuclear Information System (INIS)

    Sousselier, Y.

    1964-01-01

    Numerous studies have been made of the cost of a fuel cycle, but many of them are based on a priori studies and are therefore to be treated with reserve. Thus, in the part dealing with the treatment of irradiated fuels, some important factors in the cost have only rarely been given on the basis of practical experience: the cost of transporting the fuels themselves and the plant maintenance costs. Investigations relating to transport costs are generally based on calculations made from somewhat arbitrary data. The studies carried out in France on the transport of irradiated uranium between the EDF reactors at Chinon and the retreatment plant at La Hague of the irradiated uranium from research reactors to foreign retreatment plants, are reported; they show that by a suitable choice of transport containers and details of expedition it has been possible to reduce the costs very considerably. This has been achieved either by combining rail and road transport or by increasing the writ capacities of the transport containers: an example is given of a container for swimming-pool pile elements which can transport a complete pile core at one time, thus substantially reducing the cost. Studies concerning the maintenance costs of retreatment plants are rarer still, although in direct maintenance plants these figures represent an appreciable fraction of the total treatment cost. An attempt has been made, on the basis of operational experience of a plant, to obtain some idea of these costs. Only maintenance proper has been considered, excluding subsidiary operations such as the final decontamination of apparatus, the burial of contaminated material and radioprotection operations Maintenance has been divided into three sections: mechanical maintenance, maintenance of electrical equipment and maintenance of control and adjustment apparatus. In each of these sections the distinction has been made between manpower and the material side. In order to allow comparisons to be made with

  19. Incidence of childhood leukemia around French nuclear sites between 1990 and 1998

    International Nuclear Information System (INIS)

    White-Koning, M.; Hemon, D.; Goubin, A.; Clavel, J.; Laurier, D.; Tirmarche, M.; Jougla, E.

    2006-01-01

    The works presented here constitute the first systematic study of the incidence of childhood leukemia around the whole of French nuclear facilities. Globally, the incidence of childhood leukemia does not diverge significantly of the expected incidence during the period 1990-1998. It does not show a decrease of S.I.R. (standardized incidence ratio) in function of the distance from child's home to the nuclear site whatever be the age. This study represents the first analysis of the incidence of leukemia focusing on 29 French nuclear sites, including the whole of the 19 C.N.P.E. ( nuclear power plants that produce electric power), and is based on incidence data rather than mortality. The period, the age groups and the studied area have been all chosen a priori, that gives a statistical validity to the results. The estimation of population at risk have been made with several different methods of interpolation in order to check the stability of estimations. The different methods of statistical analysis used have lead to extremely close results, reinforcing our confidence in the reliability of our estimations. The excess of leukemia incidence observed at Chinon and Civaux and the deficit observed at Bruyere/Saclay/Fontenay loose their statistical significance when the correction of Bonferroni is applied. So, the global analysis of the 29 sites and the analysis by site have not shown statistically significant difference between the numbers of observed and expected cases. The study of the 19 C.N.P.E. gave same results, even in taken into account their electric power or their year of service. The possibility of confounding factors has been excluded. The power of the study to detect excess incidence and a decrease of S.I.R. with distance from the site was examined under different alternative hypotheses through simulation methods. For values of S.I.R. near the site (0-5 km) between 1.5 and 2 and a risk of error of 5%, the power of the study is between 96% and 100% depending

  20. EDF feedback on recent EPRI SGOG SG chemical cleanings applications for TSP blockage reduction and heat transfer recover

    International Nuclear Information System (INIS)

    Dijoux, M.; De Bouvier, O.; Mercier, S.; Pages, D.; Bretelle, J.-L.; Leclercq, P.; Mermillod, A.

    2010-01-01

    Between 2007 and 2008, six Steam Generators Chemical Cleanings (SGCC) with the inhibitor free high temperature process were applied on EDF PWR units. The main goal was to reduce the excessive Tube Support Plate blockages observed on several units of the EDF fleet and the consequences on wide range levels and the risk of tube cracks. The heat transfer recovery was the second objective. Despite the correct results obtained, the corrosion impact of the high temperature process on internal metallic surfaces, higher than expected, and the environmental issues led EDF to move to a new cleaning process. The low temperature process developed by EPRI SGOG and applied for many years was selected for the same purpose. Some qualification laboratory tests were performed by Dominion Engineering Inc (DEI) to demonstrate the innocuousness an the efficiency of the process to achieve these goals. The EPRI SGOG process was then applied seven times by Westinghouse on the EDF units Cruas 3, Cruas 2, Belleville 1, Cattenom 1, Cattenom 3, Chinon B3 and Cattenom 4 between 2008 and 2010. All these units operate from the initial start at low AVT pH 25 o C (9,2) in the secondary circuit. Due to copper presence in the deposits to remove, the cleaning sequence 'Copper - Iron - Copper steps' was performed each time. After a short description of the process, including the specific adaptation in France, lessons learned are reported in this paper in the following areas: process monitoring, corrosion, efficiency, liquid and gaseous wastes, chemical pollution during start-up. Based on the 3 first applications in 2008, some modifications of the process were implemented, particularly for the copper step. For the units cleaned, 1100 to 4500 kg of deposits per SG have been removed, including TS sludge lancing. The reduction of TSP blockages was satisfying. The effect on steam pressure improvement and the wide range level is then discussed. The paper concludes on EDF perspectives for soft

  1. The industrial production of fuel elements; La fabrication en france des elements combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Boussard, R [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Nadal, J [Societe Industrielle de Combustible Nucleaire (SICN), 75 - Paris (France); Pellen, A [Compagnie pour l' Etude et la Realisation de Combustibles Atomiques (CERCA), 75 - Paris (France)

    1964-07-01

    The authors deal successively with the industrial production of fuel elements for power reactors of the natural uranium-graphite-gas type, and more particularly for the EDF power stations, and with the industrial production of fuel elements containing enriched uranium designed for swimming-pool type reactors. 1. part: advanced fuel elements for the EDF reactors. After recalling the characteristics of the fuel elements now being produced industrially for the Marcoule and Chinon reactors, the authors give the various steps leading to the industrial production of a new type of fuel element both as concerns the can, and in certain cases the graphite sleeve, and the fuel itself. As for as the production of the fuel is concerned, they describe the various operations, stressing the original aspects of the production and of the equipment such as: - casting in hot moulds, - thermal treatments, of Uranium containing 1% in weight molybdenum, - welding of the pellets for closing the tubes of uranium, - canning, - controls in the various steps. As far as can production is concerned they show why the extruded can was replaced by a machined can and give a few characteristics of the equipment used as well as the controls effected. They give also some details concerning the production and machining of the sleeves. After recalling the state of the nuclear fuel industry in France in mid-1964 the authors stress the economic aspects of the production of fuel elements. They show the relative importance of capital costs on the cost price of the fuel itself and examine the various items involved. They analyse the cost price of a completed fuel element using present date knowledge. In conclusion the authors show the particular points which should be the subject of future efforts in order to decrease the cost of a production which is perhaps delicate but now will define, and review the development of this new industrial branch. 2. part: industrial production of fuel elements for swimming

  2. Decommissioning in western Europe

    International Nuclear Information System (INIS)

    Lundqvist, K.

    1999-12-01

    time (sometimes hundred years or more), prior to final demolition. Among the reasons for deferring the dismantling are lack of waste repositories and decreasing dose-rates for the workers. Of Europe's 218 commercial reactors in operation, the majority, 151, are located i the Western part. The biggest producers are France, United Kingdom and Germany, with 58, 35 and 20 reactors respectively. Until now mostly research- and pilot reactors have been shut-down. There are yet few experiences from decommissioning of large-scale commercial reactors. The following commercial reactors are undergoing decommissioning. (There are also a great amount of nuclear facilities of other types being decommissioned.) The three gas-cooled twin reactor plants of Berkeley, Trawsfynydd and Hunterston in UK. In Germany Gundremmingen, Lingen, Kahl and Wuergassen are being decommissioned. All of them are located in the Western part of the country. The biggest project is however the dismantling of the gigantic Greifswald facility situated on the coast of the Baltic see in former Eastern Germany. The plant has eight Russian built reactors of VVER-type. Like the rest of the former GDR-plants Greifswald was shutdown after the reunification in 1990. The strategy chosen is immediate dismantling. France is decommissioning seven reactors (Chooz A1, Chinon A1, A2, A3, St Laurent A1, A2 and Bugey 1.) The oldest, Chinon A1, closed down in 1973 and the youngest, Bugey 1, in 1994. Italy closed down all NPPs (altogether four) in 1987 after a referendum. The first reactor of the Netherlands was shutdown in 1997 mainly for economical reasons. The development of a free European electricity market will make it less profitable to run certain facilities. Vandelos 1 in Spain is undergoing decommissioning after a fire in the turbines in 1989. IAEA, OECD/NEA and EU are co-operating in the field of decommissioning. Much work is spent on harmonizing rules and preparing international guidelines. The international agencies

  3. Cost of transporting irradiated fuels and maintenance costs of a chemical treatment plant for irradiated fuels; Cout de transport des combustibles irradies et cout d'entretien d'une usine de traitement chimique des combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    Numerous studies have been made of the cost of a fuel cycle, but many of them are based on a priori studies and are therefore to be treated with reserve. Thus, in the part dealing with the treatment of irradiated fuels, some important factors in the cost have only rarely been given on the basis of practical experience: the cost of transporting the fuels themselves and the plant maintenance costs. Investigations relating to transport costs are generally based on calculations made from somewhat arbitrary data. The studies carried out in France on the transport of irradiated uranium between the EDF reactors at Chinon and the retreatment plant at La Hague of the irradiated uranium from research reactors to foreign retreatment plants, are reported; they show that by a suitable choice of transport containers and details of expedition it has been possible to reduce the costs very considerably. This has been achieved either by combining rail and road transport or by increasing the writ capacities of the transport containers: an example is given of a container for swimming-pool pile elements which can transport a complete pile core at one time, thus substantially reducing the cost. Studies concerning the maintenance costs of retreatment plants are rarer still, although in direct maintenance plants these figures represent an appreciable fraction of the total treatment cost. An attempt has been made, on the basis of operational experience of a plant, to obtain some idea of these costs. Only maintenance proper has been considered, excluding subsidiary operations such as the final decontamination of apparatus, the burial of contaminated material and radioprotection operations Maintenance has been divided into three sections: mechanical maintenance, maintenance of electrical equipment and maintenance of control and adjustment apparatus. In each of these sections the distinction has been made between manpower and the material side. In order to allow comparisons to be made with

  4. Feedback from dismantling operations (level 2) on EDF's first generation reactors

    International Nuclear Information System (INIS)

    West, J P.; Dionisio-Gomes, A.; Kus, J P.; Mervaux, P.; Bernet, P.; Dalmas, R.

    2003-01-01

    EDF's policy as regards the dismantling of the reactors that have ceased commercial operation, namely the eight power plants of the first generation and the Creys-Malville power plant, is explained. Generally speaking, prior to the year 2001, EDF had opted for the de-construction of these power plants to comply with a 'long wait' scenario, which consisted of waiting for a period of 5 to 10 years to achieve IAEA level 2 (partial release of the site), then postponing the total de-construction of the facilities for 25 to 50 years. Today, EDF has decided to undertake the total de-construction of these reactors, which have ceased commercial operation, over a period of 25 years. The purpose of this document is to present: - The reactors concerned, their background and their 'regulatory' situation, - The main operations performed and/or currently in progress, - The main elements of feedback from such operations, shedding light on the approach adopted in 2001. The installations concerned by the de-construction programme are as follows: - The 8 power plants of the first generation, which were built during the fifties and sixties and ceased commercial operation between 1973 and 1994, namely: Brennilis (industrial prototype using heavy water technology, jointly operated by EDF and CEA), the 6 power units of the NUGG type (natural uranium gas graphite) at Chinon, Saint-Laurent des Eaux and Bugey and the PWR reactor at Chooz A, - The storage silos at Saint-Laurent, where the sleeves for the fuel assemblies of reactors SLA1 and SLA2 are stored, corresponding to approximately 2000 tonnes of graphite, - The Creys-Malville reactor, FBR (fast breeder reactor) shut down in accordance with a government decision, which is currently undergoing decommissioning. At the current stage, our feedback from the dismantling operations carried out on nuclear facilities is based on (i) the work carried out or in progress that will make it possible to achieve the equivalent of IAEA level 2 in the

  5. A.C.R.O. activity report 2002

    International Nuclear Information System (INIS)

    2002-01-01

    control organisation, with the Minister of health international colloquium on the risk management, S.F.R.P. congress on radiation protection, university colloquium on risk management, S.F.R.P. congress on carbon 14, S.F.R.P. congress I.R.P.A. european congress on radiation protection presentation of the working group in radiation protection, S.F.R.P. congress on evaluation and surveillance of radioactive releases of nuclear installations, european commission stake holders conference on approaches to the management of environmental radioactivity, ethical lesson and society at the national school of the Departments of civil engineering, think tank and working groups, participation to the local commission of information (C.L.I.) and in its regular publication 'the nuclear chronicle', participation to the superior council of nuclear safety and information (C.S.S.I.N.); about the environmental surveillance two environments are the object of a regular follow-up: the plateau of La Hague (reprocessing plant and Manche plant where are treated and stored radioactive waste), Touraine area where is situated the nuclear power plant of Chinon; Radio ecological follow through of the aquatic environment both continental and marine of the sea-coast of Normandy from 2001 to 2003; Radio ecological monitoring of the environment of the Cogema la Hague building site in the Moulinets cove; measurements of radon; inventory of the tritium levels in the drinking water of the Manche department; radiation monitoring of the effluents released by the hospitals in the town of Caen. (N.C.)

  6. Photophysical properties of novel Porphyrin-Flavin Dyads

    International Nuclear Information System (INIS)

    Stark, S.

    2001-10-01

    Photosynthesis belongs to the fundamentals of life on earth, therefore it is an important matter in natural sciences. The basic principle of photosynthesis is the transformation of solar light into chemical energy. The starting steps of photosynthesis are light-induced energy- and electron-transfer-steps with singular efficiency. One attempt to enlighten the molecular processes involved is to synthesize simpler model systems with similar properties. Important research goals are the dependencies of light-induced processes on distance and orientation of donor and acceptor. A second aim next to the clarification of the molecular conditions of photosynthesis is to create molecular light-driven machines. The most simple so-called biomimetic model system consists of an electron-donor connected to an electron-acceptor via a spacer-group. This simplest form is also referred to as dyad. Beyond dyads far more complicated compounds have been introduced consisting of several donors and/or acceptors, so-called triads, tetrads, pentads etc. Usually porphyrin serves as electron-donor. Next to chinones several other electron-acceptors are used, e.g. anthracene, pyromellitimide and fullerene. Artificial photosynthetic centers are often more stable and/or the excited states are easier to detect compared to the natural photosynthetic center. The photophysical characteristics of four dyads are reported in this work. The dyads consist of porphyrin (either free-base or zinc-metallated) and flavin, connected by different spacers. These dyads reveal photo-induced electron transfer from porphyrin to flavin and energy-transfer in the reversed direction with different efficiencies. The object of the study is the dependency of these processes on the structural features. The spacer of the dyads 1a-1c is an aromatic bridge which leads to well defined donor-acceptor distances. Because of this structure conjugation through the spacer is increased, whereas the absorption in the visible and near UV

  7. Dismantling of nuclear facilities and related problems - Conference proceedings

    International Nuclear Information System (INIS)

    Tournebize, Frederic; Bordet, Didier; Charlety, Philippe; Gore, Thierry; Estrade, Jerome; Lemaire, Hermine; Ginet, Annick; Fabrier, Lionel; Evrard, Lydie; Furois, Timothee; Butez, Marc; Dutzer, Michel; Faure, Vincent; Billarand, Yann; Menuet, Lise; Lahaye, Thierry; Pin, Alain; Mougnard, Philippe; Charavy, Sylvain; Poncet, Philippe; Moggia, Fabrice; Dochy, Arnaud; Benjamin, Patrick; Poncet, Pierre-Emmanuel; Beneteau, Yannick; Richard, Jean-Baptiste; Pellenz, Gilles; Ollivier Dehaye, Catherine; Gerard, Stephane; Denissen, Luc; Davain, Henri; Duveau, Florent; Guyot, Jean-Luc; Ardellier, Luc

    2012-11-01

    facilitating the definitive shutdown of the Jules Horowitz reactor (J. Estrade); 17 - Integration of dismantling at the design stage of the French EPR reactor (Y. Beneteau, J.P. Richard); 18 - Use of the Gampix gamma camera at dismantling sites (H. Lemaire); 19 - Stakes for the wastes intended to be disposed off in waste centres in operation (F. Dutzer); 20 - Cleansing of non-nuclear contaminated sites (V. Faure); 21 - Rehabilitation of dismantling sites - management plan for the old effluents channel of the Brennilis effluents processing plant (G. Pellenz, C. Ollivier-Dehaye); 22 - Problem of confinement keeping during deconstruction (A. Ginet, L. Fabrier); 23 - Project of wells cleansing at the irradiated materials workshop (AMI) of Chinon NPP (F. Duveau); 24 - Nuclear decontamination using a laser (F. Moggia); 25 - TIVA, adaptable and ventilated intervention dress (A. Dochy, P. Benjamin); 26 - Dismantling project - optimisation thanks to virtual reality-based software solutions (L. Ardellier, A. Pin)

  8. National congress of radiation protection - SFRP 2005; Congres National de Radioprotection - SFRP 2005

    Energy Technology Data Exchange (ETDEWEB)

    Lagroye, I [Bordeaux Univ., Lab. de Bioelectromagnetisme de l' EPHE, Lab. PIOM, ENSCPB, 33 (France); Gonzague, A [EDF, Centre d' appui du parc en exploitation, Groupe prevention des risques environnement, 93 - Saint-Denis (France); Ammerich, M [Direction Generale de la Surete Nucleaire et de la radioprotection (DGSNR), 75 - Paris (France); Blanc, D; Lecomte, J F; Boucher, D; Boucher, D; Averbeck, D; Gourmelon, P; Barbey, P; Bourguignon, M; Cordoliani, Y S; Dutrillaux, B; Radecki, J J; Schieber, C; Cosset, J M; Lecomte, J F; Lochard, J; Metivier, H; Sugier, A; Tirmarche, M; Aurengo, A; Lamartine, J; Martin, M; Mallard, C; Malfoy, B; Ugolin, N; Chevillard, S; Schlumberger, M; Laurier, D; White-Koning, M L; Hemon, D; Tirmarche, M; Jougla, E; Clavel, J; Miccoli, L; Barber, R; Angulo, J F; Dubrova, Y E; Le Gall, B; Phan, G; Grillon, G; Rouit, E; Benech, H; Fattal, E; Deverre, J R; Legros, A; Beuter, A; Verrier, A; Magne, I; Souques, M; Lambrozo, J; Schmitt, P; Roth, P; Nadi, M; Joly, L; Chapel, C; Burgain, A; Marliot, F; Cordier, E; Courant, D; Elabbassi, E B; Seze, R de

    2005-07-01

    particular contamination; C.H.A.V.I.R., an interactive simulator for radiation protection; an ALARA engineering commune to the operating reactors; evolution of the radiological zoning and monitoring rules associated on the Cogema la Hague facility; an ambitious project for the nuclear park of EDF power plants : the purification project and its implementation for the Chinon B2 reactor - 2004); the eighth session concerns the environmental exposures and their consequences with the following presentations ( the concept of radioecological sensitivity and its interest in the risk management; phenomenal and analytical interpretation of the rain-deposit relationship used for the building of cesium 137 deposits in France consecutively to the Chernobyl accident; study of radioactivity source terms and transfer from medical origin in the purification network of the town of Toulouse; natural and artificial radioactivity in some marine species in manche. Case of polonium and plutonium alpha emitters. Synthesis of data acquired in the north Cotentin since 1990. elements of comparison; the role of local commissions of information (C.L.I.) in the follow up of release and monitoring of nuclear facilities); the ninth session concerns the dosimetry; the tenth session is divided in two parts radiation protection in accidental situations and radiation protection in post accidental situations with their respective presentations as follow ( evaluation of the dispersion of an aero contaminant in a ventilated area in field near an accidental source of emissions; study of the containment efficiency by gloveboxes in functioning accidental situations; the radiation protection and health; study by R.P.E. of the response of different materials in mixed field ( gamma, neutrons), application to the dosimetry reconstruction of an accident; nuclear or radiological events: organisation of medical intervention; and rehabilitation of life conditions in the contaminated territories: the contribution of

  9. Proceedings of the 6. conference days on radioprotection optimization in the nuclear, industrial and medical domains

    International Nuclear Information System (INIS)

    Vial, Eric; Bernier, Marie-Odile; De Vita, Antoine; Pignot, Christine; Bardelay, Chantal; Godet, Jean-Luc; Perrin, Marie-Line; Saad, Nawal; Deboodt, Pascal P.A.; Faure, Sophie; Fusil, Laurence; Alvarez, Manuel; Tourneux, C.; Barbey, Pierre; Pigree, Gilbert; Lemarchand, Maxime; Buchaniec, Remi; Rocourt, Nathalie; Bouden, Helene; Lasselin, Stephanie; Moeneclaey, Ludivine; Rebullida, Delphine; Werquin, Marie Odile; Dubus, Francois; Ponsard, Samuel; Marques, Sophie; K-Zerho, R.; Vacher, F.; Vrammout, D.; Guillot, E.; Fucks, I.; Moukarzel, Marianne; Ryckx, Nick; Verdun, Francis R.; Lefaure, Christian; Balduyck, Sebastien; Cruz Suarez, Rodolfo; ); Bouvy, Christophe; Geets, Jean-Michel; Nactergal, Benoit; Davet, Laurent; Carlier, Pierre; Lereculey, Clement; Livolsi, Paul; PIN, Alain; Ducou le Pointe, Hubert; Le Faou, Yann; Courageot, Estelle; Gaillard-Lecanu, Emmanuelle; Kutschera, Reinald; Le Meur, Gaelle; Lantheaume, Noel; Schiedts, Dominique; Nouveau, Philippe; Walterscheid, Bertrand; Humbert, Edouard; Tranchant, Philippe; Dabat-Blondeau, Charlotte; Renard, Francois; Lucas, Jean-Yves; Fritioff, Karin; Svedberg, Torgny; Carlson, Marie; Hennigor, Staffan; Schieber, Caroline; Andresz, Sylvain; Roch, Patrice; Celier, David; Aubert, Bernard; Etard, Cecile; Bouette, Aurelien; Carette, M.F.; Haddad, S.; Khalil, A.; Foulquier, J.N.; Parrot, A.; Ceyrolle, C.; Bechard, Pascal; Clero, E.; Leuraud, K.; Laurier, D.; Couzinet, M.; LE GUEN, B.; Davesne, Estelle; Blanchardon, Eric; Franck, Didier; Quesne, Benoit; De Vita, Antoine; Chojnacki, Eric; Grandeau, E.; Dumont, N.; Cattelotte, J.; Dine, Pierre Emmanuel; Guersen, Joel; Nwatsock, Joseph Francis; Boyer, Louis; Karmouche, K.; Moyon, J.B.; Cassagnes, L.; Garcier, J.M.; Lortal, B.; Caron, J.; Karst, M.; Rage, Estelle; Caer-Lorho, Sylvaine; Drubay, Damien; Ancelet, Sophie; Laurier, Dominique; Laroche, Pierre; Sans, Philippe; Tournier, Helene; Zvorykin, Sonia

    2014-06-01

    optimization at our cancer centre (R. Buchianec); 12 - Radioprotection optimisation during the fire detection renovation of a storage building (S. Ponsard); 13 - Supervisor position for risk prevention (S. Marques); 14 - Use of experience feedback to improve radioprotection optimisation in the medical sector (M. Moukarzel); 15 - Involvement of a medical physicist in radiology and nuclear medicine: the Swiss experience after 18 months of optimisation practice (F. Verdun); 16 - Application of ALARA method for the design of a medical department (S. Balduyck); 17 - ALARA implementation at the design stage of cyclotrons (C. Bouvy); 18 - ALARA at the design and post-incident stages (L. Davet); 19 - Radioprotection during the design and realisation of the Fessenheim NPP raft (P. Carlier); 20 - Serious games as pedagogical tools for radioprotection training (P. Livolsi); 21 - Continued professional development and Radioprotection? (H. Ducou Le Pointe); 22 - New training reference requirements in the domain of patients radioprotection (Y. Le Faou); 23 - Digital radioprotection workshop (CERNUM) at the Civaux site (E. Courageot); 24 - Presentation of the SIBAG simulator for glovebox work training (N. Lantheaume); 25 - Operating block: the radioprotection dunce? (D. Schiedts); 26 - Optimization in dismantling: three facilities, three different ways? (P. Deboodt); 27 - Cold cutting confining processes (P. Nouveau, B. Walterscheid); 28 - ALARA approach for long lasting works - The Chinon A3 example (E. Humbert); 29 - Dosimetric optimization and professional activity management (P. Tranchant); 30 - CADOR: application to the installation of biological protections during plant shutdown (F. Renard); 31 - Do you apply ALARA? Organisation of an ALARA benchmark at Forsmark and Ringhals NPPs (Sweden) (S. Andresz); 32 - Diagnostic reference levels as optimisation tool (P. Roch); 33 - Optimisation in pediatrics scanning: new tools contribution (A. Bouette); 34 - Elaboration of interventional

  10. National congress of radiation protection - SFRP 2005

    International Nuclear Information System (INIS)

    Lagroye, I.; Gonzague, A.; Ammerich, M.; Blanc, D.; Lecomte, J.F.; Boucher, D.; Boucher, D.; Averbeck, D.; Gourmelon, P.; Barbey, P.; Bourguignon, M.; Cordoliani, Y.S.; Dutrillaux, B.; Radecki, J.J.; Schieber, C.; Cosset, J.M.; Lecomte, J.F.; Lochard, J.; Metivier, H.; Sugier, A.; Tirmarche, M.; Aurengo, A.; Lamartine, J.; Martin, M.; Mallard, C.; Malfoy, B.; Ugolin, N.; Chevillard, S.; Schlumberger, M.; Laurier, D.; White-Koning, M.L.; Hemon, D.; Tirmarche, M.; Jougla, E.; Clavel, J.; Miccoli, L.; Barber, R.; Angulo, J.F.; Dubrova, Y.E.; Le Gall, B.; Phan, G.; Grillon, G.; Rouit, E.; Benech, H.; Fattal, E.; Deverre, J.R.; Legros, A.; Beuter, A.; Verrier, A.; Magne, I.; Souques, M.; Lambrozo, J.; Schmitt, P.; Roth, P.; Nadi, M.; Joly, L.; Chapel, C.; Burgain, A.; Marliot, F.; Cordier, E.; Courant, D.; Elabbassi, E.B.; Seze, R. de

    2005-01-01

    contamination; C.H.A.V.I.R., an interactive simulator for radiation protection; an ALARA engineering commune to the operating reactors; evolution of the radiological zoning and monitoring rules associated on the Cogema la Hague facility; an ambitious project for the nuclear park of EDF power plants : the purification project and its implementation for the Chinon B2 reactor - 2004); the eighth session concerns the environmental exposures and their consequences with the following presentations ( the concept of radioecological sensitivity and its interest in the risk management; phenomenal and analytical interpretation of the rain-deposit relationship used for the building of cesium 137 deposits in France consecutively to the Chernobyl accident; study of radioactivity source terms and transfer from medical origin in the purification network of the town of Toulouse; natural and artificial radioactivity in some marine species in manche. Case of polonium and plutonium alpha emitters. Synthesis of data acquired in the north Cotentin since 1990. elements of comparison; the role of local commissions of information (C.L.I.) in the follow up of release and monitoring of nuclear facilities); the ninth session concerns the dosimetry; the tenth session is divided in two parts radiation protection in accidental situations and radiation protection in post accidental situations with their respective presentations as follow ( evaluation of the dispersion of an aero contaminant in a ventilated area in field near an accidental source of emissions; study of the containment efficiency by gloveboxes in functioning accidental situations; the radiation protection and health; study by R.P.E. of the response of different materials in mixed field ( gamma, neutrons), application to the dosimetry reconstruction of an accident; nuclear or radiological events: organisation of medical intervention; and rehabilitation of life conditions in the contaminated territories: the contribution of radiation protection