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  1. FRAMATOME nuclear services

    International Nuclear Information System (INIS)

    Delorme, H.; Buttin, J.

    1985-05-01

    FRAMATOME is a French company whose main activities since 1958 have been the design and manufacture of standardized PWR Nuclear Steam Supply Systems. FRAMATOME builds the Reactor Coolant System components and installs and starts-up the extended Nuclear Steam Supply Systems. In addition to the supply of spare parts of tooling, the services offered by Framatome are implementation of backfits aimed at performance and safety improvement and equipment reliability, technical assistance and, maintenance and repair services

  2. Framatome. 1997 annual report

    International Nuclear Information System (INIS)

    1997-01-01

    The Framatome group is the first nuclear engineering group worldwide and the number three in connectors engineering. in the nuclear domain, Framatome is manufacturer of reactors, supplier of fuels and provides specialized services. This activity report summarizes the highlights, key data and economic position of the group, the nuclear activities (realizations, fuels, services, non-destructive testing), the construction of industrial equipment (electromechanics, alternators, turbines, compressors, heat exchangers etc..), the connectors engineering activity, and the financial and economical results of the group for 1997. (J.S.)

  3. Integration of Framatome ANP

    International Nuclear Information System (INIS)

    Krebs, W.D.; Bouteille, F.

    2001-01-01

    The environment of nuclear power has changed greatly in the past few years. Cross-border exchanges of electricity have increased considerably, and more and more free and open markets add to the transparency of the cost situation in power generation. This is the environment in which a new firm is offering the necessary know-how to power companies and nuclear power plant operators. The two leading firms, Framatome and Siemens, have merged their nuclear divisions into Framatome ANP. The new company is active in all areas of nuclear power: New nuclear power plant construction, maintenance, nuclear fuel supply and nuclear power plant services in Europe, Asia, and America. More than ninety nuclear power plants, which is tantamount to 30% of the capacity installed worldwide, were built by the two companies, which makes Framatome ANP a leading enterprise for the long-term development of nuclear power. Framatome ANP merges a number of activities characterized by histories and corporate culture of their own within the framework of their respective political, economic, and social environments. The outcome is variety to be combined with extensive experience. Cooperation on the basis of a combination of best experience, the exchange of know-how, and the acceptance of differences offers the best opportunities for future developments which, however, also require the best possible preparation. This is underscored by the experience that some 75% of all company mergers fail to achieve the desired goals of synergy and cost savings. (orig.) [de

  4. Intercontrole acquiring by Framatome

    International Nuclear Information System (INIS)

    1997-01-01

    The Framatome group, as the worldwide leader in nuclear power plant construction, has reinforced his competences in nuclear services thanks to the acquiring of the Intercontrole company, specialized in non-destructive testing in nuclear and industrial environments. After a presentation of the functioning principle and of the safety aspects of a PWR reactor, this press dossier presents in a first part the role of nuclear services and in particular of non-destructive testing in nuclear power plants (in-service inspection, regulatory aspects, testing processes). This part is illustrated with some examples of inspection performed on some components of the primary coolant loop (steam generators, reactor vessel, pressurizer, pipes, primary pumps). A second part presents the technical centres and units of Framatome in charge of performing non-destructive inspections, while a third part describes the industrial policy and strategy of the group in this domain (market of nuclear park maintenance in France, in the USA and worldwide, creation of the 'inspection and control' centre of Framatome). A last part presents the activities of the Intercontrole company and of its daughter companies with some examples of actions realized in the nuclear and natural gas domains. (J.S.)

  5. FRAMATOME, Annual Report, 1998

    International Nuclear Information System (INIS)

    Vignon, Dominique

    1999-01-01

    Framatome conducts its activity in two large domains: - in the power field it is a world leader for nuclear power plant constructions and the related activities; - in the telecommunication field where it is at present number two world leader. Framatome is number one world leader in the technology of pressurized water reactors, is developing advanced nuclear fuels of type AFA 3G and Alliance and is running nuclear service activities specialized in non-destructive testing. In the field of telecommunication Framatome will acquire, following acquisition in 1998 of Berg Electronics, a leading position in America, Europe and Asian-Pacific zones. The report presents the activities of the group, highlights the significant events of 1998 and gives key figures of the activity in 1998. In the field of power there are presented the nuclear power and nuclear fuels development, the nuclear services, the mechanical structure and boilers and associated industrial equipment. In the field of telecommunication the report presents relevant facts in communications, computer science, aviation, space and defence industries, power transmission and equipment, and automobile industries. Finally, the report presents the financial account on 1998

  6. Framatome's 1997 advertisement campaign

    International Nuclear Information System (INIS)

    Tonnac, Alain de

    1998-01-01

    As many other companies involved in the nuclear business, Framatome was initially concentrating on corporate advertisements in business newspapers and magazines. The first goal was to concentrate on our traditional nuclear core business, while selecting the protection of the environment at large, and particularly the greenhouse effect, one of the most sensible issues of the moment. The 1997 campaign was shaped around the need to motivate European decision makers, while maintaining a domestic consensus towards nuclear power for the future resumption of constructions. The brief elaborated for Ad agencies was roughly threefold: elaborate simple messages, unquestionable, and explained with serenity; put emphasis on the benefits of nuclear power for the environment; establish a balanced comparison between nuclear and fossil fuels. A pre-test was conducted with about 100 people, half of which from the energy sector, and politicians, mainly members of the French and European Parliaments, the other half from the general public. Being accustomed to a usually discrete, if not 'ashamed' nuclear communication, people were generally surprised by such an optimistic tone about nuclear power, but agreed, on average. The campaign lasted one month (spread over June-July 97), and the three selected ads appeared successively in the form of a colour double page. Beyond nuclear magazines, the media plan included French daily newspapers le Figaro, le Monde, les Echos, Liberation, and weekly magazines: le Point, le Nouvel Observateur, I'Express, etc. All of them are intended for middle to high social class readers. In addition, some advertisements were inserted in The European Voice, a weekly publication reaching Brussels Commission and European parliament members. As an average, the campaign was perceived as dynamic (69%), and original (61%). But credibility and conviction were poor (resp 33%, 26%), probably because it was coincident with La Hague being on the carpet. On the other hand

  7. Framatome start up activities

    International Nuclear Information System (INIS)

    Derrien, C.

    1982-09-01

    By the end of 1981, fifteen 900 MWe plant units of a twenty eight unit programme will have gone on-line. Eight units have reached criticality during 1980 and seven will go critical during the present year. Much however still has to be done to complete this ambitious programme. Though we are only half way through our programme, it is still possible to make an initial review of these startups. This review first outlines the content of a PWR testing programme and then considers the way in which FRAMATOME has organised its testing division. Lessons learned from construction leadtimes are discussed and the difficulties and major incidents encountered during these startups are described

  8. Framatome. 1997 annual report; Framatome. Rapport annuel 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    The Framatome group is the first nuclear engineering group worldwide and the number three in connectors engineering. in the nuclear domain, Framatome is manufacturer of reactors, supplier of fuels and provides specialized services. This activity report summarizes the highlights, key data and economic position of the group, the nuclear activities (realizations, fuels, services, non-destructive testing), the construction of industrial equipment (electromechanics, alternators, turbines, compressors, heat exchangers etc..), the connectors engineering activity, and the financial and economical results of the group for 1997. (J.S.)

  9. FRAMATOME, Annual Report, 1998; FRAMATOME, Rapport Annuel, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Vignon, Dominique [FRAMATOME, Tour Framatome - 92084 Paris, La Defense Cedex (France); and others

    1999-07-01

    Framatome conducts its activity in two large domains: - in the power field it is a world leader for nuclear power plant constructions and the related activities; - in the telecommunication field where it is at present number two world leader. Framatome is number one world leader in the technology of pressurized water reactors, is developing advanced nuclear fuels of type AFA 3G and Alliance and is running nuclear service activities specialized in non-destructive testing. In the field of telecommunication Framatome will acquire, following acquisition in 1998 of Berg Electronics, a leading position in America, Europe and Asian-Pacific zones. The report presents the activities of the group, highlights the significant events of 1998 and gives key figures of the activity in 1998. In the field of power there are presented the nuclear power and nuclear fuels development, the nuclear services, the mechanical structure and boilers and associated industrial equipment. In the field of telecommunication the report presents relevant facts in communications, computer science, aviation, space and defence industries, power transmission and equipment, and automobile industries. Finally, the report presents the financial account on 1998.

  10. Framatome announces its 1997 results; Framatome annonce ses resultats 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-18

    This press dossier presents the 1997 financial year of Framatome group: turnover and key-numbers, results, sectoral analysis (nuclear engineering (nuclear realizations, fuels, services and equipments); connectors engineering (automotive, electrical, electronic, interconnection and microelectronic industries), industrial equipments). Then, the 1998 objectives are presented with the strategy of the group (Chinese, central and eastern Europe nuclear programs, French-German joint EPR project, services and nuclear fuels, connectors engineering, industrial equipments, manpower, research and development programs). This part is followed by a presentation of some 1997 events and by the text of the press conference from May 18, 1998 which presented the activities of the group, its competences and know-how in the nuclear domain. (J.S.)

  11. Framatome announces its 1997 results

    International Nuclear Information System (INIS)

    1998-01-01

    This press dossier presents the 1997 financial year of Framatome group: turnover and key-numbers, results, sectoral analysis (nuclear engineering (nuclear realizations, fuels, services and equipments); connectors engineering (automotive, electrical, electronic, interconnection and microelectronic industries), industrial equipments). Then, the 1998 objectives are presented with the strategy of the group (Chinese, central and eastern Europe nuclear programs, French-German joint EPR project, services and nuclear fuels, connectors engineering, industrial equipments, manpower, research and development programs). This part is followed by a presentation of some 1997 events and by the text of the press conference from May 18, 1998 which presented the activities of the group, its competences and know-how in the nuclear domain. (J.S.)

  12. The Framatome RCVS concept and physics

    International Nuclear Information System (INIS)

    Vallee, A.; Millot, J.P.; Bruna, G.

    1986-06-01

    We have tried through this presentation to emphasize on what FRAMATOME thinks to be the most specific problems of the advanced RCVS (Reactor core with spectral shift) core concept (Spectral shift, voidage, reactivity control). Besides, FRAMATOME is analysing the most important safety related topics typically LOCA and DNBR, and has launched developments on them, in connection with CEA. The core behaviour during a loss of Coolant Accident is quite similar to PWR's, the pitch between rods being sufficiently large for clad ballooning not to cause any damage. To conclude, the core improvements developed by FRAMATOME on the RCVS concept economize the use of fissile materials

  13. Acquisitive Framatome nurtures its core businesses

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    For the past five years, Framatome's objective has been to be world leader in each of its core businesses. Whenever interesting opportunities become available, the company aims to develop through acquisition, which enables it either to penetrate growing market or to increase its existing market share. In the past 20 years, Framatome teams have designed, produced and installed 62 nuclear reactors with a combined generating capacity of 62000 MWe on 25 different sites in France and abroad (eg Belgium, South Africa, South Korea and China). Today, Framatome continues to build nuclear plants and manufacture big nuclear components, while adapting its activities to the new demands of the market. (Author)

  14. A survey of Framatome's expert systems activity

    International Nuclear Information System (INIS)

    Delaigue, D.; Grundstein, M.

    1987-01-01

    The French multinational nuclear energy world leader, Framatome, has designed and installed more than 40000 MWe of power in both France and abroad using Pressurized Water Reactor (PWR) technology. The French nuclear program ranks as one of the most successful in the world. In 1983, Framatome entered the Applied Artificial Intelligence (A.I.) field by setting up FRAMENTEC S.A., a joint venture with TEKNOWLEDGE Inc. Today, Framentec is a wholly-owned subsidiary of Framatome and is among the leading European companies specializing in Applied Artificial Intelligence. Framatome now has a 7.5% stake in Teknowledge Inc. The main applications in the nuclear industry can be summarized as follows: quality assurance; design of systems subject to extreme operating conditions; maintenance of complex systems; control of complex phenomenon producing high velocity transients; expert advice in multiple fields; compliance with complex regulations; high-skill personnel requirements; heavy financial investments

  15. Worldwide supply of Framatome ANP Fuel

    International Nuclear Information System (INIS)

    Jouan, J.

    2002-01-01

    Framatome-ANP is organized according to a matrix structure with 4 business groups and 3 regional divisions. The fuel business group with a workforce of about 4600 people is active in all the trades needed to design and manufacture nuclear fuel. The activity ranges from the production of zirconium alloys to the production of finished fuel assemblies, facilities are located in France, Germany and Usa. Framatome-ANP is the foremost vendor of LWR fuel worldwide with 41 % of the PWR market share and 22 % of the BWR market share. The global operating experience built up is based on more than 150.000 fuel assemblies delivered to 169 reactors in 18 countries. This long history has allowed Framatome-ANP to develop an efficient quality-improvement program based on experience feedback, for instance fuel rod failures induced by debris have been almost completely eliminated with the introduction of anti-debris devices equipping bottom nozzles. Framatome-ANP has developed a large range of engineering services, for instance core design teams can provide the most cost-effective fuel management schemes for cycle lengths from 6 to 24 months. The first technology transfer between China entities and Framatome related to the AFA-2G technology started in 1991 and was completed successfully in 1994. Since this date the Chinese manufacturer has supplied fuel reload for the units of Daya-Bay. (A.C.)

  16. Environmental management in Framatome nuclear fuel

    International Nuclear Information System (INIS)

    Thiebaut, B.; Ferre, A.

    1999-01-01

    Environmental preservation is both a national regulatory requirement and a condition for economic and social development. The various industrial sites belonging to the Framatome Nuclear Fuel Organisation, whose activities range from the processing and transformation of Zirconium alloy products to the fabrication of fuel assemblies, have always demonstrated that protection of the environment was their prime concern by implementing low pollution level processes and reducing and/or recycling industrial waste and effluents. As early as January 1996, a directive issued by the Framatome Group defined its environmental policy and responsibilities in the matter. Within the Framatome Nuclear Fuel Organization, this directive has been applied by implementation of: low level pollution processes; better performance of recycling of effluents, by-products and waste; environmental information policy. In all its plants, the Framatome Nuclear Fuel Organization has decided to pursue and to step up its environmental protection policy by: officializing its action through compliance with ISO standard 14001 and certification of all its industrial sites by 2001 at the latest; launching new actions and extra investment programs. In this context, FBFC has applied for a modification of the decrees concerning the dumping of liquid and gas effluents at the Romans factory. (authors)

  17. Framatome offers new high density Cadminox racks

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Framatome have developed a new material called Cadminox for use in high density spent fuel storage racks. It is claimed that Cadminox will remain stable stable in pond storage when racks submerged in boronated water are irradiated by the spent fuel they contain. A brief description of the storage module is given, including the aseismic bearing device which minimises loads on pond walls, racks and fuel assemblies. (UK)

  18. Evolution of Framatome pressurized water reactor systems

    International Nuclear Information System (INIS)

    Leroy, C.; Bitsch, D.; Millot, J.P.

    1985-10-01

    FRAMATOME's PWR experience covers a total of 63 units, 36 of which are operating by end of 1984. More than 10 units were operated in load follow mode. Progress features, resulting from the feedback of construction and operating experience, and from the returns of a vast research and development program, were incorporated in their design through subsequent series of standard units. The last four loop standard, the N4 model, integrates in a rational way all those progress features, together with a significant design effort. The core design is based on the new Advanced Fuel Assemblies. The reactor control implements the ''Reactor Maximum Flexibility Package'' (R-MAX) which provides a high level of automatic reactor control. The steam generator incorporates an axial-mixed flow economizer design. The triangular-pitch tube bundle, together with modular steam/water separators and a rearrangement of the dryers resulted in a compact design. The reactor coolant pump benefits of higher performances over that of previous models due to an optimal hydraulic design, and of mechanical features which increase margins and facilitate the maintenance work. Following the N4 project, design work on advanced concepts is pursued by FRAMATOME. A main way of research is focused on the optimal use of fissile materials. These concepts are based on tight pitch fuel arrays, associated with a mechanical spectral shift device

  19. Experience feedback from the transportation of Framatome fuel assemblies

    International Nuclear Information System (INIS)

    Robin, M.E.; Gaillard, G.; Aubin, C.

    1998-01-01

    Framatome, the foremost world nuclear fuel manufacturer, has for 25 years been delivering fuel elements from its three factories (Dessel, Romans, Pierrelatte) to the various sites in France and abroad (Germany, Sweden, Belgium, China, Korea, South Africa, Switzerland). During this period, Framatome has built up experience and expertise in fuel element transportation by road, rail and sea. In this filed, the range of constraints is very wide: safety and environmental protection constraints; constraints arising from the control and protection of nuclear materials, contractual and financial constraints, media watchdogs. Through the experience feedback from the transportation of FRAMATOME assemblies, this paper addresses all the phases in the transportation of fresh fuel assemblies. (authors)

  20. Framatome Contribution to Chinese NPP Development and Standardization

    International Nuclear Information System (INIS)

    Charbonneau, S.

    1996-01-01

    First discussions in 1978 between Framatome and Chinese authorities about the supply of an NPP were successfully concluded in 1986 by the signature of the supply contracts (nuclear islands, conventional islands, nuclear fuel assemblies, and project management assistance) for the Daya Bay NPP. Since then teams of engineers and technicians from Framatome and other French companies, and from relevant Chinese institutes and agencies have gotten to know each other better and have deepened their relationships

  1. Framatome technologies awarded nickel plating contract at St. Lucie

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    Framatome Technologies is to perform nickel plating on 120 pressurizer heater sleeves at Florida Power and Light's St. Lucie unit 1 during the fall 1997 outage; replacement heaters, fabricated by Framatome, that use stainless steel for the heather sheath, will be installed. The nickel layer is deposited on the inside surface of the heater sleeves, which protects the Inconel 600 material and significantly reduces the intergranular stress-corrosion cracking, as proved in other US and European plants

  2. Síndrome Parry-Romberg

    Directory of Open Access Journals (Sweden)

    Elayne Esther Santana Hernández

    2015-02-01

    Full Text Available El síndrome de Parry-Romberg, también conocido como hemiatrofia facial progresiva, es un síndrome neurocutáneo raro de etiología desconocida. Las principales características son la atrofia de los tejidos blandos, y algunas veces del hueso, en una mitad de la cara o parte frontal de la cabeza, sin debilitamiento facial. Estudios recientes plantean la posibilidad hereditaria de esta patología, ya que se recogen afectados en una misma familia. En este trabajo se describe un sujeto afectado que viene con su hija con una asimetría facial. Es importante el seguimiento de estos pacientes y su familia para realizar un diagnóstico que permita actuar precozmente.

  3. ANTARES: The HTR/VHTR project at Framatome ANP

    International Nuclear Information System (INIS)

    Gauthier, Jean-Claude; Brinkmann, Gerd; Copsey, Bernie; Lecomte, Michel

    2006-01-01

    Framatome ANP is developing a very high temperature reactor (VHTR), relying on its previous experience with high temperature reactor concepts, from its participation in the MODUL and the GT-MHR designs. While being a major actor in the nuclear reactor business with proven light water technology, AREVA wishes to be ready to meet the new challenges calling for small grid requirements, high temperature process heat and cogeneration. The Framatome ANP VHTR design for electricity production is based on an indirect cycle coupled to an 'off-the-shelf' combined cycle gas turbine. Although direct cycle HTRs are being promoted for their high efficiency, preliminary evaluations show that the Framatome ANP design efficiency is on par with a direct cycle while avoiding power generation system (PGS) developments and keeping the PGS contamination free. Moreover, the nuclear heat source of the indirect cycle could also be used to meet the heat supplies from a standard design for multiple applications

  4. Parry-Romberg Syndrome Associated with Localized Scleroderma

    Directory of Open Access Journals (Sweden)

    Jelena Maletic

    2010-06-01

    Full Text Available Parry-Romberg syndrome is a rare neurocutaneous disorder of unknown origin. It is characterized by progressive facial hemiatrophy and frequently overlaps with a condition known as linear scleroderma ‘en coup de sabre’. Neurological involvement is frequently described in these patients, including migraine, facial pain and epilepsy, which represent the commonest neurological conditions, sometimes associated with brain abnormalities ipsilaterally to the skin lesions. We present a case of Parry-Romberg syndrome with neurological involvement in a patient with diagnosed localized scleroderma (morphea.

  5. Parry-Romberg Syndrome Associated with Localized Scleroderma

    Science.gov (United States)

    Maletic, Jelena; Tsirka, Vassiliki; Ioannides, Panos; Karacostas, Dimitrios; Taskos, Nikolaos

    2010-01-01

    Parry-Romberg syndrome is a rare neurocutaneous disorder of unknown origin. It is characterized by progressive facial hemiatrophy and frequently overlaps with a condition known as linear scleroderma ‘en coup de sabre’. Neurological involvement is frequently described in these patients, including migraine, facial pain and epilepsy, which represent the commonest neurological conditions, sometimes associated with brain abnormalities ipsilaterally to the skin lesions. We present a case of Parry-Romberg syndrome with neurological involvement in a patient with diagnosed localized scleroderma (morphea). PMID:20671858

  6. Framatome experience in fuel assembly repair and reconstitution

    International Nuclear Information System (INIS)

    Leroy, G.

    1998-01-01

    Since 1985, FRAMATOME has build up extensive experience in the poolside replacement of fuel rods for repair or R and D purposes and the reconstitution of fuel assemblies (i.e. replacement of a damaged structure to enable reuse of the fuel rod bundle). This experience feedback enables FRAMATOME to improve in steps the technical process and the equipment used for the above operations in order to enhance their performance in terms of setup, flexibility, operating time and safety. In parallel, the fuel assembly and fuel rod designs have been modified to meet the same goals. The paper will describe: - the overall experience of FRAMATOME with UO 2 fuel as well as MOX fuel; the usual technical process used for fuel replacement and the corresponding equipment set; - the usual technical process for fuel assembly reconstitution and the corresponding equipment set. This process is rather unique since it takes profit of the specific FRAMATOME fuel assembly design with removable top and bottom nozzles, so that fuel rods insertion by pulling through in the new structure is similar to what is done in the manufacturing plant; - the usual inspections done on the fuel rods and/or the fuel assembly; - the design of the new reconstitution equipment (STAR) compared with the previous one as well as their comparative performance. The final section will be a description of the alternative reconstitution process and equipment used by FRAMATOME in reactors in which the process cannot be used for several reasons such as compatibility or administrative authorization. This process involves the pushing of fuel rods into the new structure, requiring further precautions. (author)

  7. Challenge nuclear power: portrait of the Framatome ANP

    International Nuclear Information System (INIS)

    Gueldner, R.

    2004-01-01

    The energy industry, which needs to meet the global energy and in particular the power demand of a world population that is continuously increasing - at present there are over 6.2 billion living on this Earth -, has for a few years now been undergoing fundamental change: In the wake of liberalization the course has been set for global competition. The companies involved in the field of nuclear energy, both plant operators and suppliers, have also been impacted by this change. Besides internal programs to cut costs and enhance capabilities, corporate mergers at the national and international level are also playing a significant role. Companies will thus be able to tackle future challenges, with good prospects for nuclear energy as a cost-effective, environmentally friendly form of power generation. In response to market trends the nuclear business activities of Framatome and Siemens were merged in early 2001 to form Framatome ANP, which now is an AREVA ad Siemens company. Framatome ANP is dedicated to the development and turnkey construction of nuclear power plants and research reactors as well as comprehensive engineering, electrical and I and C systems, plant services, modernization, fuel supplies and heavy component manufacture for many reactor designs, including those supplied by other vendors. The company is headquartered in Paris with regional subsidiaries in Germany and the U.S. AREVA has a 66 percent stake and Siemens a 34 percent stake in Framatome ANP. The German regional subsidiary Framatome ANP GmbH has its head offices in Erlangen. Its subsidiaries are Advanced Nuclear Fuels GmbH (ANF), which focuses on fuel production, and intelligeNDT Systems and Services GmbH and Co. KG, which performs nondestructive testing in the field of nuclear engineering and other high-tech branches of industry. (orig.)

  8. Nuclear energy in France. Respective part of CEA, EDF, FRAMATOME

    International Nuclear Information System (INIS)

    Graf, J.J.

    1976-01-01

    In France, the three actors on the nuclear stage are CEA, EDF, and industry. The CEA, important organism of research and development, represents the public power, counsels the Government for safety and constitutes the State interference by the indirect mean of budget which is assigned to it. The industry, FRAMATOME, is commissioned to build plants. EDF has vocation to provide electricity at the lower costs [fr

  9. Framatome, from the nuclear engineering office to the international group

    International Nuclear Information System (INIS)

    Lorin, Philippe

    1995-01-01

    A simple office of studies by its inceptions, Framatome became during 30 years an international and diversified group, a world nuclear leader, as designer-manufacturer, fuel supplier and servicing provider. It asserts itself also as a foreground actor in the industrial equipment and connections. This book not only presents an exciting and capital episode of the history of nuclear energy in France but it demonstrate also how an company with a little bit of chance, a lot of endeavour, a plenty of talent and a huge firmness succeeded in becoming an incontestable reference authority in its sector. Staking on technological choices, although different from the creeds inspiring the French decision makers, Framatome has obtained its first orders ahead other French companies, much more powerful and prestigious at the time. The impressive Framatome evolution is presented along six chapters entitled as follows: 1. Beginning of nuclear power; 2. Technological challenge; 3. Industrial challenge; 4. Sectorial challenge; 5. Management challenge; 6. Future. The following four witness' papers are inserted with in the main text: 1. Beginning of Framatome (by P. Boulin); 2. The difficult choice for the PWR system (by M. Boiteux); 3. Impossibly is not French (by A. Giraud); 4. A fabulous common effort (by M. Hug). The book is addressed to the public at large but aims also at the Company's personnel, both the people witnessing the Company's beginning and the newcomers who should know the social body they have chosen to join and to the effort of which they have to contribute with their inventiveness and dynamism

  10. Progress made by Framatome in neutron flux mapping technology

    International Nuclear Information System (INIS)

    Mourlevat, J.L.

    1999-01-01

    A fixed in-core system based on self-powered neutron detectors (SPNDs) could improve the power distribution measurement accuracy and hence improve core operating margin knowledge. For that purpose, Framatome has tested rhodium neutron detectors as fixed in-core sensors. Two such in-core strings were installed during tie summer of 1997 at Golfech Unit 2, for a three-year experiment. (author)

  11. Framatome, from the nuclear engineering office to the international group; Framatome, du bureau d'ingenierie nucleaire au groupe international

    Energy Technology Data Exchange (ETDEWEB)

    Lorin, Philippe [Direction de la Communication, FRAMATOME, Tour Framatome, 92084 Paris La Defense Cedex (France)

    1995-07-01

    A simple office of studies by its inceptions, Framatome became during 30 years an international and diversified group, a world nuclear leader, as designer-manufacturer, fuel supplier and servicing provider. It asserts itself also as a foreground actor in the industrial equipment and connections. This book not only presents an exciting and capital episode of the history of nuclear energy in France but it demonstrate also how an company with a little bit of chance, a lot of endeavour, a plenty of talent and a huge firmness succeeded in becoming an incontestable reference authority in its sector. Staking on technological choices, although different from the creeds inspiring the French decision makers, Framatome has obtained its first orders ahead other French companies, much more powerful and prestigious at the time. The impressive Framatome evolution is presented along six chapters entitled as follows: 1. Beginning of nuclear power; 2. Technological challenge; 3. Industrial challenge; 4. Sectorial challenge; 5. Management challenge; 6. Future. The following four witness' papers are inserted with in the main text: 1. Beginning of Framatome (by P. Boulin); 2. The difficult choice for the PWR system (by M. Boiteux); 3. Impossibly is not French (by A. Giraud); 4. A fabulous common effort (by M. Hug). The book is addressed to the public at large but aims also at the Company's personnel, both the people witnessing the Company's beginning and the newcomers who should know the social body they have chosen to join and to the effort of which they have to contribute with their inventiveness and dynamism.

  12. Framatome advanced nuclear power-benefits for our clients from the new company

    International Nuclear Information System (INIS)

    Weber, P.

    2001-01-01

    Framatome ANP (Advanced Nuclear Power) merges the complementary strengths of two global nuclear industry leaders Framatome and Siemens - offering clients the best technological solutions for safe, reliable and economical plant performance. With a combined workforce of 13,300 skilled individuals, Framatome ANP is now the nuclear industry's leading supplier. Serving as Original Equipment Manufacturer (OEM) for more than 90 reactors that provide about 30% of the world's total installed nuclear power capacity, our experienced resources remain focused on the local needs of individual clients, wherever in the world they may be. The Company main business used to be turnkey construction of complete Nuclear Power plants, BWR and PWR capabilities, heavy equipment manufacturing, comprehensive I and C capabilities, and also expertise and knowledge of VVER. Framatome ANP will benefit in all of its fields of activity of the experience gained through Framatome and Siemens' collaboration on the next generation reactor, the EPR, as well as on steam generators replacements and or modernization of VVER. Framatome ANP nuclear fuel designs for both PWR and BWR plants provide innovative features and world-leading performance. Framatome ANP is organized according a matrix organization with: - 4 Business Groups (Project and Engineering, Service, Nuclear Fuel, Mechanical Equipment) - 3 Regional Divisions (Framatome Advanced Nuclear Power S.A.S., France; Framatome Advanced Nuclear Power GmbH, Germany; Framatome Advanced Nuclear Power Inc., USA). By 30th January 2001 Siemens Nuclear Power GmbH, founded in 2000 as successor of the Nuclear Division of Siemens Power Generation Group (KWU), was renamed to Framatome Advanced Nuclear Power GmbH forming the German part of the world wide acting company. Over the past 40 years 23 nuclear power plants all around the world - not only pressurized and boiling water reactors, but also two heavy-watermoderated reactors have been designed, constructed and

  13. Presentation of the 1998 financial results of the Framatome group

    International Nuclear Information System (INIS)

    Vignon, D.

    1999-01-01

    This document makes a statement of the activity of the Framatome group during the year 1998. The activities of the group are shared into two main sectors of comparable size: the energy sector (nuclear fuels, nuclear realizations, nuclear services and industrial equipments) and the connectors engineering sector (electronics, electricity, automotive industry, interconnections and microelectronics). The financial results show an important growth of the connectors engineering sector while the energy sector remained satisfactory. Results are detailed by sector and activity: energy (realizations and nuclear equipments, nuclear services, nuclear fuels and industrial equipments), connectors engineering, and research and development activity of the group. (J.S.)

  14. NPI one year on [Framatome-Siemens common product

    International Nuclear Information System (INIS)

    Ruess, F.; Lebreton, G.

    1990-01-01

    Nuclear Power International (NPI), a joint subsidiary of Framatome and Siemens was established in April 1989 to coordinate the development and marketing of a common PWR technology for the world market. Both parent companies command well proven PWR technology and can rely on experience gained with over 100 000MWe of nuclear capacity in operation, under construction or on order. The technology from each is being offered through NPI until the joint PWR technology which is under development, becomes available. NPI's experience to date is reviewed. (author)

  15. Framatome technologies successfully performs SG re-sleeving at Kewaunee

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    Framatome Technologies teamed with ABB-CE (Connecticut) to remove previously installed sleeves from the Kewaunee nuclear power stations steam generator tubes and install new sleeves. Recent inspections indicated problems at the upper joint of many of the previous sleeves. The process involved removing most of the hydraulic expansion joint (HEJ) sleeve, expanding the sleeve remnant and the tube section at the upper joint, and installing a TIG-welded sleeve that bridges the problem portion of the tube that the HEJ sleeve covered

  16. Framatome ANP worldwide experience in ageing and plant life management

    International Nuclear Information System (INIS)

    Daeuwel, W.; Kastner, B.; Nopper, H.

    2004-01-01

    The deregulation of the power generation industry has resulted in increased competitive pressure and is forcing operators to improve plant operating economy while maintaining high levels of plant safety. A key factor to meet this challenge is to apply a comprehensive plant life management (PLIM) approach which addresses all relevant ageing and degradation mechanisms regarding the safety concept, plant components and documentation, plant personnel, consumables, operations management system and administrative controls. For this reason, Framatome ANP has developed an integrated PLIM concept focussing on the safety concept, plant components and documentation. Representative examples for plant wide analyses are described in the following. The results of the analyses support the plant owner for taking the strategic decisions, involved in plant life extension (PLEX). (orig.)

  17. Specification of water quality for the FRAMATOME PWR secondary circuit

    International Nuclear Information System (INIS)

    Nordmann, F.

    1980-03-01

    This paper describes the purpose, theory and scope of secondary system chemical specifications for FRAMATOME PWR nuclear power plants. All volatile treatment was chosen: controlling the feedwater pH by means of a volatile amine (ammonia, morpholine), and excluding oxygen by the addition of hydrazine. The pollutants are monitored at the steam generator drains by completely automatic measurements using simple and reliable techniques: pH measurement and a diagram of the cation conductivity versus sodium. An explanation is given of the monitoring techniques and to the effect of the various kinds of possible pollutant. A new concept is described, the annual quota expressed in day.microsiements.cm -1 which enables the amount of absorbed pollutants in the steam generator to be evaluated. The methods used for maintaining the desired chemical quality are dealt with [fr

  18. Components installation. Scheduling techniques applied at Framatome for the French nuclear program

    International Nuclear Information System (INIS)

    Cremese, G.

    1982-09-01

    The first scheduling objective is a timely delivery of heavy components manufactured by FRAMATOME factories: reactor vessel, steam generators and pressurizer. The second scheduling function is the preparation and updating of overall and detailed schedules for the coordination and follow-up of: design activities, progress at equipment suppliers, construction and erection activities of sub-contractors, test and start-up tasks by FRAMATOME and customer teams, and maintenance operations by FRAMATOME teams. I shall first describe the schedules for the contract first unit then show how the following units of the contract are scheduled in their turn

  19. Parry-Romberg syndrome (progressive hemifacial atrophy) with spasmodic dysphonia--a rare association.

    Science.gov (United States)

    Mugundhan, K; Selvakumar, C J; Gunasekaran, K; Thiruvarutchelvan, K; Sivakumar, S; Anguraj, M; Arun, S

    2014-04-01

    Parry-Romberg syndrome is a rare clinical entity characterised by progressive hemifacial atrophy with appearance of 'saber'. Various neurological and otorhinolaryngological disorders are associated with this syndrome. The association of Parry -Romberg syndrome with Spasmodic dysphonia has rarely been reported. A 37 year old female presented with progressive atrophy of tissues of left side of face for 10 years and change in voice for 1 year. On examination, wasting and atrophy of tissues including tongue was noted on left side of the face. ENT examination revealed adductor spasmodic dysphonia. We report the rare association of Parry -Romberg syndrome with spasmodic dysphonia.

  20. CLINICAL AND RADIOGRAPHIC FEATURES OF PARRY-ROMBERG SYNDROME

    Directory of Open Access Journals (Sweden)

    Mithula NAIR

    2017-10-01

    Full Text Available Parry-Romberg syndrome or progressive hemifacial atrophy is a craniofacial disorder characterized by slow and progressive atrophy, generally unilateral, of facial tissues including muscles, bones and skin. The coup de sabre is a clear line of demarcation seen between the normal and abnormal structures. The severity of the facial deformity is dependent on the age of onset of the disease. Cosmetic management is the only available treatment and has to be delayed until facial growth is completed. The present case report deals with a 43-year-old woman with progressive hemifacial atrophy which started from the age of 10 months. Despite almost complete involvement of the right paramedian area and the early age of onset, she had neither eye changes nor any dental malformations.

  1. Framatome recent developments and application on site in NDE of steam generator tubes

    International Nuclear Information System (INIS)

    Bieth, M.

    1986-01-01

    The increasing needs concerning the follow up and expertise of PWR steam generator (SG) tubing have led Framatome to develop a quick on-site intervention mobile unit, which could implement any current technique and equipment. Besides, Framatome has developed several non destructrive examination methods to solve the specific problems encountered in service on the SG tubes: profilometry of the SG tubes by eddy current. Inside and above the tube sheet, eddy current inspection of tube sleeving by ultrasonic testing and eddy current

  2. Framatome's experience in implementing and runnig RELAP5 MOD1

    Energy Technology Data Exchange (ETDEWEB)

    Truong, T.X.; Rousset, P.

    1984-12-01

    Implementation of RELAP MOD1 on Framatome's computer began in 1982, when we were working with the electrical power research institute on a safety and relief valve test program. It has been carried out in two stages: a first implementation on the CISI CYBER 740 computer; a transfer of files and a second on implemented our own CYBER 835 computer. The RELAP5 version currently implemented and used in Framatome is the cycle 19 standard version, no modification has been made yet, though some changes in data output files are intended.

  3. Globalization of the nuclear industry: Developing technology - Framatome ANP's experience

    International Nuclear Information System (INIS)

    Kaluzny, Y.; Dams, W.; Reynolds, R.

    2006-01-01

    Full text: In the last 15 years, Framatome ANP has moved from being a purely national player to being a global market leader. This is due to a series of successful mergers and acquisitions, including the acquisition of the nonmilitary nuclear activity of Babcock and Wilcox in the late 1980s and, more recently, the merger with Siemens-KWU's nuclear activities. Integration presented a number of challenges. There were undeniable cultural differences, reorganization was required to bring the business under control and a number of activities, such as finance, sales, R and D, marketing, engineering and manufacturing, and information systems had to be rationalized and integrated. The key factors that contributed to the success of this integration included a management team that was clearly committed to the success of the merger and the quick and clear definition of the strategy, vision and values of the new company, which had to be effectively communicated. A global organization which was not simply a group of three companies, each working in its own corner, was quickly established and multiregional task forces were appointed to identify possible synergies and propose how they could be put into practice. One of the key issues is R and D, which will be discussed as an example of what has been achieved. This activity is essential when preparing the future of the company as a whole, and one of the major challenges that had to be met was to find the best way of making use of all the skills available in it. A special multiregional, multi-activity organization has identified the existing skills and potential synergies in each of the technical areas and core businesses. A global R and D management process has been put in place under the strong leadership of the corporate R and D function. This process involves all the business units worldwide and has made it possible to set R and D objectives and identify the action to be taken in line with the group's strategic objectives

  4. Science version 2: the most recent capabilities of the Framatome 3-D nuclear code package

    International Nuclear Information System (INIS)

    Girieud, P.; Daudin, L.; Garat, C.; Marotte, P.; Tarle, S.

    2001-01-01

    The Framatome nuclear code package SCIENCE developed in the 1990's has been fully operational for nuclear design since 1997. Results obtained using the package demonstrate the high accuracy of its physical models. Nevertheless, since the first release of the SCIENCE package, continuous improvement work has been carried out at Framatome, which leads today to Version 2 of the package. The intensive use of the package by Framatome teams, for example, while performing reload calculations and the associated core follow, is a permanent opportunity to point out any trend or scattering in the results, even the smaller they are. Thus the main objective of improvements was to take advantage of the progress in computer performances in using more sophisticated calculation schemes conducting to more accurate results. Besides the implementation of more accurate physical models, SCIENCE Version 2 also exploits developments conducted in other fields, mainly for transient calculations using 3-D kinetics or coupling with open-channel core thermal-hydraulics and the plant simulator. These developments allow Framatome to perform accident analyses with advanced methodologies using the SCIENCE package. (author)

  5. Current and anticipated uses of the CATHARE code at EDF and FRAMATOME

    Energy Technology Data Exchange (ETDEWEB)

    Gandrille, J.L.; Vacher, J.L.; Poizat, F.

    1997-07-01

    This paper presents current industrial applications of the CATHARE code in the fields of Safety Studies and Simulators where the code is intensively used by FRAMATOME, EDF and CEA, the development partners of CATHARE. Future needs in these fields are also recapitulated.

  6. Current and anticipated uses of the CATHARE code at EDF and FRAMATOME

    International Nuclear Information System (INIS)

    Gandrille, J.L.; Vacher, J.L.; Poizat, F.

    1997-01-01

    This paper presents current industrial applications of the CATHARE code in the fields of Safety Studies and Simulators where the code is intensively used by FRAMATOME, EDF and CEA, the development partners of CATHARE. Future needs in these fields are also recapitulated

  7. Application and licensing requirements of the Framatome ANP RLBLOCA methodology

    International Nuclear Information System (INIS)

    Martin, R.P.; Dunn, B.M.

    2004-01-01

    The Framatome ANP Realistic Large-Break LOCA methodology (FANP RLBLOCA) is an analysis approach approved by the US NRC for supporting the licensing basis of 3- and 4-loop Westinghouse PWRs and CE 2x4 PWRs. It was developed consistent with the NRC's Code Scaling, Applicability, and Uncertainty (CSAU) methodology for performing best-estimate large-break LOCAs. The CSAU methodology consists of three key elements with the second and third element addressing uncertainty identification and application. Unique to the CSAU methodology is the use of engineering judgment and the Process Identification and Ranking Table (PIRT) defined in the first element to lay the groundwork for achieving the ultimate goal of quantifying the total uncertainty in predicted measures of interest associated with the large-break LOCA. It is the PIRT that not only directs the methodology development, but also directs the methodology review. While the FANP RLBLOCA methodology was generically approved, a plant-specific application is customized in two ways addressing how the unique plant characterization 1) is translated to code input and 2) relates to the unique methodology licensing requirements. Related to the former, plants are required by 10 CFR 50.36 to define a technical specification limiting condition for operation based on the following criteria: 1. Installed instrumentation that is used in the control room to detect, and indicate, a significant abnormal degradation of the reactor coolant pressure boundary. 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a

  8. Framatome and the maintenance of nuclear power plant. An approach of reactivity in the reliability of interventions

    International Nuclear Information System (INIS)

    Hertzog, D.

    1997-01-01

    This text gives a commentary on the dispositions taken by Framatome to come with the operators face to the new stakes in their operations of maintenance and particularly, the reduction of costs and dosimetry of intervention. (N.C.)

  9. Sizewell B cycle 5 core design with Framatome ANP's CASCADE-3D and British Energy's PANTHER

    International Nuclear Information System (INIS)

    Attale, F.; Koegl, J.; Knight, M.; Bryce, P.

    2001-01-01

    Sizewell B Cycle 5 is the first cycle, after 4 cycles with BNFL fuel, with a reload consisting of Framatome ANP HTP (high thermal performance) fuel assemblies. The impact of this fuel vendor change on the Nuclear Design area is that, according to British energy's (BE) practice, the Framatome ANP's nuclear design code system CASCADE-3D is used for the majority of the cycle specific safety case calculations. However, other parts of the safety submission (e.g. 3D transient analyses) are made by using the BE code PANTHER. Before using in parallel two different code systems for reload core licensing extensive comparisons of applied methodologies and obtained results were required to ensure an acceptable level of agreement. (orig.)

  10. The nuclear power challenge: the role of the new Framatome ANP

    International Nuclear Information System (INIS)

    Gueldner, R.

    2001-01-01

    Nuclear power will contribute a decisive share to the future electricity supply. It meets sustainability requirements in terms of continuity of supply, resource conservation and climate protection, and recent developments in the United States are revealing clearcut economic benefits. In response to trends on the market, the merger of the nuclear activities of Framatome and Siemens to Framatome ANP early this year has created a global company. It is active in all nuclear markets, such as construction projects, upgrading, nuclear fuels and service. Three regional companies in France, Germany, and USA offer services worldwide of the four corporate divisions, i.e. Projects and Engineering, Nuclear Service, Nuclear Fuel, and Mechanical Components. The German regional company, Framatome ANP GmbH, has its head office in Erlangen and, through its subsidiaries Advanced Nuclear Fuels GmbH (ANF), has expertise in fuel fabrication and, through intelligeNDT Systems and Services GmbH and Co. KG, in non-destructive testing in nuclear technology and HiTec industries. (orig.) [de

  11. Síndrome de Parry-Romberg: Visión de su tratamiento Parry-Romberg's syndrome: View of its treatment

    Directory of Open Access Journals (Sweden)

    María Elena González Espíndola

    2005-08-01

    Full Text Available El síndrome de Parry-Romberg o atrofia hemifacial progresiva, enfermedad de Romberg o también denominada trofoneurosis facial, fue descrito por Parry en 1925 y por Romberg en 1946. Se considera una malformación craneofacial poco frecuente en la práctica diaria y en edades tempranas, ya que es una enfermedad progresiva que suele empezar en la adolescencia. Se caracteriza por presentar la atrofia del tejido graso (celular subcutáneo, piel, músculos faciales y en algunos casos pueden estar afectados también los huesos y cartílagos de un lado de la cara; su evolución dura de 2 a 12 años, pero puede detenerse en cualquier momento. Su diagnóstico temprano, así como un adecuado plan de tratamiento, resultan importantes y se deben ejecutar por un equipo multidisciplinario para lograr un buen desarrollo funcional y psicológico, así como el establecimiento de una buena relación de oclusión que mejore la armonía facial, que eleve la calidad de vida de estos pacientes. El objetivo del presente trabajo es mostrar un caso que ha sido tratado por el equipo multidisciplinario de Cirugía Maxilofacial del Hospital Pediátrico de Centro Habana.Parry-Romberg's syndrome or progressive hemifacial atrophy, Romberg's disease, or facial trophoneurosis as it is also called, was described by Parry in 1925 and by Romberg in 1926. It is considered an uncommon craniofacial malformation in the daily practice and at early ages, since it is a progressive disease that usually appears in adolescence. It is characterized by the atrophy of the fatty tissue (cellular subcutaneous, skin, facial muscles and in some cases the bones and cartilages of a side of the face may be affected. Its evolution lasts from 2 to 12 years, but it may stop at any time. Its early diagnosis, as well as an adequate treatment plan are important and they should be made by a multidisciplinary team to achieve a good functional and psychological development and the establishment of a good

  12. Meaning and proscription in formal logic variations on the propositional logic of William T. Parry

    CERN Document Server

    Ferguson, Thomas Macaulay

    2017-01-01

    This book aids in the rehabilitation of the wrongfully deprecated work of William Parry, and is the only full-length investigation into Parry-type propositional logics. A central tenet of the monograph is that the sheer diversity of the contexts in which the mereological analogy emerges – its effervescence with respect to fields ranging from metaphysics to computer programming – provides compelling evidence that the study of logics of analytic implication can be instrumental in identifying connections between topics that would otherwise remain hidden. More concretely, the book identifies and discusses a host of cases in which analytic implication can play an important role in revealing distinct problems to be facets of a larger, cross-disciplinary problem. It introduces an element of constancy and cohesion that has previously been absent in a regrettably fractured field, shoring up those who are sympathetic to the worth of mereological analogy. Moreover, it generates new interest in the field by illustrat...

  13. Parry-Romberg syndrome: findings in advanced magnetic resonance imaging sequences - case report

    Energy Technology Data Exchange (ETDEWEB)

    Paula, Rafael Alfenas de; Ribeiro, Bruno Niemeyer de Freitas, E-mail: alfenas85@gmail.com [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro, RJ (Brazil). Hospital Universitario Clementino Fraga Filho; Bahia, Paulo Roberto Valle [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro, RJ (Brazil). Dept. de radiologia; Ribeiro, Renato Niemeyer de Freitas [Hospital de Clinica de Jacarepagua, Rio de Janeiro, RJ (Brazil); Carvalho, Lais Balbi de [Universidade Presidente Antonio Carlos (Unipac), Juiz de Fora, MG (Brazil)

    2014-05-15

    Parry-Romberg syndrome is a rare disease characterized by progressive hemifacial atrophy associated with other systemic changes, including neurological symptoms. Currently, there are few studies exploring the utilization of advanced magnetic resonance sequences in the investigation of this disease. The authors report the case of a 45-year-old patient and describe the findings at structural magnetic resonance imaging and at advanced sequences, correlating them with pathophysiological data. (author)

  14. A case report of Parry Romberg Syndrome initially presenting as periodontitis

    OpenAIRE

    Taylor, Greig; Culshaw, Shauna; Armas, Jose; Savarrio, Lee; Goodall, Christine

    2017-01-01

    Parry Romberg Syndrome (PRS) is a rare disorder of progressive hemifacial atrophy, involving soft tissues, fat and occasionally bone. It can co-exist with presentations of Morphea. We describe an unusual case of persistent periodontal and alveolar destruction associated with PRS. A 56-year-old African female initially presented with persistent periodontal destruction, which showed minimal response to conventional periodontal treatment. After non-surgical treatment, surgical debridement follow...

  15. Cell-Assisted Lipotransfer for the Treatment of Parry-Romberg Syndrome

    OpenAIRE

    Yanko Castro-Govea; Oscar De La Garza-Pineda; Jorge Lara-Arias; Hernán Chacón-Martínez; Gabriel Mecott-Rivera; Abel Salazar-Lozano; Everardo Valdes-Flores

    2012-01-01

    Progressive facial hemiatrophy, also known as Parry-Romberg syndrome, is a progressive and self-limited deformation of the subcutaneous tissue volume on one side of the face that creates craniofacial asymmetry. We present the case of a patient with a five-year history of progressive right facial hemiatrophy, who underwent facial volumetric restoration using cell-assisted lipotransfer (CAL), which consists of an autologous fat graft enriched with adipose-derived stem cells (ASCs) extracted fro...

  16. Parry-Romberg syndrome in a pediatric patient. A case report.

    Directory of Open Access Journals (Sweden)

    Edgar Reyes

    2015-07-01

    Full Text Available The Parry-Romberg syndrome is a rare degenerative disease of unknown etiology that has dental implications. It is characterized by a progressive hemifacial atrophy that appears in the early stages of life. It causes aesthetic, functional and psychological alterations, and has social implications for the patient. There is no definitive treatment for the Parry-Romberg syndrome. Systemic and immune alterations produce oral and maxillofacial manifestations, which need to be managed by specialized dental professionals. The aim of this paper is to do a literature review of the Parry-Romberg syndrome and describe the oral and clinical characteristics of this condition in a 12-year-old male pediatric patient, who had a history of neurological disorders and facial asymmetry on the left side. Dentists require an adequate knowledge of the clinical and dental characteristics of this syndrome. With early diagnosis and appropriate surgical and orthodontic treatment at an early age, they can improve the quality of life of patients and minimize invasive long-term effects.

  17. Framatome ANP GmbH concept of Plant Life Management (PLIM)

    International Nuclear Information System (INIS)

    Daeuwel, W.; Biemann, W.; Danisch, R.; Kastner, B.; Meyer, W.; Nopper, H.; Waas, U.; Warnken, L.

    2002-01-01

    The deregulation of the power generation industry has resulted in increased competitive pressure and is forcing operators to improve plant operating economy while maintaining high levels of plant safety. A key factor to meeting this challenge is to apply a comprehensive plant life management (PLIM) approach which addresses all relevant ageing and degradation mechanisms regarding the safety concept, plant component structures and documentation, plant personnel, consumables, operations management system and administrative controls. For this reason, Framatome ANP GmbH has developed an integrated PLIM concept applicable for both new and operating plants and focusing on the safety concept, plant component structures and documentation. (orig.)

  18. National Physics Conference. Paper Abstracts

    International Nuclear Information System (INIS)

    Marinela Dumitriu, Editorial Coordination.

    1995-01-01

    This book contains the abstracts of the proceedings of the annual Romanian Physics Conference organized by Romanian Physics Society. The conference was held on November 30 to December 2, 1995 in the city of Baia Mare. It was organized in the following nine sections: 1 - Astrophysics, Particle Physics, Nuclear Physics, Molecular and Atomic Physics; 2 - Plasma Physics; 3 - Biophysics; 4 - Technical Physics; 5 - Theoretical Physics; 6 -The Physics of Energy; 7 - The Physics of Environment 8 - Solid State Physics; 9 - Optical and Quantum Electronics. The full texts can be obtained on request from the Romanian Physical Society or directly from authors

  19. Cell-assisted lipotransfer for the treatment of parry-romberg syndrome.

    Science.gov (United States)

    Castro-Govea, Yanko; De La Garza-Pineda, Oscar; Lara-Arias, Jorge; Chacón-Martínez, Hernán; Mecott-Rivera, Gabriel; Salazar-Lozano, Abel; Valdes-Flores, Everardo

    2012-11-01

    Progressive facial hemiatrophy, also known as Parry-Romberg syndrome, is a progressive and self-limited deformation of the subcutaneous tissue volume on one side of the face that creates craniofacial asymmetry. We present the case of a patient with a five-year history of progressive right facial hemiatrophy, who underwent facial volumetric restoration using cell-assisted lipotransfer (CAL), which consists of an autologous fat graft enriched with adipose-derived stem cells (ASCs) extracted from the same patient. ASCs have the capacity to differentiate into adipocytes. They also promote angiogenesis, release angiogenic growth factors, and some can survive as stem cells. The use of autologous fat as a filler in soft tissue atrophy has been satisfactory in patients with mild and moderate Parry-Romberg syndrome. Currently, CAL has showed promising results in the long term by decreasing the rate of fat reabsorption. The permanence and stability of the graft in all the injected areas has showed that autologous fat grafts enriched with stem cells could be a promising technique for the correction of defects caused by this syndrome.

  20. Cell-Assisted Lipotransfer for the Treatment of Parry-Romberg Syndrome

    Directory of Open Access Journals (Sweden)

    Yanko Castro-Govea

    2012-11-01

    Full Text Available Progressive facial hemiatrophy, also known as Parry-Romberg syndrome, is a progressive and self-limited deformation of the subcutaneous tissue volume on one side of the face that creates craniofacial asymmetry. We present the case of a patient with a five-year history of progressive right facial hemiatrophy, who underwent facial volumetric restoration using cell-assisted lipotransfer (CAL, which consists of an autologous fat graft enriched with adipose-derived stem cells (ASCs extracted from the same patient. ASCs have the capacity to differentiate into adipocytes. They also promote angiogenesis, release angiogenic growth factors, and some can survive as stem cells. The use of autologous fat as a filler in soft tissue atrophy has been satisfactory in patients with mild and moderate Parry-Romberg syndrome. Currently, CAL has showed promising results in the long term by decreasing the rate of fat reabsorption. The permanence and stability of the graft in all the injected areas has showed that autologous fat grafts enriched with stem cells could be a promising technique for the correction of defects caused by this syndrome.

  1. Cell-Assisted Lipotransfer for the Treatment of Parry-Romberg Syndrome

    Directory of Open Access Journals (Sweden)

    Yanko Castro-Govea

    2012-11-01

    Full Text Available Progressive facial hemiatrophy, also known as Parry-Romberg syndrome, is a progressive andself-limited deformation of the subcutaneous tissue volume on one side of the face thatcreates craniofacial asymmetry. We present the case of a patient with a five-year historyof progressive right facial hemiatrophy, who underwent facial volumetric restoration usingcell-assisted lipotransfer (CAL, which consists of an autologous fat graft enriched withadipose-derived stem cells (ASCs extracted from the same patient. ASCs have the capacityto differentiate into adipocytes. They also promote angiogenesis, release angiogenic growthfactors, and some can survive as stem cells. The use of autologous fat as a filler in soft tissueatrophy has been satisfactory in patients with mild and moderate Parry-Romberg syndrome.Currently, CAL has showed promising results in the long term by decreasing the rate of fatreabsorption. The permanence and stability of the graft in all the injected areas has showedthat autologous fat grafts enriched with stem cells could be a promising technique for thecorrection of defects caused by this syndrome.

  2. Fuel-cladding interaction. Framatome CEA experiment on pencils preirradiated in nuclear power plants

    International Nuclear Information System (INIS)

    Atabek, Rosemarie; Vignesoult, Nicole

    1979-01-01

    The study of the fuel-cladding interaction is the subject of an important joint research programme between Framatome and the CEA. Tests are performed either on whole fuel rods, not exceeding two metres in length, from BR3 or the CAP (PRISCA experiment) or on fuel rods refabricated in hot cells from fuel rods of power reactors (FABRICE experiment). The first results reveal the two mechanical and chemical aspects of the interaction phenomenon: the permissible power surge of the fuel elements passes through a minimum for an integrated fast dose (E>1MeV) of around 1.5x10 21 n/cm 2 ; a study made with the electronic microprobe and the scanning microscope shows that the Te, I and Cs fission products are the corrosive agents of the cladding [fr

  3. GEDEON: A joint venture between research (CEA and CNRS) and industry (EDF and FRAMATOME)

    CERN Document Server

    Schapira, J P

    1999-01-01

    Nuclear waste partitioning and transmutation (P and T) are considered in France as an official line of research, in accordance with the Law of December 30, 1991 concerning research in the field of long lived and highly active nuclear waste. A research group called GEDEON (GEstion des DEchets par des Options Nouvelles) has been set up between CEA, CNRS, EDF and FRAMATOME with the aim to carry out basic research related to the use of accelerator driven subcritical systems (ADS) and of thorium as an option to reduce the waste long term impacts. In the partners agreement of GEDEON, the following subjects have been identified: spallation physics, nuclear data, subcritical neutronic studies, materials, thorium, system and scenario studies. The organization as well as the scientific program and activities of GEDEON are presented.

  4. Framatome-ANP extended burnup experience and views on LWR fuels

    International Nuclear Information System (INIS)

    Esteve, B.; Gueldner, R.; Hoffman, R.; Watteau, M.

    2002-01-01

    In every sense of the term, nuclear fuel forms the core of nuclear power plants (NPPs). Although there are many equipment items important for their safety function or for their participation in NPP availability, the fuel, in essence renewable, is one of the key elements which have to be acted upon if utilities are to be helped to fulfil their mission of generating power in total safety and supplying the kWh to their customers at the best price. Nuclear fuel is also the core business of the Framatome-ANP Fuel Business Group: pooling and rationalising the available skills - technical, cultural and human - supplied by each of the partners forms a challenge which it is up to each and every one to meet in a cooperative spirit. This paper gives an outline of the company's extended burnup experience, current R and D, and its plans for the future. (author)

  5. Replacement of heavy components of the Main Primary System (MPS). Recent innovations made by Framatome ANP

    International Nuclear Information System (INIS)

    Chanussot, J.M.; Thevenet, R.

    2006-01-01

    The replacement of heavy components is the result of widespread stress corrosion of Inconel 600 (and alloys 82/182) in the primary system. Following the corrosion of steam generator tubes, which led to the first steam generator replacement (SGR) operations, work has begun on reactor vessel head replacements (RVHR) and pressurizer replacements, pending treatment of the dissimilar butt welds (DBW). The replacement of sections of the Main Primary System is one way of optimizing plant lifetime besides preventing stress corrosion in primary components and combating phenomena as thermal fatigue or certain metallurgical weaknesses. The increase in the number of major operations carried out in the reactor building on PWR and BWR reactor geometries has called for major technical innovations. AREVA, has over the past twenty years carried out more than forty SGRs throughout the world, including the supply of 115 steam generators of all types. This equates to over 60% of all SGR operations performed in Europe and the USA. Today, most SGR operations are performed in the USA, though some still continue in Europe and Asia. Operations have been planned until 2015. The first RVHR operations were carried out in France in 1993, and have been widespread in Europe since 1996 (Spain and Belgium), and in the USA since 2002 (Davis Besse). Since 1993 AREVA, through its subsidiaries Framatome ANP, Jeumont SA and SGT, has performed 72 RVHRs, i.e. most of those carried out in Europe and the USA. Today, RVHR operations take place throughout the world and have been planned until 2014. The first pressurizer replacement took place in the fall of 2005 in Saint Lucie, USA. Others are to follow (Fort Calhoun, Millestone). A significant number of partial or complete pressurizer replacements are now being scheduled. Special focus must be given to this new operation, as a decision is required between the following types of replacements, taking into account the number of pressurizer heaters and the

  6. Deep Orbital Sub-Q Hyaluronic Acid Filler Injection for Enophthalmic Sighted Eyes in Parry-Romberg Syndrome.

    Science.gov (United States)

    Feldman, Ilan; Sheptulin, Vladimir A; Grusha, Yaroslav O; Malhotra, Raman

    2018-01-23

    The authors present a consecutive series of deep orbital Sub-Q injections to treat enophthalmic sighted eyes in Parry-Romberg syndrome patients. Retrospective, interventional case series in 2 centers. Data were collected on patient demographics, Parry-Romberg syndrome onset age, previous orbital and eyelid surgeries, diplopia, ocular movement restriction before and after the injection, number of injections, interval between injections, indication for any top-up or dissolution of filler, and any other complications. In all cases, the hyaluronic acid gel used was Restylane Sub-Q + Lidocaine. A total of 8 injections on 3 patients with Parry-Romberg syndrome, and significant enophthalmos is reported. All injections were with deep orbital Sub-Q filler. All patients were females, aged 32, 24, and 52 years old while their symptoms started at 15, 16, and 30 years old, respectively. None had orbital surgery prior to the injection. Follow up period was 2, 7, and 5 years respectively. All presented a significant enophthalmos of 4 mm which reduced to 1 mm after the injection, and duration effect was 18, 24, and 20 months, respectively. We observed a significant improvement in enophthalmos, lagophthalmos, exposure keratopathy, and even ocular motility. Lagophthalmos improved from 1, 4, and 7 mm to 0, 1, and 2 mm post injection. Ocular motility improved with no onset of new limitation or diplopia. Lower eyelid retraction increased in 1 patient after orbital injection. No other complications occurred. Deep orbital Sub-Q hyaluronic injection for treatment of enophthalmos in Parry-Romberg syndrome is an useful option in sighted eyes.

  7. Framatome experience and programs in relation to guide tube support pin cracking

    International Nuclear Information System (INIS)

    Benhamou, C.; Poitrenaud, P.

    1989-01-01

    Guide tube support pins installed in the upper internals of pressurized water reactors (PWR) have failed by stress corrosion cracking (SCC). Typical pin crack locations are in the first thread area, shank-to-shoulder transition, and at the end of the leaves. The support pins were made of Inconel X-750 with a solution treatment between 885 degree C (1625 degree F) and 1150 degree C (2100 degree F), followed by a single or double aging, depending on the material supplier. EDF and Framatome initiated an extensive program to address the concern for the potential of support pin cracking in 21 operating units. Short-term actions identified the cause of cracking as a combination of inherent high design stress and a material susceptible to stress corrosion cracking. Long-range objectives are to determine the relation between metallurgy and SCC resistance and to decrease the operating stress. Second-generation design improvements to increase SCC resistance included a revised heat treatment of solution annealing at 1093 degree C (2000 degree F) followed by aging at 704 degree C (1300 degree F), and use of a parabolic radius in the shank/shoulder area, and decreasing the installation torque. Third generation changes included an improved torquing procedure, polishing of crack-sensitive areas, and tighter dimensional control. Fourth-generation pin modifications required the use of Inconel X-750 water quenched from the solution-annealing temperature to improve resistance to SCC with thread rolling after aging. Stress corrosion cracking tests of Inconel X-750, 718, and A286 in a PWR environment were performed. Smooth tensile data on Inconel X-750 with the second-generation heat treatment allowed a life prediction of 80,000 hours or 11 years for a stress level about yield strength. The effect of grain size, grain boundary phases, and precipitate morphology on resistance to stress corrosion cracking were also evaluated

  8. Numerical simulation of residual stress in piping components at Framatome-ANP

    International Nuclear Information System (INIS)

    Gilies, P.; Franco, C.; Cipiere, M.-F.; Ould, P.

    2005-01-01

    Numerous manufacturing processes induce residual stresses and distortions in piping components and associated welds: quenching of cast pipings, machining and welding. In Pressurized Water Reactors, most of the components have a large thickness for sustaining pressure and distortions are a minor source of concern. This is not the case for residual stresses which may have a strong influence on several type of damage such as fatigue, corrosion, brittle fracture. In low toughness components, residual stress fields may contribute to ductile tearing initiation. These potential damages are mitigated after welding by stress relief heat treatment, which is applied in a systematic manner to ferritic components of the primary system in nuclear reactors. This treatment is not applied on austenitic piping for which the heat treatment temperature is limited due to the risk of sensitization and residual stresses are difficult to eliminate completely. Since on site measurements are costly and difficult to perform, numerical simulation appears to be an attractive tool for estimating residual stress distributions. Framatome-ANP is working on modelling manufacturing processes with that purpose in mind. This paper presents three kinds of applications illustrating efforts on welding, quenching and machining simulation. First a comparison is shown between computations and measurements of residual stress induced by welding of a dissimilar weld metal junction. Then numerical simulations of quenching of a cast stainless steel nozzle are presented. Finally quenching followed by machining and grinding of this cast component are considered in a full simulation of the manufacturing process. Computed distortions and residual stresses are compared with experimental measurements at different stages of the manufacturing process. (authors)

  9. Within AREVA, FRAMATOME ANP and its worldwide experience with PWR and BWR fuels

    International Nuclear Information System (INIS)

    Watteau, Michel; Esteve, Bernard; Giese, Ulrich; Matheson, John

    2002-01-01

    Faced with obvious energy procurement security needs and the increasing concern about global warming, many countries are making a lucid analysis of their energy situation and reconsidering the multiple assets of nuclear energy. After the European Commission's Green Paper evaluation which was endorsed by the European Parliament, the United States gave a strong signal to the whole world by deciding to extent the operating life time of its existing NPPs and by envisioning the construction of new ones. In Asia, here in Korea, and in Japan, the People's Republic of China, Taiwan, large-scale nuclear power plant programs are being pursued. It was in this context, with the aim of ever-greater competitiveness, that the AREVA group was conceived. The aim is for all our skills to have a higher profile on the international markets, so that we are in a stronger position to develop a leadership in our two main high tech sectors of interconnect - electronics and nuclear. In the nuclear sector, the pooling of the Cogema and Framatome ANP forces is enabling AREVA to offer a comprehensive service package ranging from uranium mining to decommissioning, encompassing the design and construction of plants and their fuel; AREVA's experience is grounded in unequalled know-how. Further, with the CEA, a multidisciplinary research organization in charge of anticipating the emerging technologies, as a close partner, AREVA has a unique strategic vision. With this set-up, AREVA has the financial resources it needs to forge the alliances necessary for its development, so that it can best confront international competition and meet the requirements of its customers world-wide

  10. Integration of process-oriented control with systematic inspection in FRAMATOME-FBFC fuel manufacturing

    International Nuclear Information System (INIS)

    Kopff, G.

    2000-01-01

    The classical approach to quality control is essentially based on final inspection of the product conducted through a qualified process. The main drawback of this approach lies in the separation and , therefore, in the low feedback between manufacturing and quality control, leading to a very static quality system. As a remedy, the modern approach to quality management focuses on the need for continuous improvement through process-oriented quality control. In the classical approach, high reliability of nuclear fuel and high quality level of the main characteristics are assumed to be attained, at the manufacturing step, through 100% inspection of the product, generally with automated inspection equipment. Such a 100% final inspection is not appropriate to obtain a homogeneous product with minimum variability, and cannot be a substitute for the SPC tools (Statistical Process Control) which are rightly designed with this aim. On the other hand, SPC methods, which detect process changes and are used to keep the process u nder control , leading to the optimal distribution of the quality characteristics, do not protect against non systematic or local disturbances, at low frequency. Only systematic control is capable of detecting local quality troubles. In fact, both approaches, SPC and systematic inspection, are complementary , because they are remedies for distinct causes of process and product changes. The term 'statistical' in the expression 'SPC' refers less to the sampling techniques than to the control of global distribution parameters of product or process variables (generally location and dispersion parameters). The successive integration levels of process control methods with systematic inspection are described and illustrated by examples from FRAMATOME-FBFC fuel manufacturing, from the simple control chart for checking the performance stability of automated inspection equipment to the global process control system including systematic inspection. This kind of

  11. Parry Romberg Syndrome: The Socially Appalling Yet Less Acknowledged Diagnosis: Case Series and Literature Review

    Directory of Open Access Journals (Sweden)

    Ali Zohair Nomani

    2018-01-01

    Full Text Available The dilemma of facing a facial cosmetic issue at a young age is the most troublesome symptom hampering social well-being. Beginning in the teen ages and progressing to variable extents, Parry Romberg Syndrome (PRS leads to facial asymmetry in the form of hemiatrophy secondary to loss of subcutaneous tissues, often fat but sometimes the underlying muscles and bones. It is indistinctly associated with seizure disorders at times or with other neurological sequelae. The first case was an 18 year old Pakistani male who presented with progressive wasting of the left side of the face for the past two and a half years. The second case was an 18-year-old Pakistani girl who presented to the neurology OPD with primary complaints of a seizure disorder for 3 years. In addition, she had progressive subtle asymmetry of her face. Over the course of time, a faint curvilinear grooved line showed up towards the right side of her forehead reaching on to her head up to the vertex. She also had hair loss ipsilateral to the line. The presentation of above cases depicts that although some features of PRS like facial asymmetry is characteristic, the presentation of a patient primarily with seizures should ideally include a thorough search for a secondary cause or of possible associations so that prognosis can be defined and appropriate interventions planned.

  12. Measures introduced for improving the resistance against degradation by corrosion of steam generators in Framatome designed PWR'S

    International Nuclear Information System (INIS)

    Smith, K.; Slama, G.; Sort, M.

    1986-01-01

    The operational experience of FRAMATOME plants now extends to more than 8 years with a total of 35 PWR plants commissioned and in operation for periods of time varying from 1 to 7.5 years. Overall, the 1.600 Steam Generator (S.G.) tubes are significantly free from secondary side corrosion problems. On the primary side, several instances of stress corrosion cracking have occurred, this cracking is principally at the transitions of the mechanical roll in 1.600 Mill Annealed tubing. This paper reviews the design and material changes which have been, or are being, introduced to improve the resistance to corrosion. In addition, the application is described of the FRAMATOME shot peening surface treatment to the primary side tube surface of the mechanically rolled expansions. The objective of this treatment is to increase the resistance to primary side stress corrosion cracking by appreciable reduction of the surface tensile stresses. The steam generators of several operational plants have been successfully treated by this technique

  13. Application of risk-informed methods to in-service piping inspection in Framatome type nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Jin Hoi; Lee, Jeong Seok; Yun, Eun Sub

    2014-01-01

    The Pressurized water reactor owners group (PWROG) developed and applied a risk-informed in-service inspection (RI-ISI) program, as an alternative to the existing ASME Section XI sampling inspection method. The RI-ISI programs enhance overall safety by focusing inspections of piping at high safety significance (HSS) locations where failure mechanisms are likely to be present. Additionally, the RI-ISI program can reduce nondestructive evaluation (NDE) exams, man-rem exposure for inspectors, and inspection time, among other benefits. The RI-ISI method of in-service piping inspection was applied to 3 units (KSNPs: Korea standard nuclear power plants) and is being deployed to the other units. In this paper, the results of RI-ISI for a Framatome type (France CPI) nuclear power plant are presented. It was concluded that application of RI-ISI to the plant could enhance and maintain plant safety, as well as provide the benefits of greater reliability.

  14. Framatome-ANP France UO2 fuel fabrication. Criticality safety analysis in the light of the JCO accident

    International Nuclear Information System (INIS)

    Doucet, M.; Zheng, S.; Mouton, J.; Porte, R.

    2003-01-01

    In France the 1999' Tokai Mura criticality accident in Japan had a big impact on the nuclear fuel manufacturing facility community. Moreover this accident led to a large public discussion about all the nuclear facilities. The French Safety Authorities made strong requirements to the industrials to revisit completely their safety analysis files mainly those concerning nuclear fuels treatments. The FRAMATOME-ANP production of its French low enriched (5 w/o) UO2 fuel fabrication plant (FBFC/Romans) exceeds 1000 metric tons a year. Special attention was given to the emergency evacuation plan that should be followed in case of a criticality accident. If a criticality accident happens, site internal and external radioprotection requirements need to have an emergency evacuation plan showing the different routes where the absorbed doses will be as low as possible for people. The French Safety Authorities require also an update of the old based neutron source term accounting for state of the art methodology. UO2 blenders units contain a large amount of dry powder strictly controlled by moderation; a hypothetical water leakage inside one of these apparatus is simulated by increasing the water content of the powder. The resulted reactivity insertion is performed by several static calculations. The French IRSN/CEA CRISTAL codes are used to perform these static calculations. The kinetic criticality code POWDER simulates the power excursion versus time and determines the consequent total energy source term. MNCP4B performs the source term propagation (including neutrons and gamma) used to determine the isodose curves needed to define the emergency evacuation plant. This paper deals with the approach FRAMATOME-ANP has taken to assess Safety Authorities demands using the more up to date calculation tools and methodology. (author)

  15. Mild Cognitive Impairment as a single sign of brain hemiatrophy in patient with Localized Scleroderma and Parry-Romberg Syndrome.

    Science.gov (United States)

    Klimiec, Elzbieta; Klimkowicz-Mrowiec, Aleksandra

    2016-01-01

    Neurologic involvement is well recognized in Systemic Scleroderma and increasingly reported in Localized Scleroderma. MRI brain abnormalities are often associated with symptoms such as seizures or headaches. In some cases they may be clinically silent. We describe a 23 years old female with head, trunk and limbs scleroderma who developed Parry-Romberg Syndrome. Brain MRI showed ipsilateral temporal lobe atrophy without any prominent neurologic symptoms. Neuropsychological examination revealed Mild Cognitive Impairment. During the 7 years of follow up we have noticed progression of face atrophy but no progression of brain atrophy. Cognitive functions have been stable. This case highlight that major MRI brain abnormalities in LS may occur with only subtle clinical manifestation such as Mild Cognitive Impairment. Copyright © 2016 Polish Neurological Society. Published by Elsevier Urban & Partner Sp. z o.o. All rights reserved.

  16. Sizewell B cycle 5 core design with Framatome ANP's CASCADE-3D and British Energy's PANTHER

    Energy Technology Data Exchange (ETDEWEB)

    Attale, F.; Koegl, J. [Framatome ANP GmbH, Nuclear Fuel Cycle, Erlangen (Germany); Knight, M.; Bryce, P. [British Energy, Nuclear Technology Branch, Gloucester (United Kingdom)

    2001-07-01

    Sizewell B Cycle 5 is the first cycle, after 4 cycles with BNFL fuel, with a reload consisting of Framatome ANP HTP (high thermal performance) fuel assemblies. The impact of this fuel vendor change on the Nuclear Design area is that, according to British energy's (BE) practice, the Framatome ANP's nuclear design code system CASCADE-3D is used for the majority of the cycle specific safety case calculations. However, other parts of the safety submission (e.g. 3D transient analyses) are made by using the BE code PANTHER. Before using in parallel two different code systems for reload core licensing extensive comparisons of applied methodologies and obtained results were required to ensure an acceptable level of agreement. (orig.)

  17. Three steam generator replacement projects in 1995: Consortium Siemens Framatome is well prepared to contribute its experience to the SGR at the Krsko NPP

    International Nuclear Information System (INIS)

    Holz, R.; Clavier, G.

    1996-01-01

    Since the companies Siemens AG and Framatome S.A. joined their experience and efforts in the field of steam generators replacements and formed a consortium in 1991, the following projects were performed in 1995: Ringhals 3, Tihange 3 and Asco 2. Further projects will follow in 1996, i.e., Doel 4 and Asco 2. Currently, this European consortium is bidding for the contract to replace the steam generators at the Krsko NPP and hopes to be awarded in 1996. An overview of the way the Consortium Siemens and Framatome approaches SG replacement projects is given based on the projects performed in 1995. Various aspects of project planning, management, licensing, personnel qualification and techniques used on site will be discussed. (author)

  18. Radiation parameter monitoring of the irradiation channel of the RVS-3 loop during the FRAMATOME 1 experiment in 1996/1997

    International Nuclear Information System (INIS)

    Hrabanek, J.

    1997-11-01

    The monitoring system serving to measure the neutron fluence rate with self-powered rhodium detectors and the radiative heating on iron with calorimeters is highlighted. The sensor signal transmission routes and instrumentation for their measurement and recording are described. The method of observed data evaluation is characterized and the results of this processing are given for the FRAMATOME 1 experiment, which was carried out on the RVS-3 loop of the LVR-15 reactor in 1996-1997. (author)

  19. The effects of radiations on materials for core internals of PWRs: EDF-CEA-Framatome joint research programme

    International Nuclear Information System (INIS)

    Mathan, N. de; Buisine, D.; Goltrant, O.; Dubuisson, P.; Scott, P.; Deydier, D.; Trenty, A.

    1998-01-01

    The effects of neutron irradiation on materials for the core internals of PWRs (austenitic stainless steels) are potentially a significant economic and regulatory concern for EDF. The maintenance strategy for EDF relies primarily on in-service inspection, safety analysis and characterization of materials irradiated in-service. In addition, to anticipate likely future behaviour of highly irradiated materials, EDF has initiated, in collaboration with CEA and Framatome, a large R and D programme designed to (i) evaluate the effects of neutron irradiation on mechanical properties and stress corrosion cracking sensitivity (IASCC), and (ii) identify possible replacement materials. The programme, currently in progress, involves mechanical tests (tensile, fracture toughness, irradiation creep), stress corrosion cracking tests (in flux and out of flux) and metallurgical examinations. The test materials are being irradiated in several experimental reactors in France and Russia up to PWR-related end of life doses (∼ 80 dpa) at several PWR-relevant irradiation temperatures (300-400 deg. C). The presentation will describe the objectives and early results of this ongoing R and D programme. (author)

  20. Framatome's ''SAF'' engineering simulator: a first step toward defining the engineer's simulation tool of the year 2000

    International Nuclear Information System (INIS)

    Constantieux, T.

    1986-01-01

    Among the techniques available to engineers today, computerized simulation is taking on an ever-growing importance. The ''SAF'' simulator, designed by Framatome for the use of its own engineers, has been in service since 1985. The SAF simulator provides continuous assistance to the engineer, from the preliminary design stage to the precise definition of operating procedures, including safety analysis and sizing computations. For the engineer of the year 2000, who will be used to dialoguing with the computer from a very young age, the SAF represents a first step toward a comprehensive simulation tool. Interactive and thus ''alive'', the SAF combines both extensive programming and data processing capabilities. Its simulation domain can still be considerably extended. Highly modular and equipped with easy-to-use compilers, the SAF can be readily modified and reconfigured by the user, to enable testing new models or new systems, in the complex and detailed environment of the nuclear unit being analysed. Employing the advanced computer programs used in project design, the SAF simulator is a particularly high-performance tool for simulating and analysing complex accident scenarios, including multiple equipment failures and possible operator errors, which may extend to complete draining of the reactor vessel and the release of radioactive fission products within the containment structure

  1. CNS imaging findings associated with Parry-Romberg syndrome and en coup de sabre: correlation to dermatologic and neurologic abnormalities.

    Science.gov (United States)

    Doolittle, Derrick A; Lehman, Vance T; Schwartz, Kara M; Wong-Kisiel, Lily C; Lehman, Julia S; Tollefson, Megha M

    2015-01-01

    Parry-Romberg syndrome (PRS) and en coup de sabre (ECS) are variants of morphea. Although numerous findings on central nervous system (CNS) imaging of PRS and ECS have been reported, the spectrum and frequency of CNS imaging findings and relation to cutaneous and neurologic abnormalities have not been fully characterized. We retrospectively reviewed patients younger than 50 years at our institution over a 16-year interval who had clinical diagnosis of PRS and ECS by a skin or facial subspecialist. Two neuroradiologists evaluated available imaging and characterized CNS imaging findings. Eighty-eight patients with PRS or ECS were identified (62 women [70.4 %]; mean age 28.8 years). Of the 43 patients with CNS imaging, 19 (44 %) had abnormal findings. The only finding in 1 of these 19 patients was lateral ventricle asymmetry; of the other 18, findings were bilateral in 11 (61 %), ipsilateral to the side of facial involvement in 6 (33 %), and contralateral in 1 (6 %). Sixteen patients had serial imaging examinations over an average of 632 days; 13 (81 %) had stable imaging findings, and 3 (19 %) had change over time. Of six patients with progressive cutaneous findings, five (83 %) had stable imaging findings over time. Among the 23 patients with clinical neurologic abnormality and imaging, 12 (52 %) had abnormal imaging findings. All seven patients with seizures (100 %) had abnormal imaging studies. In PRS and ECS, imaging findings often are bilateral and often do not progress, regardless of cutaneous disease activity. Findings are inconsistently associated with clinical abnormalities.

  2. Resource utilisation by deep-sea megabenthos in the Canadian High Arctic (Baffin Bay and Parry Channel)

    Science.gov (United States)

    Bourgeois, Solveig; Witte, Ursula; Harrison, Ailish M.; Makela, Anni; Kazanidis, Georgios; Archambault, Philippe

    2016-04-01

    Ongoing climate change in the Arctic is causing drastic alteration of the Arctic marine ecosystem functioning, such as shifts in patterns of primary production, and modifying the present tight pelagic-benthic coupling. Subsequently benthic communities, which rely upon organic matter produced in the top layers of the Ocean, will also be affected by these changes. The benthic megafaunal communities play a significant role in ecological processes and ecosystem functioning (i.e. organic matter recycling, bioturbation, food source for the higher trophic levels…). Yet, information is scarce regarding the main food sources for dominant benthic organisms, and therefore the impact of the ongoing changes is difficult to assess. The goal of this study is to investigate the preferential feeding of different carbon sources by megabenthic organisms in the Canadian High Arctic and to identify environmental drivers which explain the observed trends. In summer 2013, benthic megafauna was collected at 9 stations spread along latitudinal (58 to 81°N) and longitudinal (62 to 114°W) transects in the Baffin Bay and Parry Channel, respectively. Carbon and nitrogen bulk stable isotope analyses (δ13C and δ15N) were performed on several species divided into groups according to their feeding type. This study highlights distinct trends in δ13C values of benthic organisms suggesting the importance of both phytoplankton and ice algae as carbon sources for megafauna in the Canadian High Arctic. The importance of physical and biological parameters as drivers of food web structure will be furthermore discussed.

  3. Pilot-Scale Demonstration of In-Situ Chemical Oxidation Involving Chlorinated Volatile Organic Compounds - Design and Deployment Guidelines (Parris Island, SC, U.S. Marine Corp Recruit Depot, Site 45 Pilot Study)

    Science.gov (United States)

    A pilot-scale in situ chemical oxidation (ISCO) demonstration, involving subsurface injections of sodium permanganate (NaMnO4), was performed at the US Marine Corp Recruit Depot (MCRD), site 45 (Parris Island (PI), SC). The ground water was originally contaminated with perchloroe...

  4. Parry-Romberg (Syndrome)

    Science.gov (United States)

    ... is affected. In mild cases, the disorder usually causes no disability other than cosmetic effects. Clinical Trials Throughout the U.S. and Worldwide NINDS Clinical Trials Related Information Patient Organizations Epilepsy Foundation March of Dimes See all related organizations ...

  5. Clonal variation in gas exchange and freezing tolerance development of interior spruce (Picea glauca (Moench) Voss x P. engelmannii Parry ex Engelm.) during autumn acclimation

    Energy Technology Data Exchange (ETDEWEB)

    Fan, Shihe; Grossnickle, S.C. [British Columbia Research Corp., Vancouver, BC (Canada). Forest Biotechnology Centre

    1999-08-01

    Variation in physiological response during autumn acclimation was investigated in somatic seedlings of 10 interior spruce (Picea glauca (Moench) Voss x P. engelmannii Parry ex Engelm.) clones from five full-sib families. Experiments were conducted on 2-yr-old seedlings through simulation in a growth chamber. Throughout the experimental period, gas-exchange parameters (net photosynthesis, stomatal conductance to water vapour and instantaneous water-use efficiency) were measured weekly and freezing tolerance was determined five times. Results showed that as seedlings acclimated to decreasing air temperature and photoperiod, stomatal conductance decreased linearly, photosynthesis was unchanged until air temperature and photoperiod were below 10 deg C and 11 h, respectively, water-use efficiency nearly doubled and freezing tolerance increased in a curvilinear fashion. There was significant between- and within-family clonal variation in all of these physiological parameters. 47 refs, 7 figs

  6. The chronic encephalopathy of Parry Romberg Syndrome and en coupe de sabre with a 31-year-history in a West Indian woman: clinical, immunologic and neuroimaging abnormalities

    Directory of Open Access Journals (Sweden)

    Karan Seegobin

    2016-09-01

    Full Text Available We describe a case of Parry Romberg syndrome/ en coupe de sabre in a woman whose disease started as seizures at age 8 but was diagnosed at the age 39. During these 31 years she got married, completed a first degree at university, had two successful pregnancies and has been gainfully employed. The features of generalized tonic-clonic seizures, autoimmune abnormalities, ocular abnormalities, morphea en coup de sabre and brain imaging abnormalities were present. Areas of parietal lobe cerebral calcification were encountered on the computed tomographic scan and bilateral periventricular white matter changes on the magnetic resonance imaging with frontal, temporal and parietal lobe brain atrophy ipsilateral to the facial hemiatrophy. Clinical, immunologic and neuroradiological abnormalities are discussed. In some cases, this illness can run a benign and stable course.

  7. Determinación de HLA en pacientes con Síndrome de Parry Romberg atendidos en el Servicio de Cirugía Plástica y Reconstructiva del Hospital General "Dr. Manuel Gea González"

    Directory of Open Access Journals (Sweden)

    Damián Palafox

    Full Text Available Introducción y Objetivo. El síndrome de Parry Romberg se caracteriza por atrofia hemifacial progresiva; afecta piel y tejidos blandos y en ocasiones provoca también atrofia de músculos, cartílago y estructuras óseas subyacentes. Su diagnóstico diferencial incluye: esclerodermia generalizada, morfea y síndrome de CREST. Las alteraciones en piel se asocian con variantes alélicas (polimórficas del sistema HLA (antígeno leucocitario humano. La esclerodermia se ha asociado con HLA DR11, el CREST con DR1 y DR3, en tanto que la morfea no parece asociarse a genes del HLA en población mexicana. El propósito de este trabajo es explorar la posibilidad de asociación del síndrome de Parry Romberg con algún alelo del sistema HLA con el fin de entender el mecanismo fisiopatogénico y el probable papel de la etnicidad en la prevalencia e incidencia de esta enfermedad en individuos mestizos mexicanos. Material y método. Estudiamos 24 pacientes con Parry Romberg, de la consulta externa de Cirugía Plástica y Reconstructiva del Hospital General "Dr. Manuel Gea González" de la Ciudad de México. El diagnóstico se basó en hallazgos clínicos, imagenología e histopatología de las lesiones dérmicas. Establecimos las frecuencias génicas y haplotípicas de los antígenos del sistema HLA en los 24 pacientes (48 haplotipos. El estudio incluyó los loci HLA A, B, DR, DQ. Comparamos los resultados con las frecuencias presentes en un grupo de 99 controles mestizos mexicanos sin antecedentes de enfermedades autoinmunes y/o metabólicas. Analizamos las diferencias en las frecuencias génicas mediante estadística no paramétrica que incluyó prueba de Chi cuadrado y exacta de Fisher, además de determinación de RM (razón de momios e intervalos de confianza de 95%. Resultados. Encontramos en los pacientes con Parry Romberg aumento significativo del HLA DRB1*16 (frecuencia génica: 14% en SPR vs 1% en normales. p=0.002, OR: 6.5, IC 95%: 1.9-21.7 y

  8. Lack of IgG antibody seropositivity to Borrelia burgdorferi in patients with Parry-Romberg syndrome and linear morphea en coup de sabre in Mexico.

    Science.gov (United States)

    Gutiérrez-Gómez, Claudia; Godínez-Hana, Ana L; García-Hernández, Marisela; Suárez-Roa, María de Lourdes; Toussaint-Caire, Sonia; Vega-Memije, Elisa; Gutiérrez-Mendoza, Daniela; Pérez-Dosal, Marcia; Medina-De la Garza, Carlos E

    2014-08-01

    Progressive hemifacial atrophy or Parry-Romberg Syndrome (PRS) is a rare, acquired, progressive dysplasia of subcutaneous tissue and bone characterized by unilateral facial involvement. Its etiology is unknown, but theories about its pathogenesis include infectious, degenerative, autoimmune, and traumatic causes among others. The causal relationship of PRS and linear morphea en coup de sabre (LMCS) with Borrelia burgdorferi infection remains controversial. Our goal was to serologically determine anti-B. burgdorferi antibodies in patients diagnosed with PRS and LMCS to establish a possible association as a causative agent. We conducted a serology study with patients belonging to a group of 21 individuals diagnosed with PRS, six with LMCS, and 21 matched controls. Anti-Borrelia IgG antibodies were determined by ELISA. A descriptive statistical analysis and Fischer's exact test were done. In serological tests, only two cases had borderline values and were further analyzed by Western blot with non-confirmatory results. For both the PRS and LMCS group, the association test was not significant, suggesting a lack of association between PRS or LMCS and the presence of anti-Borrelia antibodies. In Mexico there are no previous studies on Borrelia infection and its relationship between PRS or LMCS. Our result showed a lack of association of either clinical entities with anti-Borrelia-antibodies. Former reports of this association may suggest coincidental findings without causal relationship. © 2014 The International Society of Dermatology.

  9. Autologous fat graft and bone marrow-derived mesenchymal stem cells assisted fat graft for treatment of Parry-Romberg syndrome.

    Science.gov (United States)

    Jianhui, Zhao; Chenggang, Yi; Binglun, Lu; Yan, Han; Li, Yang; Xianjie, Ma; Yingjun, Su; Shuzhong, Guo

    2014-09-01

    Progressive facial hemiatrophy, also called Parry-Romberg syndrome (PRS), is characterized by slowly progressive atrophy of one side of the face and primarily involves the subcutaneous tissue and fat. The restoration of facial contour and symmetry in patients affected by PRS still remains a challenge clinically. Fat graft is a promising treatment but has some shortcomings, such as unpredictability and low rate of graft survival due to partial necrosis. To obviate these disadvantages, fat graft assisted by bone marrow-derived mesenchymal stem cells (BMSCs) was used to treat PRS patients and the outcome was evaluated in comparison with the conventional treatment by autologous fat graft. Autologous fat graft was harvested by tumescent liposuction. Bone marrow-derived mesenchymal stem cells were then isolated by human Lymphocytes Separation Medium through density gradient centrifugation. Twenty-six patients were treated with autologous fat graft only (group A), whereas 10 other patients were treated with BMSC-assisted fat graft (group B). The Coleman technique was applied in all fat graft injections. The follow-up period was 6 to 12 months in this study, In group A, satisfactory outcome judged by symmetrical appearances was obtained with 1 injection in 12 patients, 2 injections in 8 patients, and 3 injections in 4 patients. However, the result of 1 patient was not satisfactory and 1 patient was overcorrected. In group B, 10 patients obtained satisfactory outcomes and almost reached symmetry by 1 injection. No complications (infection, hematoma, or subcutaneous mass) were observed. The results suggest that BMSC-assisted fat graft is effective and safe for soft tissue augmentation and may be superior to conventional lipoinjection. Additional study is necessary to further evaluate the efficacy of this technique.

  10. Determinación de HLA en pacientes con Síndrome de Parry Romberg atendidos en el Servicio de Cirugía Plástica y Reconstructiva del Hospital General "Dr. Manuel Gea González"

    OpenAIRE

    Palafox, Damián; Gutiérrez-Gómez, Claudia; Granados, Julio; Barquera, Rodrigo; Ortega-Hernández, Esteban; Hernández-Zaragoza, Diana I.; Pérez-Dosal, Marcia; Pacheco-Ubaldo, Hanna R.; Lona-Sánchez, Abraham

    2016-01-01

    Introducción y Objetivo. El síndrome de Parry Romberg se caracteriza por atrofia hemifacial progresiva; afecta piel y tejidos blandos y en ocasiones provoca también atrofia de músculos, cartílago y estructuras óseas subyacentes. Su diagnóstico diferencial incluye: esclerodermia generalizada, morfea y síndrome de CREST. Las alteraciones en piel se asocian con variantes alélicas (polimórficas) del sistema HLA (antígeno leucocitario humano). La esclerodermia se ha asociado con HLA DR11, el CREST...

  11. Clinical application of human adipose tissue-derived mesenchymal stem cells in progressive hemifacial atrophy (Parry-Romberg disease) with microfat grafting techniques using 3-dimensional computed tomography and 3-dimensional camera.

    Science.gov (United States)

    Koh, Kyung Suk; Oh, Tae Suk; Kim, Hoon; Chung, In Wook; Lee, Kang Woo; Lee, Hyo Bo; Park, Eun Jung; Jung, Jae Seob; Shin, Il Seob; Ra, Jeong Chan; Choi, Jong Woo

    2012-09-01

    Parry-Romberg disease is a rare condition that results in progressive hemifacial atrophy, involving the skin, dermis, subcutaneous fat, muscle, and, finally, cartilage and bone. Patients have been treated with dermofat or fat grafts or by microvascular free flap transfer. We hypothesized that adipose-derived stem cells (ASCs) may improve the results of microfat grafting through enhancing angiogenesis. We evaluated the utility of ASC in microfat grafting of patients with Parry-Romberg disease by measuring the change in the hemifacial volumes after injection of ASCs with microfat grafts or microfat grafts alone. In April 2008, this investigation was approved by the Korean Food and Drug Administration and the institutional review board of the Asan Medical Center (Seoul, Korea) that monitor investigator-initiated trials. Between May 2008 and January 2009, 10 volunteers with Parry-Romberg disease (5 men and 5 women; mean age, 28 y) were recruited; 5 received ASC and microfat grafts and 5 received microfat grafts only. The mean follow-up period was 15 months. Adipose-derived stem cells were obtained from abdominal fat by liposuction and were cultured for 2 weeks. On day 14, patients were injected with fat grafts alone or plus (in the test group) 1 × 10 ASCs. Patients were evaluated postoperatively using a 3-dimensional camera and 3-dimensional CT scans, and grafted fat volumes were objectively calculated. Successful outcomes were evident in all 5 patients receiving microfat grafts and ASCs, and the survival of grafted fat was better than in patients receiving microfat grafts alone. Before surgery, the mean difference between ipsilateral and contralateral hemiface volume in patients receiving microfat grafts and ASCs was 21.71 mL decreasing to 4.47 mL after surgery. Overall resorption in this ASC group was 20.59%. The mean preoperative difference in hemiface volume in those receiving microfat grafts alone was 8.32 mL decreasing to 3.89 mL after surgery. Overall

  12. Abelian properties of Parry words

    Czech Academy of Sciences Publication Activity Database

    Turek, Ondřej

    2015-01-01

    Roč. 566, FEB (2015), s. 26-38 ISSN 0304-3975 R&D Projects: GA MŠk LG14004 Institutional support: RVO:61389005 Keywords : Abelian complexity * finite automata * recurrent word * balance function Subject RIV: BE - Theoretical Physics Impact factor: 0.643, year: 2015

  13. Total mandibular subapical osteotomy and Le Fort I osteotomy using piezosurgery and computer-aided designed and manufactured surgical splints: a favorable combination of three techniques in the management of severe mouth asymmetry in Parry-Romberg syndrome.

    Science.gov (United States)

    Scolozzi, Paolo; Herzog, Georges

    2014-05-01

    Although its pathogenesis remains obscure, Parry-Romberg syndrome (PRS) has been associated with the linear scleroderma en coup de sabre. PRS is characterized by unilateral facial atrophy of the skin, subcutaneous tissue, muscles, and bones with at least 1 dermatome supplied by the trigeminal nerve. Facial asymmetry represents the most common sequela and can involve the soft tissues, craniomaxillofacial skeleton, dentoalveolar area, and temporomandibular joint. Although orthognathic procedures have been reported for skeletal reconstruction, treatment of facial asymmetry has been directed to augmentation of the soft tissue volume on the atrophic side using different recontouring or volumetric augmentation techniques. Total mandibular subapical osteotomy has been used in the management of dentofacial deformities, such as open bite and mandibular dentoalveolar retrusion or protrusion associated with an imbalance between the lower lip and the chin. Management of orthognathic procedures has been improved by the recent introduction of stereolithographic surgical splints using computer-aided design (CAD) and computer-aided manufacturing (CAM) technology and piezosurgery. Piezosurgery has increased security during surgery, especially for delicate procedures associated with a high risk of nerve injury. The present report describes a combined total mandibular subapical osteotomy and Le Fort I osteotomy using piezosurgery and surgical splints fabricated using CAD and CAM for the correction of severe mouth asymmetry related to vertical dentoalveolar disharmony in a patient with PRS. Copyright © 2014 American Association of Oral and Maxillofacial Surgeons. Published by Elsevier Inc. All rights reserved.

  14. Lipoinfiltrado enriquecido con células madre en población pediátrica con síndrome de Parry-Romberg: actualización

    Directory of Open Access Journals (Sweden)

    E. Arana

    2013-12-01

    Full Text Available La Hemiatrofia Facial Progresiva, comúnmente conocida como Síndrome de Parry-Romberg (SPR, es una enfermedad idiopática, progresiva y autolimitada, que afecta de manera variable y unilateral en la mayor parte de los casos a la piel, tejido celular subcutáneo, grasa, músculo y, con menor frecuencia, a las estructuras osteocartilaginosas faciales produciendo asimetría craneofacial. En el manejo quirúrgico del SPR en estadios medios y moderados se ha empleado desde hace años la infiltración de injertos grasos; sin embargo, se trataba de una técnica de resultados impredecibles dada su tendencia a la reabsorción. Gracias a los avances en biología molecular se ampliaron nuestros horizontes ante la posibilidad de usar las células madre propias del tejido adiposo con el fin de asegurar la viabilidad y permanencia del implante graso a través del tiempo. En este trabajo presentamos nuestra experiencia de los últimos 3 años en el tratamiento del SPR en pacientes pediátricos, consiguiendo la restauración de la volumetría y la simetría faciales mediante el uso de injertos grasos enriquecidos con células madre extraídas del propio paciente y en el mismo acto quirúrgico.

  15. Framatome ANP outage optimization support solutions

    International Nuclear Information System (INIS)

    Bombail, Jean Paul

    2003-01-01

    Over the last several years, leading plant operators have demonstrated that availability factors can be improved while safety and reliability can be enhanced on a long-term basis and operating costs reduced. Outage optimization is the new term being used to describe these long-term initiatives through which a variety of measures aimed at shortening scheduled plant outages have been developed and successfully implemented by these leaders working with their service providers who were introducing new technologies and process improvements. Following the leaders, all operators now have ambitious outage optimization plans and the median and average outage duration are decreasing world-wide. Future objectives are even more stringent and must include plant upgrades and component replacements being performed for life extension of plant operation. Outage optimization covers a broad range of activities from modifications of plant systems to faster cool down rates to human behavior improvements. It has been proven to reduce costs, avoid unplanned outages and thus support plant availability and help to ensure the utility's competitive position in the marketplace

  16. Technology transfer and localization: A Framatome perspective

    International Nuclear Information System (INIS)

    Preneuf, R. de

    2000-01-01

    Localization and technology transfer have been important factors influencing the decision-making process in countries embarking on a nuclear power programme. It seems natural that relationships between donors and recipients of technology, beginning with sub-contracting, should evolve towards technology transfers and cooperation on an equal footing. France was both a receiver and a donor of technology transfer in the area of nuclear power. This paper describes the French experience in technology transfer and the lesson learned therefrom. (author)

  17. France: Thrust and parry over nuclear risks

    International Nuclear Information System (INIS)

    Balter, M.

    1997-01-01

    Claims about the health risks posed by nuclear-power installations are always controversial, but nowhere more so than in France, where some 75% of the nation's electricity is generated from nuclear energy. So, it was no surprise that publication of a study by two French epidemiologists earlier this month claiming to show a link between cases of childhood leukemia and the nuclear-waste reprocessing plant at La Hague on the Normandy coast sparked fireworks in the French press. Several French epidemiologists sharply criticized the study's methodology and conclusions. Their attacks have now drawn an unusual response from the British Medical Journal (BMJ), in which the paper appeared

  18. International symposium on macromolecules (SIM), Rio de Janeiro, Brazil, 26--31 July 1974. Contributed papers: abstracts and discussion

    Energy Technology Data Exchange (ETDEWEB)

    Mano, E B; Tabak, D; Tarvin, R F; von Dietrich, C P; de Souza Gomes, A [eds.

    1974-07-01

    Abstracts of the papers presented are compiled. The Symposium considered four topics: polymer chemistry, polymer physical chemistry, polymer technology, and biopolymers. A companion volume contains the discussions relating to various presentations. (JSR)

  19. Selected Papers & Abstracts from the Annual International Conference of the Association for Experiential Education (32nd, Norfolk, Virginia, November 4-7, 2004)

    Science.gov (United States)

    Roberts, Nina S., Ed.; Galloway, Shayne, Ed.

    2005-01-01

    In an effort to persist with providing members--and interested others--with the content of workshops from the 32nd Annual Conference held in Norfolk, the Association for Experiential Education (AEE) has decided to develop a hybrid publication that has materialized in two parts. Part I includes 11 papers: (1) Adventure Coaching (Doug Gray); (2)…

  20. Modern systems of instrumentation and control of FRAMATOME ANP: instrument to the future

    International Nuclear Information System (INIS)

    Kraft, U.; Richter, S.

    2003-01-01

    Based on the applications of the TELEPERM XS and XP platforms, experience with these operating and safety I and C system in nuclear plants both in Europe and abroad is described here. To quote information from customers in the nuclear field, the positive results can be confirmed by specific nuclear plants from all over the world, so that with the application of these new digitial platforms alternatives exist for quasi all types of nuclear plant. The TELEPERM XS and XP system families can be easily applied for modernization projects for existing I and C systems, resulting in a high degree of availability and economic advantages, in accordance with modern technology. In order to demonstrate to the readers of this article the status of development of the TELEPERM XS safety I and C system, further important information regarding the general characteristics, to the architecture of the hardware and the engineering process as well as the development of the software is given. In this way one can obtain a general idea of the TELEPERM XS system as well as an outlook combined with the successful application of this modern safety I and C system for nuclear plants world wide. (Author)

  1. Genetic conservation and management of the Californian endemic, Torrey Pine (Pinus torreyana Parry)

    Science.gov (United States)

    Jill A. Hamilton; Jessica W. Wright; F. Thomas. Ledig

    2017-01-01

    Torrey pine (Pinus torreyana) is one of the rarest pine species in the world. Restricted to one mainland and one island population in California, Torrey pine is a species of conservation concern under threat due to low population sizes, lack of genetic variation, and environmental stochasticity. Previous research points to a lack of within population variation that is...

  2. Hemiatrofia facial progressiva (doença de Parry-Romberg: relato de dois casos associados a trigeminalgia e câimbras Progressive facial hemiatrophy (Parry-Romberg disease: report of two cases associated with trigeminal neuralgia and cramps

    Directory of Open Access Journals (Sweden)

    José Correia de Farias Brito

    1997-09-01

    Full Text Available Os autores relatam dois casos de hemiatrofia facial progressiva (HFP, ambos do sexo feminino, associados à hiperexcitabilidade neuromuscular, representada por dores neurálgicas e espasmos musculares (câimbras numa hemiface. Uma das pacientes (Caso 1, com 41 anos de idade, começou a notar a presença de atrofia no lado esquerdo da face, ao término da primeira década de vida. Nos últimos 3 meses, achando-se a doença estacionaria, a paciente passou a sofrer crises álgicas típicas de neuralgia do trigêmeo, cujo alívio só foi possível através de tratamento neurocirúrgico. A outra paciente (Caso 2, com 33 anos de idade, tem uma história de doença de 8 anos de duração, quando notou o desenvolvimento de atrofia ao nível da bochecha direita. Há cerca de 2 meses observou redução do diâmetro da coxa direita, o que sugere achar-se a doença em plena atividade. Freqüentemente, é acometida de espasmos dolorosos (câimbras na região submandibular direita, provocados, algumas vezes, pela abertura da boca. Uma possível relação entre os fenômenos de irritação neuromuscular e a HFP é discutida.The authors report two cases of progressive facial hemiatrophy (PFH associated with cranial nerves hyperexcitability. One of them (Case 1, a 41-year-old-woman noticed a slight atrophy on the left side of her face at age of ten. For the last three months, she has been suffering from fits of neuralgic pains on the left side of her face which have not ceased by drug treatment. In view of this, a surgery procedure was planned for the patient. The other patient (Case 2, a 33-year-old-woman has a 8 year history which started with cutaneous abnormalities (white and dark spots. Two years later she observed that her right cheek and right thigh had got a mild atrophy. Frequently, she has been complaining of cramps in the mandibular region which are precipitated, sometimes, by opening the mouth. A probable relation between neural excitability and PHF is discussed.

  3. Development of integrated management practices for the control of Chinese tallow on Parris Island Marine Corps Recruit Depot

    Science.gov (United States)

    Lauren S. Pile; G. Geoff Wang; Patricia A. Layton

    2015-01-01

    Chinese tallow [Triadica sebifera (L.) Small] is an aggressive, fast-growing, highly adaptable invasive tree of the southeastern United States coastal region. Since its introduction in the early 1800s, Chinese tallow has become a serious threat to native grassland and forest communities from mid-coastal North Carolina to Northern Florida and West to Central Texas

  4. Progress report of Applied Physics Division. 1 October 1980 - 30 June 1981. Acting Division Chief - Dr. J. Parry

    International Nuclear Information System (INIS)

    2004-01-01

    In September 1980, the Commission approved a reorganization of Physics Division, Engineering Research Division and Instrumentation and Control Division to form two new research divisions to be known as Applied Physics Division and Nuclear Technology Division. The Applied Physics Division will be responsible for applied science programs, particularly those concerned with nuclear techniques. The Division is organized as four sections with the following responsibilities: (1) Nuclear Applications and Energy Studies Section. Program includes studies in nuclear physics, nuclear applications, ion implantation and neutron scattering. (2) Semiconductor and Radiation Physics Section. Studies in semiconductor radiation detectors, radiation standards and laser applications. (3) Electronic Systems Section. This includes systems analysis, digital systems, instrument design, project instrumentation and instrument maintenance. (4) Fusion Physics Section. This covers work carried out by staff currently attached to university groups (author)

  5. Progress report of Physics Division. 1 October 1979 - 30 September 1980. Acting Division Chief - Dr. J. Parry

    International Nuclear Information System (INIS)

    2004-01-01

    The work of the Division concentrated on topics reported in the previous Progress Report with one additional project, namely, the application of ion beam techniques and laser annealing to the production of photovoltaic devices. The MOATA reactor and 3 MeV accelerator operated for Divisional projects and for other work, including collaborative projects supported by the Australian Institute of Nuclear Science and Engineering. Staff were seconded to the Reactors Department (New Reactor Study) and to universities (plasma physics and fusion program). Results obtained on four main themes (reactor calculations, neutron physics, nuclear applications and plasma physics) are reported in the following sections (author)

  6. 76 FR 62631 - Archers Creek, Ribbon Creek, and Broad River; U.S. Marine Corps Recruit Depot, Parris Island, SC...

    Science.gov (United States)

    2011-10-11

    ...: Effective date: November 10, 2011. ADDRESSES: U.S. Army Corps of Engineers, Attn: CECW-CO (David B. Olson), 441 G Street NW., Washington, DC 20314-1000. FOR FURTHER INFORMATION CONTACT: Mr. David B. Olson...

  7. Injury Reduction Effectiveness of Prescribing Running Shoes Based on Plantar Shape in Marine Corps Basic Training San Diego, CA and Parris Island, SC

    Science.gov (United States)

    2009-05-01

    in excessive pronation, creating a torsional force that repeatedly overstretched the plantar fascia , leading to the fasciitis. On the basis of one...COVERED (From – To) MARCH 2007–OCTOBER 2007 4. TITLE AND SUBTITLE Injury-Reduction Effectiveness of Assigning Running Shoes Based on Plantar Shape... plantar surface influenced injury risk in Marine Corps basic training. After foot examinations, Marine Corps recruits in an experimental group (E

  8. Injury-Reduction Effectiveness of Prescribing Running Shoes Based on Plantar Shape in Marine Corps Basic Training, San Diego, CA, and Parris Island, SC

    Science.gov (United States)

    2007-10-01

    in excessive pronation, creating a torsional force that repeatedly overstretched the plantar fascia , leading to the fasciitis. On the basis of one...COVERED (From – To) MARCH 2007–OCTOBER 2007 4. TITLE AND SUBTITLE Injury-Reduction Effectiveness of Assigning Running Shoes Based on Plantar Shape... plantar surface influenced injury risk in Marine Corps basic training. After foot examinations, Marine Corps recruits in an experimental group (E

  9. Annual report 1999. Energy and connectors; Rapport annuel 1999. Energie connectique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This report presents the industrial activities and the financial results of Framatome in 1999. Framatome's activities are divided into 2 sectors: energy and connectors, which represents respectively 54% and 46% of the turnover and 40% and 60% of the staff (26000 people). In 1999 the turnover reached 4.2 milliard euros. Framatome and Siemens have decided to merge their nuclear activities in a common company (66% for Framatome, 34% for Siemens). (A.C.)

  10. Annual report 1999. Energy and connectors

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents the industrial activities and the financial results of Framatome in 1999. Framatome's activities are divided into 2 sectors: energy and connectors, which represents respectively 54% and 46% of the turnover and 40% and 60% of the staff (26000 people). In 1999 the turnover reached 4.2 milliard euros. Framatome and Siemens have decided to merge their nuclear activities in a common company (66% for Framatome, 34% for Siemens). (A.C.)

  11. Annual report 1999. Energy and connectors; Rapport annuel 1999. Energie connectique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This report presents the industrial activities and the financial results of Framatome in 1999. Framatome's activities are divided into 2 sectors: energy and connectors, which represents respectively 54% and 46% of the turnover and 40% and 60% of the staff (26000 people). In 1999 the turnover reached 4.2 milliard euros. Framatome and Siemens have decided to merge their nuclear activities in a common company (66% for Framatome, 34% for Siemens). (A.C.)

  12. Use of Children's Popular Culture in Literacy Curricula: An Analysis of the Papers by Parry (2002) and Dickie and Shuker (2014) through the Lenses of "No Research Can Be Value-Laden

    Science.gov (United States)

    Altintug, Fatma Aslanturk; Debrelu, Emre

    2018-01-01

    This paper focuses on the importance of children's out-of-school experiences as their popular culture and discusses how such experiences contribute to their creativity and critical thinking. In addition to this, the paper also discusses the critical role of researchers' values in terms of how values affect the design and process of research. From…

  13. Annual report 2000

    International Nuclear Information System (INIS)

    2001-01-01

    This report presents the industrial activities and the financial results of the Framatome group (Framatome-SA) in 2000. and Siemens have merged their nuclear activities and have created Framatome-ANP (advanced nuclear power) owned by Framatome (66%) and Siemens (34%). This new society represents a turnover of 3 millions Euros and a staff of 13.000 employees. In the sector of connectors, FCI (Framatome Connectors International) has reinforced its second position in the world, FCI has enjoyed a high growth in the sector of telecommunication and has created a department dealing with optic fibers. 32% of the activities of Framatome-SA have been performed in France, 26% in North America and 42% in the rest of the world. In 2000 the trading results after having paid taxes reached 306 millions Euros, it represents 6.1% of the turnover. (A.C.)

  14. Annual report 2000; Rapport annuel 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This report presents the industrial activities and the financial results of the Framatome group (Framatome-SA) in 2000. and Siemens have merged their nuclear activities and have created Framatome-ANP (advanced nuclear power) owned by Framatome (66%) and Siemens (34%). This new society represents a turnover of 3 millions Euros and a staff of 13.000 employees. In the sector of connectors, FCI (Framatome Connectors International) has reinforced its second position in the world, FCI has enjoyed a high growth in the sector of telecommunication and has created a department dealing with optic fibers. 32% of the activities of Framatome-SA have been performed in France, 26% in North America and 42% in the rest of the world. In 2000 the trading results after having paid taxes reached 306 millions Euros, it represents 6.1% of the turnover. (A.C.)

  15. Functional Analysis and Treatment of Coprophagia

    Science.gov (United States)

    Ing, Anna D.; Roane, Henry S.; Veenstra, Rebecca A.

    2011-01-01

    Coprophagia, the ingestion of fecal matter, occurs among some individuals with developmental disabilities and is associated with a variety of health risks (e.g., diarrhea, intestinal parasites, blood-borne pathogens; Parry-Jones & Parry-Jones, 1992). Studies that have evaluated operant-based treatments of coprophagia have been limited by a lack of…

  16. NIC (Nuclear Industry in China) exhibition. Press file

    International Nuclear Information System (INIS)

    1998-01-01

    Framatome participated to the NIC exhibition which took place in Beijing (China) on March 1998. This press dossier was distributed to visitors. It presents in a first part the activities of the Framatome group in people's republic of China (new constructions (Daya Bay, Ling Ao project), technological cooperation and contracts in the nuclear domain, technology transfers in the domain of nuclear fuels, activities and daughter companies in the domain of industrial equipments, Framatome Connectors International (FCI) daughter company in the domain of connectors engineering). Then, the general activities of Framatome in the nuclear, industrial equipment, and connectors engineering domains are summarized in the next 3 parts. (J.S.)

  17. 5/8'' baffle bolt replacement

    International Nuclear Information System (INIS)

    Pinaud, T.; Grypczynski, D.

    1999-01-01

    Both Framatome Nuclear Services in France and its U.S. arm, FT1, are now equipped with baffle bolt inspection and replacement packages. These packages allow them to tackle baffle bold degradation on both two- and three-loop nuclear power plants. Framatome and FT1 together are world leaders in addressing reactor vessel internal bolting concerns

  18. Project management. A discipline which contributes to project success

    International Nuclear Information System (INIS)

    Hoch, G.

    2008-01-01

    The presentation covers the following topics: description of the Project - a contract was signed between KNPP and European Consortium Kozloduy (ECK) consisting of Framatome ANP GmbH as Leader (63%), Framatome ANP S.A.S. (17%), Atomenergoexport (20%) ; Project management in the modernization of NPP Kozloduy units 5 and 6; Project management process within AREVA NP GmbH; current status

  19. PWR heavy equipments manufacture for nuclear power plants

    International Nuclear Information System (INIS)

    Boury, C.; Terrien, J.F.

    1983-10-01

    The manufacture of boilers has been imported by the French nuclear program to the societe FRAMATOME. FRAMATOME, because of the size of this market, has constructed two special plants for manufacturing of nuclear components (vapor generators, reactor tanks, pressurizers); these two high technical facilities are presented: production, staff training, technical overseas assistance, and technical and economical repercussions on the industrial vicinity [fr

  20. Improved sealing for in-core systems

    International Nuclear Information System (INIS)

    Dunford, S.

    1989-01-01

    The in-core instrumentation sealing nozzles designed by Framatome have three mechanical seals in series instead of the one traditional seal, and are pressurized by simply tightening up the nozzle covers. They have been installed from the start on all Framatome PWRs, as well as having been backfitted on Belgium and Yugoslavian units and chosen for the Chinese Qinshan plant. (author)

  1. Industrial organization. The government draws a new french nuclear landscape

    International Nuclear Information System (INIS)

    Foucher, N.

    2000-01-01

    This paper presents and explains the new nuclear industry. In order to rationalize Cogema and Framatome are going to be grouped in an holding called Topco with a nuclear pole and an electronic and new technologies pole. Framatome will be split in two parts and its connector technology subsidiary will be introduced on Change. (A.L.B.)

  2. High density aseismic spent fuel storage racks

    International Nuclear Information System (INIS)

    Louvat, J.P.

    1985-05-01

    After the reasons of the development of high density aseismic spent fuel racks by FRAMATOME and LEMER, a description is presented, as also the codes, standards and regulations used to design this FRAMATOME storage rack. Tests have been carried out concerning criticality, irradiation of Cadminox, corrosion of the cell, and the seismic behaviour

  3. Integrated CAD/CAE for nuclear power plants

    International Nuclear Information System (INIS)

    Lecoq, P.; Lachat, J.C.

    1987-01-01

    The size of the French nuclear power program has led both EDF and Framatome to equip themselves progressively with management software, computer-assisted design (CAD) systems, and computer-assisted engineering (CAE) systems. The nature of the projects and of the respective activities of EDF and Framatome determined the essential specifications of these computerized systems. EDF and Framatome have pooled their CAD/CAE efforts in a joint venture (Groupement d'Interet Economique) called GIAO, set up in 1985 by EDF and Aquitaine Systeme (a subsidiary of Framatome and Elf Aquitaine). GIAO's ambition is to become a pole of French CAD/CAE efforts and to foster progress in integrated computer-assisted engineering, by enlarging the synergy of EDF and Framatome in this field to other enterprises that participate in design and construction of complex industrial plants

  4. Dignity and death: a reply.

    Science.gov (United States)

    Brooks, S A

    1985-01-01

    Some form of utilitarian approach can be discerned as underlying much current medical ethical decision-making. Criticisms of the practical effects of such an approach are not parried by asserting the fundamental strengths of utilitarianism as theory. PMID:4009639

  5. Appiah-Adjei et al

    African Journals Online (AJOL)

    PUBLICATIONS1

    ing, sale of automobile spare parts, and metal fabrication. Some of these activities generate huge ... Keywords: Groundwater quality, pollution, waste disposal, Suame, Ghana ... of fertilizers (Chen et al., 2007; Parris, 2011;. Shen et al., 2011), ...

  6. Dignity and death: a reply.

    OpenAIRE

    Brooks, S A

    1985-01-01

    Some form of utilitarian approach can be discerned as underlying much current medical ethical decision-making. Criticisms of the practical effects of such an approach are not parried by asserting the fundamental strengths of utilitarianism as theory.

  7. Dignity and death: a reply.

    Science.gov (United States)

    Brooks, S A

    1985-06-01

    Some form of utilitarian approach can be discerned as underlying much current medical ethical decision-making. Criticisms of the practical effects of such an approach are not parried by asserting the fundamental strengths of utilitarianism as theory.

  8. Effectiveness of Information and Communication Technologies in ...

    African Journals Online (AJOL)

    Museum

    new different ways of enhancing interpretation, making explicit associations and linkages that can only be implicit in the physical site (Parry & Sawyer, 2005). In fact ... facilitate globally public awareness of the role and functions of a museum.

  9. Application of the ex-Gaussian function to the effect of the word blindness suggestion on Stroop task performance suggests no word blindness

    Directory of Open Access Journals (Sweden)

    Benjamin Andrew Parris

    2013-09-01

    Full Text Available The aim of the present paper was to apply the ex-Gaussian function to data reported by Parris et al. (2012 given its utility in studies involving the Stroop task. Parris et al. showed an effect of the word blindness suggestion when Response-Stimulus Interval (RSI was 500ms but not when it was 3500ms. Analysis revealed that: 1 The effect of the suggestion on interference is observed in µ, supporting converging evidence indicating the suggestion operates over response competition mechanisms; and, 2 Contrary to Parris et al., an effect of the suggestion was observed in µ when RSI was 3500ms. The reanalysis of the data from Parris et al. (2012 supports the utility of ex-Gaussian analysis in revealing effects that might otherwise be thought of as absent. We suggest that word reading itself is not suppressed by the suggestion but instead that response conflict is dealt with more effectively.

  10. 75 FR 82036 - Agency Information Collection Activities: Submission for OMB Review; Comment Request

    Science.gov (United States)

    2010-12-29

    ... Treatment for Opioid Addiction State Profiles.'' These publications will be used by the Federal government...-7285. Dated: January 22, 2010. Elaine Parry, Director, Office of Management, Technology and Operations...

  11. Experiences in transferring of AFA 3G fuel assembly fabrication

    International Nuclear Information System (INIS)

    Yang Xiaodong; Wu Zhiming; Luo Jiankang

    2002-01-01

    Implementation program is developed for the transferring of AFA 3G technology, together with the project management experts designated by Framatome Company, to facilitate the technology import under the guidance of strict program. Technical documents and quality insurance management documents are developed based on the full understanding of the information provided by Framatome to guide the fabrication of AFA 3G fuel elements. Technical requirement suggested by Framatome is adopted as much as possible, considering the practical process capability of YFP. The focus is the technology about fabrication difficulties in the AFA 3G technology, to insure the successful transfer of the AFA 3G fabrication technology

  12. The reorganization of the nuclear sector in France

    International Nuclear Information System (INIS)

    2001-05-01

    In November 2000, the French ministry of economy, finances and industry presented a project of reorganization of the overall French nuclear sector which aims at grouping together the activities of CEA-Industrie, Cogema and Framatome in a single huge industrial group. This group will comprise two main poles, a purely nuclear one around Cogema and Framatome, and a pole devoted to new technologies with the connector activities of Framatome and the shares of CEA-Industrie in STMicroelectronics. This new group should make a funded turnover of 10 billions of euros with a net result (share of the group) of 500 millions of euros. It will employ 45000 people. (J.S.)

  13. Travelling cranes for heavy reactor component handling

    International Nuclear Information System (INIS)

    Champeil, M.

    1977-01-01

    Structure and operating machinery of two travelling cranes (600 t and 450 t) used in the Framatome factory for handling heavy reactor components are described. When coupled, these cranes can lift loads up to 1000 t [fr

  14. Methods and equipments used in power reactors

    International Nuclear Information System (INIS)

    Beraha, R.; Delevallee, A.

    1976-01-01

    The various reactor γ fuel scanning facilities presently operating around the world are reviewed. Both equipments proposed by FRAMATOME are described: one is intended for scanning removable fuel pencils, and the other one for fuel assembly scanning [fr

  15. Steam generator tube extraction

    International Nuclear Information System (INIS)

    Delorme, H.

    1985-05-01

    To enable tube examination on steam generators in service, Framatome has now developed a process for removing sections of steam generator tubes. Tube sections can be removed without being damaged for treating the tube section expanded in the tube sheet

  16. News from the fuel elements industry

    International Nuclear Information System (INIS)

    Racine, R.; Delannay, M.; Dehon, C.; Jouan, J.; Beuneche, M.

    1981-01-01

    This article deals successively with: the re-structuring of the PWR fuel industry in France, with the setting up of Fragema and Cogema Framatome Combustible; Fragema products, from standard fuel assembly to the development of a new advanced fuel assembly; Framatome's experience with PWR fuel; fuel performances in the light of requirements imposed by network needs follow-up; devices developed by Fragema for on-site analysis of irradiated fuel [fr

  17. Advanced I and C system of security level for nuclear power station

    International Nuclear Information System (INIS)

    Liu Yanyang

    2001-01-01

    Advanced I and C system of security level using for PWR developed by Framatome and Schneider collective, SPINLINE3, are introduced. The technology is used to outside reactor nuclear measurement system in Qinshan II period. It's succeed benefits by Framatome and Schneider's more years development experience in nuclear power station digitallization security level I and C system field, which improve security and reliability of PWR, and, easy operation and maintains. SPINLINE3 based on digitallization and modularization technical proposal, and covered entireness reactor protect system and correlative control system. The paper also introduce CLARISSE (computer aided design aid) and SCADE (embedded software aid) for developing SPINLINE3. SPINLINE3 fills correlative IS and rule, based on software and hardware unit which certificate and launch into operation. After brief review of Framatome and Schneider's experience, the paper are introducing design guideline, application technology and how to fill demand of security level I and C system

  18. Crisis assistance to nuclear operators: the manufacturer missions and methods

    International Nuclear Information System (INIS)

    Touati, J.

    1995-01-01

    Since 1985, the Framatome Company has provided to Electricite de France (EDF) a technical assistance in the case of major accident on a nuclear power plant. During the accident crisis, Framatome establishes a diagnosis and a forecast about the installation state and proposes the safest solutions to the operator for a limitation of accident consequences. Different tools have been developed by Framatome to identify the consequences of electric power outages or to control the state of coolant circuits using expert systems and a data base about reactor component characteristics. A thermo-hydraulic analysis of the accident is performed by the system, using data transmitted to the crisis center, and hypotheses about the origin of the accident are proposed by the expert. After validation, a classification of risks is established and the best strategy to follow is determined by the system, in particular when non-conventional means are required. (J.S.). 1 fig

  19. The Daya Bay nuclear power plant performance. An example of international cooperation

    International Nuclear Information System (INIS)

    Hertzog, D.

    1998-01-01

    Technology transfer is an integral part of Framatome's general approach to its Chinese partners for the Daya Bay, Ling Ao, and Qinshan phase 2 nuclear power plant projects. It has been the subject of major operations covering all activities relevant to project management, design and engineering, manufacturing, and maintenance know-how. This presentation is more particularly devoted to nuclear island maintenance knowledge, which has been extensively transferred by Framatome to the Daya Bay plant owner over a period of four years, through a program including the constitution of mixed Franco-Chinese teams to handle plant maintenance, shadow training of Chinese specialists in the maintenance work performed by Framatome or its subcontractors in France, and theoretical training sessions on equipment mockups in China and France. (author)

  20. Post accidental small breaks analysis

    International Nuclear Information System (INIS)

    Depond, G.; Gandrille, J.

    1980-04-01

    EDF ordered to FRAMATOME by 1977 to complete post accidental long term studies on 'First Contrat-Programme' reactors, in order to demonstrate the safety criteria long term compliance, to get information on NSSS behaviour and to improve the post accidental procedures. Convenient analytical models were needed and EDF and FRAMATOME respectively developped the AXEL and FRARELAP codes. The main results of these studies is that for the smallest breaks, it is possible to manually undertake cooling and pressure reducing actions by dumping the steam generators secondary side in order to meet the RHR operating specifications and perform long term cooling through this system. A specific small breaks procedure was written on this basis. The EDF and FRAMATOME codes are continuously improved; the results of a French set of separate effects experiments will be incorporated as well as integral system verification

  1. EPR meeting international safety standards with margin

    International Nuclear Information System (INIS)

    Mazurkiewicz, S.M.; Brauns, J.; Blombach, J.

    2005-01-01

    The EPR provides technology that offers a solution to the market's need for safe, economic power. The EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product capable of international licensing. As such, the EPR is a global product with commercial units currently being built in Finland at the Olkiluoto site, and planned for France, at the Flamanville site. Framatome ANP has recently proposed four EPR units to China in response to a request for vendor bids. In addition, Framatome ANP has announced their intent to pursue design certification with the United States Nuclear Regulatory Commission (NRC). This paper discusses how EPR's innovative safety philosophy ensures compliance with international safety standards for advanced light-water reactors (ALWRs). (author)

  2. EPR meeting international safety standards with margin

    International Nuclear Information System (INIS)

    Mazurkiewicz, S.M.; Brauns, J.; Blombach, J.

    2005-01-01

    The EPR provides technology that offers a solution to the market's need for safe, economic power. The EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product capable of international licensing. As such, the EPR is a global product with commercial units currently being built in Finland at the Olkiluoto site, and planned for France, at the Flamanville site. Framatome ANP has recently proposed four EPR units to China in response to a request for vendor bids. In addition, Framatome ANP has announced their intent to pursue design certification in with the United States Nuclear Regulatory Commission (NRC). This paper discusses how EPR's innovative safety philosophy ensures compliance with international safety standards for advanced light-water reactors (ALWRs). (author)

  3. Forum: Learning Outcomes in Communication. Civic Engagement and a Communication Research Agenda

    Science.gov (United States)

    Ball, Timothy C.; Procopio, Claire H.; Goering, Beth; Dong, Qingwen; Bodary, David L.

    2016-01-01

    Civic engagement has long been a pedagogical and societal goal for communication scholars (Arnett & Arneson, 1999; Bennett, Wells, & Freelon, 2011). Kidd and Parry-Giles (2013) point out that belief in the "inherent civic value of speech to meaningful citizenship" is the "pedagogical core of the discipline" (n.p.).…

  4. Climate Change, Growth, and Poverty in Ethiopia

    Science.gov (United States)

    2013-06-01

    intergration Tests 8 Empirical Strategy 8 Discussion of Estimation Results 9 Climate Change and Economic Growth...production and marketing (Parry, 2007; Barrios et al , 2004), the impact of which can easily be transmitted to Ethiopia through trade channels with...Ethiopia and other developing countries to depend particularly on expensive cereal imports, worsening the trade balance in these countries However

  5. The Development and Application of the Coping with Bullying Scale for Children

    Science.gov (United States)

    Parris, Leandra N.

    2013-01-01

    The Multidimensional Model for Coping with Bullying (MMCB; Parris, in development) was conceptualized based on a literature review of coping with bullying and by combining relevant aspects of previous models. Strategies were described based on their focus (problem-focused vs. emotion-focused) and orientation (avoidance, approach-self,…

  6. The Role of Osteopontin in the Malignancy of Human Breast Carcinoma

    Science.gov (United States)

    1999-07-01

    1997; Yebra et al., 1996). 1990). Probes for human proteinase and uPAR genes The finding that human breast epithelial cells up- included: MMP-9 (92...680 -Senger DR and Perruzzi CA. (1996). Biochim. Biaphys. 69D.Adta., 1314, 13-24. Yebra M, Parry GCN, Str6mblad S, Mackman N,Shanmugamn V

  7. Interspecific hybrid of xeric Shepherdia rotundifolia and riparian Shepherdia argentea: description, and traits suitable for low-water urban landscapes

    Science.gov (United States)

    Shepherdia rotundifolia Parry (roundleaf buffaloberry), a shrub endemic to the U.S. Colorado Plateau high desert, has aesthetic and drought tolerance qualities desirable for low-water urban landscapes. However, slow growth and too often fatal sensitivity to wet or disturbed soil stymies nursery pro...

  8. Modelling Impacts of Climate Change: Case Studies using the New Generation of Erosion Models

    Science.gov (United States)

    Climate change is expected to impact upon a number of soil erosion drivers and processes, which should be taken into account when designing a modelling strategy. The fourth assessment report of the Intergovernmental Panel for Climate Change (IPCC) (Parry et al., 2007; Solomon et al., 2007) reviews a...

  9. A Novel Strategy to Control and Prevent Norovirus Gastroenteritis

    Science.gov (United States)

    2006-11-01

    Vibrio cholerae , Candida, etc.) have been reported to recognize the HBGAs as their receptors. NV is the first viral pathogen in the list. Human...and genogroup II: BUDS (AY660568), Grimsby (GrV; AJ004864), Hawaii (HV; U07611), Mexico (MxV; U22498), MOH (AF397156), Parris Island (PiV

  10. African Journal of Psychiatry - Vol 16, No 1 (2013)

    African Journals Online (AJOL)

    Monitoring the prevalence of methamphetamine-related presentations at psychiatric hospitals in Cape Town, South Africa · EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT. A Plüddemann, S Dada, CDH Parry, R Kader, JS Parker, H Temmingh, S van Heerden, C de ...

  11. African Journal of Psychiatry - Vol 14, No 5 (2011)

    African Journals Online (AJOL)

    Methamphetamine use and sexual risk behaviour in Cape Town, South Africa: A review of data from 8 studies conducted between 2004 and 2007 · EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT. CDH Parry, A Plüddemann, B Myers, WM Wechsberg, AJ Flisher, 372- ...

  12. Browse Title Index

    African Journals Online (AJOL)

    Vol 103, No 7 (2013), Decline in adolescent treatment admissions for methamphetamine use in Cape Town, Abstract PDF. A Plüddemann, S Dada, C Parry. Vol 107, No 9 (2017), Declining prevalence of duodenal ulcer at endoscopy in Ile-Ife, Nigeria, Abstract PDF. O Ijarotimi, D.O. Soyoye, O Adekanle, D.A. Ndububa, B.I. ...

  13. Book Review: Principles of Medicine in Africa | Farham | African ...

    African Journals Online (AJOL)

    Principles of Medicine in Africa Ed. by David Mabey, Geoffrey Gill, Eldryd Parry, Martin W Weber and. Christopher JM Whitty. 4th ed. Cambridge: Cambridge University Press, 2013. ISBN 978-1-107-00251-7. Full Text: EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT · DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT.

  14. Operation REDWING

    Science.gov (United States)

    1956-07-31

    rtr| aji ^-i^-iaaa^a^W|a,&ai|-^il^;,^^T^^tfJ^i^^«Ul^ ■:. u ■-ZSt^.^^^ " il SECTION XI - MILITARY POLICE ACTIVITIES: 1» Mission« To odvisc the...AIWSiVORTH on 19 March 1 1956. I During Mr-rch and April 1956, military police detachments were activntod on PARRY, RUNIT, ENYU, ROJO /., TEITEIRIPUCCHI

  15. Optimum ADP Support for Financial Management of Marine Corps Facilities Maintenance.

    Science.gov (United States)

    1983-06-01

    Japan X Camp Smedley D. Eutler, Okinawa, Japan X Camp H.M. Smith, Oahu, Hawaii X Regur Ind ze. Trinin MCDEC Quantico, Virginia x MCED Parris Island, South...18 May 1983 21. Interview with dr. Robert Herd, Administrative Divisicn, Fac. maint. Dept., MCB Camp Pendletcn cn 18 May 1983 22. Department of

  16. 75 FR 78720 - Agency Information Collection Activities: Submission for OMB Review; Comment Request

    Science.gov (United States)

    2010-12-16

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Substance Abuse and Mental Health Services Administration... Substance Abuse and Mental Health Services Administration (SAMHSA) will publish a summary of information...-7285. Dated: December 1, 2010. Elaine Parry, Director, Office of Management, Technology and Operations...

  17. 75 FR 78721 - Agency Information Collection Activities: Submission for OMB Review; Comment Request

    Science.gov (United States)

    2010-12-16

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Substance Abuse and Mental Health Services Administration... Substance Abuse and Mental Health Services Administration (SAMHSA) will publish a summary of information..., 2010. Elaine Parry, Director, Office of Management, Technology and Operations. [FR Doc. 2010-31586...

  18. New directions in climate change vulnerability, impacts, and adaptation assessment: summary of a workshop

    National Research Council Canada - National Science Library

    National Research Council (U.S.). Subcommittee for a Workshop on New Directions in Vulnerability, Impacts, and Adaptation Assessment; National Academies Press (U.S.); National Research Council (U.S.). Division of Behavioral and Social Sciences and Education; National Research Council (U.S.). Committee on the Human Dimensions of Global Change; Brewer, Jennifer F

    ... special thanks for providing the original idea, motivation, and organizational efforts. Our work also benefited significantly from the thoughtful contributions of Gary Yohe and Linda Mearns. In addition to the members of the subcommittee, the other workshop presenters, Neil Leary, Richard Moss, Martin Parry, and Roger Pulwarty, helped greatly in orie...

  19. Further Insight and Additional Inference Methods for Polynomial Regression Applied to the Analysis of Congruence

    Science.gov (United States)

    Cohen, Ayala; Nahum-Shani, Inbal; Doveh, Etti

    2010-01-01

    In their seminal paper, Edwards and Parry (1993) presented the polynomial regression as a better alternative to applying difference score in the study of congruence. Although this method is increasingly applied in congruence research, its complexity relative to other methods for assessing congruence (e.g., difference score methods) was one of the…

  20. Toward a generic model of trust for electronic commerce

    NARCIS (Netherlands)

    Tan, YH; Thoen, W

    2000-01-01

    The authors present a generic model of trust for electronic commerce consisting of two basic components, party trust and control trust, based on the concept that trust in a transaction with another party combines trust in the other parry and trust in the control mechanisms that ensure the successful

  1. Female sex workers in Africa: Epidemiology overview, data gaps ...

    African Journals Online (AJOL)

    E. N. Ngugi, E. Roth, Theresa Mastin, M. G. Nderitu, and Seema Yasmin

    –897. Morojele, N.K., Kachienga, M.A., Mokoko, E., Nkoko, M.A., Parry, C.D.H.,. Nkowane, A.M., et al. (2006). Alcohol use and sexual behaviour among risky drinkers and bar and she been patrons in Gauteng province, South Africa.

  2. 76 FR 31968 - Agency Information Collection Activities: Proposed Collection; Comment Request

    Science.gov (United States)

    2011-06-02

    ... serious mental illnesses. SOAR has three main components: Strategic planning for systems change, training for case managers and ongoing technical assistance. During the SOAR training, the importance of... days of this notice. Dated: May 24, 2011. Elaine Parry, Director, Office of Management, Technology and...

  3. 75 FR 22554 - Notice of Petitions by Firms for Determination of Eligibility To Apply for Trade Adjustment...

    Science.gov (United States)

    2010-04-29

    ... Specialty truck cabs, Joplin, MO 68801. hoods, etc.; construction and military cabs, hoods, etc.; Water... Company, Inc 1209 Logan Circle NW., 4/13/2010 The firm produces custom Atlanta, GA 30318. wood counter, table, and vanity tops. Primary material is wood. KMS Fab, LLC 100 Parry Street, Luzerne, 4/14/2010...

  4. Disease: H01766 [KEGG MEDICUS

    Lifescience Database Archive (English)

    Full Text Available S, Parry NR, Stanga PE, Trump D ... TITLE ... X-linked retinoschisis: an update. ... JOURNAL ... J Med Genet 44:225-32 (2007) DOI:10.1136/jmg.2006.047340 ... ...e; Eye disease ... ICD-10: Q14.1 MeSH: D041441 OMIM: 312700 PMID:17172462 ... AUTHORS ... Sikkink SK, Biswas

  5. Juvenile Scleroderma

    Science.gov (United States)

    ... of the tongue. Obvious cases of en coup de sabre and Parry Romberg syndrome differ significantly, but many children present with cross-over manifestations, which can make it difficult to determine with certainty which form of ... en coup de sabre is mixed. If the lesions are confined ...

  6. 75 FR 79011 - Agency Information Collection Activities: Submission for OMB Review; Comment Request

    Science.gov (United States)

    2010-12-17

    ... physicians, medical students, and social workers) and non-traditional (e.g., clergy, and alternative health... gains/changes as a result of training attendance. The multi-site data collection design uses a two...-7285. Dated: December 13, 2010. Elaine Parry, Director, Office of Management, Technology and Operations...

  7. Decay of subalpine fir in Colorado

    Science.gov (United States)

    Thomas E. Hinds; Frank G. Hawksworth; Ross W. Davidson

    1960-01-01

    Spruce-fir is one of the major forest types in the central Rocky Mountains. Engelmann spruce, Picea engelmanni Parry, is usually the predominant species with subalpine fir, Abies lasiocarpa (Hook. ) Nutt., making up one-fourth or less of the total volume. Lodgepole pine, Pinus contorta Dougl. ex Loud., is frequently present at the lower elevations of the spruce-fir...

  8. Journal of Child and Adolescent Mental Health - Vol 13, No 1 (2001)

    African Journals Online (AJOL)

    Prevalence And Detection Of Psychiatric Disorders Among Children And Adolescents Attending A Primary Health Care Clinic. BA Robertson, K Ensink, CDH Parry, D Chalton ... Case Study: Narrative Of A Psychotherapeutic Treatment Of Dissociative Identity Disorder In An Adolescent. Kathleen Hanley ...

  9. Tsherez 30 let Jevropu zahvatjat "varvarõ" / Mihhail Ozerov

    Index Scriptorium Estoniae

    Ozerov, Mihhail

    2006-01-01

    Briti kontradmiral Chris Parry hoiatab oma ettekandes, et lähema 30 aasta jooksul hõivavad Euroopa immigrandid Kolmandast Maailmast, neil ei midagi ühist Euroopaga, veelgi enam - nad vihkavad seda. Intervjuu Briti parlamendiliikme Boris Johnsoniga. Postindustriaalse ühiskonna uurimise keskuse teaduslik juht Vladislav Inozemtsev on seisukohal, et immigrandid Venemaa julgeolekut ei ohusta. Tabel

  10. SIEMENS

    International Nuclear Information System (INIS)

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. This chapter contains information about Siemens and it participation on reconstruction of Bohunice V1 and V1 NPPs. It consists of next parts: (1) FRAMATOME ANP - worldwide activities of the FRAMATOME are presented; (2) Nuclear power engineering - present activities focus on: Upgrading and Backfitting (Siemens WWER activities since 1971); Electrical instrumentation and control systems; Fuel assemblies and related services; Reactor development and construction of new plants; (3) Safety improvement; (4) Siemens in Slovakia (activities of Siemens in Slovakia during 1993-2000 are presented); (5) More than 150-year history

  11. Reactor vessel closure head replacements in 1997

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    The Framatome-Jeumont Industrie consortium have completed in 1997 28 reactor vessel (RV) closure head replacements, including five on 1300 MWe class PWR units. Framatome manages the operations and handles removal and reinstallation of equipment (not including the control rod drive mechanisms (CRDM)) and the requalification tests, while JI, which manufactures the CRDMs, is involved in the CRDM cutting, re-machining and welding operations, using tools of original design, in order to optimize the RV closure head operation in terms of costs, schedule and dosage

  12. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    International Nuclear Information System (INIS)

    Vignes, A.

    1983-02-01

    Evidence is presented to show how the integrity of the reactor pressure vessel to be constructed for the proposed Sizewell B nuclear power station could be achieved by the French company Framatome. Following a description of the organization and experience of Framatome, their ability to manufacture the pressure vessel to the preferred design and to meet all the requirements of the National Nuclear Corporation is demonstrated. Then it is shown, using examples, how the various procurement and fabrication operations are carried out and controlled and how the quality of the materials and products is assessed and guaranteed. (U.K.)

  13. Bilateral cooperation and technology transfer between France and China at Daya-Bay, Qinshan II and Yibin

    International Nuclear Information System (INIS)

    Ma Fubanf; Zenf Wenxing; He Jiacheng; Charbonneau, S.; Darolles, J.F.; Ellia, G.; Freslon, H.

    1994-01-01

    The Daya-Bay nuclear power station in Guangdong Province, The Qinshan phase II nuclear power station in Zhejiang Province, and the fuel manufacturing facility at Yibin in Sichuan Province have all afforded Framatome the opportunity to develop wide-ranging bilateral cooperation and technology transfer with the People's Republic of china. These projects are all good examples of how a country with some nuclear power experience, such as the now-operating Qinshan 1 (300 M We) nuclear power unit designed and build by China itself, can make much more rapid progress in its civil nuclear power program through cooperation with an industry leader, such as Framatome

  14. Best estimate LB LOCA approach based on advanced thermal-hydraulic codes

    International Nuclear Information System (INIS)

    Sauvage, J.Y.; Gandrille, J.L.; Gaurrand, M.; Rochwerger, D.; Thibaudeau, J.; Viloteau, E.

    2004-01-01

    Improvements achieved in thermal-hydraulics with development of Best Estimate computer codes, have led number of Safety Authorities to preconize realistic analyses instead of conservative calculations. The potentiality of a Best Estimate approach for the analysis of LOCAs urged FRAMATOME to early enter into the development with CEA and EDF of the 2nd generation code CATHARE, then of a LBLOCA BE methodology with BWNT following the Code Scaling Applicability and Uncertainty (CSAU) proceeding. CATHARE and TRAC are the basic tools for LOCA studies which will be performed by FRAMATOME according to either a deterministic better estimate (dbe) methodology or a Statistical Best Estimate (SBE) methodology. (author)

  15. NPP operation and maintenance with french-built NPPs

    International Nuclear Information System (INIS)

    Mira, J.J.

    1987-01-01

    In Frace, 80% of the electricity production will be nuclear in 1990. More than to-day, PWR units will be operated by ELECTRICITE DE FRANCE on a load-follow basis. Every effort is made to reduce planned and forced outages. Maintenance is shared between EDF and FRAMATOME, the latter being in charge of high technology operations. All these actions are eased by the standardization of units, within each power class, the resulting build-up of experience being available to all PWR operators in the world, more particularly to those of FRAMATOME-built units

  16. The nuclear industry in France

    International Nuclear Information System (INIS)

    Degot, D.

    1981-02-01

    The French nuclear industry is organized around the following main participants: - The E.D.F., owners, industrial architects and operators of the power stations, - The C.E.A. for research and development, with its subsidiary the COGEMA, who deal with all problems involving the fuel cycle, - The Industry with FRAMATOME in charge of the manufacture of nuclear boilers, and ALSTHOM-ATLANTIQUE in charge of turbo-generator units. This paper deals with the activities covered by FRAMATOME and its industrial environment. The standardization of PWR power stations built by French industry and the possibilities of exporting PWR power stations are given a brief mention [fr

  17. Solutions against PWSCC in dissimilar welds cracks of reactor components

    International Nuclear Information System (INIS)

    Schlader, D.; Michaut, B.; Knapp, M

    2005-01-01

    This article provides a brief overview of the experience accumulated by Framatome ANP in the development and use of repair and mitigation techniques of the PWSCC in dissimilar welds cracks of reactor components. A brief description of the alternatives available to the industry for the solution of this problem for both PWR and BWR reactor types is also included. These solutions have been implemented many times by Framatome ANP in Europe and the US. The article also describes the way the know-how is shared among the different regions of the company in order to offer customer specific solutions. (Author)

  18. Measurement by eddy currents of tube-antivibratory bar gap steam generators of PWR power plants

    International Nuclear Information System (INIS)

    Savin, E.; Bieth, M.; Floze, J.C.

    1990-01-01

    In steam generators tubes are maintained by AVB to limit vibrations amplitude induced by secondary fluid flow. After some years wear sometimes occurs. For gap measurement between tubes and AVB Framatome developed a method based on eddy current and using a probe rotating inside the tube [fr

  19. Post-test analysis of the experiment 5.2C - total loss of feed water at the BETHSY test facility

    Energy Technology Data Exchange (ETDEWEB)

    Krepper, E; Schaefer, F

    1998-10-01

    The BETHSY-test facility is a 1:100 scaled thermohydraulic model of a 900 MW(el) pressurized water reactor (FRAMATOME). The test facility is mainly designed to investigate various accident scenarios and to provide an experimental data base for code validation and for the verification of accident management measures. (orig.)

  20. NPP Mochovce - a project of extraordinay significance

    International Nuclear Information System (INIS)

    Chwolik, I.; Debru, M.

    2000-01-01

    In this paper and in this presentation the reactor safety upgrading of two blocks of the NPP V-1 Bohunice, some results of participation on safety upgrading by the German-French consortium EUCOM (Framatome and Siemens-KWU) are presented. (author)

  1. Functional approaches: a new view of nuclear reactors management

    International Nuclear Information System (INIS)

    Papin, B.

    2000-01-01

    Since many years a research program on the future reactors command, has been decided by the CEA, in collaboration with EDF and Framatome. This program aims to enhance the reactor safety by a better control of the installation in any exploitation situations. The paper presents the state of the art and the first reflexions. (A.L.B.)

  2. Chinese imperative: nuclear energy to bridge geographic and economic gaps

    International Nuclear Information System (INIS)

    Zongyu, T.

    1994-01-01

    Encouraged by successful operation of its first three nuclear units -Quinshan-1 (own design) and Daya Bay-1 and -2 (Framatome) - China is rapidly preparing to expand both sites. The immediate need is to overcome the shortage of electricity on the East coast. Medium to long term, the need is to ensure power for economic growth throughout China. (author) 2 figs., 1 tab

  3. Mechanical behaviour of pressure vessel head penetrations

    International Nuclear Information System (INIS)

    Faidy, C.; Ternon, F.; Vagner, J.; Vaindirlis, M.

    1994-01-01

    After leaks on Bugey 3 penetrations EdF and Framatome have started a study on the stress corrosion phenomenon of Inconel 600. In this paper, limited to the mechanical aspect, we present an estimation of in service stresses, the experimental program on mockup for visualize the surface stress and the noxiousness of potential cracks. 5 figs., 6 tabs., 5 refs

  4. Expert system for assisting the diagnostic and localisation of breakdowns on the fuel elements loading machine

    International Nuclear Information System (INIS)

    Merlin, J.; Pradal, B.

    1990-01-01

    An expert system is developed in order to minimize the time lost through breakdowns of the fuel loading device. The expert system developed by FRAMATOME uses MAINTEX software. The expert systems MACHA and SEDMAC were designed respectively for use on 1300 MWe and 900 MWe loading machines [fr

  5. Press travel to the Mochovce power plant in Slovakia

    International Nuclear Information System (INIS)

    1998-07-01

    This press dossier gives, first, a general presentation of the Mochovce power plant of the republic of Slovakia (history, technical characteristics, safety aspects, technical particularities of VVER 440/213 reactors (safety analysis, recent improvements), financing of the modernization project). Then, the activities of the Framatome group in central and eastern Europe are presented (partnerships, cooperation agreements and contracts). (J.S.)

  6. Technology transfer

    International Nuclear Information System (INIS)

    Boury, C.

    1986-01-01

    This paper emphasizes in the specific areas of design, engineering and component production. This paper presents what Framatome has to offer in these areas and its export oriented philosophy. Then, a typical example of this technology transfer philosophy is the collaboration with the South Korean firm, Korea Heavy Industries Corporation (KHIC) for the supply of KNU 9 and KNU 10 power stations

  7. Reproducibility of the results in ultrasonic testing

    International Nuclear Information System (INIS)

    Chalaye, M.; Launay, J.P.; Thomas, A.

    1980-12-01

    This memorandum reports on the conclusions of the tests carried out in order to evaluate the reproducibility of ultrasonic tests made on welded joints. FRAMATOME have started a study to assess the dispersion of results afforded by the test line and to characterize its behaviour. The tests covered sensors and ultrasonic generators said to be identical to each other (same commercial batch) [fr

  8. I and C modernization of Loviisa Nuclear Power Plant

    International Nuclear Information System (INIS)

    Niedzballa, G.; Wagner, E.

    2005-01-01

    A brief review of the Framatome finished and current safety I and C project is given. The general concept for modernization of the instrumentation and control systems of the Loviisa NPP units 1 and 2 is presented. An overview on the scope of supply and time schedule is also shown

  9. Toward full MOX core design

    International Nuclear Information System (INIS)

    Rouviere, G.; Guillet, J.L.; Bruna, G.B.; Pelet, J.

    1999-01-01

    This paper presents a selection of the main preliminary results of a study program sponsored by COGEMA and currently carried out by FRAMATOME. The objective of this study is to investigate the feasibility of full MOX core loading in a French 1300 MWe PWR, a recent and widespread standard nuclear power plant. The investigation includes core nuclear design, thermal hydraulic and systems aspects. (authors)

  10. Compact fuel storage rack for fuel pools

    International Nuclear Information System (INIS)

    Parras, F.; Louvat, J.P.

    1986-01-01

    ETS LEMER and FRAMATOME propose a new compact storage rack. This rack permits a considerable increase of the storage capacity of cooling pools. A short description of the structure and the components is presented, to propose racks that are: . Inalterable, . Compact, . Insensitive to earthquakes. Installation in pools already in operation is simplified by their light structure and the bearing device [fr

  11. Industrial tests of rhodium self-powered detectors: the Golfech 2 experimentation

    International Nuclear Information System (INIS)

    Mourlevat, J.L.; Janvier, D.; Warren, H.D.

    2000-01-01

    In co-operation with Electricite de France (EDF), FRAMATOME has been testing two in-core strings which are equipped with rhodium self-powered detectors (SPDs) in the Golfech Unit 2 reactor (1300 MW, 4L plant) since August 1997. The rhodium SPDs and the strings which support them were designed and built by the US FRAMATOME subsidiary FRAMATOME-COGEMA-FUEL (FCF). The rhodium signals and some other plant parameters are acquired through the use of a specific device designed by the CEA (Commissariat a l'Energie Atomique) and are processed off-line by FRAMATOME. This demonstration test is planned to last until mid-2000. The following presentation is focused on the results obtained during the first demonstration cycle (from 08/97 to 12/98). The tests that have been conducted consist of checking the rhodium depletion and of comparing the rhodium signals to the movable probes. In order to compensate for the delay in the rhodium signals, a deconvolution algorithm has also been tested. Up to now, the results are very satisfactory and a future large scale industrial application is being discussed with the EDF. The main objective of the next experimentation phase is to test - under industrial conditions - a prototype of an on-line monitoring unit known as the Partial In-Core Monitoring System (PIMS). This system will include 16 rhodium in-core strings and will use an on-line 3-D core model. (authors)

  12. A knowledge-based diagnosis system for welding machine problem solving

    International Nuclear Information System (INIS)

    Bonnieres, P. de; Boutes, J.L.; Calas, M.A.; Para, S.

    1986-06-01

    This paper presents a knowledge-based diagnosis system which can be a valuable aid in resolving malfunctions and failures encountered using the automatic hot-wire TIG weld cladding process. This knowledge-based system is currently under evaluation by welding operators at the Framatome heavy fabricating facility. Extension to other welding processes is being considered

  13. Contribution of artificial intelligence to operation

    International Nuclear Information System (INIS)

    Malvache, P.; Mourlevat, J.L.

    1993-01-01

    Artificial Intelligence techniques are already used in nuclear plants for assistance to operation: synthesis from numerous information sources may be then derived, based on expert knowledge. Artificial intelligence may be used also for quality and reliability assessment of software-based control-command systems. Various expert systems developed by CEA, EDF and Framatome are presented

  14. Improvement of NSSS design to reduce occupational radiation exposure (ORE)

    International Nuclear Information System (INIS)

    Dubourg, M.

    1985-05-01

    As a result of its R and D activities, FRAMATOME has initiated concrete measures to help to reduce personnel radiation exposure. These measures include reduction in the sources and quantity of activable products, and in the duration of personnel exposure during maintenance

  15. A worldwide fuel strategy by AREVA

    International Nuclear Information System (INIS)

    Bordy, Michel

    2004-01-01

    Operating as a global company, inside AREVA the Fuel Sector implements a common strategy among three Business Units of fuel activities. These Business Units which are in Framatome ANP Zirconium, Manufacturing and Design and Sales Units, are operated in Germany (former Siemens activity), in USA (former BWFC Babcock and Wilcox Fuel Co,. and SPC Siemens Power Co. activities), in Belgium and in France (former Framatome activity). They have resources and facilities which are cooperatively working on R and D, engineering, project management, sales and services to achieve synergy on a cross-business basis. Based on its experience of worldwide activities and taking advantage of its diversified fuel design knowledge, Framatome ANP proposes a full range of fuel products and services on the BWR and PWR markets. With the ability to supply all fuel assembly arrays and fuel pellet types, supplemented by the range of stationary and movable core components, and completed by a full-range of on-site fuel services and performance of fuel packing and delivery, Framatome ANP is positioned as a major participant on the world fuel market. Today, Framatome ANP takes advantage of the cross-fertilization in the short term of existing products which include four original PWR fuel designs of HTP TM alloy as the reference material for cladding tubes, guide thimbles, and grids, -- Gradual incorporation of the valuable high-stiffiness MONOBLOC tM guide thimble, -- Progressive integressive integration of the High Mechanical Performance (HMP) Inconel end grid, -- Planned standardization of mechanical components such as nozzles, holddown systems and top and bottom connections. As a continuation of its existing technology, Framatome ANP is developing improved technical features within the scope of the Alliance fuel assembly qualification program. With an irradiation program ranging up to a burnup of 70 MWd/kgU expected to be reached in 2006, Alliance shows excellent behaviour with very low corrosion

  16. Most advanced HTP fuel assembly design for EPR

    International Nuclear Information System (INIS)

    Francillon, Eric; Kiehlmann, Horst-Dieter

    2006-01-01

    End 2003, the Finnish electricity utility Teollisuuden Voima Oy (TVO) signed the contract for building an EPR in Olkiluoto (Finland). Mid 2004, the French electricity utility EDF selected an EPR to be built in France. In 2005, Framatome ANP, an AREVA and Siemens company, announced that they will be pursuing a design certification in the U.S. The EPR development is based on the latest PWR product lines of former Framatome (N4) and Siemens Nuklear (Konvoi). As an introductory part, different aspects of the EPR core characteristics connected to fuel assembly design are presented. It includes means of ensuring reactivity control like hybrid AIC/B4C control rod absorbers and gadolinium as burnable absorber integrated in fuel rods, and specific options for in-core instrumentation, such as Aeroball type instrumentation. Then the design requirements for the EPR fuel assembly are presented in term of very high burnup capacity, rod cladding and fuel assembly reliability. Framatome ANP fuel assembly product characteristics meeting these requirements are then described. EPR fuel assembly design characteristics benefit from the experience feedback of the latest fuel assembly products designed within Framatome ANP, leading to resistance to assembly deformation, high fuel rod restraint and prevention of handling hazards. EPR fuel assembly design features the best components composing the cornerstones of the upgraded family of fuel assemblies that FRAMATOME ANP proposes today. This family is based on a set of common characteristics and associated features, which include the HMP grid as bottom end spacer, the MONOBLOC guide tube and the Robust FUELGUARD as lower tie plate, the use of the M5 Alloy, as cladding and structure material. This fully re-crystallized, ternary Zr-Nb-O alloy produces radically improved in-reactor corrosion, very low hydrogen uptake and growth and an excellent creep behavior, which are described there. EPR fuel assembly description also includes fuel rod

  17. A study on the dependency evaluation for multiple human actions in human reliability analysis of probabilistic safety assessment

    International Nuclear Information System (INIS)

    Kang, D. I.; Yang, J. E.; Jung, W. D.; Sung, T. Y.; Park, J. H.; Lee, Y. H.; Hwang, M. J.; Kim, K. Y.; Jin, Y. H.; Kim, S. C.

    1997-02-01

    This report describes the study results on the method of the dependency evaluation and the modeling, and the limited value of human error probability (HEP) for multiple human actions in accident sequences of probabilistic safety assessment (PSA). THERP and Parry's method, which have been generally used in dependency evaluation of human reliability analysis (HRA), are introduced and their limitations are discussed. New dependency evaluation method in HRA is established to make up for the weak points of THERP and Parry's methods. The limited value of HEP is also established based on the review of several HRA related documents. This report describes the definition, the type, the evaluation method, and the evaluation example of dependency to help the reader's understanding. It is expected that this study results will give a guidance to HRA analysts in dependency evaluation of multiple human actions and enable PSA analysts to understand HRA in detail. (author). 23 refs., 3 tabs., 2 figs

  18. Infrastructure Damage/Fragility Models and Data Quality Issues Associated with Department of Defense Climate Vulnerability and Impact Assessment

    Science.gov (United States)

    2015-01-26

    Jeffrey Donnelly, Richard Moss,  Joseph Donoghue, Steve Kish, Jim Elsner, Robert Evans, David LaBranche, Justin LaRose, Adam  Parris,  Chris  Weaver...Garrow, L.,  Higgins , M., and Meyer, M. (2013). ”Impacts of Climate Change on Scour‐ Vulnerable Bridges: Assessment Based on HYRISK.” J. Infrastruct...Adam Parris  NOAA Regional Integrated Sciences and  Assessments Program  Y  Chris  Weaver  U.S. Global Change Research Program  Y    83    Name

  19. Radiological consequence analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW

    International Nuclear Information System (INIS)

    Khan, L.A.; Raza, S.S.

    1993-12-01

    Radiological consequence analysis has been carried out for upgradation of PARR-I from 9 to 10 MW. A hypothetical loss of coolant accident resulting in core meltdown and release of fission products to the atmosphere has been analyzed. Whole body and thyroid doses have been calculated as a function of time and distance from the containment building. Based on these dose estimates, boundaries of exclusion and low population zones are assessed. (author)

  20. London-type congestion tax with revenue-recycling

    OpenAIRE

    Yukihiro Kidokoro

    2005-01-01

    Road pricing in London attracts a great deal of interest. A challenging aspect of the London scheme is that congestion tax revenue is used to upgrade public transit networks. Although Parry and Bento (2001) show that the total social surplus would increase if congestion tax revenues are used to cut labor taxes, political difficulties exist in implementing revenue-recycling between congestion taxes and labor taxes. Given such political difficulties, the London scheme seems to be very attractiv...

  1. Cyber Deterrence: The Wrong Question for the Wrong Problem

    Science.gov (United States)

    2018-04-20

    eye. Cyber thrusts. parries, and ripostes occur at speeds only artificial intelligence can truly monitor. But humans do retain an advantage in...fallen to various entities spread across the government spanning services, agencies, offices, and directorates. Despite the citation of cybersecurity as...Staff for an Executive Branch Cybersecurity Coordinator, a fully realized national cyber strategy remains elusive.3 A leading reason that effective

  2. Pengaruh Azadirachtin a Terhadap Serangga Dolleschalia Polibete

    OpenAIRE

    KARDfNAN, AGUS; MUSTIKA, IKA; ISKANDAR, MOMO; SUKMANA, CUCU

    1999-01-01

    Research on the effect of azadirachtin A isolated from neem tree (Azadirachla tndica A Juss) on msect Dolleschalia polibete. the most poten¬ tial insect destroying Graptophyllum pictum crop was caried out at the Entomological laboratory duing November 1997 to May 1998 The objective of the research was to evaluate the effect of azadirachtin A on some biological aspects of D. polibete. The formulation was obtained from FID Parry Ltd. (India), containing 1% azadirachtin A. The concentration reco...

  3. Medical Surveillance Monthly Report (MSMR). Volume 19, Number 3, March 2012

    Science.gov (United States)

    2012-03-01

    injury events (Parris Island/Beaufort, SC [n=899], MCB Camp Lejeune/Cherry Point, NC [n=659], Fort Polk, LA [n=555], Fort Cambell , KY [n=508]). Of the...7.7 MCB Camp Lejuene/ Cherry Hill, NC 659 5.7 Fort Polk, LA 555 4.8 Fort Cambell , KY 508 4.4 Camp Pendleton, CA 336 2.9 Fort Hood, TX 330 2.8 Fort

  4. Climate Change Science,Technology & Policy

    Indian Academy of Sciences (India)

    Table of contents. Climate Change Science,Technology & Policy · Slide 2 · Slide 3 · Slide 4 · Slide 5 · Millions at Risk from Parry et al., 2001 · Slide 7 · Slide 8 · Slide 9 · Slide 10 · Climate Change · Is the global warming in the 20th century due to the increase in radiation emitted by the sun? Frohlich C, Lean J. 1998; ...

  5. 82D Airborne Division in Sicily and Italy

    Science.gov (United States)

    1945-11-01

    34L.1 ranki, wou1d1 refrain from flashUing his tc;rch inrsiLd4e the caro Neithbler T1’ayloEcr no<->r 3-ar di ror f el+- : nyXr real chill o- f fea -r... Mendez , Louis G, Myers, Joseph F, Muzynski, TWalter J, Nau, Charles E, Ostberg, EJe Parris, Harold L; Polette, Lloyd L, Prager, Clarence’ Prager, Leonard A

  6. Sociology of a scandal : the emergence of ‘FIFAgate’

    OpenAIRE

    Bayle, Emmanuel; Rayner, Hervé

    2016-01-01

    This article examines the social forces underlying FIFAgate. Why do corrupt practices, which are often highly consolidated or even institutionalized, suddenly become scandalous? What is a scandal? Why did FIFA fall into crisis in 2015 and not before? To answer these questions, it is necessary to look at the sequence of thrusts and parries between all the parties involved. Our analysis embraces the notion that social processes are based on relationships in order to provide insig...

  7. Vegetation and Terrain Relationships in South-Central New Mexico and Western Texas

    Science.gov (United States)

    1980-11-01

    QUlADRANTS CLASS FREQUENCY FREQUENCY __ Shrubs Acacia constricta 5 141.7 4.6 Agave lechequilla 1 1 8.3 0.9 Agave Parryi 3 1 25.0 2.8 Aloysia Wrightii...Wrightii and Tridens muticus. The shrub species were A .acia constricta, Agave sp., Dyssodia acerosa, Ephedra sp., Fouquieria splendens, Koe- berlina spinosa...dagger; Torrey yucca) AMARYLLIDACEAE (Amaryllis Family) Agave techegwitta,Torr. (lecheguilla) Agave Pauyq,Engelm. (mescal; Parry agave ) SALICACEAE

  8. Case of Rapid Progression of Hemiatrophy on the Face: A New Clinical Entity?

    Directory of Open Access Journals (Sweden)

    Hisashi Nomura

    2015-01-01

    Full Text Available A lot of diseases, including lupus profundus, morphea, lipodystrophy, and Parry-Romberg syndrome, may manifest progressive hemifacial atrophy. These diseases usually progress slowly and rapid progression of atrophy is extremely rare. We report a case of elderly-onset rapid progression of hemifacial atrophy only in three weeks. Our case did not meet variable differential diagnoses. We discuss the clinical character of the patient against the past of literature and suppose it may be a new clinical entity.

  9. Not Untitled.

    OpenAIRE

    McCaughey, Peter

    2012-01-01

    This chapter situates my own practice within an emergent field of urban intervention. It discusses the process, value of and inherent dangers in reframing interventionist practices and generating critical discourse around the 'invisible' and 'unofficial,' in interventionist practice.\\ud From the introduction:\\ud Cultural hijack is a term that cropped up in conversation with the editor, Ben Parry, in a bar in Glasgow some time ago. I was referring to that moment of being taken unawares by an e...

  10. LESSONS FROM THE EVALUATION OF A PUBLIC OUT-PATIENT SUBSTANCE ABUSE TREATMENT PROGRAMME IN THE WESTERN CAPE

    Directory of Open Access Journals (Sweden)

    Strebel, Anna

    2013-05-01

    Full Text Available Substance abuse is widely regarded as a major health and social problem in South Africa, and particularly in the Western Cape (Corrigall, Ward, Stinson, Struthers, Frantz, Lund, Flisher & Joska, 2007; Myers, Fakier & Louw, 2009. The complex nature of patterns of substance abuse, as well as the particular problems associated with this abuse, has implications for the development and implementation of treatment interventions. The most common primary drug of abuse in the Western Cape amongst patients admitted to treatment programmes is methamphetamine (known locally as “tik” (Dada, Plüddemann, Parry, Vawda & Fourie, 2012. The previous decade saw a dramatic rise in methamphetamine (hereafter indicated as MA use, particularly among youths, with over half the patients in treatment for MA abuse being younger than 25 years (Plüddemann, Parry, Dada, Bhana, Bachoo & Fourie, 2010. MA is also often used in combination with other drugs, and this prevalence of poly-substance abuse needs to be taken into account in the planning of services (Harker, Kader, Myers, Falkier, Parry, Flisher, Peltzer, Ramlagan & Davids, 2008.

  11. β-expansion attractors observed in A/D converters

    Science.gov (United States)

    Kohda, Tohru; Horio, Yoshihiko; Aihara, Kazuyuki

    2012-12-01

    The recently proposed β-encoders, analog-to-digital converters using an amplifier with a factor β and a flaky quantizer with threshold ν, have proven to be explained by the deterministic dynamics of multi-valued Rényi-Parry maps. Such a map is locally eventually onto [ν-1, ν), which is topologically conjugate to Parry's (β,α)-map with α =(β-1)(ν-1). This implies that β-encoders have a closed subinterval [ν-1,ν), which includes an attractor. Thus, the iteration of the multi-valued Rényi-Parry map performs the β-expansion of x while quantization errors in β-encoders behave chaotically and do not converge to a fixed point. This β-expansion attractor is relatively simpler than previously reported attractors. The object of this paper is twofold: to observe the embedded attractors in the β-encoder and to identify attractors that are useful for spread-spectrum codes and optimization techniques using pseudo-random numbers.

  12. Shot peening of doel 3 plant

    International Nuclear Information System (INIS)

    Slama, G.; Sort, M.

    1985-12-01

    The process implementation for DOEL consisted in: developing tooling and test procedures for an industrial application including ALARA considerations; qualifying process, tooling and procedures using representative conditions (full size mock-up, of steam generator channel head and associated working area); Establishing the reliability of tooling and procedures to comply permanently with the required criteria (chiefly Almen Intensity); and training and qualifying personnel. A variety of tests were performed by FRAMATOME and BELGATOM to qualify the process and characterize its effects on both inside and outside diameters of the tubes. These are: Mg Cl 2 ; 10% caustic tests at high temperature and pressure; tetrathionate; strain gauges and X rays stresses measurements; effects on precracked tubes; Leak tests after shot peening. The operation was performed at Doel in July 1985. Laboratory tests performed on mockups by FRAMATOME and BELGATOM could demonstrate that on tubes without cracks no difference was found between Eddy current signals from tubes shot-peened or not

  13. Total qualification of class 1E electric equipment

    International Nuclear Information System (INIS)

    Chauvin, G.

    1982-09-01

    For nuclear power plant projects in France, Framatome and its partners Electricite de France (EDF) and the Commissariat a l'Energie Atomique (CEA) have responded to the present qualification context by implementing a wide-ranging qualification program to acquire significant organizational and practical experience. The following sections detail Framatome's approach to the activities of an organization mandated to provide a complete spectrum of qualification services. Thorough implementation of a Class 1E electric equipment qualification program by the competent organization or qualifier entails completion of three consecutive steps: 1) program preparation, 2) program implementation, and 3) analysis of test results and conclusion. The qualifier assumes extensive responsibility for each of these steps. The following sections present test facilities used in France to conduct a total qualification program for Class 1E electric equipment

  14. German-French PWR cooperation

    International Nuclear Information System (INIS)

    Ruess, F.; Vignon, D.

    1990-01-01

    In April 1989, the two leading European nuclear power plant vendors, Framatome and Siemens, signed an agreement on cooperation covering the joint development and worldwide marketing of pressurized water reactors. For this purpose a joint subsidiary, Nuclear Power International (NPI) was founded, in which equal interests are held by Framatome and Siemens. The firm has its headquarters in Paris and another sales office in Erlangen. Its main activities are the coordination of the development of a joint advanced pressurized water reactor technology and the marketing of pressurized water reactors. Until the joint technology under development has reached commercial maturity, the lines so far developed by the parent companies will continue to be distributed. (orig.) [de

  15. Three Steam Generator Replacement Projects in 1995

    International Nuclear Information System (INIS)

    Holz, R.; Clavier, G.

    1996-01-01

    Since the companies Siemens AG and Framatome S. A. joined their experience and efforts in the field of steam generator replacements and formed a consortium in 1991, the following projects were performed in 1995: Ringhals 3, Tihange 3 and Asco 1. Further projects will follow in 1996, i. e., Doel 4 and Asco 2. Currently, this European consortium is bidding for the contract to replace the steam generators at the Krsko NPP and hopes to be awarded in 1996. An overview of the way the Consortium Siemens and Framatome approaches SG replacement projects is given based on the projects performed in 1995. Various aspects of project planning, management, licensing, personnel qualification and techniques used on site will be discussed. (author)

  16. Nuclear power industry

    International Nuclear Information System (INIS)

    1999-01-01

    This press dossier presented in Shanghai (China) in April 1999, describes first the activities of the Framatome group in the people's republic of China with a short presentation of the Daya Bay power plant and of the future Ling Ao project, and with a description of the technological cooperation with China in the nuclear domain (technology transfers, nuclear fuels) and in other industrial domains (mechanics, oil and gas, connectors, food and agriculture, paper industry etc..). The general activities of the Framatome group in the domain of energy (nuclear realizations in France, EPR project, export activities, nuclear services, nuclear fuels, nuclear equipments, industrial equipments) and of connectors engineering are presented in a second and third part with the 1998 performances. (J.S.)

  17. Improved statistical confirmation of margins for setpoints and transients

    International Nuclear Information System (INIS)

    Nutt, W.T.

    2001-01-01

    Framatome ANP Richland, Inc. has developed an integrated, automated, statistical methodology for Pressurized Water Reactors (PWRs). Margins for transients and calculated trips are confirmed using several new applications of probability theory. The methods used for combining statistics reduces the conservatisms inherent in conventional methods and avoids the numerical limitations and time constraints imposed by Monte Carlo techniques. The new methodology represents the state of the art in the treatment of uncertainties for reactor protection systems. It all but eliminates concerns with the calculated trips for PWRs and by improving the margin for all transients will allow for far more aggressive peaking limits and fuel management schemes. The automated nature of the bulk of this process saves Framatome ANP time and effort, minimizes the potential for errors and makes the analysis for all cycles and plants consistent. The enhanced margins remove analytical limitations from the customer and allow for more economical operation of the plant. (authors)

  18. Advanced fuel assemblies for economic and flexible operation of light water reactors

    International Nuclear Information System (INIS)

    Urban, P.; Bender, D.

    2001-01-01

    Increasing competition in the electricity market sets up a corresponding competition between the different electricity producing technologies. This makes further improvements in the economics of nuclear power generation a vital item for the future of nuclear energy. Though the costs for development, design and fabrication of fuel assemblies contribute only about 10% to the fuel cycle costs, the design and the performance of the fuel assemblies considerably influences total electricity generation cost. By the recent creation of Framatome ANP the nuclear activities of Framatome and Siemens were combined into one company. In the past, both had made considerable achievements in the development of fuel assemblies and related services supporting the goal of safe and economic electricity generation by light water reactors. The examples described in this paper cover former Siemens products and experience. In the future, our combined experience bases will be an ideal platform to offer further substantial improvements to our customers. (author)

  19. PWR: nuclear islands

    International Nuclear Information System (INIS)

    1989-01-01

    Framatome and its partners have produced this glossary of technical terms that can be used in writing English language documents relating to power plants (nuclear islands, individual components, nuclear services, etc.) with the hope of improving the quality of the documents intended for their clients, suppliers and partners and for others. This glossary will be particularly useful to the translators and authors of technical proposals, design documents, manufacturing documents, construction and operating documents concerning Pressurized Water Reactors written in English or French. It can also be useful as a reference document for students, researchers, journalists, etc., having to write on this subject. We would like to thank all those individuals working at the Ministere de la Recherche et de la Technologie, Electricite de France, Jeumont Schneider and Framatome who have contributed to this glossary. We would also appreciate any comments or sugestions intended to improve subsequent editions of this glossary [fr

  20. Plant life management

    International Nuclear Information System (INIS)

    Charbonneau, S.; Framatome, J.B.

    1992-01-01

    Plant life assessment and extension studies have been performed by numerous companies all over the world. Critical equipment has been identified as well as various degradation mechanisms involved in the plant aging process. Nowadays one has to think what to implement to improve the existing situation in the Nuclear Power Plant (NPP). FRAMATOME has undertaken this thought process in order to find the right answers and bring them to utilities facing either critical concern for plant life extension or the problem of management of power plant potential longevity. This is why we prepared a Plant Life Improvement Action Plan, comprising 10 (ten) major items described hereafter using examples of work performed by FRAMATOME for its utility customers desiring to manage the lives of their plants, both in France with EDF and abroad

  1. Maintenance or replacement of primary equipments

    International Nuclear Information System (INIS)

    Branchu, J.

    1995-01-01

    The principal materials, such as the primary equipments of a PWR type steam generator, have a finite service life. Framatome, builder of steam generators and maintenance contractor of Electricite de France has developed a methodology for the maintenance or the replacement of primary equipments. The paper describes the methodology followed by Framatome to identify and localize the wear mode and to treat or repair the component. Four failure modes have been considered: crack propagation, rubbing/vibration wear, neutron irradiation and corrosion propagation under permanent stress. A kinetic modelling of wear propagation has been computerized and validated using mechanical tests on Inconel 600 mockups. These analyses have allow to determine the strategy of repair or replacement of vessel heads for each unit. The method is evaluated taking into account the risk assessment, cost, dosimetry, efficiency and time delay involved. (J.S.). 1 fig., 3 photos

  2. Waste Package Misload Probability

    International Nuclear Information System (INIS)

    Knudsen, J.K.

    2001-01-01

    The objective of this calculation is to calculate the probability of occurrence for fuel assembly (FA) misloads (i.e., Fa placed in the wrong location) and FA damage during FA movements. The scope of this calculation is provided by the information obtained from the Framatome ANP 2001a report. The first step in this calculation is to categorize each fuel-handling events that occurred at nuclear power plants. The different categories are based on FAs being damaged or misloaded. The next step is to determine the total number of FAs involved in the event. Using the information, a probability of occurrence will be calculated for FA misload and FA damage events. This calculation is an expansion of preliminary work performed by Framatome ANP 2001a

  3. The Franko-German aproach for a nuclear power plant in Turkey

    International Nuclear Information System (INIS)

    Ruess, F.

    1994-01-01

    Nuclear Power International (N P1) has been established as a joint subsidiary of Siemens and Framatome in 1989, thereby combining the experience accumulated in both parent companies with more than 100,000 MW capacity installed or on order in nuclear field. We intend to compete in a potential nuclear power project in Turkey on the basis of the German Pressurized Water Reactor Technology. We intend to establish a Consortium which on the foreign suppliers side will include Siemens, Framatome and GEC-Alsthom. In addition to the foreign partners in the Consortium we will include the Turkish industry in our proposal in order to achieve a maximum possible local content, which in our previous proposal was in the range of 30 % of the contract-value

  4. Preserving maintenance know-how from a nuclear vendor's viewpoint

    International Nuclear Information System (INIS)

    Huemmeler, A.; Sprehe, J.

    2002-01-01

    The merging of Europe's major nuclear vendors to form Framatome ANP established the largest nuclear engineering corporation in the world, with a separate regional company based in the German market. The headquarters of the German company may be in Erlangen and the customers also see familiar faces at all locations in Germany. Within the new, globally aligned Framatome ANP, Siemens is contributing towards preserving this know-how on the domestic market. But we are still not satisfied. Not only do we wish to retain our expertise in the field of maintenance - in collaboration with the customers as well as other major service providers, but Siemens also wants to continuously improve and expand it even further in the future. (orig.) [de

  5. Surveillance of nuclear power reactors

    International Nuclear Information System (INIS)

    Marini, J.

    1983-01-01

    Surveillance of nuclear power reactors is now a necessity imposed by such regulatory documents as USNRC Regulatory Guide 1.133. In addition to regulatory requirements, however, nuclear reactor surveillance offers plant operators significant economic advantages insofar as a single day's outage is very costly. The economic worth of a reactor surveillance system can be stated in terms of the improved plant availability provided through its capability to detect incidents before they occur and cause serious damage. Furthermore, the TMI accident has demonstrated the need for monitoring certain components to provide operators with clear information on their functional status. In response to the above considerations, Framatome has developed a line of products which includes: pressure vessel leakage detection systems, loose part detection systems, component vibration monitoring systems, and, crack detection and monitoring systems. Some of the surveillance systems developed by Framatome are described in this paper

  6. Integrated services and maintenance in nuclear power plants

    International Nuclear Information System (INIS)

    Roos, Georg

    2001-01-01

    The general situation concerning services and nuclear power maintenance is reviewed following liberalization of Europa's power market. Issues relating to outsourcing maintenance services, effectiveness and reducing cost structure of maintenance are addressed on the cases of power markets in northern countries, Spain, Switzerland, Germany and Hungary. A special attention is paid on range of maintenance activity offered and performanced by Framatome. Ways of reducing costs in the field of maintenance as well as of reducing outage time are indicated. In conclusion, the following items are emphasized: - liberalization of Europe's power market in eastern Europe at its beginning; - in-house service in eastern Europe with numerous personnel; - Framatome ANP covers the entire range of maintenance competence; - consultance can be the first approach for a common co-operation

  7. Modular robotic applications in nuclear power plant maintenance

    International Nuclear Information System (INIS)

    Glass, S.W.; Ranson, C.C.; Reinholtz, C.F.; Calkins, J.M.

    1996-01-01

    General-purpose factory automation robots have experienced limited use in nuclear maintenance and hazardous-environment work spaces due to demanding requirements on size, weight, mobility and adaptability. Robotic systems in nuclear power plants are frequently custom designed to meet specific space and performance requirements. Examples of these custom configurations include Framatome Technologies COBRA trademark Steam Generator Manipulator and URSULA trademark Reactor Vessel Inspection Manipulator. The use of custom robots in nuclear plants has been limited because of the lead time and expense associated with custom design. Developments in modular robotics and advanced robot control software coupled with more powerful low-cost computers, however, are helping to reduce the cost and schedule for deploying custom robots. A modular robotic system allows custom robot configurations to be implemented using standard (modular) joints and adaptable controllers. This paper discusses Framatome Technologies (FTI) current and planned developments in the area of modular robot system design

  8. Ratchetting in PWR: on use of numerical simulations to reduce the conservatism of design rules

    International Nuclear Information System (INIS)

    Geyer, P.; Meziere, Y.; Taheri, S.

    1996-01-01

    The French design Code (RCC-M Code) for pressurised water nuclear power plants includes criteria with regard to the risk of progressive deformation. With the new operating conditions, some components no longer check this criteria. Therefore, R and D actions were initiated in 1991 by EDF, CEA and FRAMATOME with the aim of putting forward more suitable design criteria that the present rules, which seem to be too conservative. In the two first parts, this paper presents the RCC-M design rules with regard to the risk progressive deformation, the components that don't check the criteria, and the alternative solutions proposed by FRAMATOME. In the two last parts, we focus on one R and D study to show the theoretical and experimental ways used to solve the problem. Numerical simulations become necessary to model experimental results. But constitutive equations for cyclic plasticity derived from Chaboche model appear inadequate to get accurate predictions. (authors)

  9. The nuclear instrumentation system of the French 1400 MWe reactors

    International Nuclear Information System (INIS)

    Bourgerette, A.; Mauduit, J.P.

    1993-01-01

    The nuclear instrumentation systems in power reactors in France have made considerable advances thanks to technological progress. The appearance of an integrated digital protection system (SPIN) and the extension of digital techniques have considerably improved performance and operating flexibility. Working on the basis of technology developed jointly with the Nuclear Electronics and Instrumentation Department at the French Atomic Energy Commission (CEA), Framatome and Merlin Gerin have designed the new nuclear instrumentation system for 1400 MW reactors. (authors). 4 figs

  10. Simulation of control performance under house load transients for nuclear power plant

    International Nuclear Information System (INIS)

    Liao Zhongyue; Wang Yuanlong; Tang Yuyuan; Liu Jiong

    1999-01-01

    The CATIA2 code is used to simulate the extreme normal transients--house load transients of Qinshan Phase II 600 MW nuclear power plant. The simulating results show that all of the reactor main parameters are operating in the allowable ranges, the reactor system is stable, and the control characteristics of the nuclear power plant is satisfactory. They are also good in agreement with Framatome's results

  11. Modernization of electrical systems in NPP Kozloduy unit 5 and 6. Feedback of experience

    International Nuclear Information System (INIS)

    Stinshoff, H.

    2005-01-01

    In the frame of the modernization program for the nuclear power plant Kozloduy unit 5 and 6 Framatome ANP has implemented measures to increase the safety and availability of the electrical systems. The hardware installation is scheduled in the refueling outages of the years 2003 to 2005. In this paper the following items are presented: 1) an overview of the modernization measures; 2) some important technical features of the new equipment and diagnostic measures; 3) feedback of experience

  12. EPR: The reactor generation for the 21st century. SFEN-KTG congress 'The EPR Project'', Strasbourg, 13-14 Nov. 1994

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The foundation of the subsidiary in 1989, Nuclear Power International (NPI), brought together as partners the two formerly competing companies Siemens/KWU and Framatome who now are planning the novel reactor type within the framework of the joint EPR project. The project goal is to develop a novel French-German PWR reactor type for power generation, named European Pressurized Water Reactor (EPR). The article summarizes the main results of papers and discussions of the congress. (orig./UA) [de

  13. The TS 600: automatic control system for eddy currents

    International Nuclear Information System (INIS)

    Poulet, J.P.

    1986-10-01

    In the scope of fabrication and in service inspection of the PWR steam generator tubing bendle, FRAMATOME developed an automatic Eddy Current testing system: TS600. Based on a mini-computer, TS600 allows to digitize, to store and to process data in various ways, so it is possible to perform several kinds of inspection: conventional inservice inspection, roll area profilometry...... TS600 can also be used to develop new methods of examination [fr

  14. The selection of quality assurance regulations by a developing country

    International Nuclear Information System (INIS)

    Perrin, R.

    1982-01-01

    The negotiations of Framatome in recent years with potential customers (both advanced and developing countries) have led to the following conclusions. A developing country which orders a nuclear power plant may adopt one of several attitudes to quality assurance: (1) it may show no interest at all, though this category of customer is on the wane; (2) it may establish its own regulations, but this course poses problems of both cost and competence; (3) it may use American standards, which are also indirectly applied to French PWR plants since the reference power plants used are American. Up to 1979, Framatome advocated the last approach in its negotations. The American nuclear quality assurance standards are the oldest in existence and reflect the experience gained from the longest period of application. In addition, the application of those standards is monitored in the USA by the organizations which issue or adopt them. (4) The country may adopt other equivalent regulations available on the market. Although not American, these provide the same guarantees and benefit from the experience on which the deserved popularity of the American standards is based. Since 1979, Framatome has considered that the IAEA Code of Practice meets these specifications and will from now on suggest in its export bids that this Code be applied. The Code is an international guide, published in four languages, and advocates the same guarantees as American texts. In addition, since EDF and Framatome have decided to apply the IAEA Code to French PWR plants as of 1980, experience gained through applying the Code and the resultant legal knowledge will quickly build up. The adoption of the Code of Practice by purchasing countries should further their relations with suppliers, facilitate the technical assistance provided by the latter, and enable the purchaser to find in most supplier countries the same code as that which he applies himself and to employ a variety of suppliers, if need be, without

  15. Nuclear energy

    International Nuclear Information System (INIS)

    1996-01-01

    Several issues concerning nuclear energy in France during 1996 are presented: permission of a demand for installing underground laboratories in three sites (Marcoule, Bure and Chapelle-Baton); a report assessing the capacity of Superphenix plant to operate as a research tool; the project of merging between Framatome and Gec-Alsthom companies; the revision of a general report on nuclear energy in France; the issue of military plutonium management

  16. Reactor safety research in France

    International Nuclear Information System (INIS)

    Bussac, J.; Zammite, R.

    1989-01-01

    The paper deals withs PWR research only and covers programs performed in CEA or in cooperation between CEA and EDF or Framatome. Emphasis is being given to core cooling faults and associated procedures, primary circuit two-phase thermohydraulics, core damage, safeguarding of confinement, evaluation of accidental releases, and management of accident consequences. Most of the design and construction adequacy problems have already been solved in a generic manner, nevertheless new designs are now being studied and may require complementary research. (DG)

  17. A decade of reconstruction

    International Nuclear Information System (INIS)

    Christopher, Thomas A.

    2004-01-01

    This article is an excerpt from an interview of Thomas A. Christopher, President and Chief Executive Officer, Framatome, ANP, Inc. conducted at NEI's Nuclear Energy Assembly in New Orleans, Louisiana on 13 May 2004. Areas highlighted include the views on how European plant standards compare to those in the US, key differences between European and US NRC requirements, design differences, fuel cost and plant life extension and upgrade impacts on the economy, company training and outsourcing issues, and ending with success stories

  18. Improvement of the characterization of ultrasonic data by means of digital signal processing

    International Nuclear Information System (INIS)

    Bieth, M.; Romy, D.; Weigel, D.

    1985-01-01

    The digital signal processing method for averaging using minima developed by Framatome allows to improve signal-to-noise ratio up to 7 dB during ultrasonic testing of cast stainless steel structures (primary pipes of PWR power plants). Application of digital signal processing to industrial testing conditions requires the availability of a fast analog-digital converter capable of real time processings which has been developed by CGR [fr

  19. Nuclear engineering and manufacturing technology transfer coproduction with technical assistance

    International Nuclear Information System (INIS)

    Marillier, J.C.; Boury, C.

    1985-10-01

    This paper emphasizes in the specific areas of design, engineering, and component production. This paper presents what Framatome has to offer in these areas and its export oriented philosophy. Then, a typical example of successful implementation of this technology transfer philosophy is the collaboration with the South Korean firm, Korea Heavy Industries Corporation (KHIC) for the supply of KNU 9 and KNU 10 power stations

  20. A solution to level 3 dismantling of gas-cooled reactors: Graphite incineration

    International Nuclear Information System (INIS)

    Dubourg, M.

    1993-01-01

    This paper presents an approach developed to solve the specific decommissioning problems of the G2 and G3 gas cooled reactors at Marcoule and the strategy applied with emphasis in incinerating the graphite core components, using a fluidized-bed incinerator developed jointly between the CEA and FRAMATOME. The incineration option was selected over subsurface storage for technical and economic reasons. Studies have shown that gaseous incineration releases are environmentally acceptable

  1. Areva: a future to be prepared; Areva: un avenir a preparer

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The Areva group was created on September 3, 2001 from the fusion of the activities of CEA-Industrie, Framatome and Cogema. It is today one of the first world actor of the nuclear sector, of the sector of new technologies and of the sector of connectors engineering. This paper recalls the factors that led to a reorganization of the French nuclear sector and to the creation of the Areva group. It briefly summarizes the forthcoming missions of Areva. (J.S.)

  2. Design and qualification of nuclear fittings

    International Nuclear Information System (INIS)

    Coppolani, P.

    1985-01-01

    This paper gives a definition of nuclear fittings and presents its characteristics, its operating conditions and the safety function that they ensure. The classification of fittings and the consequences on its design are presented. The procedures of design verification and the validation in loop are given. Two equipments are finally presented: the Framatome Velan Rateau valve and the VR3-1500 LB valve [fr

  3. Quality assurance in the fuel fabrication

    International Nuclear Information System (INIS)

    Darmayan, P.

    1995-01-01

    The paper concentrates on the evolutions that FBFC Franco Belge de Fabrication de Combustible has initiated in order to make a further step in improving quality: 1. Improving each personnel's involment and responsability towards quality. 2. Incorporating quality assurance in a total quality management policy, involving both the fabrication teams of FBFC and the design teams of Framatome in order to improve quality. (orig./HP)

  4. Areva's privatization uncertainties

    International Nuclear Information System (INIS)

    Jemain, A.

    2004-01-01

    The French nuclear public group Areva (the fusion of CEA-Industrie, Framatome and Cogema companies) will actively prepare its privatization and stock exchange introduction before the end of the first half of 2005, in order to re-launch its acquisitions and associations policy. However, the advantages of this privatization with a preponderant public share-holding will depend on the intentions of the French government. Short paper. (J.S.)

  5. Preventive detection of incipient failure and improvement of availability of French PWR using acoustic emission

    International Nuclear Information System (INIS)

    Audenard, B.; Marini, J.

    1982-08-01

    Laboratory tests, on site experience gained on PWR during start up test as well as during nominal functioning have given FRAMATOME very great confidence in A.E. techniques for preventive detection of incidents. Loose part and leakage monitoring are already being used on an industrial basis. Crack growth detection and monitoring are still in the investigation phase and various. Research and Development programs are presently being carried out

  6. Simulation of the control rod drop under seismic excitations. Experimental program

    International Nuclear Information System (INIS)

    Chaudat, Th.

    2001-01-01

    This paper describes the experimental program that will be performed at the end of 1998 at the CEA Saclay on a specially constructed analytical mock-up of a control rod. The purpose of these tests is to partially validate the current methodology of the drop time numerical calculations of a PWR (pressurized water reactor) control rod under seismic excitations. The French nuclear partners (EDF and FRAMATOME) are involved in this program. (author)

  7. Water-hammer in the feed-water pipes for PWR steam generators

    International Nuclear Information System (INIS)

    Gonnet, Bernard; Leroy, Claude; Oullion, Jean; Yazidjian, J.-C.

    1979-01-01

    PWR boiler water feed pipes have been known for several years to be affected by violent water-hammer during start-ups and operation of the plant. In view of the varying results of corrective design modifications in America and Europe, FRAMATOME undertook an experimental research programme which resulted in the adoption of cruciform tubes on the feed-water distributor as the most reliable solution. Subsequent tests at Fessenheim I confirmed the effectiveness of this device [fr

  8. French participation to PISC III

    International Nuclear Information System (INIS)

    Birac, C.

    1994-06-01

    The PISC III programme was set up in 1986 after the conclusions of the PISC II programme. The main objective was assessment of ISI procedures on few particular components or materials. France with IPSN, CEA/DTA, DCN INDRET, EDF, FRAMATOME and INTERCONTROLE decided to have an important participation in several of the eight actions. This paper describes shortly the key points of this participation and the consequences in France. (authors). 10 figs., 1 tab

  9. Demands on project management of comprehensive modernization projects in the electrical systems area. Example of modernization of electrical systems of Kozloduy NPP Unit 5 and 6

    International Nuclear Information System (INIS)

    Stinshoff, Helmut; Weber, Patrick

    2006-01-01

    In nuclear power plants, station supply with electric energy must be guaranteed any time. This applies in particular also during the implementation of complex electrical systems modernization projects. Highest demands on the project management, extensive experience and system knowledge are required. In the frame of the Modernization Program for the nuclear power plant Kozloduy unit 5 and 6 in Bulgaria Framatome ANP has approved its ability to implement a large scope of modernization measures during the refueling outages of the years 2003 to 2005. The Contract of the Modernization Program for the European Consortium Kozloduy (Framatome ANP, Atomenergoexport) was signed in July 1999 and became effective in June 2001. The project will be finished by May 2006, with the approval of the Updated Final Safety Analysis Report. The scope of hardware work has been implemented within 6 plant outages during the years 2002 to 2005. The focus of the Modernization Program is mainly oriented to nuclear safety aspects, with the aim of upgrading of the Units to a high safety level in compliance with international practice. A further section of the project is dedicated to upgrading of operational equipment. Framatome ANP personnel have shown that besides the technical challenges which had to be faced, also the intercultural and language barriers were successfully overcome. The good teamwork between the partners of the Consortium ECK, its Bulgarian subcontractors and with Kozloduy plant personnel has been an important success factor. (authors)

  10. Inspection and replacement of baffle assembly screws inside American reactor vessels

    International Nuclear Information System (INIS)

    Neal, K.; Chaumont, J.C.

    1999-01-01

    The baffle assembly inside the vessel of a 900 MWe reactor designed by Framatome, is made up of 44 plates fixed on 8 horizontal supports by a system of about 1000 screws. These plates undergo high neutron flux and the problem of screw cracking appeared at the end of the eighties in the first-generation reactors. The first operation on a large scale concerning the screws of a Westinghouse type reactor, was performed on the Tihange-1 power plant where Framatome controlled 960 screws and replaced 91. In 1997 as a consequence of the Belgian and French feedback experience, American plant operators launched a vast program of preventive actions: material analysis, inspection of baffle plate screws and replacement of defective screws. This program was held in cooperation with EPRI (electric power research institute) and under the control of NRC (nuclear regulatory commission). Framatome Technologies Inc (FTI) was in charge of the in-situ inspection and replacement of the screws. FTI designed special tools and equipment adapted to the 2-loop American reactors but the basis ideas were those applied on the Tihange reactor. The successful experience of FTI has allowed the firm to be commissioned for 6 2-loops American reactors. (A.C.)

  11. The European Pressurized Water Reactor (EPR). State of the art after the preliminary design phase

    International Nuclear Information System (INIS)

    Bouteille, F.; Schneider, D.

    2002-01-01

    The European Pressurized Water Reactor (EPR) is an evolutionary development of the pressurized water reactor product lines built by Framatome and Siemens in France and Germany. Under the technical leadership of both nuclear power plant suppliers (now merged in Framatome ANP, a joint venture of AREVA and Siemens) the future-oriented plant concepts was developed in close cooperation with German and French utilities and in compliance with the European Utility Requirements. The EPR has safety features with which even extremely improbable, beyond design-basis events can be controlled and their effects can be limited to such an extent that no emergency response actions need be taken outside of the immediate plant site. This also means that safety systems prevent containment failure even in the improbable case of a core melt. This was confirmed by the French and German reactor safety authorities. The selected high thermal output also insures the economic viability of the innovative reactor concept, so that the power generation costs which can be achieved with the EPR will be absolutely competitive with those of fossil energy carriers. Framatome ANP has thus developed a pressurized water reactor ready for offer at the right time, which can completely fulfill the most rigorous requirements in terms of nuclear safety and economy. (Author)

  12. Analysis of stratification effects on mechanical integrity of pressurizer surge line

    International Nuclear Information System (INIS)

    Thomas-Solgadi, E.; Taupin, P.; Ensel, C.

    1992-01-01

    Unexpected thermal movements in pressurizer surge lines have been reported by several PWR operating utilities. Sometimes gaps between pipe and pipe whip restraints can become closed and plastic deformations could result. Moreover these movements, which have not been considered at conception, can induce additional stresses, and design limits on fatigue and stresses may be exceeded. These piping movements are caused by thermal stratification phenomenon in the horizontal part of the surge line (difference of temperature between hot leg and pressurizer varying from 30 C to above 160 C). To assess the mechanical consequences of this 3-dimensional phenomenon, FRAMATOME has developed a computer program using simplified models (1 and 2-dimensional). This method integrates past investigations on thermal-hydraulic variation of the stratification based on plant monitoring programs carried out by FRAMATOME since 1981, and based also on thermal-hydraulic tests and thermal-hydraulic computer code results. The methodology developed by FRAMATOME permits the following calculations: movements of the line in the elastic and plastic domains; stresses (Mises criterion -- calculations in compliance with ASME or RCC-M codes); usage factors in different components (elbows, welds, ...); crack propagation taking into account stratification and plastic shakedown

  13. Coherence of reactor design and fuel element design

    International Nuclear Information System (INIS)

    Vom Scheidt, S.

    1995-01-01

    Its background of more than 25 years of experience makes Framatome the world's leading company in the design and sales of fuel elements for pressurized water reactors (PWR). In 1994, the fuel fabrication units were incorporated as subsidiaries, which further strengthens the company's position. The activities in the fuel sector comprise fuel element design, selection and sourcing of materials, fuel element fabrication, and the services associated with nuclear fuel. Design responsibility lies with the Design and sales Management, which closely cooperates with the engineers of the reactor plant for which the fuel elements are being designed, for fuel elements are inseparable parts of the respective reactors. The Design and Sales Management also has developed a complete line of services associated with fuel element inspection and repair. As far as fuel element sales are concerned, Framatome delivers the first core in order to be able to assume full responsibility vis-a-vis the customer for the performance of the nuclear steam supply system. Reloads are sold through the Fragema Association established by Framatome and Cogema. (orig.) [de

  14. GTM (Guangdong ten year modifications): the Chinese experience in plant safety alignment

    International Nuclear Information System (INIS)

    Louvat, J.-P.; Chauvin, T.

    2005-01-01

    The present article introduces the recent experience by Framatome-ANP of developing a large scale engineering project in China. The so-called GTM project deals with the studies and the site implementation of a dozen of major design improvements at the Guangdong Nuclear Power Station on Daya Bay site, stemming from the Periodic Safety Reassessment (PSR) carried-out by the Utility. This article focuses on the benefits of sharing with the Chinese utility the long experience of the study of the modification batches 'lot93' and 'VD2' implemented on the French CPY 900 MWe series units and on the confidence gained throughout years of continuous sinofrench technical cooperation that was established by the plant owner in Framatome- ANP's capabilities to carry-out the successful development of the project. Indeed Framatome-ANP involved its Chinese partners Beijing Institute of Nuclear Engineering, China Nuclear Industry 23rd Company and Shenzhen Nuclear Engineering Company to localize design and erection activities. The successful achievement of the GTM studies proved the maturity of the Chinese engineering competencies to set-up a sustainable industrial scheme devoted to the further development of nuclear engineering services in China. (authors)

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

    International Nuclear Information System (INIS)

    Nigon, J.L.

    1987-01-01

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

  16. PWR reactor vessel in-service-inspection according to RSEM

    International Nuclear Information System (INIS)

    Algarotti, Marc; Dubois, Philippe; Hernandez, Luc; Landez, Jean Paul

    2006-01-01

    Nuclear services experience Framatome ANP (an AREVA and Siemens company) has designed and constructed 86 Pressurized Water Reactors (PWR) around the world including the three units lately commissioned at Ling Ao in the People's Republic of China and ANGRA 2 in Brazil; the company provided general and specialized outage services supporting numerous outages. Along with the American and German subsidiaries, Framatome ANP Inc. and Framatome ANP GmbH, Framatome ANP is among the world leading nuclear services providers, having experience of over 500 PWR outages on 4 continents, with current involvement in more than 50 PWR outages per year. Framatome ANP's experience in the examinations of reactor components began in the 1970's. Since then, each unit (American, French and German companies) developed automated NDT inspection systems and carried out pre-service and ISI (In-Service Inspections) using a large range of NDT techniques to comply with each utility expectations. These techniques have been validated by the utilities and the safety authorities of the countries where they were implemented. Notably Framatome ANP is fully qualified to provide full scope ISI services to satisfy ASME Section XI requirements, through automated NDE tasks including nozzle inspections, reactor vessel head inspections, steam generator inspections, pressurizer inspections and RPV (Reactor Pressure Vessel) inspections. Intercontrole (Framatome ANP subsidiary dedicated in supporting ISI) is one of the leading NDT companies in the world. Its main activity is devoted to the inspection of the reactor primary circuit in French and foreign PWR Nuclear Power Plants: the reactor vessel, the steam generators, the pressurizer, the reactor internals and reactor coolant system piping. NDT methods mastered by Intercontrole range from ultrasonic testing to eddy current and gamma ray examinations, as well as dye penetrant testing, acoustic monitoring and leak testing. To comply with the high requirements of

  17. Thermodynamic and dynamic ice thickness contributions in the Canadian Arctic Archipelago in NEMO-LIM2 numerical simulations

    Science.gov (United States)

    Hu, Xianmin; Sun, Jingfan; Chan, Ting On; Myers, Paul G.

    2018-04-01

    Sea ice thickness evolution within the Canadian Arctic Archipelago (CAA) is of great interest to science, as well as local communities and their economy. In this study, based on the NEMO numerical framework including the LIM2 sea ice module, simulations at both 1/4 and 1/12° horizontal resolution were conducted from 2002 to 2016. The model captures well the general spatial distribution of ice thickness in the CAA region, with very thick sea ice (˜ 4 m and thicker) in the northern CAA, thick sea ice (2.5 to 3 m) in the west-central Parry Channel and M'Clintock Channel, and thin ( Program data at first-year landfast ice sites except at the northern sites with high concentration of old ice. At 1/4 to 1/12° scale, model resolution does not play a significant role in the sea ice simulation except to improve local dynamics because of better coastline representation. Sea ice growth is decomposed into thermodynamic and dynamic (including all non-thermodynamic processes in the model) contributions to study the ice thickness evolution. Relatively smaller thermodynamic contribution to ice growth between December and the following April is found in the thick and very thick ice regions, with larger contributions in the thin ice-covered region. No significant trend in winter maximum ice volume is found in the northern CAA and Baffin Bay while a decline (r2 ≈ 0.6, p < 0.01) is simulated in Parry Channel region. The two main contributors (thermodynamic growth and lateral transport) have high interannual variabilities which largely balance each other, so that maximum ice volume can vary interannually by ±12 % in the northern CAA, ±15 % in Parry Channel, and ±9 % in Baffin Bay. Further quantitative evaluation is required.

  18. The Effect of Propellant Optical Properties on Composite Solid Propellant Combustion

    Science.gov (United States)

    1991-01-01

    10.0 [cal/gJ CpAP . = 1.3 [J/(g K)1 LhrMp =433. [cal/g] CpfTBp = 1.3 [J/(g K)] Using the experimental burning rates, the surface temperatures of the AP...Photo- Flash Lamps." Journatl of the Optical Society of North America, Vol. 37, No. 8. pp. 652-659, 1947. 17. Parry, D.L.. Ph.D. Thesis, The University of...the light emitters in photoflash lamps. In 1947, Brockman 4 made spectroscopic measurements of the light emitted by flash lamps filled with aluminum

  19. Contributions of research Reactors in science and technology

    International Nuclear Information System (INIS)

    Butt, N.M.; Bashir, J.

    1992-12-01

    In the present paper, after defining a research reactor, its basic constituents, types of reactors, their distribution in the world, some typical examples of their uses are given. Particular emphasis in placed on the contribution of PARR-I (Pakistan Research Reactor-I), the 5 MW Swimming Pool Research reactor which first became critical at the Pakistan Institute of Nuclear Science and Technology (PINSTECH) in Dec. 1965 and attained its full power in June 1966. This is still the major research facility at PINSTECH for research and development. (author)

  20. The Toxicity of Inhaled Sulphur Mustard

    Science.gov (United States)

    2012-10-01

    lobes, weighed and then dried in an oven (40 oC). The samples were weighed daily until a stable weight had been achieved (approx. 5 days), to...into account). Lung samples were taken, weighed and then dried in an oven (40o C) until a stable weight had been achieved, to determine lung wet...large porcine model: A 6 hour study. Inhal. Tox. (in press). 16. Garner JP, Watts S, Parry C, Bird J and Kirkman E. 2009. Development of a large

  1. Agricultural land purchases for alternative uses – evidence from two farming areas in the Western Cape province, South Africa

    CSIR Research Space (South Africa)

    Reed, LL

    2009-09-30

    Full Text Available to spend on other activities (Healy & Short, 1978:185; Parris, 2004:197; Maybery et al., 2005:59; Holmes, 2006:142-144). Increased incomes around the world have led to a change in tastes and societal values, where people have become more environmentally... al., 2003:22). Rural areas with open space, close to natural amenities with aesthetic or recreational appeal has become an attractive alternative for people who want to escape from overpopulated cities with congested traffic, or as a place to cash...

  2. Uyt saecke des doots. Het belastbare feit van de erfbelasting begrepen, hervormd en toegepast

    OpenAIRE

    Kooiman, Willem Reynder

    2016-01-01

    In the Netherlands, levying tax on inheritances at death has been a fact of life for centuries. The presumed double taxation and its sad precursor are elements of the discussion about the levy of this inheritance tax, but so too are the possibilities to reduce the tax through ingenious legal constructions. In its zeal to counter such clever plans the legislature has turned the law into a complex body without parrying all the avoidance behaviour. On top of that, the effects of the current law ...

  3. Successful autologous hematopoietic stem cell transplantation for a patient with rapidly progressive localized scleroderma.

    Science.gov (United States)

    Nair, Velu; Sharma, Ajay; Sharma, Sanjeevan; Das, Satyaranjan; Bhakuni, Darshan S; Narayanan, Krishnan; Nair, Vivek; Shankar, Subramanian

    2015-03-01

    Autologous hematopoietic stem cell transplant (HSCT) for rapidly progressive disease has not been reported in localized scleroderma. Our patient, a 16-year-old girl had an aggressive variant of localized scleroderma, mixed subtype (linear-generalized) with Parry Romberg syndrome, with no internal organ involvement, that was unresponsive to immunosuppressive therapy and was causing rapid disfigurement. She was administered autologous HSCT in June 2011 and has maintained drug-free remission with excellent functional status at almost 3.5 years of follow-up. © 2015 Asia Pacific League of Associations for Rheumatology and Wiley Publishing Asia Pty Ltd.

  4. Indonesia, Malaysia, and the Philippines Security Cooperation in the Celebes Sea

    Science.gov (United States)

    2008-06-01

    html (accessed April 1, 2008). 141 Parkinson, Tony, “ Mahathir Agrees to Pact on Terror,” The Age, August 1, 2002, National News. 142 “Malaysia...Counterterrorism Center,” Department of State, http://www.state.gov/r/pa/prs/ps/2003/25047.htm (accessed June 5, 2008). 143 Tony Parkinson, “ Mahathir ...9, 2005. Parkinson, Tony. “ Mahathir Agrees to Pact on Terror.” The Age, August 1, 2002, National News Section. Parry, Richard Lloyd. “Carnage and

  5. Full system decontamination (FSD) at NPP Stade prior to dismantling activities

    International Nuclear Information System (INIS)

    Christoph Stiepani; Karl Seidelmann

    2006-01-01

    Full text of publication follows: Introduction: Minimization of personnel dose rates and generation of material free for release is of the highest priority and requires Full System Decontamination (FSD) as a first and important measure when decommissioning Nuclear Power Plants. Framatome ANP has many years experience with Full System Decontaminations for operating nuclear power plants in general and for decommissioning in particular. The latest decommissioning project was the FSD at the PWR Stade which was permanently shut down in November 2003 after 31 years of operation. FSD was scheduled within a short period after shutdown and prior to decommissioning activities. Full System Decontamination at Stade: The PWR Stade is a 4 loop design. FSD included the entire primary circuit with RPV and the auxiliary systems (RHR, VCS and RWCU). The decontamination circuit had a total volume of ∼310 m 3 and an overall surface of ∼17000 m 2 . The Framatome ANP decontamination process HP/CORD R UV was selected for application. The decontamination was performed by using NPP systems in combination with the Framatome mobile decontamination equipment AMDA R (Automated Mobile Decontamination Appliance). A total of 4 decontamination cycles were performed and excellent results were obtained. The average decontamination factor (DF) was 160 for the steam generators with an outstanding ambient dose reduction factor (DRF) of 75. Conclusions: FSD at the PWR Stade has shown that the HP/CORD UV process yields excellent results in primary and auxiliary systems. The significant ambient dose reduction factor of 75 is remarkable. This very high DRF, no other decontamination application came even close, will result in excellent cost-benefit ratios for additional decommissioning activities at Stade. The applied HP/CORD UV process is not a specific decontamination process for decommissioning. Therefore the obtained decontamination and dose reduction factors demonstrate the advantage/potential for

  6. Você conhece esta síndrome? Do you know this syndrome?

    Directory of Open Access Journals (Sweden)

    Luciana Baptista Pereira

    2007-02-01

    Full Text Available Trata-se de criança de oito anos, portadora de atrofia na hemiface direita, desde os seis anos. A ressonância magnética do encéfalo evidenciou espessamento cortical e formação de cistos. A hemiatrofia facial progressiva, ou síndrome de Parry-Romberg, mais freqüente nas duas primeiras décadas de vida, caracteriza-se por atrofia unilateral da face, acometendo área inervada por um ou mais ramos do trigêmeo. A relação dessa síndrome com a esclerodermia localizada é discutida.The authors report a case of an 8-year-old child with facial hemiatrophy since the age of 6. A resonance imaging showed areas of white matter hyperintensity and cysts. Progressive facial hemiatrophy (Parry-Romberg syndrome usually develops during the first or second decade of life. It is characterized by unilateral facial atrophy affecting dermatomes of one or multiple branches of the trigeminal nerve. The relationship between progressive facial hemiatrophy and scleroderma is discussed.

  7. The Arctic: Glacial Refugium or Area of Secondary Contact? Inference from the Population Genetic Structure of the Thick-Billed Murre (Uria lomvia), with Implications for Management.

    Science.gov (United States)

    Tigano, Anna; Damus, Martin; Birt, Tim P; Morris-Pocock, Jamie A; Artukhin, Yuri B; Friesen, Vicki L

    2015-01-01

    Quaternary glaciations affected the distribution of many species. Here, we investigate whether the Arctic represented a glacial refugium during the Last Glacial Maximum or an area of secondary contact following the ice retreat, by analyzing the genetic population structure of the thick-billed murre (Uria lomvia), a seabird that breeds throughout the North Atlantic, North Pacific and Arctic Oceans. The thick-billed murre is a species of socio-economic importance and faces numerous threats including hunting, oil pollution, gill netting, and climate change. We compared variation in the mitochondrial DNA (mtDNA) control region (n = 424), supplemented by 4 microsatellite loci (n = 445), among thick-billed murres sampled throughout their range. MtDNA data indicated that colonies comprise 4 genetically differentiated groups (Φst = 0.11-0.81): 1) Atlantic Ocean plus New Siberian Islands region, 2) Cape Parry, 3) Chukchi Sea, and 4) Pacific Ocean. Microsatellite variation differed between Atlantic and Pacific populations. Otherwise, little substructure was found within either ocean. Atlantic and Pacific populations appear to have been genetically isolated since the last interglacial period and should be considered separate evolutionary significant units for management. The Chukchi Sea and Cape Parry appear to represent areas of secondary contact, rather than arctic refugial populations. © The American Genetic Association 2015. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  8. The yawning chasm of French nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    This is an account of a paper appeared in Energy Economist, February 1988 and contains a severe critique of the French nuclear power policy, in particular the Electricite de France, Cogema and Framatome. It is argued that the blueprint of the original nuclear power program has not been achieved in many topics. Points of critique to the EdF are: the electricity price, overcapacities and financial indeptedness. The French industries are not flourishing due to ample supply of cheap energy, nor do French nuclear manufacturers sell the fast breeder technology throughout the world. (qui)

  9. General meeting. Technical reunion: the numerical and experimental simulation applied to the Reactor Physics; Assemblee generale. Reunion technique: la simulation numerique et experimentale appliquee a la physique des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-10-01

    The SFEN (French Society on Nuclear Energy), organized the 18 october 2001 at Paris, a technical day on the numerical and experimental simulation, applied to the reactor Physics. Nine aspects were discussed, giving a state of the art in the domain:the french nuclear park; the future technology; the controlled thermonuclear fusion; the new organizations and their implications on the research and development programs; Framatome-ANP markets and industrial code packages; reactor core simulation at high temperature; software architecture; SALOME; DESCARTES. (A.L.B.)

  10. Automatic systems for opening and closing reactor vessels, steam generators, and pressurizers

    International Nuclear Information System (INIS)

    Samblat, C.

    1990-01-01

    The need for shorter working assignments, reduced dose rates and less time consumption have caused Electricite de France and Framatome to automate the entire procedure of opening and closing the main components in the primary system, such as the reactor vessel, steam generator, and pressurizer. The experience accumulated by the two companies in more than 300 annual revisions of nuclear generating units worldwide has been used as a basis for automating all bolt opening and closing steps as well as cleaning processes. The machines and automatic systems currently in operation are the result of extensive studies and practical tests. (orig.) [de

  11. Expert systems and computer based industrial systems

    International Nuclear Information System (INIS)

    Dunand, R.

    1989-01-01

    Framentec is the artificial intelligence subsidiary of FRAMATOME. It is involved in expert-system activities of Shells, developments, methodology and software for maintenance (Maintex) and consulting and methodology. Specific applications in the nuclear field are presented. The first is an expert system to assist in the piping support design prototype, the second is an expert system that assists an ultrasonic testing operator in determining the nature of a welding defect and the third is a welding machine diagnosis advisor. Maintex is a software tool to provide assistance in the repair of complex industrial equipment. (author)

  12. Vibrations measurement in fast and PWR reactor study

    International Nuclear Information System (INIS)

    Tigeot, Y.; Epstein, A.; Hareux, F.

    1975-01-01

    In the past severe damages have occured in several nuclear reactors, by structural vibrations induced by the primary cooling flow. To avoid this kind of troubles, the SEMT makes studies for two different types of reactors. For the light pressurized water reactors, some tests have been made on the SAFRAN test loop which is a three loop 1/8 scale internal model of a 900 MWe reactor. This study is actually undertaken jointly with Framatome. Elsewhere, measurements have been made on the Phenix fast breeder sodium reactor, and studies are planned for the Super Phenix reactor [fr

  13. Application of directional solidification ingot (LSD) in forging of PWR reactor vessel heads

    International Nuclear Information System (INIS)

    Benhamou, C.; Poitrault, I.

    1985-09-01

    Creusot-Loire Industrie uses this type of ingot for manufacture of Framatome 1300 and 1450 MW 4-loop PWR reactor vessel heads. This type of ingot offers a number advantages: improved internal soundness; greater chemical, structural and mechanical homogeneity of the finished part; simplified forging process. After a brief description of the pouring and solidification processes, this paper presents an analysis of the results of examinations performed on the prototype forging, as well as review of results obtained during industrial fabrication of dished heads from LSD ingots. The advantages of the LSD ingot over conventional ingots are discussed in conclusion

  14. Three-dimensional testing of power plant components

    International Nuclear Information System (INIS)

    Martin, A.

    1989-01-01

    Industrial photogrammetry is a dimensional checking procedure whose main advantages are the fast acquisition of the basic data (image), contactless inspection, and independent data processing. As a result of these basic characteristics, photogrammetry is particularly well suited to the maintenance of nuclear power plants. Since 1983, Framatome has employed photogrammetry in a number of cases for 3D dimensional checks and inspections of systems for repair purposes. To this day, e.g., the tube plates of steam generators have been inspected, the dimensional stability of the support rings in steam generators have been checked, and the alignment pins of fuel elements have been examined in this way. (orig.) [de

  15. Transfer of technology in maintenance tools

    International Nuclear Information System (INIS)

    Delorme, H.; Cartry, J.P.

    1985-10-01

    For maximum reliability of maintenance operations, FRAMATOME has aimed to improve the accessibility of highly irradiated and contaminated reactor coolant system equipment by the active promotion of an automation and robotization strategy. A number of robot designs have been developed providing replacement of operators inside the steam generator channel head, smooth handling of heavy or cumbersome objects in this zone, easy marking of steam generator tubes and increased speed of repetitive channel head operations: maintenance spider, theta-theta prime robotic service arm, R-theta robotic service arm, remote manipulator arm. Two operations are described: channel head folding cover plate and, operation of the torquing machine for head cover plate

  16. Design and construction of nuclear power plants for export. Adaptation of a reference plant from a series in a national power generating program

    International Nuclear Information System (INIS)

    Marcaillou, J.; Haond, H.

    1977-01-01

    The recent evolution of primary energy supplies places those countries having a nuclear industry in an exporting role. Exporting countries have generally developed a limited number of national reactor types and attempt to extend their manufacture with as few changes as possible. The E.D.F. in France is implementing an important PWR 900 MW program based on FRAMATOME nuclear reactors, initially conceived by WESTINGHOUSE. Such standardization poses certain problems for the importing countries. These problems and ways in which they can be solved are discussed [fr

  17. An example of RCCM application to exportation. Manufacture of components for 900 MW nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Bitouzet, P.

    1983-03-01

    The National Korean Electricy society KEPCO ordered the KNU9 and 10 power plants from FRAMATOME. This contract involve an important fabrication of components. The KHIC society has been indicated to manufacture the main components. This paper gives some precisions about the organization of the Technical Assistance for the Korean realization of five big components (pressure vessel, steam generator, pressurizer, accumulator and injection reservoir of boron), components manufactured according to French standard, including RCC (design and construction rules). Finally, it is shown how this Technical Assistance is carried out [fr

  18. The dismantling of fast reactors: sodium processing

    International Nuclear Information System (INIS)

    Rodriguez, G.; Berte, M.; Serpante, J.P.

    1999-01-01

    Fast reactors require a coolant that does not slow down neutrons so water can not be used. Metallic sodium has been chosen because of its outstanding neutronic and thermal properties but sodium reacts easily with air and water and this implies that sodium-smeary components can not be considered as usual nuclear wastes. A stage of sodium neutralizing is necessary in the processing of wastes from fast reactors. Metallic sodium is turned into a chemically stable compound: soda, carbonates or sodium salts. This article presents several methods used by Framatome in an industrial way when dismantling sodium-cooled reactors. (A.C.)

  19. Fracture resistance of cracked duplex stainless steel elbows under bending with or without internal pressure

    International Nuclear Information System (INIS)

    Semete, P.; Le Delliou, P.; Ignaccolo, S.

    1997-12-01

    EDF, in co-operation with Framatome, has conducted a research program on the fracture behaviour of aged cast duplex stainless steel elbows. One important task of this program consisted of testing three large diameter (580 mm O.D.) aged cast elbows, which are 2/3-scale models of PWR primary loop elbows. Furthermore, detailed finite element analyses of those three tests were conducted in order to be compared with experimental results. The results of this research program are presented. (K.A.)

  20. PWR fuel physico chemistry. Improvements of the Sage code to compute thermochemical balance in PWR fuel

    International Nuclear Information System (INIS)

    Garcia, P.; Baron, D.; Piron, J.P.

    1993-02-01

    A physicochemical survey of high burnup fuel has been undertaken in the context of a 3-party action (CEA Cadarache - EDF/DER - FRAMATOME). One of the tasks involved consists in adapting the SAGE code for assessment of the thermochemical equilibria of fission products in solution in the fuel matrix. This paper describes the first stage of this task. Even if other improvements are planned, the oxid oxygen potentials are yet properly reproduced for the simulated burnup. (authors). 63 figs., 4 tabs., 41 refs

  1. The CEA-industrie Group. Report for 1986

    International Nuclear Information System (INIS)

    1987-01-01

    From the end of 1983, the whole affiliates and participations of CEA are hept by CEA-industry. The group activity is principally in the nuclear field. Cogema and the whole fuel cycle, construction, maintenance, improvement of nuclear power plants, research reactors and naval propulsion boilers and the sector Power plants and nuclear services (Framatome, Technicatome, Intercontrole, Stmi, principally). A non-nuclear sector comes from new techniques or activities developed for the nuclear needs: computer science (CISI), biomedical field (ORIS-industrie), different activities such as ultrafiltration or robotics-productics [fr

  2. Impact of frequency control on PWR

    International Nuclear Information System (INIS)

    Constantieux, Thierry; Gautier, Alain; Deat, Max.

    1979-01-01

    This paper deals with experimental data that were recorded at TIHANGE 1, a Belgo-French nuclear power reactor, while the plant was performing frequency control with no load regulation. Frequency control induces quasi-permanent reactor power variations, whose effects on the following equipment must be analyzed carefully: rod mechanisms, fuel cladding and pressurizer components. A comparison of the experimental data with calculations performed on a hybrid computer is presented, together with a brief description of the hybrid program, DELTA, which was developed by FRAMATOME

  3. Advanced digital I and C technology in nuclear power plants. A success story from Finland and China

    International Nuclear Information System (INIS)

    Liebschner, T.; Heidowitzsch, B.

    2005-01-01

    FRAMATOME ANP together with Siemens PGL have just commissioned the I and C systems for the Chinese Nuclear Power Plant Tianwan Unit 1, design the I and C systems for the first European Pressurized Water Reactor Olkiluoto 3 in Finland and started one of the most extensive and ambitious modernization project in a nuclear power plant for Loviisa NPP in Finland. The presentation delivers an insight into the problematic of digital I and C systems integration and focuses on aspects regarding design criteria, Structure and test approaches. (author)

  4. Use of flow models to analyse loss of coolant accidents

    International Nuclear Information System (INIS)

    Pinet, Bernard

    1978-01-01

    This article summarises current work on developing the use of flow models to analyse loss-of-coolant accident in pressurized-water plants. This work is being done jointly, in the context of the LOCA Technical Committee, by the CEA, EDF and FRAMATOME. The construction of the flow model is very closely based on some theoretical studies of the two-fluid model. The laws of transfer at the interface and at the wall are tested experimentally. The representativity of the model then has to be checked in experiments involving several elementary physical phenomena [fr

  5. EDF advanced fuel management strategies for the next century

    International Nuclear Information System (INIS)

    Kocher, A.; Charmensat, P.; Larderet, M.

    1999-01-01

    The French nuclear fleet represents 57 PWRs in operation, accounting for 80 % of France's total electricity production. The performance achieved by EDF reactors, in terms of availability (82.6% in 1997) and good cost control, have allowed to improve the nuclear KWh cost by 2% since 1992. The implementation of longer fuel cycles on the 1300 MW reactors from 1996 has contributed to this improvement and, as competitiveness is one of the main challenges for EDF, improving core management strategies is still at the order of the day. With this aim, a thinking process has been initiated to evaluate the benefit brought by the use of a fuel assembly like ALLIANCE, the new fuel product developed by Framatome-Fragema and FCF (Framatome Cogema Fuels) in close cooperation with EDF. The considered product provides enhanced performance, particularly as regards discharge burnup (at least up to 70 GWd/t) and thermal-hydraulic and mechanical behaviour. Fuel management improvements rely on the expertise gained by Framatome through designing core management strategies in a wide range of operating conditions prevailing in nuclear reactors all over the world. It will however be taken into account the necessity for EDF to adopt a policy of stepwise change owing to the potential impact of a 'series effect' on its numerous units. The proposed paper will describe innovative fuel managements, achievable thanks to advanced fuel assembly performance, that are jointly investigated by EDF and Framatome. It includes the following optimization schemes: extending cycle length by using higher enrichments up to 5%, while keeping the same reload size (1/3 core for example for the 1300 MW reactors); decreasing reload size (from 1/3 to 1/4 core), while keeping the same cycle length, using more enriched (up to 5 %) fuel assemblies; reaching annual cycle, with maximization of fuel cycle cost optimization (1/5 core). Beyond such schemes, combinations of optimized loading patterns and neutronic features of

  6. Application of image processing methods to industrial radiography

    International Nuclear Information System (INIS)

    Goutte, R.; Odet, C.; Tuncer, T.; Bodson, F.; Varcin, E.

    1985-01-01

    This study was carried out with the financial support of the Commission of the European Communities as part of the CECA research program comprising of IRSID, INSA de Lyon and the Framatome and Creusot Loire companies. Its purpose was to evaluate the possibility of using digital enhancement of radiographic images to improve defect visibility in industrial radiography, thereby providing assistance in defect detection and a method for automatic analysis of radiographs. This paper provides full results obtained from work on digital processing of radiographs showing real and artificial defects. Furthermore, work on simulated automatic defect detection is also presented. 2 refs

  7. Participation of Skoda Praha a.s. in completion of NPP Mochovce

    International Nuclear Information System (INIS)

    Poukar, F.

    1997-01-01

    The history of the construction of the Mochovce nuclear power plant is briefly described. In 1995, after obtaining promises of loans from Czech banks the Slovak government decided that the completion of the mechanical and electrical parts of units 1 and 2 would be placed with Skoda Praha in the position of general supplier; Skoda together with Siemens and Framatome would also be charged with implementing the safety measures necessary to reach European standards. Evaluation of safety studies and risk audits, and elaboration of safety measures are now under way. (M.D.)

  8. Business data processing in the service of quality and safety in nuclear power plant construction

    International Nuclear Information System (INIS)

    Chassignet, C.

    1980-01-01

    Construction of a nuclear power plant implies collection and correlation of several thousand items of information which must be identified and which must remain retrievable throughout the service life of the plant. The Framatome Corporation, which has one of the largest nuclear power plant construction programs in the world, therefore set up a processing and checking system for the documents containing this information. The author describes the functions and principles of this system (known as SHARAD), together with its technical data and its operation [fr

  9. Summary on out-of-pile and in-pile properties of M5 alloy

    International Nuclear Information System (INIS)

    Zhao Wenjin

    2001-01-01

    The out-of-pile and in-pile corrosion, mechanical properties, microstructure,hydrogen absorption, creep and growth resistances of M5 alloy using as PWR fuel rod cladding materials developed by FRAMATOME in France has been summarized with reference to the literatures. The results obtained from in-pile irradiation tests show that the corrosion and hydrogen absorption resistances, creep and irradiation growth resistances of M5 alloy cladding are superior to that of the optimized Zircaloy-4. It could be estimated that the M5 alloy enables rod burnups close to 65GWd/tU to be reached

  10. Experimental evaluation of J in cracked straight and curved pipes under bending

    International Nuclear Information System (INIS)

    Moulin, D.; Touboul, F.; Foucher, N.; Lebey, J.; Acker, D.

    1989-01-01

    An experimental program is being carried out at the CEA Saclay in collaboration with FRAMATOME and IPSN with a view to validate analysis methods applicable for evaluation of leak before break behavior in P.W.R. piping. A large experimental work was already performed in USA, Germany and Japan and cracked pipes made of stainless steel material under bending. The methods of analysis got same validations for straight pipes. However applicability to elbows and comparison with toughness values obtained on small specimens like CT specimens was not completely dealt with

  11. CERCA 01: a new safe multi-design MTR transport cask

    Energy Technology Data Exchange (ETDEWEB)

    Faure-Geors, B.S. [Framatome ANP Nuclear Fuel, CERCA, F-26104 Romans (France); Doucet, M.E. [Framatome ANP Nuclear Fuel, F-69006 Lyon (France)

    2001-07-01

    CERCA, a subsidiary company of FRAMATOME ANP, manufactures fuel for research reactors all over the world. To comply with customer requirements, fabrication of material testing reactors elements is a mixed of various parameters. Worldwide transportation of elements requires a flexible cask, which accommodates different designs and meets international transportation regulations. To be able to deliver most of fuel elements, and to cope with non-validation of casks used previously, CERCA decided to design its own cask. All regulatory tests were successfully performed. They completely validated and qualified the safety of this new cask concept. No matter the accidental conditions are, a 5 % {delta}K subcriticality margin is always met.

  12. Energy consensus talks collapse over nuclear issues

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    Germany's energy consensus talks, ongoing since March 1993, were brought to unsuccessful end on October 26. Representatives from the Social Democratic Party (SDP), led by Lower Saxony's prime minister, Gerhard Schroeder, failed to get approval from party leaders on continued development of advanced reactors with enhanced safety - notably the Siemens/Framatome-designed 1500-MWe European pressurized water reactor (EPR) plan, for which the prospective schedule envisages a construction start in 1998. Nor would the SDP leadership accept the continued operation of existing nuclear plans to the end of their design life (some 20 to 25 years)

  13. Experimental results on the MOX fuel. Study of the calculus/measures divergences

    International Nuclear Information System (INIS)

    Martin, S.

    1997-01-01

    For each nuclear plant unit restart, all safety criterion have to be respected. Various parameters as boron concentration, temperature coefficient, worth or power and activity distributions related to fuel assemblies, have to be calculated. To compute these parameters Framatome uses the neutronic channel Science. Before the validation they are compare to experimental measures. For UO 2 fuel the divergence calculus/measures are correct. But for MOX fuels the divergence worsening. This paper discusses tis divergence and research the origin. (A.L.B.)

  14. Regulatory aspects of Olkiluoto 3 nuclear power plant (EPR-1600) (Draft, 12 Sept. 2005)

    International Nuclear Information System (INIS)

    Sandberg, J.; Tiippana, P.

    2005-01-01

    A 1600 MWe European Pressurized Water Reactor (EPR) supplied by the Framatome ANP - Siemens Consortium is under construction at the Olkiluoto site in Finland. Current international safety requirements and especially French and German operating experience have been applied in the design. Finnish requirements and operating experience have also been applied, especially regarding site-specific features. Severe accidentmanagement and protection against a collision of a large passenger airplane are implemented in the plant design. The plant safety features, licensing procedure, Finnish regulatory requirements, changes to the original EPR design, project quality management and regulatory control are discussed. (author)

  15. The technology for safety I and C systems in nuclear power plants: the SPINLINE 3 solution

    International Nuclear Information System (INIS)

    Rebreyend, P.; Burel, J.-P.

    2000-01-01

    The SPINLINE 3 technology is the latest digital technology produced by Schneider to offer the most adequate solution to safety I and C systems, particularly for modernisation of VVER reactors. This technology developed in co-operation with FRAMATOME has the great advantage of more than 200 reactors x years of cumulated experience in the field of digital safety systems. The design criteria mainly devoted to achieve the most stringent safety requirement are also combined with the economic objectives in term of investment, maintenance and long term operation. The SPINLINE 3 technology is fully supported by the activity on the French Nuclear Program with 59 NPPs in operation. (author)

  16. Expert-systems and computer-based industrial systems

    International Nuclear Information System (INIS)

    Terrien, J.F.

    1987-01-01

    Framatome makes wide use of expert systems, computer-assisted engineering, production management and personnel training. It has set up separate business units and subsidiaries and also participates in other companies which have the relevant expertise. Five examples of the products and services available in these are discussed. These are in the field of applied artificial intelligence and expert-systems, in integrated computer-aid design and engineering, structural analysis, computer-related products and services and document management systems. The structure of the companies involved and the work they are doing is discussed. (UK)

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

    International Nuclear Information System (INIS)

    2001-10-01

    The SFEN (French Society on Nuclear Energy), organized the 18 october 2001 at Paris, a technical day on the numerical and experimental simulation, applied to the reactor Physics. Nine aspects were discussed, giving a state of the art in the domain:the french nuclear park; the future technology; the controlled thermonuclear fusion; the new organizations and their implications on the research and development programs; Framatome-ANP markets and industrial code packages; reactor core simulation at high temperature; software architecture; SALOME; DESCARTES. (A.L.B.)

  18. PWR reactor pressure vessel failure probabilities

    International Nuclear Information System (INIS)

    Dufresne, J.; Lanore, J.M.; Lucia, A.C.; Elbaz, J.; Brunnhuber, R.

    1980-05-01

    To evaluate the rupture probability of a LWR vessel a probabilistic method using the fracture mechanics under probabilistic form has been proposed previously, but it appears that more accurate evaluation is possible. In consequence a joint collaboration agreement signed in 1976 between CEA, EURATOM, JRC Ispra and FRAMATOME set up and started a research program covering three parts: a computer code development, data acquisition and processing, and a support experimental program which aims at clarifying the most important parameters used in the COVASTOL computer code

  19. Replacement of a vessel head, an operation which today gets easily into its stride

    International Nuclear Information System (INIS)

    Mardon, P.; Chaumont, J.C.; Lambiotte, P.

    1995-01-01

    In 1992, one year after the detection of a leak in a vessel head of the Electricite de France (EDF) Bugey 4 reactor, the head was replaced by the Framatome-Jeumont Industrie Group. Today, this group, which has developed new methods and new tools to optimize the cost, the time-delay and the dosimetry of this kind of intervention, has performed 11 additional replacements, two of which on 1300 MWe power units. This paper describes step by step the successive operations required for a complete vessel head replacement, including the testing of safety systems before starting up the reactor. (J.S.). 7 photos

  20. Chemical cleaning of steam generators: application to Nogent 1

    International Nuclear Information System (INIS)

    Fiquet, J.M.; Veysset, J.P.; Esteban, L.; Saurin, P.

    1991-01-01

    EDF has patented a chemical cleaning process for PWR steam generators, based on the use of a mixture or organic acids in order to dissolve iron oxides and copper with a single solution and clean dented crevices. Qualification tests have permitted to demonstrate effectiveness of the solution and its innocuousness related to steam generator materials. The process, the licence of which belongs to SOMAFER RA and Framatome has been implemented in France at Nogent. The goal was to dissolve iron oxides allowing metallic particles, aggregated on the tubesheet, to be released and mechanically removed. The effectiveness was satisfactory and this treatment is to be extended to other units. (author)

  1. Introductory speeches

    International Nuclear Information System (INIS)

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. This chapter consist of introductory commentary and 4 introductory speeches (video records): (1) Introductory speech of Vincent Pillar, Board chairman and director general of Slovak electric, Plc. (SE); (2) Introductory speech of Stefan Schmidt, director of SE - Bohunice Nuclear power plants; (3) Introductory speech of Jan Korec, Board chairman and director general of VUJE Trnava, Inc. - Engineering, Design and Research Organisation, Trnava; Introductory speech of Dietrich Kuschel, Senior vice-president of FRAMATOME ANP Project and Engineering

  2. KTG seminar: nuclear power plants for the 21. century

    International Nuclear Information System (INIS)

    Buescher, T.; Fischer, C.

    2004-01-01

    Just a year ago, in December 2003, the Finnish electricity utility Teollisuuden Voima Oy (TVO) has signed a contract with AREVA, represented through Framatome ANP, and Siemens to build an EPR (European Pressurized Water Reactor) at the Olkiluoto site in Finland. The project is currently realized. According to this one of the two annual meetings in 2004 for the YOUNG GENERATION dealt with this topic. The EPR as well as the challenges for the future electricity production have been discussed during this well established meeting in Erlangen with experts from the Industry. (orig.)

  3. Analytical out-of-pile and in-pile experiments on gadolinia bearing fuels

    International Nuclear Information System (INIS)

    Bruet, M.; Francois, B.; Do, Q.; Bergeron, J.; Trotabas, M.

    1986-06-01

    New fuel management schemes in PWRs can be achieved through the use of burnable poisons like gadolinia bearing fuel rods. However, the introduction of such a design has required a qualification program, which has been performed in collaboration between CEA, FRAGEMA and/or FRAMATOME by specialized teams in CEA facilities. The main scoops of this program concern: the fabrication process; the out of pile physical properties determination: the in pile thermomechanical behaviour and fission product release; the neutronic studies in view to validate the Computed Gd efficiency and the LBP depletion calculation schemes and to analyse and assess various schemes of core calculations

  4. Construction of new nuclear power plant in Bulgaria - incentives and problems

    International Nuclear Information System (INIS)

    Popov, M.; Bataklieva, L.; Hinovski, I.

    2002-01-01

    Advantages and disadvantages of constriction of new nuclear power plant in Bulgaria are discussed. Several options for further development are considered: Completion of the Belene NPP; Evolutionary design installations PWR technology, 600 MW (AP-600 Westinghouse design; B-407 Russian design); Standard design of Framatome, 900 MW; Standard design - heavy water technology CANDU-6 (700 MW) and other.The results of the preliminary economic analyses show that the first two options are approximately equal, but the all options are acceptable from investment point of view, considering an average macro economic environment. The need of assessment of all aspects (technical, economical, financial, social, environmental, national infrastructure) of nuclear sector development is outlined

  5. ENC 98

    International Nuclear Information System (INIS)

    1998-01-01

    This press dossier document reports on the main points presented by the Framatome group at the ENC'98 colloquium which took place in Nice (France) on September 25 1998. The summary comprises 4 main parts: the 1997-98 highlights (nuclear realizations in France, China and Turkey, nuclear services, nuclear fuels), the international activities in the nuclear domain (USA, China, Eastern Europe), the research and development activities (the French-German joint EPR project, the high temperature reactor (HTR) project), and the service and nuclear fuel activities (maintenance, improvements, control and expertise). (J.S.)

  6. Influence of temperature on the Zircaloy-4 plastic anisotropy; Influence de la temperature sur l`anisotropie plastique du Zircaloy-4

    Energy Technology Data Exchange (ETDEWEB)

    Limon, R.; Bechade, J.L.; Lehmann, S.; Maury, R.; Soniak, A. [CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Direction des Technologies Avancees; Mardon, J.P. [Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Paris-La-Defense (France)

    1995-12-31

    In order to improve the comportment modelling of PWR fuel pin, and more precisely their canning tubes, Framatome and the CEA have undertake an important study program of Zircaloy-4 mechanical properties. It includes in particular the study of the plasticity between 20 and 400 degree Celsius. This material being not isotropic because of the zirconium hexagonal crystal network and the texture presented by the canning tubes, its plastic anisotropy has been measured. The obtained results for the canning in *slack* and recrystallized before irradiation Zircaloy-4 are presented and the deformation systems able to explain the observed anisotropy is researched. (O.L.). 6 refs., 4 figs., 1 tab.

  7. Franco-German nuclear cooperation: from the 'common product' to the first European pressurized water reactor

    International Nuclear Information System (INIS)

    Vignon, D.

    1999-01-01

    It has now been 10 years since Framatome and Siemens decided to collaborate on the design and sales of an advanced nuclear power plant (NPP) model based on pressurized water reactor (PWR) technology. Originally called the 'common product', this model was renamed the European pressurized water reactor when Electricite de France (EDF) and the German electric utilities joined this cooperative development effort in 1992. Since the beginning, this cooperation has been formalized in the framework of an agreement that led to the founding of a joint and equally owned subsidiary, Nucler Power International (NPI), which is reponsible for leading the development of the new model and later handling its export sales

  8. NSSS operating characteristics: experience obtained from Fessenheim nuclear power station start-up

    International Nuclear Information System (INIS)

    Gouffon, A.; Wilmart, Y.

    1978-01-01

    The two 900 MWe units of the Fessenheim Nuclear Power Plant are the first of a series of 26 installations equipped with Framatome 3-loop PWR-type NSSS systems which are scheduled to enter into service in France by 1982. The tests carried out at Fessenheim represented the first of the series, and thus it was important to provide the most complete tests possible. We shall examine here only the part of the operating tests which made it possible to demonstrate the correct behavior of these reactors under transient conditions and the adaptation of regulation systems required to meet the needs of a modern operation

  9. Valuation of fissured steam generator tubes at the level of the roll transition area, repaired by nickel plating

    International Nuclear Information System (INIS)

    Laire, C.; Stubbe, J.; Slama, G.; Michaut, M.; Anxionnaz-Steltzlen, F.; Leblois

    1990-01-01

    At DOEL 2, SG-tubes cracked at the roll transition area were repaired by nickel plating in 1985 and in 1986 by Laborelec and Framatome using different process parameters. The characteristics of these different deposits and their service behaviour were investigated on tubes pulled out after 1 or 2 cycles. It is confirmed that this repair technique can be used for through wall cracked tubes, when: - the cracks are not too broad; - the deposit is of good quality, free of irregularities due to deposition. After this expertise the improvement of the plating procedure was focused on ductile nickel without initial deposit defects [fr

  10. DESCRIPTION OF THE TRITIUM-PRODUCING BURNABLE ABSORBER ROD FOR THE COMMERCIAL LIGHT WATER REACTOR TTQP-1-015 Rev 19

    Energy Technology Data Exchange (ETDEWEB)

    Burns, Kimberly A.; Love, Edward F.; Thornhill, Cheryl K.

    2012-02-01

    Tritium-producing burnable absorber rods (TPBARs) used in the U.S. Department of Energy’s Tritium Readiness Program are designed to produce tritium when placed in a Westinghouse or Framatome 17x17 fuel assembly and irradiated in a pressurized water reactor (PWR). This document provides an unclassified description of the current design baseline for the TPBARs. This design baseline is currently valid only for Watts Bar reactor production cores. A description of the Lead Use TPBARs will not be covered in the text of the document, but the applicable drawings, specifications and test plan will be included in the appropriate appendices.

  11. Environmental and sanitary evaluation of electro-nuclear sites: methodological research and application to prospective scenarios

    International Nuclear Information System (INIS)

    2004-12-01

    In the framework of the radioactive wastes disposal of the law of 1991, an exchange forum constituted by ANDRA, CEA, COGEMA, EdF, Framatome-ANP and IRSN implemented an environmental and sanitary evaluation of the different methods of radioactive wastes management. This report presents the six studies scenarios, the proposed methodology, the application to the six scenarios and the analysis of the results which showed the efficiency of the different recycling options towards the electronuclear cycle impacts limitation, and a technical conclusion illustrated by improvement possibilities of the methodology. (A.L.B.)

  12. Assessment of margins with respect to pressurized thermal shock for the 3 loop plants of the French program

    International Nuclear Information System (INIS)

    Buchalet, C.; Haussaire, P.; Houssin, B.; Vagner, J.

    1983-08-01

    Presentation of the FRAMATOME and EDF program on pressurized thermal shock which objectives are to demonstrate that present and older French reactor vessels have adequate safety margins and to provide recommendations of feasible plant specific modifications, both technically and economically. Phase I consists in a thorough analysis of pressure and temperature transients that the R.P.V. beltine could undergo during plant operations; phase II is the fracture mechanics analysis; phase III estimates the safety margins available during normal, upset, emergency and faulted conditions

  13. Improving plant state information for better operational safety

    International Nuclear Information System (INIS)

    Girard, C.; Olivier, E.; Grimaldi, X.

    1994-01-01

    Nuclear Power Plant (NPP) safety is strongly dependent on components' reliability and particularly on plant state information reliability. This information, used by the plant operators in order to produce appropriate actions, have to be of a high degree of confidence, especially in accidental conditions where safety is threatened. In this perspective, FRAMATOME, EDF and CEA have started a joint research program to prospect different solutions aiming at a better reliability for critical information needed to safety operate the plant. This paper gives the main results of this program and describes the developments that have been made in order to assess reliability of different information systems used in a Nuclear Power Plant. (Author)

  14. Maintenance and repair tools of the 900 MW PWR units in France

    International Nuclear Information System (INIS)

    Blary, F.; Castaing, C.; Hassig, J.

    1985-01-01

    EDF and FRAMATOME have developed special tools and, repair and maintenance procedures to decrease the unavailability of the PWR units and the dosimetry of the personnel of maintenance. This report presents the solution adopted to face the problem of replacement of the internal upper structure pins of 21 units: 1) study and realisation of important industrial means; 2) development of a strategy: the pin replacement is separated from the guide tube replacement by the creation of a pin replacement shop, and, as often as it is possible, the ''AQUARIUM'' method allows to replace the guide-tubes with the aid of a mobile pool called AQUARIUM outside the critical way of shutdown [fr

  15. Experimental microstructures MOX fuels elaboration

    International Nuclear Information System (INIS)

    Gotta, M.J.; Dubois, S.; Lechelle, J.; Sornay, P.

    2000-01-01

    In order to propose a new MOX fuel, owning higher combustion rate, studies are realized at the CEA in collaboration with Cogema, EDF and Framatome. New microstructures of MOX are looked for around two approaches: the grains size and the plutonium distribution. These approaches are presented and discussed in this paper. The first one develops big grains microstructures obtained, either with anionic (sulfur), or cationic (Cr 2 O 3 ) additives. The second one concerns the CER-CER type composite microstructures. (A.L.B.)

  16. Integrating design and purchasing [in nuclear engineering] with Ingecad

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    Ingecad was developed by the Ingevision division of Framatome to overcome deficiencies in traditional computer-aided design. It was developed for nuclear power project engineering around the principle of the shared management of a common database, thus making it possible to integrate several engineering disciplines. The multiuser database is managed and accessed by the different application softwares, corresponding to particular aspects of the engineering task: electrical and process control schematics; plant piping design; pressurized equipment design etc. The use of a common database ensures coherence between the different engineering disciplines, particularly between the process engineering, the plant layout design, the piping, and the instrumentation and control engineering. (author)

  17. Final Technical Report for the MIT Annular Fuel Research Project

    International Nuclear Information System (INIS)

    Mujid S. Kazimi; Pavel Hejzlar

    2008-01-01

    MIT-NFC-PR-082 (January 2006) Abstract This summary provides an overview of the results of the U.S. DOE funded NERI (Nuclear Research Energy Initiative) program on development of the internally and externally cooled annular fuel for high power density PWRs. This new fuel was proposed by MIT to allow a substantial increase in power density (on the order of 30% or higher) while maintaining or improving safety margins. A comprehensive study was performed by a team consisting of MIT (lead organization), Westinghouse Electric Corporation, Gamma Engineering Corporation, Framatome ANP(formerly Duke Engineering) and Atomic Energy of Canada Limited

  18. Plant upgrading and backfitting in France

    International Nuclear Information System (INIS)

    Moxley, Nigel; Raimondo, Emile

    1992-01-01

    The service life of a nuclear power plant is linked to good operating and maintenance practices and effective management which should begin when the plant starts operating. In France the construction of two series of virtually identical reactors has enabled Framatome to use feedback from early units to modify and improve later ones. The intention is to keep the plants safe and to extend life as far into the next century as is feasible. Remedial measures that can be applied include improvements to plant operation itself, plant modifications and the implementation of effective preventive and corrective maintenance operations which may cover planned provision for the replacement of obsolete or susceptible components. (author)

  19. Steam generator replacement project in 2000

    International Nuclear Information System (INIS)

    Cerjak, J.; Holz, R.; Haus, J.; Gloaguen, C.

    1999-01-01

    NE Krsko has awarded the contract for the Steam Generator Replacement Project, which is one of the modernization projects in Krsko, to the Consortium of Siemens / Framatome in February 1998. This paper deals with the various aspects of the project: scope planning, engineering, preparation of modification packages for licensing, management, major techniques used, etc., showing also the status of the activities for the project which are scheduled to be performed in April through June 2000. The project is being performed on a turnkey basis, that means the Consortium is performing all engineering, preparation of the modification packages and site activities; NE Krsko is dealing with the licensing of the project.(author)

  20. Mistral: a program in collaboration with Japan

    International Nuclear Information System (INIS)

    Cabrillat, J.C.

    1997-01-01

    The MISTRAL (MOX investigation of Systems which are Technically Relevant of Advanced Light water reactors) experimental program is performed with the Eole reactor at Cadarache (France) in the framework of a collaboration between the CEA, Electricite de France (EdF), Framatome and the NUPEC Japanese organism. This low power experimental reactor is devoted to critical dimensioning configuration tests of light water reactor cores fueled exclusively with mixed uranium-plutonium oxide (MOX) fuels. This program follows the previous EPICURE program devoted to the study of partial MOX fueling of PWR cores. (J.S.)

  1. Chemical cleaning of PWR steam generators: application at Nogent 1

    International Nuclear Information System (INIS)

    Fiquet, J.M.; Veysset, J.P.; Esteban, L.; Saurin, P.

    1990-01-01

    EDF has developed and patented a chemical cleaning process for PWR steam generators, based on the use of a mixture of organic acids in order to: - dissolve iron oxides and copper with a single solution; - clean dented crevices. Qualification tests have permitted to demonstrate effectiveness of the solution and its inocuousness related to steam generator materials. The process, the license of which belongs to SOMAFER R.A. and FRAMATOME, has been implemented in France at Nogent. The goal was to dissolve iron oxides allowing metallic particles, aggregated on the tubesheet, to be released and mechanically removed. The effectiveness was satisfactory and this treatment is to be extended to other units [fr

  2. Automated systems help prevent operator error during [reactor] I and C [instrumentation and control] testing

    International Nuclear Information System (INIS)

    Courcoux, R.

    1989-01-01

    On a nuclear steam supply system, even a minor failure can involve actuation of the whole reactor protection system (RPS). To reduce the likelihood of human error leading to unwanted trips during the maintenance of instrumentation and control systems, Framatome has been developing and installing various automated testing systems. Such automated systems are particularly helpful when periodic tests with a potential for RPS actuation have to be carried out, or when the test is on the critical path for the refuelling outage. The Sensitive Channel Programme described is an example of the sort of work that has been done. (author)

  3. PWR Power Plant Reactor Maintenance: Site Experience and Technology Transfer

    International Nuclear Information System (INIS)

    Callot, T. R.

    1986-01-01

    In France, Framatome participates in every scheduled outage. Abroad our participation which was restricted only to Belgium, a few years ago now includes several stations in Europe, South Africa and the United States. In conclusion, whatever the work may be and whenever it is to be performed far away from the home office, it is the policy of Fumarate to find an arrangement with a local company for technology transfer either on a case by cast basis or more suitable within the framework of a general cooperation agreement

  4. Case of nuclear and other sources of electric energy

    International Nuclear Information System (INIS)

    Tonnac, A. de

    1999-01-01

    This work is destined primarily to the FRAMATOME personnel and aim at endowing them with knowledge necessary to answer the usual questions raised by inquiring people. The booklet presents basic data, figures and arguments necessary in sustaining a discussion upon the nuclear energy controversial issues. These data are grouped around the following 13 issues: 1. Electric power in the world; 2. Production costs; 3. Resources and reserves; 4.Safety and nuclear accidents; 5. Accidents related to the energy production; 6. Health and radiation protection; 7. Environment and refuses; 8. Reprocessing; 9. Radioactive waste transportation; 10. Wastes; 11. Dismantling; 12; PWR and non-proliferation; 13. Public opinion and nuclear energy

  5. Nuclear choice. Towards the EPR with mincing steps

    International Nuclear Information System (INIS)

    Jemain, A.

    2003-01-01

    The French government is on the way to give its green light for the construction of the EPR (European Pressurized water Reactor), the 1600 MWe demonstrator reactor of third generation of Framatome ANP (Areva). Fifty seven months will be necessary for its construction which, with the public inquiry, would lead to a first commissioning by 2010. This reactor will progressively renew the present day park between 2015-2020. The EPR project will cost 3 billions of euros but the financing remains to be found. Short paper. (J.S.)

  6. Steam generators: improvement of separator/dryer performance

    International Nuclear Information System (INIS)

    Holcblat, A.

    1985-10-01

    The first generation of steam generators built in France (model 51) experienced some moisture problems. As early as 1976, a large-scale development program was undertaken by Framatome, in collaboration with the French Commissariat a l'Energie Atomique and Electricite de France, to enhance design of SG separation equipment. The goal of this program was to enhance equipment operating efficiency by improving our understanding of separation phenomena. This paper presents an overview of the design and testing effort engaged within the framework of the separator development program, along with a summary of program results and forthcoming developments

  7. RSE-M code progress in the field of examination evaluation and flaw acceptance criteria

    International Nuclear Information System (INIS)

    Barthelet, B.; Le Delliou, P.; Heliot, J.; Faidy, C.; Drubay, B.

    1995-01-01

    The RSE-M Code provides rules and requirements for in service inspection of light water cooled nuclear power plants. The code first edition was established by EDF and published in 1990 by AFCEN. In 1992, a second RSE-M project was launched by EDF and FRAMATOME with the objective to address a 1995 edition more completed considering the needs of owners, users, manufacturers and inspectors. This paper focuses on evaluation of examination results and presents the work done in the field of flaw acceptance criteria over the last three years. (author). 5 refs., 3 figs

  8. Influence of temperature on the Zircaloy-4 plastic anisotropy

    International Nuclear Information System (INIS)

    Limon, R.; Bechade, J.L.; Lehmann, S.; Maury, R.; Soniak, A.

    1995-01-01

    In order to improve the comportment modelling of PWR fuel pin, and more precisely their canning tubes, Framatome and the CEA have undertake an important study program of Zircaloy-4 mechanical properties. It includes in particular the study of the plasticity between 20 and 400 degree Celsius. This material being not isotropic because of the zirconium hexagonal crystal network and the texture presented by the canning tubes, its plastic anisotropy has been measured. The obtained results for the canning in *slack* and recrystallized before irradiation Zircaloy-4 are presented and the deformation systems able to explain the observed anisotropy is researched. (O.L.). 6 refs., 4 figs., 1 tab

  9. Ultra-thin lithium micro-batteries. Performances and applications; Microaccumulateurs ultra minces au lithium. Performances et applications

    Energy Technology Data Exchange (ETDEWEB)

    Martin, M.; Terrat, J.P. [Hydromecanique et frottement (HEF), 42 - Andrezieux Boutheon (France); Levasseur, A.; Vinatier, P.; Meunier, G. [Centre National de la Recherche Scientifique (CNRS), 33 - Talence (France). Institut de Chimie de la Matiere Condensee et Physique de Bordeaux

    1996-12-31

    This short paper (abstract) describes the characteristics and performances of prototypes of ultra-thin lithium micro-batteries (thickness < 0.2 mm) which can be incorporated into microelectronic circuits. (J.S.)

  10. Proceedings of the international conference on radiation test facilities for the CTR surface and materials program, Argonne, Illinois, July 15--18, 1975

    Energy Technology Data Exchange (ETDEWEB)

    1975-01-01

    Separate abstracts were prepared for the 42 included papers. Abstracts for all 42 papers appear in Nuclear Science Abstracts while abstracts for 32 of the papers appear in ERDA Research Abstracts. (MOW)

  11. Browse Title Index

    African Journals Online (AJOL)

    2004), Equations for predicting the biomass of Acacia cyclops and Acacia saligna in the western and eastern Cape regions of South Africa: Part 1: tree-level models: scientific paper, Abstract. A Van Laar, JM Theron. Vol 201 ...

  12. Ultra-thin lithium micro-batteries. Performances and applications; Microaccumulateurs ultra minces au lithium. Performances et applications

    Energy Technology Data Exchange (ETDEWEB)

    Martin, M; Terrat, J P [Hydromecanique et frottement (HEF), 42 - Andrezieux Boutheon (France); Levasseur, A; Vinatier, P; Meunier, G [Centre National de la Recherche Scientifique (CNRS), 33 - Talence (France). Institut de Chimie de la Matiere Condensee et Physique de Bordeaux

    1997-12-31

    This short paper (abstract) describes the characteristics and performances of prototypes of ultra-thin lithium micro-batteries (thickness < 0.2 mm) which can be incorporated into microelectronic circuits. (J.S.)

  13. Introduction of advanced pressurized water reactors in France

    International Nuclear Information System (INIS)

    Millot, J.P.; Nigon, M.; Vitton, M.

    1988-01-01

    Designed >30 yr ago, pressurized water reactors (PWRs) have evolved well to match the current safety, operating, and economic requirements. The first advanced PWR generation, the N4 reactor, is under construction with 1992 as a target date for commercial operation. The N4 may be considered to be a technological outcome of PWR evolution, providing advances in the fields of safety, man/machine interfaces, and load flexibility. As a step beyond N4, a second advanced PWR generation is presently under definition with, as a main objective, a greater ability to cope with the possible deterioration of the natural uranium market. In 1986, Electricite de France (EdF) launched investigations into the possible characteristics of this advanced PWR, called REP-2000 (PWR-2000: the reactor for the next century). Framatome joined EdF in 1987 but had been working on a new tight-lattice reactor. Main options are due by 1988; preliminary studies will begin and, by 1990, detailed design will proceed with the intent of firm commitments for the first unit by 1995. Commissioning is planned in the early years of the next century. This reactor type should be either an improved version of the N4 reactor or a spectral shift convertible reactor (RCVS). Through research and development efforts, Framatome, Commissariat a l'Energie Atomique (CEA), and EdF are investigating the physics of fuel rod tight lattices including neutronics, thermohydraulics, fuel behavior, and reactor mechanics

  14. EPR design features to mitigate severe accident challenges

    International Nuclear Information System (INIS)

    Mazurkiewicz, S.M.; Fischer, M.; Bittermann, D.

    2005-01-01

    The EPR, an evolutionary pressurized water reactor (PWR), is a 4300-4500 MWth that incorporates proven technology within an optimized configuration to enhance safety. EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product. Commercial EPR units are currently being built in Finland at the Olkiluoto site, and planned for France at the Flamanville site. In recent months, Framatome ANP announced their intention to market the EPR units to China in response to a request for vendor bids as well as their intent to pursue design certification in the United States under 10CFR52. The EPR safety philosophy is based on a deterministic consideration of defense-in-depth complemented by probabilistic analyses. Not only is the EPR designed to prevent and mitigate design basis accidents (DBAs), it employs an extra level of safety associated with severe accident response. Therefore, as a design objective, features are included to ensure that radiological consequences are limited such that the need for stringent counter measures, such as evacuation and relocation of the nearby population, can be reasonably excluded. This paper discusses some of the innovative features of the EPR to address severe accident challenges. (author)

  15. The development of nuclear energy in China

    International Nuclear Information System (INIS)

    Chavardes, D.

    2001-01-01

    In China the consumption of coal has been steadily decreasing for a few years while the economic growth rate is being maintained at 10% a year. Today the production of electricity relies on coal for 81%, on hydraulics for 17% and on nuclear energy for 0.4%. The demand for electric power increases by 7.5% a year, and at this rate the demand will double in a decade. The resort to only coal or hydraulics to sustain such a development, would have too substantial impacts on the environment (CO 2 emission, climate changing, flooding of entire regions) to be viable, so the way is paved for nuclear energy. The new 10. five-year plan supports the development of nuclear energy and Chinese authorities might agree to build 4 power plant units in the eastern and southern coastal zones. France has a valuable history of cooperation with China concerning nuclear energy. 2 reactors are successfully operating at Daya-bay and Framatome is building 2 other units on the Ling-Ao site. Framatome has succeeded in the Chinese demand for localizing a part of the manufacturing work in China. (A.C.)

  16. 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)

  17. The nuclear adventure in France: great and little story

    International Nuclear Information System (INIS)

    Boulin, Philippe; Boiteux, Marcel

    2001-01-01

    An ex-chairman of Framatome proposes an historical overview of the French nuclear programme since the 1950's, and outlines that, when considering oil quantity which would have necessary to produce the same amount of electric power, the assessment is rather positive. Then, he highlights the difficulties met by this programme with its different actors: EDF and the CEA on the public side, and the Empain-Schneider group on the private side. He recalls the difficulties to obtain good quality vessels by Westinghouse, and some decisions taken about the Chooz plant construction. He outlines the importance of the decision to use enriched uranium. He evokes the main partners of Framatome (Westinghouse) and its competitors (CGE, Babcock), and the evolution of the competition during the 1970's. This contribution is briefly commented by Marcel Boiteux who used to be an EDF chairman. A debate is transcribed which addressed the implementation process after the political decision, the drawbacks of competition, the prevailing role of experts, social issues raised by the nuclear

  18. Rest-lifetime evaluation of equipment and facilities of NPP Kozloduy 3 and 4 and development of an ageing management program

    International Nuclear Information System (INIS)

    Erve, M.; Schmidt, J.; Kastner, B.; Gledatchev, I.; Sabinov, S.; Stoev, M.; Korneev, V.; Strombach, Y.

    2001-01-01

    The task indicated in the title is part of a comprehensive upgrading program for Units 3 and 4 of the Kozloduy plant executed in a Consortium between Framatome ANP (a Framatome and Siemens company) and the Russian company Atomstroyexport. It comprises an evaluation of the residual service life of components/systems/plants subject to acceptance by international experts, identifying the need for further investigations/calculations in certain cases, and finding solutions for improvements that achieve a consensus of safety and economy. The initial results are: Walkdowns revealed no clear knock-out point for the plants, however there are preliminary hints for necessary further improvements. Investigations of templates taken from the RPV of Unit 1 were started: the results are still preliminary, but can be considered very positive; their transfer to the RPV of Unit 3 would mean that the latest safety analyses of the Unit 3 RPV are conservative. The general work program was successfully applied on the batteries as a pattern for the electrical equipment: parameters for the computer database and proposals for an effective aging management program were addressed. (author)

  19. Olkiluoto 3: Finland has chosen a EPR

    International Nuclear Information System (INIS)

    Brummer, S.

    2003-01-01

    According to the Finn law any nuclear project has to be declared conformed to the general interest of the country by the government and then has to be approved by the parliament. In may 2002 the Finn parliament approved the project of the TVO company: the construction of a new nuclear unit on the Olkiluoto site and the direct and definitive disposal of spent fuels in the granite underground layers of the same site. The project was agreed with 109 votes for and 92 against. In september 2002 an international invitation to tender was launched and 4 companies made proposals: Westinghouse, Atomstroexport, Framatome-ANP and General Electric. Westinghouse withdrew its offer some time later. In october 2003 TVO announced that the unit will be a 1600 MW EPR (European pressurized reactor) built by Framatome-ANP. The construction work will begin in spring 2005 and the unit is scheduled to enter into service in 2009. At that time the contribution of nuclear energy to the Finn energy production will reach 35%. (A.C.)

  20. Criterion of independence applied to personnel responsible for in-house verification

    International Nuclear Information System (INIS)

    Pavaux, F.

    1982-01-01

    Framatome's experience has shown that one of the most difficult criteria to interpret in applying quality assurance programmes is that of ''organization''. In particular, this requires that personnel responsible for in-house verification should have ''sufficient independence''. The author examines how Framatome interprets the criterion of sufficient independence. It may seem easy to deal with this problem on paper, by redistributing the boxes of the organizational chart, but to do so is both unrealistic and deceptive; the development of reference models runs into difficulties when it comes to practical application and these difficulties alone justify trying another approach to the problem. The method advocated here consists in analysing each situation as it arises, taking into account the criterion in question, and disregarding any pre-defined model or reference situation. The analysis should involve all quality assurance functions and not, as is too often the case, only the independence of the quality assurance service. The analysis should also examine organizational freedom and independence from direct pressures of cost and schedule considerations. To support this recommendation, three standard cases are described (manufacturing control, design verification, on-site inspection team) which demonstrate how these criteria can give rise to different difficulties in different cases. The author concludes that, in contrast to other criteria so often applied by successive approximations, organizational changes should only be decided upon when absolutely necessary and after a detailed analysis of the particular case in question has been performed. (author)

  1. Toward semi-autonomous control of mobile robots for constrained environments

    International Nuclear Information System (INIS)

    Mercier, O.; Cara, O.

    1991-01-01

    Drawing from long-time experience in nuclear maintenance robotics, FRAMATOME leads with several partners an important effort with the goal of developing the decision and operator assistance capabilities of mobile robots. Future robots shall be better adapted (in size and configuration) to the operational requirements of nuclear plants work than current demonstrators. Due regards shall be paid to safety aspects and qualification procedure shall be specified soon. Also, dosimetry gains (e.g. as evaluated by DOSIANA) shall be evaluated to establish further the advantages of robotic solutions. Current achievements and plans for the next two years are expected to provide the necessary know-how for semi-autonomous control of various mobile robots in actual missions in nuclear plant environment. These advances in many closely connected disciplines and technologies should put FRAMATOME in a leader position as systems integrator or as developer for future markets in autonomous mobile robotics, not only in the nuclear field but in other domains as well. (author)

  2. In-reactor fuel cladding external corrosion measurement process and results

    International Nuclear Information System (INIS)

    Thomazet, J.; Musante, Y.; Pigelet, J.

    1999-01-01

    Analysis of the zirconium alloy cladding behaviour calls for an on-site corrosion measurement device. In the 80's, a FISCHER probe was used and allowed oxide layer measurements to be taken along the outer generating lines of the peripheral fuel rods. In order to allow measurements on inner rods, a thin Eddy current probe called SABRE was developed by FRAMATOME. The SABRE is a blade equipped with two E.C coils is moved through the assembly rows. A spring allows the measurement coil to be clamped on each of the generating lines of the scanned rods. By inserting this blade on all four assembly faces, measurements can also be performed along several generating lines of the same rod. Standard rings are fitted on the device and allow on-line calibration for each measured row. Signal acquisition and processing are performed by LAGOS, a dedicated software program developed by FRAMATOME. The measurements are generally taken at the cycle outage, in the spent fuel pool. On average, data acquisition calls for one shift per assembly (eight hours): this corresponds to more than 2500 measurement points. These measurements are processed statistically by the utility program SAN REMO. All the results are collected in a database for subsequent behaviour analysis: examples of investigated parameters are the thermal/hydraulic conditions of the reactors, the irradiation history, the cladding material, the water chemistry This analysis can be made easier by comparing the behaviour measurement and prediction by means of the COROS-2 corrosion code. (author)

  3. The EPR - technology for the 3rd Millennium

    International Nuclear Information System (INIS)

    Bernstrauch, O.

    2000-01-01

    The Basic Design of the European Pressurized Water Reactor (EPR) was completed 1997 , the Basic Design Optimization Phase 1998 and the Detailed Design Phase will start in the near future. With these milestones, a new generation of PWRs is moving forward. Most of all, this is another story of a successful Franco-German cooperation. It is a rundown of the history of the EPR, before a decision is made to launch the lead-unit construction. The EPR project was launched in 1992 by Nuclear Power International (NPI), a joint company of FRAMATOME and Siemens KWU, supported by EDF and nine German electric utilities. Each step of the development of the EPR was harmonized with the Nuclear Safety Authorities both in France and Germany to reach an early approval. The EPR integrates the latest technological advances, especially in safety and operational aspects and comprises more than 30 years operating experience. Thus, the EPR combines the qualities of its predecessors, the French N4 and the German Konvoi. Presently, Siemens KWU and FRAMATOME are preparing the detailed design phase and the following construction and commissioning phase. The decision to build an EPR is not yet made either by the German electric utilities or by EdF, but it will be expected within the next months as a strong statement to follow the nuclear way and to ensure the know-how transfer. (author)

  4. Actions undertaken in order to solve the tube guide pins cracking

    International Nuclear Information System (INIS)

    Benhamou, C.; Briois, J.P.; Tuncer, T.; Drean, H.

    1985-01-01

    Short-term actions have been developed after the discovery of defects on the guide tube pins (upper internal rector components) of 21 units in France. The impact analysis of a pin failure on the safety by Framatome show that short-term consequences are not very important. Improvements in regard with the design and the stress corrosion resistance of the material, which can be applied to the pins, have been defined. Framatome and EDF developed tools and the mastery of replacement operations what led to limit considerably the unavailability of units; 17 units have been treated for two years and half; the four last ones will be treated in 1985. Parallel studies allow to estimate the available marge of in-service behavior of the replacement pins; this marge is increased in units which are built now by means of new developments concerning the design and the mounting conditions. A method and tools utilizing ultrasonic waves have been developed for on-site inspection of the pins [fr

  5. Investigation on the relation between pressure drops and fluid chemical treatment

    International Nuclear Information System (INIS)

    Brun, C.; Engler, N.; Berthollon, G.; Muller, T.; Sala, B.; Combrade, P.; Turluer, G.

    2002-01-01

    Variations of primary coolant flow rate were sometimes observed on some plants some years ago. These variations come from variations of pressure drops in the various zones of the primary system. After many investigations, these changes were attributed to variations of physical and chemical conditions. One specific difficulty was to explain the level of head loss variations with the low amount of oxide present in a primary circuit. Another one was to account for the formation of deposits under high water velocity conditions. Therefore, Framatome-ANP launched laboratory tests to reproduce the observed head loss variations, identify the conditions of their occurrence and try to identify the root mechanisms. A small loop - called EMILIE - was implemented in the laboratories of the Technical Centre of Framatome-ANP in Le Creusot. It allows us to study the effect of the water chemistry and velocity, as well as the nature of the circuit surfaces on the occurrence of head loss variations and their relation with the amount, nature and morphology of oxide deposits. This paper summarizes the first results obtained and briefly discusses a possible mechanism. (authors)

  6. Industrial structure at research reactor suppliers

    International Nuclear Information System (INIS)

    Roegler, H.-J.; Bogusch, E.; Friebe, T.

    2001-01-01

    Due to the recent joining of the forces of Framatome S. A. from France and the Nuclear Division of Siemens AG Power Generation (KWU) from Germany to a Joint Venture named Framatome Advanced Nuclear Power S.A.S., the issue of the necessary and of the optimal industrial structure for nuclear projects as a research reactor is, was discussed internally often and intensively. That discussion took place also in the other technical fields such as Services for NPPs but also in the field of interest here, i. e. Research Reactors. In summarizing the statements of this presentation one can about state that: Research Reactors are easier to build than NPPs, but not standardised; Research Reactors need a wide spectrum of skills and experiences; to design and build Research Reactors needs an experienced team especially in terms of management and interfaces; Research Reactors need background from built reference plants more than from operating plants; Research Reactors need knowledge of suitable experienced subsuppliers. Two more essential conclusions as industry involved in constructing and upgrading research reactors are: Research Reactors by far are more than a suitable core that generates a high neutron flux; every institution that designs and builds a Research Reactor lacks quality or causes safety problems, damages the reputation of the entire community

  7. The participation of Industry in the ITER engineering design activities

    International Nuclear Information System (INIS)

    Bogusch, E.

    2005-01-01

    Since the beginning of the ITER Engineering Design Activities in 1992 the participation of industry in the European contribution to the ITER project has increased continuously. A major boost resulted from a framework contract between the European Commission acting through EFDA and the European industry grouping EFET EWIV regarding the industry contribution for the ITER engineering design. The members of EFET include Ansaldo (Italy), Belgatom (Belgium), Fortum (Finland), the AREVA companies Framatome ANP GmbH (Germany) and Framatome ANP SAS (France), IBERTEF (Spain) and NNC (United Kingdom). Together with other special European engineering companies and manufacturers EFET contributed significantly to ITER Engineering Design Activities. In 1996 a list of qualified competitive companies was established which could bid for the manufacturing of prototype components in initially 15, later 17 Technologies considered essential for ITER construction preparation. In total, contracts of about 70 Mio Euro have been awarded to industry during the period 1993 to 2004. In addition to engineering design and prototype manufacturing, industry participated in various assessments of the ITER project and ITER siting investigations. Furthermore, industry has been invited by the European Commission to introduce its proposals for the promotion of the ITER project in Europe and abroad and later for the organization and management of ITER construction. (orig.)

  8. Design description of the European pressurized water reactor

    International Nuclear Information System (INIS)

    Leverenz, R.

    1999-01-01

    The EPR (the European Pressurized Water Reactor) is an evolutionary PWR developed by Nuclear Power International and its parent companies, Framatome and Siemens, in co-operation with Electricite de France and German Utilities. NPI can rely on the huge experience gained by its parent companies; they have constructed more than 100 nuclear power plants throughout the world. The total installed capacity exceeds 100,000 MW - about 25% of the total world-wide figure. Following the conceptual design phase of the so-called Common Product conducted by NPI, Framatome and Siemens, from 1989 through 1991, Electricite de France (EDF) and several major German utilities decided to merge their own development programmes, - the N4 Plus and REP 2000 projects on the French side and the further development of the KONVOI technology on the German side, - with the NPI project. From that time on, the NPI project became one single common development line for both countries. In parallel, EDF and the German utilities decided to establish, together with other European utilities, specifications that would represent common utility views on the design and performance of future nuclear power plants. These are documented in the European Utility Requirements (EURs). The basic design has been completed in 1997, and in 1998 a design optimization is being carried out with the goal to even increase the economic competitiveness of nuclear power. This paper provides a brief design description of the EPR. (author)

  9. Nickel electroplating of steam generator tubes (kiss sleeving process)

    International Nuclear Information System (INIS)

    Michaut, B.

    1988-01-01

    This process, the nickel electroplating of steam generator tubes, has been jointly developed under a Belgatom (Laborelec) and Framatome agreement with shared experience gained by both companies, industrial applications being under the responsibility of Framatome. Application of the coating in zones where residual stresses or cracks are present prevents contact between the primary water and the tube, which stops the stress corrosion process. In the Doel 2 plant, 91 tubes have been plated since 1985, and different sets of parameters have been used for comparison purposes. Among these tubes, 9 have been preventively plugged because of defective plating, 9 have been pulled out for laboratory examinations, 2 just after plating and 7 after 1 or 2 yr of service. There are 73 plated tubes still in service. From the tests that were performed, it was possible to select an optimized set of parameters guaranteeing the following properties: bridging of existing cracks and good behavior of the coating in relevant zones, good adhesion to the Inconel tube, high ductility, low residual stresses, thermal shock resistance, corrosion resistance, erosion resistance, and low cobalt content. The licensability of this process is being completed. It is based first on the leak-before-break concept to determine the characteristics of the nickel plating, thickness in particular, and second on the inspectability of ultrasonic testing methods

  10. Scleroderma and dentistry: Two case reports.

    Science.gov (United States)

    Dixit, Shantanu; Kalkur, Chaithra; Sattur, Atul P; Bornstein, Michael M; Melton, Fred

    2016-10-24

    Scleroderma is a chronic connective tissue disorder with unknown etiology. It is characterized by excessive deposition of extracellular matrix in the connective tissues causing vascular disturbances which can result in tissue hypoxia. These changes are manifested as atrophy of the skin and/or mucosa, subcutaneous tissue, muscles, and internal organs. Such changes can be classified into two types, namely, morphea (localized) and diffuse (systemic). Morphea can manifest itself as hemifacial atrophy (Parry-Romberg syndrome) although this remains debatable. Hence, we present a case of morphea, associated with Parry-Romberg syndrome, and a second case with the classical signs of progressive systemic sclerosis. Case one: A 20-year-old man of Dravidian origin presented to our out-patient department with a complaint of facial asymmetry, difficulty in speech, and loss of taste sensation over the last 2 years. There was no history of facial trauma. After physical and radiological investigations, we found gross asymmetry of the left side of his face, a scar on his chin, tongue atrophy, relative microdontia, thinning of the ramus/body of his mandible, and sclerotic lesions on his trunk. Serological investigations were positive for antinuclear antibody for double-stranded deoxyribonucleic acid and mitochondria. A biopsy was suggestive of morphea. Hence, our final diagnosis was mixed morphea with Parry-Romberg syndrome. Case two: A 53-year-old woman of Dravidian origin presented to our out-patient department with a complaint of gradually decreasing mouth opening over the past 7 years. Her medical history was noncontributory. On clinical examination, we found her perioral, neck, and hand skin to be sclerotic. Also, her fingers exhibited bilateral telangiectasia. An oral examination revealed completely edentulous arches as well as xerostomia and candidiasis. Her serological reports were positive for antinuclear antibodies against centromere B, Scl-70, and Ro-52. A hand and

  11. Impulse position control algorithms for nonlinear systems

    Energy Technology Data Exchange (ETDEWEB)

    Sesekin, A. N., E-mail: sesekin@list.ru [Ural Federal University, 19 S. Mira, Ekaterinburg, 620002 (Russian Federation); Institute of Mathematics and Mechanics, Ural Division of Russian Academy of Sciences, 16 S. Kovalevskaya, Ekaterinburg, 620990 (Russian Federation); Nepp, A. N., E-mail: anepp@urfu.ru [Ural Federal University, 19 S. Mira, Ekaterinburg, 620002 (Russian Federation)

    2015-11-30

    The article is devoted to the formalization and description of impulse-sliding regime in nonlinear dynamical systems that arise in the application of impulse position controls of a special kind. The concept of trajectory impulse-sliding regime formalized as some limiting network element Euler polygons generated by a discrete approximation of the impulse position control This paper differs from the previously published papers in that it uses a definition of solutions of systems with impulse controls, it based on the closure of the set of smooth solutions in the space of functions of bounded variation. The need for the study of such regimes is the fact that they often arise when parry disturbances acting on technical or economic control system.

  12. Impulse position control algorithms for nonlinear systems

    Science.gov (United States)

    Sesekin, A. N.; Nepp, A. N.

    2015-11-01

    The article is devoted to the formalization and description of impulse-sliding regime in nonlinear dynamical systems that arise in the application of impulse position controls of a special kind. The concept of trajectory impulse-sliding regime formalized as some limiting network element Euler polygons generated by a discrete approximation of the impulse position control This paper differs from the previously published papers in that it uses a definition of solutions of systems with impulse controls, it based on the closure of the set of smooth solutions in the space of functions of bounded variation. The need for the study of such regimes is the fact that they often arise when parry disturbances acting on technical or economic control system.

  13. Waardenburg syndrome: A rare case

    Directory of Open Access Journals (Sweden)

    Shivlal M Rawlani

    2018-01-01

    Full Text Available Waardenburg Syndrome is a rare disorder of neural crest cell development. It is genetically inherited. Varying in prevalence from 1:42000 to 1:50,000, it compromises approximately 2-5% of congenital deaf children. The syndrome is not expressed in its complete form, in about 20% cases, which adds for its heterogenisity . Even among people affected in the same family,the features do vary. Unilateral heterochromia that manifests as lighter pigmentation of one iris is associated with Waardenburg syndrome and Parry-Romberg syndrome and less commonly with Hirschsprung disease. A case of ten yrs. old boy with a typical facial profile and hearing loss is reported.

  14. Leaders Navigating Organizational and Personal Boundaries on Social Media

    DEFF Research Database (Denmark)

    Agerdal-Hjermind, Annette; Kampf, Constance Elizabeth

    examined include LinkedIn Groups and professional group pages on Facebook. In addition, we have interviewed six corporate leaders who are active on social media in Denmark.  Key words: Leadership style, leadership communication, social media Paper type: Explorative Empirical Study References Lee, C......Being a leader in an ever more transparent world requires more openness and presence in dealing with questions from the public by using highly visible platforms such as social media. However, recent research on social media and leadership communication is scarce and mainly focuses on an internal...... perspective (Lee, 2015) and leaders’ technology acceptance level (Parry & Solidoro, 2013; Sedej & Justinek, 2013), not focusing on employees and leaders as users of social media outside the internal communication context. We argue for expanding the understanding of communicative leadership on social media...

  15. Long time management of fossil fuel resources to limit global warming and avoid ice age onsets

    Science.gov (United States)

    Shaffer, Gary

    2009-02-01

    There are about 5000 billion tons of fossil fuel carbon in accessible reserves. Combustion of all this carbon within the next few centuries would force high atmospheric CO2 content and extreme global warming. On the other hand, low atmospheric CO2 content favors the onset of an ice age when changes in the Earth's orbit lead to low summer insolation at high northern latitudes. Here I present Earth System Model projections showing that typical reduction targets for fossil fuel use in the present century could limit ongoing global warming to less than one degree Celcius above present. Furthermore, the projections show that combustion pulses of remaining fossil fuel reserves could then be tailored to raise atmospheric CO2 content high and long enough to parry forcing of ice age onsets by summer insolation minima far into the future. Our present interglacial period could be extended by about 500,000 years in this way.

  16. Neurologic Involvement in Scleroderma en Coup de Sabre

    Science.gov (United States)

    Amaral, Tiago Nardi; Marques Neto, João Francisco; Lapa, Aline Tamires; Peres, Fernando Augusto; Guirau, Caio Rodrigues; Appenzeller, Simone

    2012-01-01

    Localized scleroderma is a rare disease, characterized by sclerotic lesions. A variety of presentations have been described, with different clinical characteristics and specific prognosis. In scleroderma en coup de sabre (LScs) the atrophic lesion in frontoparietal area is the disease hallmark. Skin and subcutaneous are the mainly affected tissues, but case reports of muscle, cartilage, and bone involvement are frequent. These cases pose a difficult differential diagnosis with Parry-Romberg syndrome. Once considered an exclusive cutaneous disorder, the neurologic involvement present in LScs has been described in several case reports. Seizures are most frequently observed, but focal neurologic deficits, movement disorders, trigeminal neuralgia, and mimics of hemiplegic migraines have been reported. Computed tomography and magnetic resonance imaging have aided the characterization of central nervous system lesions, and cerebral angiograms have pointed to vasculitis as a part of disease pathogenesis. In this paper we describe the clinical and radiologic aspects of neurologic involvement in LScs. PMID:22319646

  17. Exponential rate of correlation decay for characters in a three-parameter class of toral skew endomorphisms

    International Nuclear Information System (INIS)

    Siboni, S.

    1998-01-01

    A detailed analysis of the correlation decay for characters in a three-parameter class of mappings of the 2-torus onto itself is presented. Being these mappings the natural extension of toral transformations previously considered with regard to a model of modulated diffusion, they show the structure of a skew product between the Bernoulli endomorphism B p (x) and a translation on T 1 . The family of characters for which correlation decay occurs is fully characterized for any choice of the parameters, and the decay is proved to be exponential, with a rate analytically computable. This improves a previous result by W. Parry, provides a lower bound to the spectral radius of a Perron-Frobenius operator introduced by the same author in his proof and answers positively to the conjecture that the poorest is the rational approximation of the coupling parameter of the map the fastest is the decay rate

  18. Neutron spectrum unfolding using computer code SAIPS

    International Nuclear Information System (INIS)

    Karim, S.

    1999-01-01

    The main objective of this project was to study the neutron energy spectrum at rabbit station-1 in Pakistan Research Reactor (PARR-I). To do so, multiple foils activation method was used to get the saturated activities. The computer code SAIPS was used to unfold the neutron spectra from the measured reaction rates. Of the three built in codes in SAIPS, only SANDI and WINDOWS were used. Contribution of thermal part of the spectra was observed to be higher than the fast one. It was found that the WINDOWS gave smooth spectra while SANDII spectra have violet oscillations in the resonance region. The uncertainties in the WINDOWS results are higher than those of SANDII. The results show reasonable agreement with the published results. (author)

  19. Spirituality in Sport – Athletes’ Experiences and Reflections

    DEFF Research Database (Denmark)

    Ronkainen, Noora; Nesti, Mark; Tikkanen, Olli

    Northern European countries, England and Finland. Our inquiry was grounded on existential-narrative framework and a broad existentialist definition of spirituality (Webster, 2004). The empirical data was collected through essay writing. Eight elite athletes were invited to write a reflective story about...... mainly, but not exclusively, humanistic dimensions of spirituality. The emerging themes included transcendence, movement as a way of being and experiencing, love for the sport, wonder and awe. We suggest that although many people in Northern European countries may not identify their experiences......-cognitive theorizing. References Parry, J., Robinson, S., Watson, N. and Nesti, M. (2007). Sport and Spirituality: An Introduction. London: Routledge. Webster, R. (2004). An Existential Framework of Spirituality. International Journal of Children’s Spirituality 9: 7–19....

  20. Facial hemiatrophy: Review of literature and a case report

    Directory of Open Access Journals (Sweden)

    Manisha S Tijare

    2011-01-01

    Full Text Available A case report of hemifacial atrophy is presented in this paper. It is also known as Parry-Romberg syndrome, is an uncommon degenerative and poorly understood condition. It is characterized by progressive atrophy of the skin, subcutaneous tissue, muscle, cartilage or bone; the condition can leave a marked deformity on one side of the face. The incidence and the cause of this alteration is debatable. The most common complications that appear in association to this health disorder are: trigeminal neuritis, facial paresthesia, severe headache and epilepsy. Now, plastic surgery with graft of autogenous fat can be performed, after stabilization of the disease, to correct the deformity. Orthodontic treatment can help in the correction of any associated malformation. This presentation gives a review of concern literature about the etiology, physiopathology, differential diagnosis and treatment of hemifacial atrophy.

  1. Grave's disease 1835-2002.

    Science.gov (United States)

    Weetman, A P

    2003-01-01

    This brief review describes the history of Graves' disease, starting with the original descriptions by Parry, Graves and von Basedow. The true aetiology of the disorder was uncovered in the 1950s and 1960s, based on the search for a novel thyroid stimulator which turned out to be an immunoglobulin G autoantibody. Assays for these thyroid stimulatory antibodies have been continually refined and their epitopes on the thyroid stimulating hormone receptor are increasingly well characterized. We also understand far more about the genetic and environmental susceptibility factors that predispose to disease, and even thyroid-associated ophthalmopathy has now been better defined as primarily a T-cell-mediated disease resulting from cytokine stimulation of orbital fibroblasts. These advances should improve treatment options for Graves' disease in the foreseeable future.

  2. Concept development of control system for perspective unmanned aerial vehicles

    Directory of Open Access Journals (Sweden)

    Koryanov Vsevolod V.

    2018-01-01

    Full Text Available Presented actual aspects of the development of the control system of unmanned aerial vehicles (UAVs in the example of perspective. Because the current and future UAV oriented to implementation of a wide range of tasks, taking into account the use of several types of payload, in this paper discusses the general principles of construction of onboard control complex, in turn, a hardware implementation of the automatic control system has been implemented in the microcontroller Arduino platform and the Raspberry Pi. In addition, in the paper presents the most common and promising way to ensure the smooth and reliable communication of the command post with the UAV as well as to the ways of parry considered and abnormal situations.

  3. Bone fractures as indicators of intentional violence in the eastern Adriatic from the antique to the late medieval period (2nd-16th century AD).

    Science.gov (United States)

    Slaus, Mario; Novak, Mario; Bedić, Zeljka; Strinović, Davor

    2012-09-01

    To test the historically documented hypothesis of a general increase in deliberate violence in the eastern Adriatic from the antique (AN; 2nd-6th c.) through the early medieval (EM; 7th-11th c.) to the late-medieval period (LM; 12th-16th c.), an analysis of the frequency and patterning of bone trauma was conducted in three skeletal series from these time periods. A total of 1,125 adult skeletons-346 from the AN, 313 from the EM, and 466 from the LM series-were analyzed. To differentiate between intentional violence and accidental injuries, data for trauma frequencies were collected for the complete skeleton, individual long bones, and the craniofacial region as well as by type of injury (perimortem vs. antemortem). The results of our analyses show a significant temporal increase in total fracture frequencies when calculated by skeleton as well as of individuals exhibiting one skeletal indicator of deliberate violence (sharp force lesions, craniofacial injuries, "parry" fractures, or perimortem trauma). No significant temporal increases were, however, noted in the frequencies of craniofacial trauma, "parry" fractures, perimortem injuries, or of individuals exhibiting multiple skeletal indicators of intentional violence. Cumulatively, these data suggest that the temporal increase in total fracture frequencies recorded in the eastern Adriatic was caused by a combination of factors that included not only an increase of intentional violence but also a significant change in lifestyle that accompanied the transition from a relatively affluent AN urban lifestyle to a more primitive rural medieval way of life. Copyright © 2012 Wiley Periodicals, Inc.

  4. Implications of the Goal Theory on air show programs planning

    Directory of Open Access Journals (Sweden)

    Dewald Venter

    2014-01-01

    Full Text Available Events have long played an important role in human society (Shone & Parry, 2010: 3. The toils and efforts of daily lives have often been broken up by events of all kinds as humans seek an escape from the harsh reality of existence and events provide the outlet. Events are classified into four categories according to Shone and Parry (2010: 5 namely leisure (sport, recreation, personal (weddings, birthdays, cultural (art, folklore and organizational (politics, commercial. Successful events either match or exceed visitor motives and goals. It is critical that data be collected from visitors to determine their motives and goals in order to satisfy them and thereby encouraging repeat visits. One such event is the annual air show held at the Zwartkop Air Force Base (AFB in Pretoria, South Africa. Zwartkop AFB is also home to the South African Air Force (SAAF museum that also the hosts of the air show. Much of the museum‟s funds are generated through hosting the air show and sponsor contributions. Visitor goal satisfaction should therefore be of critically importance to the program planners. Military hardware has long held a fascination for those who used them and inspired the imagination of young and old. Such hardware often serves as a remembrance of times passed and as a testament to those who perished. For many visiting museums and air shows, curiosity plays a big role. The particular focus of this article will be on how the goal theory of leisure travel can be utilized by the air show organizers to enhance visitor experience to an air show.

  5. Design, implementation and licensing of improvement measures

    International Nuclear Information System (INIS)

    Rousset, P.

    2000-01-01

    Modifications are designed to contribute to improve the level of safety, and the level of performance of the plants. The successful implementation of a modification depends on the quality of the design and particularly the good fitting of the modification in the existing design, on the perfect consistency of the licensing approach and on the good management of the project constraints and interfaces. Over the last ten years, FRAMATOME has accumulated a large and varied experience in these activities, as shown in the few examples briefly described in the presentation. Within the Mochovce completion project, FRAMATOME has been in charge of the basic design or implementation of about twenty safety measures. This involved establishing efficient partnerships with design organizations and suppliers in the Slovak Republic, Czech Republic, and Russia. A similar approach is used in the frame of the Kozloduy 5-6 modernization program, where the basic engineering contract is conducted since 1998 and the main contract under discussion. From the very beginning of the TACIS program FRAMATOME has been involved in projects dealing with the design of reactor safety systems. For example, an extensive work aiming at developing a methodology for accident analysis in VVER reactor was initiated in 1993, in collaboration with Siemens, Kurchatov Institute and OKB Gidropress. This methodology was recently used successfully in a new project with the objective to evaluate the possible modification of reactor protection signals of some Russian reactors. Within the PHARE program, a complete analysis of the primary to secondary leakage risk was conducted for Paks nuclear power plant. This involved the writing and validation of the relevant emergency procedure, specification of the leak detection system, study of an improved design of the collector cover, and recommendation of some systems modifications. A last example is the study of the modifications of main steam lines performed in the frame

  6. Next generation of energy production systems; Lancement pour les systemes du futur

    Energy Technology Data Exchange (ETDEWEB)

    Rouault, J.; Garnier, J.C. [CEA Saclay Dir. de l' Energie Nucleaire DEN, 91 - Gif sur Yvette (France); Carre, F. [CEA Saclay, Dir. du Developpement et de l' Innovation Nucleares - DDIN, 91 - Gif Sur Yvette (France)] [and others

    2003-07-01

    This document gathers the slides that have been presented at the Gedepeon conference. Gedepeon is a research group involving scientists from Cea (French atomic energy commission), CNRS (national center of scientific research), EDF (electricity of France) and Framatome that is devoted to the study of new energy sources and particularly to the study of the future generations of nuclear systems. The contributions have been classed into 9 topics: 1) gas cooled reactors, 2) molten salt reactors (MSBR), 3) the recycling of plutonium and americium, 4) reprocessing of molten salt reactor fuels, 5) behavior of graphite under radiation, 6) metallic materials for molten salt reactors, 7) refractory fuels of gas cooled reactors, 8) the nuclear cycle for the next generations of nuclear systems, and 9) organization of research programs on the new energy sources.

  7. Utilization of ''CONTACT'' experiments to improve the fission gas release knowledge in PWR fuel rods

    Energy Technology Data Exchange (ETDEWEB)

    Charles, M; Abassin, J J; Bruet, M; Baron, D; Melin, P

    1983-03-01

    The CONTACT experiments, which were carried out by the French CEA, within the framework of a CEA-FRAMATOME collaboration agreement, bear on the behaviour of in-pile irradiated PWR fuel rods. We will focus here upon their results dealing with fission gas release. The experimental device is briefly described, then the following results are given: the kinetics of stable fission gas release for various linear ratings; the instantaneous fractional release rates of radioactive gases versus their decay constant in the range 1.5 10/sup -6/-3.6 10/sup -3/s/sup -1/, for various burnups, as also the influence of fuel temperature. Moreover, the influence of the nature and the pressure of the filling gas upon the release is presented for various linear ratings. The experimental results are discussed and analysed with the purpose to model various physical phenomena involved in the release (low-temperature mechanisms, diffusion).

  8. Study of the conditions affecting the critical speed of a rotating pump shaft

    International Nuclear Information System (INIS)

    Fardeau, P.; Huet, J.L.; Axisa, F.

    1983-01-01

    Knowing the parameters conditioning the critical speed of a pump shaft is important, both for safety and design purposes, since the shafts are often to operate beyond the first critical speed. These aims led CEA, associated with NOVATOME and FRAMATOME (with the cooperation of JEUMONT-SCHNEIDER) to carry out a test program on critical speeds of a full scale nuclear pump shaft. Fluid-structure interaction plays an important part in the setting of critical speed. Due to the coupling between the rotative fluid flow and the transverse vibrations of the shaft, inertial and stiffness forces are created, which are non conservative and proportional to the added mass of the fluid. The hydrostatic bearing effect and the influence of the water carried along by the pump wheel were also investigated, but proved unimportant in the case of the shaft studied. Experimental results are compared with calculations of critical speed. (orig.)

  9. The thermo-mechanics of the PWR fuel rod; La thermomecanique du crayon de combustible REP

    Energy Technology Data Exchange (ETDEWEB)

    Barral, J.C. [Electricite de France, EDF, 75 - Paris (France); Gautier, B.; Chaigne, G. [Electricite de France, Service Etudes et Projets Thermiques et Nucleaires, 75 - Paris (France)] [and others

    1999-03-29

    The fuel rod mechanics is of a great importance in the safety and performance of the reactors. In this domain a meeting has been organized by the SFEN the 18 march 1998 at Paris. With the participation of scientists from CEA, EDF and Framatome, the physics of the fuel rods was presented based on four main aspects. Two first papers dealt with the solicitations of the fuel rod in normal and accidental conditions. The physical phenomena under irradiation were then detailed in the four following talks. Three papers presented the simulation and the codes of the fuel-cladding interactions with the diabolo effect. The last paper was devoted to the experiment feedback and the research programs. (A.L.B.)

  10. The thermo-mechanics of the PWR fuel rod

    International Nuclear Information System (INIS)

    Barral, J.C.; Gautier, B.; Chaigne, G.

    1999-01-01

    The fuel rod mechanics is of a great importance in the safety and performance of the reactors. In this domain a meeting has been organized by the SFEN the 18 march 1998 at Paris. With the participation of scientists from CEA, EDF and Framatome, the physics of the fuel rods was presented based on four main aspects. Two first papers dealt with the solicitations of the fuel rod in normal and accidental conditions. The physical phenomena under irradiation were then detailed in the four following talks. Three papers presented the simulation and the codes of the fuel-cladding interactions with the diabolo effect. The last paper was devoted to the experiment feedback and the research programs. (A.L.B.)

  11. High pressure sealing systems for nuclear reactors

    International Nuclear Information System (INIS)

    Garam, E. de

    1993-01-01

    TIA is the FRAMATOME Division in charge of design, manufacture maintenance and improvement of reactor core instrumentation. In the course of its activities, TIA was rapidly confronted with problems of leakage occurring in PWR in-core instrumentation, both in the neutron flux measurement system (flux thimbles and thimble guide tubes) and in the equipment used for core temperature sensing. TIA has likewise placed emphasis, in setting objectives for its operations, on improving instrumentation reliability, reducing maintenance costs and limiting the radiation doses sustained during maintenance. The very satisfactory results achieved by TIA in all of these areas have led us to look to the future with confidence. The purpose of this presentation is to describe the various improvements devised by TIA over the years and to take inventory of the experience gained by the Division with instrumentation for all types of nuclear power plants. (author)

  12. Improvement of nuclear core power distribution analysis for Ulchin unit 1 and 2

    International Nuclear Information System (INIS)

    Chang, Jong Hwa; Zee, Sung Kyoon; Lee, Sang Ho; Park, Yong Soo; Lee, Chang Ho; Choi, Young Kil; Kim, Hee Kyung; Cho, Young Sik; Cho, In Hang

    1994-12-01

    The FMCP package which does the power shape analysis of Framatom type of reactors on IBM mainframe, is migrated to an IBM-PC system. This report describes the related technique and works. An IBM-PC software DAP is developed to replace the plant computer attached 8 inch floppy disk driver to an IBM-PC. Other programs of FMCP, such as CEDRIC, CARIN and ESTHER, are also migrated to an IBM-PC using Lahey Fortran 77 compiler. A few auxiliary programs are also developed for easy handling of FMCP in the IBM-PC environment. This report describes the usage of the developed system as well as the migration related techniques. (Author) 4 figs

  13. Thermal and in-pile densification of MOX fuels: Some recent results

    International Nuclear Information System (INIS)

    Caillot, L.; Malgouyres, P.P.; Souchon, F.; Gotta, M.J.; Warin, D.; Chotard, A.; Couty, J.C.

    1997-01-01

    In-pile densification of PWR fuels is one of the main phenomena which determine the evolution of the pellet-clad gap during the first stage of the irradiation, and thus has consequences onto the thermo-mechanical behaviours of fuel rods. It can be predicted using the results of resintering tests and appropriate correlations. In this context, CEA, FRAMATOME and EDF have undertaken a joint research programme aiming to characterize the densification of MOX fuels. Different fuels were prepared by the MIMAS process using different UO 2 powders as matrix. After a detailed characterization, fuel pellets were submitted to isothermal resintering tests and analytical irradiations. Correlations between in-pile and thermal densification were established. This paper presents the results obtained with two types of MOX fuel: one fabricated wit the AUC UO 2 powder (ammonium uranyl carbonate conversion process) and another one fabricated with the SFEROX powder (peroxide conversion process). 8 refs, 8 figs

  14. Quench tank in-leakage diagnosis at St. Lucie

    Energy Technology Data Exchange (ETDEWEB)

    Price, J.E.; Au-Yang, M.K.; Beckner, D.A.; Vickery, A.N.

    1996-12-01

    In February 1995, leakage into the quench tank of the St. Lucie Nuclear Station Unit 1 was becoming an operational concern. This internal leak resulted in measurable increases in both the temperature and level of the quench tank water, and was so severe that, if the trend continued, plant shut down would be necessary. Preliminary diagnosis based on in-plant instrumentation indicated that any one of 11 valves might be leaking into the quench tank. This paper describes the joint effort by two teams of engineers--one from Florida Power & Light, the other from Framatome Technologies--to identify the sources of the leak, using the latest technology developed for valve diagnosis.

  15. Mechanical behaviour of the reactor vessel support of a pressurized water reactor: tests and analysis

    International Nuclear Information System (INIS)

    Bolvin, M.; L'huby, Y.; Quillico, J.J.; Humbert, J.M.; Thomas, J.P.; Hugenschmitt, R.

    1985-08-01

    The PWR reactor vessel is supported by a steel ring laying on the reactor pit. This support has to ensure a good behaviour of the vessel in the event of accidental conditions (earthquake and pipe rupture). A new evolution of the evaluation methods of the applied forces has shown a significant increase in the design loads used until now. In order to take into account these new forces, we carried out a test on a representative mock-up of the vessel support (scale 1/6). This test was performed by CEA, EDF and FRAMATOME. Several static equivalent forces were applied on the experimental mock-up. Displacements and strains were simultaneously recorded. The results of the test have enabled to justify the design of the pit and the ring, to show up a wide safety margin until the collapse of the structures and to check our hypothesis about the transmission of the forces between the ring and the pit

  16. GNPS 18-months fuel cycles core thermal hydraulic design

    International Nuclear Information System (INIS)

    Liu Changwen; Zhou Zhou

    2002-01-01

    GNPS begins to implement the 18-month fuel cycles from the initial annual reload at cycle 9, thus the initial core thermal hydraulic design is not valid any more. The new critical heat flux (CHF) correlation, FC, which is developed by Framatome, is used in the design, and the generalized statistical methodology (GSM) instead of the initial deterministic methodology is used to determine the DNBR design limit. As the AFA 2G and AFA 3G are mixed loaded in the transition cycle, it will result that the minimum DNBR in the mixed core is less than that of AFA 3G homogenous core, the envelop mixed core DNBR penalty is given. Consequently the core physical limit for mixed core and equilibrium cycles, and the new over temperature ΔT overpower ΔT are determined

  17. Nuclear - the faint hope Areva

    International Nuclear Information System (INIS)

    Dupin, Ludovic

    2015-01-01

    This article discusses the future of Areva as a part of its activities (nuclear reactor building and maintenance) is now managed by EDF. The author notices that Areva's present situation looks like the Cogema's one before its merge with Framatome and some CEA activities to give birth to Areva. The main problem is the debt for a group which possesses important assets (hyper-profitable uranium mines, advanced technology plants for nuclear fuel processing) and opportunities (the possibility to become a leader in the dismantling activity, to take advantage of the increasing uranium demand), but is unable to self-finance, suffers from its heavy organisation which needs to be reviewed and even separated into two companies, and is also threatened by the cost of new reactors and by being too small to launch new projects in front of the giants of the mining sector

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

    International Nuclear Information System (INIS)

    Lacoste, A.-C.

    1993-01-01

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

  19. Ultrasonic inspection of primary pump casing by means of focussing probes

    International Nuclear Information System (INIS)

    Dombret, Ph.; Cermak, J.

    1985-01-01

    This paper describes a study conducted in laboratory on ultrasonic defect detection capabilities in primary pump casings and welds, in the framework of the joint research programme appointed by Framatome, EdF, CEA and Westinghouse, and devoted to improving the ultrasonic inspection of austenitic stainless steel components. Several transducers, including focussing probes and transmitter-receivers, were designed and compared on two 180 mm thick blocks strictly representative of the statically cast casing and of the electroslag welding, and containing various artificial and simulated reflectors. Detection trial results show that focussing probes can achieve fair sensitivity levels even through the full thickness, and appear promising as for on-site applications of this technique. 5 refs

  20. Comparison of French and German NPP water chemistry programs

    International Nuclear Information System (INIS)

    Staudt, U.; Odar, S.; Stutzmann, A.

    2002-01-01

    PWRs in the western hemisphere obey basically the same rules concerning design, choice of material and operational mode. In spite of these basic similarities, the manufacturers of PWRs in different countries developed different solutions in respect to single components in the steam/water cycle. Looking specifically at France and Germany, the difference in the tubing material of the steam generators (Inconel 600/690 chosen by Framatome and Incoloy 800 chosen by the former Siemens KWU) led to specific differences in the respective chemistry programs and in some respect to different 'philosophies' in operating the water/steam cycle. Compared to this, basic differences in operating the reactor coolant system cannot be observed. Nevertheless specific solutions as zinc injection and the use of enriched B-10 are applied in German PWRs. The application of such measures arises from a specific dose rate situation in older PWRs (zinc injection) or from economic reasons mainly (B-10). (authors)

  1. Common safety approach for future pressurized water reactors in France and Germany

    International Nuclear Information System (INIS)

    Queniart, D.; Gros, G.

    1994-01-01

    In France and Germany all major activities related to future pressurized water reactors are now proceeding in a coordinated way among the two countries. This holds for utilities and industry in the development of a joint PWR project, the ''European Pressurized Water Reactor (EPR)'' by Electricite de France (EDF), German utilities, Nuclear Power International (NPI), Framatome and Siemens as well as for the technical safety objectives for future evolutionary reactors on the basis of a common safety approach adopted by the safety authorities of both countries for plants to operate form the beginning of the next century. The proposed paper covers this common development of a safety approach and particular technical safety objectives. (authors). 5 refs. 1 fig

  2. GT-MHR as economical highly efficient inherently safe modular gas cooled reactor for electric power generation

    International Nuclear Information System (INIS)

    Baydakov, A.G.; Kodochigov, N.G.; Kuzavkov, N.G.; Vorontsov, V.E.

    2001-01-01

    The Gas Turbine Modular Helium Reactor (GT-MHR) project is a joint effort of organisations in the Russian Federation co-ordinated by the Ministry on Atomic Energy (MINATOM), General Atomics in the United States, Framatome in France, and Fuji Electric in Japan. This paper describes the structure, objectives and history of the GT-MHR project, as well as the plant design, including plant layout, components and fuel. It summarises the results of evaluations of the design safety characteristics and economics, for both a plutonium fueled single module and a uranium fueled four module plant. The plans and anticipated structure for an international project to construct the plant are also summarised. (author)

  3. FBFC

    International Nuclear Information System (INIS)

    1999-01-01

    The Franco-Belge de Fabrication de Combustibles (FBFC) is a French company which belongs to the Framatome nuclear fuel business group. FBFC is involved in the fuel fabrication from the conversion, pelletizing, rods loading, manufacturing of components for fuel assembly to the completion. This structure brings together zirconium metallurgy and fuel assembly fabrication. This booklet presents the main stages of the fabrication of fuel assemblies for PWR reactors: UF 6 /UO 2 conversion, powder and pellet preparation, loading of fuel rods, fuel assembly components, completion of fuel assemblies, the updated production resources and the latest technological progress, the quality requirements, the other suppliers and partners, the safety and environmental aspects. (J.S.)

  4. The way ahead: Success factors - PWR evolution in France

    Energy Technology Data Exchange (ETDEWEB)

    Charbonneau, S [Framatome, Paris (France)

    1990-06-01

    The first of the model N4 reactors will be commissioned in the early 1990S. This model benefits from experience gained in the design, construction and operation of the large and consistent French program achieved during the last 20 years. Subsequent units to be brought on line in the 1990s will also be of the N4 design, in accordance with the French policy of standardization to maximize safety and reduce costs. Studies under way on the reactor that will follow the N4 are oriented in two main directions: additional improvements to enhance safety and more efficient use of the fissile material. These studies take into account the development of a common nuclear island by NPI, the new joint-venture between Framatome and Siemens-KWU. The author's opinion is that the French program consistency offers the best mean to help bridging KOEBERG onto the next units which ESCOM may decide to build in the future. (author)

  5. Valves maintenance management in nuclear power plants

    International Nuclear Information System (INIS)

    Trost, J.

    2001-01-01

    The deregulation of Europe's power market will force nuclear power plant operators to introduce extensive cost-cutting measures in order to be able to compete within this new environment. The optimization of plant outages provides considerable potential for raising plant availability but can also lower operating costs by reducing expenditure on maintenance. Framatome ANP GmbH, in cooperation with plant operators is currently developing new and improved service concepts which can have a major effect on the way in which maintenance will be performed in the future. The concepts encompass optimization of the overall sequence from planning in advance to the individual measures including reduction of the scope of maintenance activities, identification of cost cutting potential and bundling of maintenance activities. (Author)

  6. Fracture probability evaluation of a LWR pressure vessel

    International Nuclear Information System (INIS)

    Grandemange, J.; Pellissier-Tanon, A.; Quero, J.; Carnino, A.; Dufresne, J.

    1978-01-01

    Fracture probability evaluation, of a LWR pressure vessel have been performed in the past, using statistical data from conventional plant. A more accurate evaluation has been requested in 1976 from the SCSIN to the CEA. With this object, a joint collaboration agreement has been signed between CEA, EURATOM/ISPRA and FRAMATOME. The whole program proceeding from this agreement is managed by a joint board including the three partners. The basic objective of this program is to develop a method which integrates, or makes it possible to integrate at a later stage, the greatest number of significant parameters. Also, in order to prepare the practical applications, a special effort is being made to collect the data corresponding to these parameters. Parallel basic research program have been launched in order to clarify our knowledge on some important parts of the main factors contributing to the evaluation. The results of this research will be progressively introduced into the method or will help checking its validity

  7. Residual heat removal during accidental situations

    International Nuclear Information System (INIS)

    Depond, M.; Sureau, H.; Tellier, N.

    1983-07-01

    Existing emergency procedures, whose purpose is residual heat removal and a safe recovery are based on sequential analysis and initiating event diagnosis. This approach was found in some cases inappropriate and inefficient, specially in case of out-of-design accidents corresponding to multiple equipment failure or simultaneous human failures. To cope with these situations, a new approach was necessary. Parallel studies performed in France at Framatome (the designer) and Electricity de France (the utility) gave a new method, called NSSS physical states approach. Prior to the implementation of this method which necessitates further studies and developments, some improvements in the existing operating procedures derived from the NSSS physical states have already been achieved: that is the case for the safety injection control and the development of an emergency procedure called ''U1''. This paper will briefly physical states approach and present the ''U1'' procedure. The tools which will be used to chack these methods are also mentioned

  8. Impact of the TMI accident on the French nuclear program and the safety analysis

    International Nuclear Information System (INIS)

    Fourest, B.; Boaretto, Y.; Cayol, A.; Droulers, Y.; Goudal, M.; Oury, J.M.

    1980-04-01

    Almost immediately after the TMI accident, Electricite de France (EdF), Framatome and the French safety authorities started a large scale program of actions designed to analyse and understand the causes of the accident, and draw lessons applicable in France. This paper discusses these actions and the main conclusions of TMI accident analysis in France, notably: the fundamental role of plant operators, and the importance of operator training, written instructions and procedures, and diagnostic aids; the importance of feeding back operating experience to design teams, and incorporating the results of accident and post-accident studies in operating procedures; the necessity to improve knowledge of core cooling modes, including during two-phase flow and natural circulation; measures to improve particular systems and components [fr

  9. A simple modelling of mass diffusion effects on condensation with noncondensable gases for the CATHARE Code

    Energy Technology Data Exchange (ETDEWEB)

    Coste, P.; Bestion, D. [Commissariat a l Energie Atomique, Grenoble (France)

    1995-09-01

    This paper presents a simple modelling of mass diffusion effects on condensation. In presence of noncondensable gases, the mass diffusion near the interface is modelled using the heat and mass transfer analogy and requires normally an iterative procedure to calculate the interface temperature. Simplifications of the model and of the solution procedure are used without important degradation of the predictions. The model is assessed on experimental data for both film condensation in vertical tubes and direct contact condensation in horizontal tubes, including air-steam, Nitrogen-steam and Helium-steam data. It is implemented in the Cathare code, a french system code for nuclear reactor thermal hydraulics developed by CEA, EDF, and FRAMATOME.

  10. Directory of the French nuclear industry

    International Nuclear Information System (INIS)

    2002-10-01

    This directory includes data sheets on the French companies operating in the nuclear industry. It begins with an introduction containing information on the French nuclear industry: 1 - nuclear power development in France (national energy plan, history, organization, economic advantages, reactors); 2 - French operator: Electricite de France (EdF); 3 - the industry (Areva, Cogema, mining activities, uranium chemistry and enrichment, processing, recycling, engineering, services, Framatome ANP); 4 - R and D and knowledge dissemination: French atomic energy commission (CEA); 5 - nuclear safety, security, control and regulation: nuclear safety authority (ASN), general direction of nuclear safety and radioprotection (DGSNR), institute of radioprotection and nuclear safety (IRSN), radioactive wastes, ANDRA's role; 6 - associations: French atomic forum (FAF), French nuclear industry trade association (GIIN), French nuclear energy society (SFEN), French radiation protection society (SFRP). Then, the data sheets of the directory follows. (J.S.)

  11. SWR 1000 severe accident control through in-vessel melt retention by external RPV cooling

    Energy Technology Data Exchange (ETDEWEB)

    Kolev, N.I. [Framatome Advanced Nuclear Power, NDSI, Erlangen (Germany)

    2001-07-01

    Framatome Advanced Nuclear Power is being designing a new generation NPP with boiling water reactor SWR1000. Besides of various of modern passive and active safety features the system is also designed for controlling of a postulated severe accident with extreme low probability of occurrence. This work presents the rationales behind the decision to select the external cooling as a safety management strategy during severe accident. Bounding scenery are analyzed regarding the core melting, melt-water interaction during relocation of the melt from the core region into the lower head and the external coolability of the lower head. The conclusion is reached that the external cooling for the SWR1000 is a valuable strategy for accident management during postulated severe accidents. (authors)

  12. SWR 1000 severe accident control through in-vessel melt retention by external RPV cooling

    International Nuclear Information System (INIS)

    Kolev, N.I.

    2001-01-01

    Framatome Advanced Nuclear Power is being designing a new generation NPP with boiling water reactor SWR1000. Besides of various of modern passive and active safety features the system is also designed for controlling of a postulated severe accident with extreme low probability of occurrence. This work presents the rationales behind the decision to select the external cooling as a safety management strategy during severe accident. Bounding scenery are analyzed regarding the core melting, melt-water interaction during relocation of the melt from the core region into the lower head and the external coolability of the lower head. The conclusion is reached that the external cooling for the SWR1000 is a valuable strategy for accident management during postulated severe accidents. (authors)

  13. Elements on reactor control

    International Nuclear Information System (INIS)

    Bruna, G.B.

    1998-01-01

    In order to achieve the two-fold goal of maximizing the energy obtained from reactor fuel and ensuring the large flexibility of plant operation in respect to safety regulations and keeping the reactor integrity the control of PWRs is generally based on real time monitoring and analysing of independent neutronic parameters: thermal power release, axial power distribution in the core and temperatures of the primary loop. Two control chains more or less coupled according to the control chosen mode are in charge of the control of these parameters. With the brief history of control in French power reactors the advanced X control mode adopted by Framatome for N4 plants is described in detail. A summary of N4 reactor control and protection system is included

  14. Design - manufacturing and characterization of specific ultrasonic probes

    International Nuclear Information System (INIS)

    Petit, J.

    1985-01-01

    Optimization of ultrasonic examinations requires essentially to determine precisely parameters used for manufacturing of probes and to check characteristics of beams used. The system presented permits an automatic determination of dimensions of beams in conditions which are totally representative of those of their use. In the field of ultrasonic examinations a good estimate or knowledge of sound beams is of great help to solve difficult examination problems. The FRAMATOME's Centre d'Etude et de Recherche en Essais Non Destructifs (CEREND) : (Study and Research Center in Non-Destructive Testing) has developed and elaborated various techniques in order to improve ultrasonic examinations with specific probes. These techniques concern design, manufacturing and characterization of these probes

  15. Annual report 2000

    International Nuclear Information System (INIS)

    2001-01-01

    This document provides information on the activities of the Cea-Industry Group during the year 2000. The following topics are presented: the profile of the Cea-Industry Group, keys data for 2000, the nuclear fuel cycle, the nuclear power plants and nuclear services, the biomedical, the semiconductors, the financial aspects and the management report of the board of directors. A special interest is given to the new organization which has been set up and which will give birth to an industrial group of global dimension, named Topco for the present. By combining the activities of Cogema, Framatome ANP and their subsidiaries, the ''nuclear technologies'' business Topco, will regroup french expertise in the atom, from the fuel cycle to cleanup and dismantling, from services to engineering. (A.L.B.)

  16. Systems reliability Benchmark exercise part 2-Contributions by the participants

    International Nuclear Information System (INIS)

    Amendola, A.

    1986-01-01

    The report describes aims, rules and results of the Systems Reliability Benchmark Exercise, which has been performed in order to assess methods and procedures for reliability analysis of complex systems and involved a large number of European organizations active in NPP safety evaluation. The exercise included both qualitative and quantitative methods and was structured in such a way that separation of the effects of uncertainties in modelling and in data on the overall spread was made possible. This second part of the report is devoted to the documentation of the single contributions by the participant teams (Swedish, GRS, ENEA, NIRA and ENEL, EWE, EdF, Risoe, KWU/IA, ECN, KEMA/KUL, and Framatome contributions)

  17. In-core fuel management: New challenges

    International Nuclear Information System (INIS)

    Kolmayer, A.; Vallee, A.; Mondot, J.

    1992-01-01

    Experience accumulated by pressurized water reactor (PWR) utilities allows them to improve their strategies in the use of eventual margins to core design limits. They are used for nuclear steam supply system (NSSS) power upgrading, to improve operating margins, or to adapt fuel management to specific objectives. As a result, in-core fuel management strategies have become very diverse: UO 2 or mixed-oxide loading, out-in or in-out fuel loading patterns, extended or annual cycle lengths with margins on design limits such as moderator temperature coefficients, boron concentrations, or peaking factors. Perspectives also appear concerning use of existing plutonium stocks or actinide incineration. Burnable poisons are most often needed to satisfactorily achieve these goals. Among them, gadolinia are now largely used, owing to their excellent performance. More than 24 Framatome first cores and reloads, representing more than 3000 gadolinia-bearing rods, have been irradiated since 1983

  18. Plant maneuvrability in France: recent developments and future prospects

    International Nuclear Information System (INIS)

    Gautier, A.; Guesdon, B.

    1986-06-01

    In the early 1970's, it was correctly anticipated that in 10 year's time PWR's would become major contributors to energy production in France and would therefore have to participate largely in adjustment of supply to demand. A substantial effort was launched between vendor (FRAMATOME), utility (EDF) and the French Atomic Energy Commission (CEA) to greatly improve PWR's flexibility, resulting in the current situation where both frequency control and load follow are now routinely performed on most plants in operation. Based on rapidly accumulating operational experience and on all expertise acquired in the past decade, a second-generation core control strategy is now being finalized for application on all future 1400 MW plants (with commercial operation scheduled in 1992 for first unit). This core control includes a maximized Reactor Advanced Maneuvrability Package (RAMP or Dispositif maximise de Manoeuvrabilite Accrue DMAX in French) and an automated system control boron concentration (SYCOBOR)

  19. Overall models and experimental database for UO2 and MOX fuel increasing performance

    International Nuclear Information System (INIS)

    Bernard, L.C.; Blanpain, P.

    2001-01-01

    COPERNIC is an advanced fuel rod performance code developed by Framatome. It is based on the TRANSURANUS code that contains a clear and flexible architecture, and offers many modeling possibilities. The main objectives of COPERNIC are to accurately predict steady-state and transient fuel operations at high burnups and to incorporate advanced materials such as the Framatome M5-alloy cladding. An extensive development program was undertaken to benchmark the code to very high burnups and to new M5-alloy cladding data. New models were developed for the M5-alloy cladding and the COPERNIC thermal models were upgraded and improved to extend the predictions to burnups over 100 GWd/tM. Since key phenomena, like fission gas release, are strongly temperature dependent, many other models were upgraded also. The COPERNIC qualification range extends to 67, 55, 53 GWd/tM respectively for UO 2 , UO 2 -Gd 2 O 3 , and MOX fuels with Zircaloy-4 claddings. The range extends to 63 GWd/tM with UO 2 fuel and the advanced M5-alloy cladding. The paper focuses on thermal and fission gas release models, and on MOX fuel modeling. The COPERNIC thermal model consists of several submodels: gap conductance, gap closure, fuel thermal conductivity, radial power profile, and fuel rim. The fuel thermal conductivity and the gap closure models, in particular, have been significantly improved. The model was benchmarked with 3400 fuel centerline temperature data from many French and international programs. There are no measured to predicted statistical biases with respect to linear heat generation rate or burnup. The overall quality of the model is state-of-the-art as the model uncertainty is below 10 %. The fission gas release takes into account athermal and thermally activated mechanisms. The model was adapted to MOX and Gadolinia fuels. For the heterogeneous MOX MIMAS fuels, an effective burnup is used for the incubation threshold. For gadolinia fuels, a scaled temperature effect is used. The

  20. PWR pressurizer discharge piping system on-site testing

    International Nuclear Information System (INIS)

    Anglaret, G.; Lasne, M.

    1983-08-01

    Framatome PWR systems includes the installation of safety valves and relief valves wich permit the discharge of steam from the pressurizer to the pressurizer relief tank through discharge piping system. Water seal expulsion pluration then depends on valve stem lift dynamics which can vary according to water-stem interaction. In order to approaches the different phenomenons, it was decided to perform a test on a 900 MWe French plant, test wich objectives are: characterize the mechanical response of the discharge piping to validate a mechanical model; open one, two or several valves among the following: one safety valve and three pilot operated relief valves, at a time or sequentially and measure the discharge piping transient response, the support loads, the

  1. Local approach of cleavage fracture applied to a vessel with subclad flaw. A benchmark on computational simulation

    International Nuclear Information System (INIS)

    Moinereau, D.; Brochard, J.; Guichard, D.; Bhandari, S.; Sherry, A.; France, C.

    1996-10-01

    A benchmark on the computational simulation of a cladded vessel with a 6.2 mm sub-clad flaw submitted to a thermal transient has been conducted. Two-dimensional elastic and elastic-plastic finite element computations of the vessel have been performed by the different partners with respective finite element codes ASTER (EDF), CASTEM 2000 (CEA), SYSTUS (Framatome) and ABAQUS (AEA Technology). Main results have been compared: temperature field in the vessel, crack opening, opening stress at crack tips, stress intensity factor in cladding and base metal, Weibull stress σ w and probability of failure in base metal, void growth rate R/R 0 in cladding. This comparison shows an excellent agreement on main results, in particular on results obtained with local approach. (K.A.)

  2. Fast reactor development program in France in 1999

    International Nuclear Information System (INIS)

    Leclere, Jacques; Teilland, C.; Astegiano, J.C.; Desreumaux, J.; Grenet, P.; Del Beccaro, R.; Vasile, A.

    2000-01-01

    The year 1999 was marked by important industrial reorganisations, especially concerning Framatome: the shareholding was modified, and at the end of the year the fusion of nuclear activities with those of Siemens was decided. The construction of the last N4 plants is completed, with no realisation expected in the near future; the decision on an EPR unit is not expected in the short term. The operation of the plants was satisfying, the availability is nevertheless lower than in 1998. Renovation, inspection and maintenance works were actively conducted at Phenix; decommissioning work was undertaken at Superphenix; the core unloading began in December. The R and D strategy was redefined; on fast reactors, work decreases on sodium and increases on other variants. International collaborations remain active. (author)

  3. Experimental studies of PWR primary piping under loca

    International Nuclear Information System (INIS)

    Caumette, Pierre; Garcia, J.L.

    1980-07-01

    The experimental program performed on AQUITAINE II facility is directed to study the mechanical behavior of primary PWR pipes and the forces exerted on the neighbouring structures as a consequence of a breach opening. It has been developed in the form of a quadripartite agreement between the Commissariat a l'Energie Atomique, Framatome, Electricite de France and Westinghouse. Some forty tests have been carried out with different pipe configurations (straight tube, elbow, S- or U-shaped tube) and different break types (single or double guillotine). The following aspects are investigated: - the dynamic behavior of the pipe and in particular the formation of a plastic hinge at the restraint; - the impact function of a pipe or an energy-absorbing bumper; - the lateral stability of both ends of a pipe, after a double-guillotine break [fr

  4. PWR accident management realated tests: some Bethsy results

    International Nuclear Information System (INIS)

    Clement, P.; Chataing, T.; Deruaz, R.

    1993-01-01

    The BETHSY integral test facility which is a scaled down model of a 3 loop FRAMATOME PWR and is currently operated at the Nuclear Center of Grenoble, forms an important part of the French strategy for PWR Accident Management. In this paper the features of both the facility and the experimental program are presented. Two accident transients: a total loss of feedwater and a 2'' cold leg break in case of High Pressure Safety Injection System failure, involving either Event Oriented - or State Oriented-Emergency Operating Procedures (EO-EOP or SO-EOP) are described and the system response analyzed. CATHARE calculation results are also presented which illustrate the ability of this code to adequately predict the key phenomena of these transients. (authors). 13 figs., 11 refs., 2 tabs

  5. The communication in safety matter

    International Nuclear Information System (INIS)

    Lacoste, A.C.

    1997-01-01

    The nuclear risk has three interesting characteristics: it is new, it is insidious and it can be disastrous. These three characteristics lead to consider a particular role of public authorities( Dsin Direction of Nuclear Installations Safety). Nuclear energy can be taxed of two original sins: the close relation between military nuclear and civil nuclear energy, and the nuclear, in France, lacks of democracy.Third point: only five speakers in front of authorities: EDF, Cea, Cogema, Framatome and Andra and these five ones are linked with State. These points summarize the French situation in nuclear energy. By communication the Dsin tries to answer to two obligation, a moral code and a democratic debate. The tools to communicate are the review 'controle' which is published every two months, the Minitel service 'Magnuc ' (code 3614 MAGNUC). This role of communication is not required especially by local elected people but it is the administration which tries to make it work. (N.C.)

  6. Aging in PWR conditions of martensitic stainless steels

    International Nuclear Information System (INIS)

    Boursier, J.M.; Buisine, D.; Fronteau, M.; Michel, D.; Rouillon, Y.; Yrieix, B.; Meyzaud, Y.

    1998-01-01

    Martensitic stainless steels are largely used in Nuclear Power Plant (pump impeller, valve stem...) because of their high mechanical characteristics and their good resistance to corrosion. Nevertheless some of those components could operate at temperature higher than 250 deg.C, which could embrittle the material by the precipitation of a chromium-rich phase during aging. In collaboration with Framatome, Electricite de France has undertaken numerous studies in order to understand this process of embrittlement. This paper presents a review of the metallurgical investigations on martensitic stainless steels components which were performed in the EDF hot laboratory. In peculiar, it should be noted the good correlation between inservice experience and the modelling developed by EDF R and D division. Finally and in association with safety analysis, these results will allow to establish the maintenance strategy of the French Nuclear Power Plants. (authors)

  7. SAPHIR, a simulator for engineering and training on N4-type nuclear power plants

    International Nuclear Information System (INIS)

    Vovan, C.

    1999-01-01

    SAPHIR, the new simulator developed by FRAMATOME, has been designed to be a convenient tool for engineering and training for different types of nuclear power plants. Its first application is for the French 'N4' four-loop 1500MWe PWR. The basic features of SAPHIR are: (1) Use of advanced codes for modelling He primary and secondary systems' including an axial steam generator model, (2) Use of a simulation workshop containing different tools for modelling fluid, electrical, instrument and control networks, (3) A Man-Machine Interface designed for an easy and convivial use which can simulate the different computerized control consoles of the 'N4' control room. This paper outlines features and capabilities of this tool, both for engineering and training purposes. (author)

  8. An integrated numerical protection system (SPIN)

    International Nuclear Information System (INIS)

    Savornin, J.L.; Bouchet, J.M.; Furet, J.L.; Jover, P.; Sala, A.

    1978-01-01

    Developments in technology have now made it possible to perform more sophisticated protection functions which follow more closely the physical phenomena to be monitored. For this reason the Commissariat a l'energie atomique, Merlin-Gerin, Cerci and Framatome have embarked on the joint development of an Integrated Numerical Protection System (SPIN) which will fulfil this objective and will improve the safety and availability of power stations. The system described involves the use of programmed numerical techniques and a structure based on multiprocessors. The architecture has a redundancy of four. Throughout the development of the project the validity of the studies was confirmed by experiments. A first numerical model of a protection function was tested in the laboratory and is now in operation in a power station. A set of models was then introduced for checking the main components of the equipment finally chosen prior to building and testing a prototype. (author)

  9. First plasma experiments in Tore Supra with a new generation of high heat flux limiters for RF antennas

    International Nuclear Information System (INIS)

    Agarici, G.; Beaumont, B.; Bibet, Ph.; Bremond, S.; Bucalossi, J.; Colas, L.; Durocher, A.; Gargiulo, L.; Ladurelle, L.; Lombard, G.; Martin, G.; Mollard, P.

    2000-01-01

    During the 1997 and 1998 Tore Supra shutdown, a first set of new antenna guard limiters was installed on one of the three ion cyclotron resonance heating (ICRH) antennas of Tore Supra. This limiter, which was one of the main technological studies of the 1998 campaign, was widely experimented in real plasma conditions, thus allowing the validation in situ, for the first time, of the technology of active metal casting (AMC) for plasma facing components. The huge improvement in the thermal response of the new limiter generation, compared to the old one, is shown on plasma pulses made identical in terms of antenna position and injected RF power profile. By using the infrared cameras installed inside Tore Supra and viewing the antennas front, the power density fluxes received by the carbon fibre composite (CFC) surface of the limiter were evaluated by correlation with the heat load tests made on the electrons beam facility of CEA/Framatome

  10. Modernization of the Nuclear Power Plant Krsko with new steam generators

    International Nuclear Information System (INIS)

    Holz, R.; Stach, U.; Gloaguen, C.

    2000-01-01

    The contract for the replacement of two steam generators at NPP Krsko was awarded in February 1998 to the Consortium SIEMENS AG FRAMATOME S.A.. The time frame for the replacement outage was scheduled from April to June 2000. The replacement itself started with the plant shut down on 15 th of April 2000 and the plant was back on line on 15 th of June, so that after an intensive engineering period of more than two years the plant was off line only 62 days, as scheduled. This document deals with the various aspects of the replacement phase itself and the techniques used. During the last years conference the engineering and licensing phase of the project have been presented. (author)

  11. Forming a cohesive steam generator maintenance strategy

    International Nuclear Information System (INIS)

    Poudroux, G.

    1991-01-01

    In older nuclear plants, steam generator tube bundles are the most fragile part of the reactor coolant system. Steam generator tubes are subject to numerous types of loading, which can lead to severe degradation (corrosion and wear phenomena). Preventive actions, such as reactor coolant temperature reduction or increasing the plugging limit and their associated analyses, can increase steam generator service life. Beyond these preventive actions, the number of affected tubes and the different locations of the degradations that occur often make repair campaigns necessary. Framatome has developed and qualified a wide range of treatment and repair processes. They enable careful management of the repair campaigns, to avoid reaching the maximum steam generator tube plugging limit, while optimizing the costs. Most of the available repair techniques allow a large number of affected tubes to be treated. Here we look only at those techniques that should be taken into account when defining a maintenance strategy. (author)

  12. Project - GEDEPEON activity report 2001-2004

    International Nuclear Information System (INIS)

    Delpech, Marc; Le Brun, Christian; Leray, S.; Tassan-Got, Laurent; Junquera, T.; Barreau, G.; Gunsing, F.; Letourneau, Alain; Bringer, Olivier; Chabod, Sebastien; Foucher, Yann; Ridikas, Danas; Toussaint, Jean-Christian; Veyssiere, Christian; Faust, Herbert; Mutti, Paolo; Al Mahamid, Ilham; Blandin, Christophe; Breaud, Stephane; Chartier, Frederic; Brissot, R.; Kirchner, Thomas; Latge, Christian; Varaine, F.; Courouau, Jean-Louis; Maitre, Alexandre; Gachon, J.C.; Fiorani, J.; Ghetta, Veronique; Balbaud-Celerier, Fanny; Martinelli, L.; Lone Sang, S.; Ngomsik, A.; Terlain, A.; Sanchez, S.; Picard, G.; Gorse, D.; Auger, T.; Guerin, S.; Lorang, G.; Majimel, J.; Pastol, J.L.; Russier, V.; Dupeux, M.; Ghetta, V.; Vogt, J.-B.; Legris, A.; Serre, I.; Wolski, Krzysztof; Heuer, D.; Meplan, O.; Sanchez, Sylvie; Picard, Gerard

    2005-04-01

    This report presents activities and publications within the frame of GEDEON (Management of wastes by new options) and GEDEPEON (Management of wastes and energy production by new options), two research actions performed in collaboration by the CEA, CNRS, EDF and Framatome, and which mainly addressed accelerator-driven systems (ADS) at the beginning, and then transmutation systems (such as ADS) and innovating systems with transmutation capacities and natural resource saving (GFR of gas fast reactor, MSR or molten salt reactor, and so on). Thus this report contains brief presentations of researches related to the following topics: nuclear data (spallation, spallation over 200 keV, nuclear data for neutron energies lower than 20 MeV), physics of sub-critical reactors, spallation targets and materials (the Megapie project, liquid metals and corrosion for spallation target), linear accelerators for a hybrid system, studies of innovating systems, systems and scenarios, pyrochemical processes

  13. Quench tank in-leakage diagnosis at St. Lucie

    International Nuclear Information System (INIS)

    Price, J.E.; Au-Yang, M.K.; Beckner, D.A.; Vickery, A.N.

    1996-01-01

    In February 1995, leakage into the quench tank of the St. Lucie Nuclear Station Unit 1 was becoming an operational concern. This internal leak resulted in measurable increases in both the temperature and level of the quench tank water, and was so severe that, if the trend continued, plant shut down would be necessary. Preliminary diagnosis based on in-plant instrumentation indicated that any one of 11 valves might be leaking into the quench tank. This paper describes the joint effort by two teams of engineers--one from Florida Power ampersand Light, the other from Framatome Technologies--to identify the sources of the leak, using the latest technology developed for valve diagnosis

  14. Criticality safety analysis of the NPP Krsko storage racks

    International Nuclear Information System (INIS)

    Kromar, M.; Kurincic, B.

    2002-01-01

    NPP Krsko is going to increase the capacity of the spent fuel storage pool by replacement of the existing racks with high-density racks. This will be the second reracking campaign since 1983 when storage was increased from 180 to 828 storage locations. The pool capacity will increase from 828 to 1694 with partial reracking by the spring 2003. The installed capacity will be sufficient for the current design plant lifetime. Complete reracking of the spent fuel pool will additionally increase capacity to 2321 storage locations. The design, rack manufacturing and installation has been awarded to the Framatome ANP GmbH. Burnup credit methodology, which was approved by the Slovenian Nuclear Safety Administration in previous licensing of existing racks, will be again implemented in the licensing process with the recent methodology improvements. Specific steps of the criticality safety analysis and representative results are presented in the paper.(author)

  15. Extended fuel cycle length

    International Nuclear Information System (INIS)

    Bruyere, M.; Vallee, A.; Collette, C.

    1986-09-01

    Extended fuel cycle length and burnup are currently offered by Framatome and Fragema in order to satisfy the needs of the utilities in terms of fuel cycle cost and of overall systems cost optimization. We intend to point out the consequences of an increased fuel cycle length and burnup on reactor safety, in order to determine whether the bounding safety analyses presented in the Safety Analysis Report are applicable and to evaluate the effect on plant licensing. This paper presents the results of this examination. The first part indicates the consequences of increased fuel cycle length and burnup on the nuclear data used in the bounding accident analyses. In the second part of this paper, the required safety reanalyses are presented and the impact on the safety margins of different fuel management strategies is examined. In addition, systems modifications which can be required are indicated

  16. Power variation and frequency regulation. Adaptation of PWR plant possibilities to the network needs

    International Nuclear Information System (INIS)

    Baboulin, J.P.; Burger, M.

    1980-01-01

    When the PWR are an important part of the power installed on a network, and that will be the case of the EDF network in the coming years, the participation of those plants to the power regulating becomes a necessity for the operating staff. This load regulating includes: daily variations of high amplitude; a permanent frequency - power regulating. The first part of the communication shows the network exploitation principles, and the resulting power variations concerning the existing nuclear power plants. Such transients are leading to stresses on fuel. The second part of the communication reports about the test program engaged by EDF in collaboration with the CEA and FRAMATOME, in order to study the fuel behaviour in real power conditions and power cycles, and that, just to the operational burn up of this fuel. (author)

  17. Experimental and analytical studies on waterhammer generated by the closing of check valves

    International Nuclear Information System (INIS)

    Huet, J.L.; Garcia, J.L.; Coppolani, P.; Ziegler, B.

    1987-01-01

    A double-guillotine rupture on a water line upstream from a check valve generates a severe transient between the check valve and the pressure vessel on the downstream side. Successively following phenomena occur: - decrease then reversal of the flow, - closing of the check valve with impact of the plug on its seat, - waterhammer propagating in the pipe downstream from the check valve. The COMMISARIAT A L'ENERGIE ATOMIQUE (C.E.A.) FRAMATOME and ELECTRICITE DE FRANCE (E.D.F.) have undertaken a joint program in order to: - investigate the behavior uf the check valve in the event of a sudden closure, - evaluate the pressure and flow transient in the line. The program includes: - full scale tests in two loops, CLAUDIA (C.E.A.) and ECLAIR (E.D.F.), - analytical studies in order to qualify the calculation codes. This paper describes the experimental program and presents the analysis results for a benchmark test

  18. AREVA Germany. International competence in nuclear technology

    International Nuclear Information System (INIS)

    Graeber, Ulrich

    2011-01-01

    AREVA NP was created in 2001 by the merger of the French nuclear technology specialist Framatome with the nuclear sector of Siemens. The company is headquartered in Paris and has regional subsidiaries in Germany and the United States. The joint venture's strength lies in its all-round competence in nuclear power plants, from reactor development to power plant services and modernization of operating plants, design and production of fuel assemblies and turn-key construction of nuclear power reactors. Major core competences are located in Germany including the test facilities which are unique in the entire group as well as electrical engineering and instrumentation and control systems. AREVA NP is part of the globally acting AREVA group which pursues a unique integrated business model. The concept covers the entire nuclear fuel cycle from uranium mining to reprocessing used fuel assemblies. At present, AREVA has 48,000 employees worldwide, of which 5,700 are Germany-based. (orig.)

  19. Safe management of NPP ageing in European union

    International Nuclear Information System (INIS)

    Grandemange, J.M.; Saurin, P.; Morel, A.; Delaye, D.; Francia, L.; Wacquier, W.; Morlent, O.

    2001-01-01

    The paper presents the results of a study conducted by Framatome, EDF, Belgatom, Unesa and IPSN, with the support of the European Commission in order to evaluate the practices and provide recommendations for the development of a methodology to monitor, control and anticipate the ageing of Nuclear Islands, in order to maintain their level of safety during the whole NPP life cycle. The study includes a synthesis of available European and International reports, the identification of potential ageing mechanisms, their effects and the available identification and mitigation methods, and an evaluation of the existing ageing management practices in Belgium, France and Spain, using international recommendations as guidance documents. Recommendations are proposed on regulatory aspects, management, prediction, detection, follow, mitigation of physical ageing, human management and adaptation of safety culture and procedures. (author)

  20. Next generation of energy production systems

    International Nuclear Information System (INIS)

    Rouault, J.; Garnier, J.C.; Carre, F.

    2003-01-01

    This document gathers the slides that have been presented at the Gedepeon conference. Gedepeon is a research group involving scientists from Cea (French atomic energy commission), CNRS (national center of scientific research), EDF (electricity of France) and Framatome that is devoted to the study of new energy sources and particularly to the study of the future generations of nuclear systems. The contributions have been classed into 9 topics: 1) gas cooled reactors, 2) molten salt reactors (MSBR), 3) the recycling of plutonium and americium, 4) reprocessing of molten salt reactor fuels, 5) behavior of graphite under radiation, 6) metallic materials for molten salt reactors, 7) refractory fuels of gas cooled reactors, 8) the nuclear cycle for the next generations of nuclear systems, and 9) organization of research programs on the new energy sources

  1. Hybrid simulation of a 900 Mwe nuclear plant

    International Nuclear Information System (INIS)

    Constantieux, Thierry; Deat, Max.

    1979-01-01

    To analyse the effects on PWRs of transients originating from the network, specific means of calculation must be elaborated. One of them which was conceived and set up on a hybrid computer by FRAMATOME and the FRENCH ATOMIC ENERGY COMMISSION, is described in this paper. The method chosen to validate this code is fairly original, since it consisted in carrying out a long duration test on a plan and in simulating this on the hybrid computer; then in carefully comparing the recorded data of the test with the results of the simulation. The quality of the results, thus obtained shows that a relatively unsophisticated model is able to give a good idea of actual process behavior, but only if the types of transients to be studied with the code are well identified before its elaboration

  2. Improvement of the reliability of the emergency diesel generators and their protections as a part of the modernization program for units 5 and 6 of the Kozloduy NPP

    International Nuclear Information System (INIS)

    Bogdanov, D.

    2003-01-01

    The measure 'Improvement of the reliability of the emergency diesel generators and their protections' 28411 is part of the modernization program for Units 5 and 6 of Kozloduy NPP. The scope of the measure includes complete change of the I and C system, the local control panels, the technological and electrical protections of the DG set, the excitation system and some of the power distribution switchboards. The new I and C system will be Teleperm XS type, produced by Framatome ANP, the power distribution switchboards type Sivacon, the excitation system Thyripart, and the electrical protection and synchronization system will be provided by Siemens. The purpose of the measure is to increase the availability, maintainability and to improve the reliability of the DG sets

  3. Comparison of French and German NPP water chemistry programs

    Energy Technology Data Exchange (ETDEWEB)

    Staudt, U. [VGB Powertech (Germany); Odar, S. [Framatome ANP GmbH (Germany); Stutzmann, A. [EDF/GDL (France)

    2002-07-01

    PWRs in the western hemisphere obey basically the same rules concerning design, choice of material and operational mode. In spite of these basic similarities, the manufacturers of PWRs in different countries developed different solutions in respect to single components in the steam/water cycle. Looking specifically at France and Germany, the difference in the tubing material of the steam generators (Inconel 600/690 chosen by Framatome and Incoloy 800 chosen by the former Siemens KWU) led to specific differences in the respective chemistry programs and in some respect to different 'philosophies' in operating the water/steam cycle. Compared to this, basic differences in operating the reactor coolant system cannot be observed. Nevertheless specific solutions as zinc injection and the use of enriched B-10 are applied in German PWRs. The application of such measures arises from a specific dose rate situation in older PWRs (zinc injection) or from economic reasons mainly (B-10). (authors)

  4. EPR design tools. Integrated data processing tools

    International Nuclear Information System (INIS)

    Kern, R.

    1997-01-01

    In all technical areas, planning and design have been supported by electronic data processing for many years. New data processing tools had to be developed for the European Pressurized Water Reactor (EPR). The work to be performed was split between KWU and Framatome and laid down in the Basic Design contract. The entire plant was reduced to a logical data structure; the circuit diagrams and flowsheets of the systems were drafted, the central data pool was established, the outlines of building structures were defined, the layout of plant components was planned, and the electrical systems were documented. Also building construction engineering was supported by data processing. The tasks laid down in the Basic Design were completed as so-called milestones. Additional data processing tools also based on the central data pool are required for the phases following after the Basic Design phase, i.e Basic Design Optimization; Detailed Design; Management; Construction, and Commissioning. (orig.) [de

  5. Safety improvement and results of commissioning of Mochovce NPP WWER 440/213

    International Nuclear Information System (INIS)

    Lipar, M.

    1998-01-01

    Mochovce NPP is the last one of this kind and compared to its predecessors, it is characterized by several modifications which contribute to the improvement of the safety level. In addition based on Nuclear Regulatory Authority requirements and based on documents: - IAEA - Safety Issues and their ranking for NPP WWER 440/213, - IAEA - Safety Improvement of Mochovce NPP Project Review Mission, - Riskaudit - Evaluation of the Mochovce NPP Safety Improvements. Additional safety measures have been implemented before commissioning. The consortium EUCOM (FRAMATOME - SIEMENS), SKODA Praha, ENERGOPROJEKT Praha, Russian organizations and VUJE Trnava Nuclear Power Plants research institute were selected for design and implementation of the safety measures. The papers summarized, safety requirements, safety measures implemented, results of commissioning and results of safety analysis report evaluation. (author)

  6. What next steps in nuclear power?

    International Nuclear Information System (INIS)

    Novak, J.

    1991-01-01

    Following the political changes in Czechoslovakia in the late 1989, preparation of a new energy policy began in the second half of 1990. The principles of this new policy include an increase in the share of electricity in the energy balance, based on an increase in the contribution of nuclear power plants. This new nuclear policy should be oriented to the use of state-of-the-art technologies from world's foremost manufacturers such as Framatome, Siemens-KWU, ABB - Combustion Engineering, Mitsubishi and Westinghouse. In February 1991, companies associated in a consortium, viz. the Czech Power Company, the Slovak Power Company, the Czechoslovak Uranium Industry and Energoprojekt, sent the world manufacturers a preliminary invitation of tenders. The bids are now being evaluated by the Belgian company Belgatom and by the Czechoslovak company Energoprojekt. The completion of the feasibility study is conditional on the decision concerning the siting of a new nuclear power plant. (Z.S.). 1 tab

  7. Towards a PSA harmonization French-Belgian comparison of the level 1 PSA for two similar PWR types

    International Nuclear Information System (INIS)

    Dupuy, P.; Corenwinder, F.; Lanore, J.M.; Gryffroy, D.; Gelder, P. de; Hulsmans, M.

    2002-06-01

    In the framework of the cooperation between French and Belgian regulatory authorities, a PSA (Probabilistic Safety Assessment) comparison exercise has been carried out for several years. This comparison deals with two PSA level 1 studies for internal events, performed for both power and shutdown states: the French PSA of the 900 MWe-series PWR, and the Belgian PSA of the Tihange 1 PWR, which both concern PWRs with a similar Framatome design. The purpose of this paper is to describe the PSA comparison methodology and to present, in a qualitative way, an overview of the insights obtained up to now. It also shows that such an 'a posteriori' benchmark exercise turns out to be a step towards PSA harmonization, and gives more confidence in the results of plant specific PSA when used for applications like precursor analysis or evaluations of importance to safety. (authors)

  8. Predictive analyses of flow-induced vibration and fretting wear in steam generator tubes

    International Nuclear Information System (INIS)

    Axisa, F.

    1989-01-01

    Maintaining the service life of PWR steam generators under highly reliable conditions requires a complex design to prevent various damaging processes, including those related to flow induced vibration. Predictive analyses have to rely on numerical tools to compute the vibratory response of multi-supported tubes in association with experimental data and semi-empirical relationships for quantifying flow-induced excitation mechanisms and tube damaging processes. In the presence of loose supports tube dynamics becomes highly nonlinear in nature. To deal with such problems CEA and FRAMATOME developed a computer program called GERBOISE. This paper provides a short description of an experimental program currently in progress at CEN Saclay to validate the numerical methods implemented in GERBOISE. According to the results obtained so far reasonable agreement is obtained between experiment and numerical simulation, especially as averaged quantities are concerned

  9. Utilization of ''CONTACT'' experiments to improve the fission gas release knowledge in PWR fuel rods

    International Nuclear Information System (INIS)

    Charles, M.; Abassin, J.J.; Bruet, M.

    1983-01-01

    The CONTACT experiments, which were carried out by the French CEA, within the framework of a CEA-FRAMATOME collaboration agreement, bear on the behaviour of in-pile irradiated PWR fuel rods. We will focus here upon their results dealing with fission gas release. The experimental device is briefly described, then the following results are given: the kinetics of stable fission gas release for various linear ratings; the instantaneous fractional release rates of radioactive gases versus their decay constant in the range 1.5 10 -6 -3.6 10 -3 s -1 , for various burnups, as also the influence of fuel temperature. Moreover, the influence of the nature and the pressure of the filling gas upon the release is presented for various linear ratings. The experimental results are discussed and analysed with the purpose to model various physical phenomena involved in the release (low-temperature mechanisms, diffusion)

  10. Methodology and boundary conditions applied to the analysis on internal flooding for Kozloduy NPP units 5 and 6

    International Nuclear Information System (INIS)

    Demireva, E.; Goranov, S.; Horstmann, R.

    2004-01-01

    Within the Modernization Program of Units 5 and 6 of Kozloduy NPP a comprehensive analysis of internal flooding has been carried out for the reactor building outside the containment and for the turbine hall by FRAMATOME ANP and ENPRO Consult. The objective of this presentation is to provide information on the applied methodology and boundary conditions. A separate report called 'Methodology and boundary conditions' has been elaborated in order to provide the fundament for the study. The methodology report provides definitions and advice for the following topics: scope of the study; safety objectives; basic assumptions and postulates (plant conditions, grace periods for manual actions, single failure postulate, etc.); sources of flooding (postulated piping leaks and ruptures, malfunctions and personnel error); main activities of the flooding analysis; study conclusions and suggestions of remedial measures. (authors)

  11. Natural circulation under variable primary mass inventories at BETHSY facility

    International Nuclear Information System (INIS)

    Bazin, P.; Clement, P.; Deruaz, R.

    1989-01-01

    BETHSY is a high pressure integral test facility which models a 3 loop Framatome PWR with the intent of studying PWR accidents. The BETHSY programme includes both accident transients and tests under successive steady state conditions. So far, tests of the latter type have been especially devoted to situations where natural circulation takes place in the primary coolant system (PCS). Tests 4.1a and 4.1a TC, the results of which are introduced, deal with PCS natural circulation patterns and related heat transport mechanisms under two different core power levels (2 and 5% of nominal power), variable primary mass inventory (100% to 30-40% according to core power) and at two different steam generator liquid levels (standard value and 1 meter). (orig.)

  12. Results of the basic design of the European Pressurized Water Reactor (EPR) and further prospective

    International Nuclear Information System (INIS)

    Fischer, U.

    1998-01-01

    The EPR is an evolutionary design, with maximum consideration given to the experience accumulated by Framatome and Siemens with the existing designs of plants successfully operating.However, substantial improvements with regard to availability, safety and economy have been included. The main target of the basic design phase was a clear definition of technical features based on common technical codes that comply with economic targets and licensability requirements in France and Germany.The EPR basic design represents a new design for a nuclear power plant that complies with the latest laws and regulations, both in France and Germany as well as in most of the countries utilizing nuclear power. Cost estimates prove the design economically viable

  13. New process for the relief of mechanically induced stresses in steam generator tubes

    International Nuclear Information System (INIS)

    Joyeux, J.P.

    1980-01-01

    Heat exchangers include very generally a set of tubes assembled in 'U-type' exchangers or in 'pass-through' exchangers. The tubes are introduced in holes drilled in the tube sheet plate, welded at their extremity and expanded to insure the necessary tightness. The steam generators built by FRAMATOME belong to the U-type and include, depending upon the nominal power of the plant, about three or five thousand inconel tubes. This material has been selected for its resistance to corrosion action at high temperatures. But one drawback of inconel is that residual stress lowers considerably this resistance to corrosion; so it is very important to apply manufacturing processes involving a residual stress level as low as possible. A new process, which involves 'kiss' rolling, is described. (author)

  14. Modernization of the Nuclear Power Plant Krsko with new steam generators

    Energy Technology Data Exchange (ETDEWEB)

    Holz, R; Stach, U [Siemens AG, Erlangen, Offenbach (Germany); Gloaguen, C [Framatome, Paris (France)

    2000-07-01

    The contract for the replacement of two steam generators at NPP Krsko was awarded in February 1998 to the Consortium SIEMENS AG FRAMATOME S.A.. The time frame for the replacement outage was scheduled from April to June 2000. The replacement itself started with the plant shut down on 15{sup th} of April 2000 and the plant was back on line on 15{sup th} of June, so that after an intensive engineering period of more than two years the plant was off line only 62 days, as scheduled. This document deals with the various aspects of the replacement phase itself and the techniques used. During the last years conference the engineering and licensing phase of the project have been presented. (author)

  15. STMI: several years of experience in nuclear plant dismantling

    International Nuclear Information System (INIS)

    Moreau, J.C.

    1985-01-01

    Since 1977, when STMI performed its first dismantling operation, the Company appreciably improved in that field through important operations: the dismantling of the calciothermy and fluoration metal Pu preparation facility, in La Hague reprocessing plant; the dismantling of the slag treatment chain, associated to calciothermy and fluoration processes, in La Hague reprocessing plant; and the cleaning of EL4 cell in Marcoule. To perform these operations, STMI's operating teams, on top of decontamination and dismantling technologies, strived to improve handling and transportation technologies, and to nuclearize many equipments. In order to increase its technical efficiency, STMI signed a cooperation agreement with FRAMATOME company. Therefore, the union between the operational know-hows of STMI and the design experience of TECHNICATOME allow the needs of any customs facing a dismantling case to be satisfied [fr

  16. Mox fuel experience: present status and future improvements

    International Nuclear Information System (INIS)

    Blanpain, P.; Chiarelli, G.

    2001-01-01

    Up to December 2000, more than 1700 MOX fuel assemblies have been delivered by Framatome ANP/Fragema to 20 French, 2 Belgian and 3 German PWRs. More than 1000 MOX fuel assemblies have been delivered by Framatome ANP GmbH (formerly Siemens) to 11 German PWRs and BWRs and to 3 Swiss PWRs. Operating MOX fuel up to discharge burnups of about 45,000 MWd/tM is done without any penalty on core operating conditions and fuel reliability. Performance data for fuel and materials have been obtained from an outstanding surveillance program. The examinations have concluded that there have been no significant differences in MOX fuel assembly characteristics relative to UO 2 fuel. The data from these examinations, combined with a comprehensive out-of-core and in-core analytical test program on the current fuel products, are being used to confirm and upgrade the design models necessary for the continuing improvement of the MOX product. As MOX fuel has reached a sufficient maturity level, the short term step is the achievement of the parity between UO 2 and MOX fuels in the EdF French reactors. This involves a single operating scheme for both fuels with an annual quarter core reload type and an assembly discharge burnup goal of 52,000 MWd/tM. That ''MOX parity'' product will use the AFA-3G assembly structure which will increase the fuel rod design margins with regards to the end-of-life internal pressure criteria. But the fuel development objective is not limited to the parity between the current MOX and UO 2 products: that parity must remain guaranteed and the MOX fuel managements must evolve in the same way as the UO 2 ones. The goal of the MOX product development program underway in France is the demonstration over the next ten years of a fuel capable of reaching assembly burnups of 70,000 MWd/tM. (author)

  17. International co-operation in developing the GT-MHR

    International Nuclear Information System (INIS)

    La Bar, M.P.; Simon, W.A.

    1997-01-01

    In the Fall of 1995, driven by budget constraints and anti-nuclear sentiments, the US government decided to discontinue financial support of the Gas Turbine-Modular Helium Reactor (GT-MHR). At that time, significant work was underway with participation of several vendors with specialized expertise in various aspects of the GT-MHR. Fortunately the US government provided for documenting the design and development status through an orderly close-out program. Concurrent elimination of government restrictions opened the door for broader international cooperation. Discussion between General Atomics and the Russian Ministry of Atomic Energy (MINATOM), in the summer of 1994, led to an agreement on a jointly funded design and development program for the GT-MHR. The program is initially focused on the burning of weapons plutonium that becomes available from dismantled nuclear weapons. The long term goal is to utilize the same design for commercial applications - using uranium fuel. This program took advantage of existing technologies and facilities in the US and Russia, but right from the beginning left the door open for broader international cooperation. Accordingly, in January 1996, FRAMATOME has joined the ongoing effort. Discussions are underway with other international entities to join this program. The program is proceeding well. Several Russian laboratories/design organizations are participating with GA and FRAMATOME. Significant improvements in the power conversion system design are a clear example of the benefit of the cooperative effort. Further work needs to be done to confirm fuel and components prior to full deployment, etc., providing ample opportunities for international cooperation in many areas

  18. Finnish EPR Olkiluoto 3. The world's first third-generation reactor now under construction

    International Nuclear Information System (INIS)

    2007-01-01

    The EPR was developed by Framatome and Siemens KWU (the nuclear division of Siemens), whose nuclear activities were combined in January 2001 to form Framatome ANP, now AREVA NP. The French electricity utility EDF (Electricite de France), together with the major German utilities, played an active role in the project. The safety authorities of the two countries joined forces to bring their respective safety standards into line and draw up joint design rules for the new reactor. On December 18, 2003, the consortium formed by AREVA and Siemens - and led by AREVA - signed a contract with TVO for the turnkey construction of the EPR. The overall Olkiluoto 3 project cost has been estimated by TVO at around euros 3 Billion. TVO is responsible for the overall project management and licensing process with the Finnish Safety Authority STUK. In the pre-qualification phase, STUK concluded that the EPR can meet the Finnish licensing requirements. All specific comments will be taken into account for the realization of the project. In January 2005, STUK emphasized in its safety assessment that the evolutionary EPR design compared to predecessor product lines has been further enhanced by AREVA. This paper presents first, The Finnish energy situation (Electricity consumption and supply, Finland's Kyoto CO 2 cutback, Competitiveness of nuclear power), and then the EPR in Olkiluoto (General schedule of responsibilities, Important milestones of the project). Finally, the EPR third-generation and advanced reactor is presented with its position in the international competition (Targeted design objectives, Main characteristics, competitiveness, safety, Additional measures to prevent the occurrence of events likely to damage the core, Increased protection against the consequences of core melt)

  19. Analysis of in-R12 CHF data: influence of hydraulic diameter and heating length; test of Weisman boiling crisis model; Analyse de donnees de flux critique en R12: influence du diametre hydraulique et de la longueur chauffante; test du modele de Weisman

    Energy Technology Data Exchange (ETDEWEB)

    Czop, V; Herer, C; Souyri, A; Garnier, J

    1993-09-01

    In order to progress on the comprehensive modelling of the boiling crisis phenomenon, Electricite de France (EDF), Commissariat a l`Energie Atomique (CEA) and FRAMATOME have set up experimental programs involving in-R12 tests: the EDF APHRODITE program and the CEA-EDF-FRAMATOME DEBORA program. The first phase in these programs aims to acquire critical heat flux (CHF) data banks, within large thermal-hydraulic parameter ranges, both in cylindrical and annular configurations, and with different hydraulic diameters and heating lengths. Actually, three data banks have been considered in the analysis, all of them concerning in-R12 round tube tests: - the APHRODITE data bank, obtained at EDF with a 13 mn inside diameter, - the DEBORA data bank, obtained at CEA with a 19.2 mm inside diameter, - the KRISTA data bank, obtained at KfK with a 8 mm inside diameter. The analysis was conducted using CHF correlations and with the help of an advanced mathematical tool using pseudo-cubic thin plate type Spline functions. Two conclusions were drawn: -no influence of the heating length on our CHF results, - the influence of the diameter on the CHF cannot be simply expressed by an exponential function of this parameter, as thermal-hydraulic parameters also have an influence. Some calculations with Weisman and Pei theoretical boiling crisis model have been compared to experimental values: fairly good agreement was obtained, but further study must focus on improving the modelling of the influence of pressure and mass velocity. (authors). 12 figs., 4 tabs., 21 refs.

  20. Analysis of in-R12 CHF data: influence of hydraulic diameter and heating length; test of Weisman boiling crisis model

    International Nuclear Information System (INIS)

    Czop, V.; Herer, C.; Souyri, A.; Garnier, J.

    1993-09-01

    In order to progress on the comprehensive modelling of the boiling crisis phenomenon, Electricite de France (EDF), Commissariat a l'Energie Atomique (CEA) and FRAMATOME have set up experimental programs involving in-R12 tests: the EDF APHRODITE program and the CEA-EDF-FRAMATOME DEBORA program. The first phase in these programs aims to acquire critical heat flux (CHF) data banks, within large thermal-hydraulic parameter ranges, both in cylindrical and annular configurations, and with different hydraulic diameters and heating lengths. Actually, three data banks have been considered in the analysis, all of them concerning in-R12 round tube tests: - the APHRODITE data bank, obtained at EDF with a 13 mn inside diameter, - the DEBORA data bank, obtained at CEA with a 19.2 mm inside diameter, - the KRISTA data bank, obtained at KfK with a 8 mm inside diameter. The analysis was conducted using CHF correlations and with the help of an advanced mathematical tool using pseudo-cubic thin plate type Spline functions. Two conclusions were drawn: -no influence of the heating length on our CHF results, - the influence of the diameter on the CHF cannot be simply expressed by an exponential function of this parameter, as thermal-hydraulic parameters also have an influence. Some calculations with Weisman and Pei theoretical boiling crisis model have been compared to experimental values: fairly good agreement was obtained, but further study must focus on improving the modelling of the influence of pressure and mass velocity. (authors). 12 figs., 4 tabs., 21 refs

  1. Graphite waste incineration in a fluidized bed

    International Nuclear Information System (INIS)

    Guiroy, J.J.

    1996-01-01

    French gas-cooled reactors belonging to the Atomic Energy Commission (CEA), Electricite de France (EDF), Hifrensa (Spain), etc., commissioned between the 1950s and 1970s, have generated large quantities of graphite wastes, mainly in the form of spent fuel sleeves. Furthermore, some of these reactors scheduled for dismantling in the near future (such as the G2 and G3 reactors at Marcoule) have cores consisting of graphite blocks. Consequently, a fraction of the contaminated graphite, amounting to 6000 t in France for example, must be processed in the coming years. For this processing, incineration using a circulating fluidized bed combustor has been selected as a possible solution and validated. However, the first operation to be performed involves recovering this graphite waste, and particularly, first of all, the spent fuel sleeves that were stored in silos during the years of reactor operation. Subsequent to the final shutdown of the Spanish gas-cooled reactor unit, Vandellos 1, the operating utility Hifrensa awarded contracts to a Framatome Iberica SA/ENSA consortium for removing, sorting, and prepackaging of the waste stored in three silos on the Vandellos site, essentially graphite sleeves. On the other hand, a program to validate the Framatome fluidized bed incineration process was carried out using a prototype incinerator installed at Le Creusot, France. The validation program included 22 twelve-hour tests and one 120-hour test. Particular attention was paid to the safety aspects of this project. During the performance of the validation program, a preliminary safety assessment was carried out. An impact assessment was performed with the help of the French Institute for Protection and Nuclear Safety, taking into account the preliminary spectra supplied by the CEA and EDF, and the activities of the radionuclides susceptible of being released into the atmosphere during the incineration. (author). 4 refs, 11 figs, 1 tab

  2. About the use of the CATHARE code for best estimate Large Break LOCA calculations: benefits for Safety and constraints

    International Nuclear Information System (INIS)

    Vacher, J.L.

    1994-01-01

    Since 1979, EDF has participated to the development of CATHARE, a best estimate accidental thermalhydraulic code, in collaboration with CEA and FRAMATOME. EDF is now investigating the use of this code for licensing studies and particularly for Large Break LOCA calculations. Until now, the work done at EDF, in relation with FRAMATOME and CEA, has mainly focused on the physical analysis of the transient and on the identification of the key phenomena. This task is a necessary step before uncertainty evaluation. To illustrate this point of view, a peculiar example of calculated Large Break transients for a 900 MW three loop plant is presented. In one of these calculations, a high value of Peak Cladding Temperature was obtained. This peculiar scenario was initiated by a large entrainment of water to the steam generators at the very beginning of the reflooding stage, followed by a strong pressurization which led to a lasting draining of the reactor vessel. The physical phenomena which determine the existence and amplitude of this scenario were identified and their influence was explained: condensation at the accumulator injection, heat exchange in the core, entrainment process to the steam generators. It appeared obvious that the large observed uncertainty was associated to only a few parameters. Although this peculiar system behaviour was obtained for only a particular combination of parameters and a narrow range of thermalhydraulic conditions, the capability of the code to simulate these phenomena was investigated in regard to experimental data. It was concluded that this scenario was definitely unrealistic on a reactor. Nevertheless, this peculiar example tends to demonstrate, firstly, that the use of a best-estimate code improves Safety as it makes possible to point out physical phenomena that could not be considered when using non mechanistic codes, secondly, that the uncertainty evaluation must be guided by a pertinent physical analysis of the transient, focusing

  3. Vibration behavior of PWR reactor internals Model experiments and analysis

    International Nuclear Information System (INIS)

    Assedo, R.; Dubourg, M.; Livolant, M.; Epstein, A.

    1975-01-01

    In the late 1971, the CEA and FRAMATOME decided to undertake a comprehensive joint program of studying the vibration behavior of PWR internals of the 900 MWe, 50 cycle, 3 loop reactor series being built by FRAMATOME in France. The PWR reactor internals are submitted to several sources of excitation during normal operation. Two main sources of excitation may effect the internals behavior: the large flow turbulences which could generate various instabilities such as: vortex shedding: the pump pressure fluctuations which could generate acoustic noise in the circuit at frequencies corresponding to shaft speed frequencies or blade passing frequencies, and their respective harmonics. The flow induced vibrations are of complex nature and the approach selected, for this comprehensive program, is semi-empirical and based on both theoretical analysis and experiments on a reduced scale model and full scale internals. The experimental support of this program consists of: the SAFRAN test loop which consists of an hydroelastic similitude of a 1/8 scale model of a PWR; harmonic vibration tests in air performed on full scale reactor internals in the manufacturing shop; the GENNEVILLIERS facilities which is a full flow test facility of primary pump; the measurements carried out during start up on the Tihange reactor. This program will be completed in April 1975. The results of this program, the originality of which consists of studying separately the effects of random excitations and acoustic noises, on the internals behavior, and by establishing a comparison between experiments and analysis, will bring a major contribution for explaining the complex vibration phenomena occurring in a PWR

  4. The GENEPI-MASURCA coupling for the neutronic investigations of subcritical multiplying media in presence of an external neutron source: The MUSE experiments

    International Nuclear Information System (INIS)

    Soule, R.; Granget, G.; Chauvin, J.P.

    1999-01-01

    Full text: Accelerator Driven Systems (ADS) are being explored in France in the frame of the research program on radioactive waste management options. Besides studies aimed to clarify the motivations for ADS, a significant program has been started to validate experimentally the main physics principles of these systems. This program was initiated at CEA Cadarache in 1995, with the sponsorship of EdF and Framatome. Since 1997, the CNRS has joined the program, which is now a common CEA-CNRS- EdF-Framatome program, open to external partners, in particular the European Community in the frame of the 5th FW Program. The experimental programs allow to validate nuclear data and calculation methods used to describe the sub-critical core, in terms of reactivity, spatial flux distributions, neutron spectra and external source worth. If the source can be used in continuous and pulsed modes, static and dynamic reactivity measurements are possible. This point is of relevance, since the experimental investigation of the different techniques to monitor the sub-criticality level during the operation of an ADS is still an open question. The future MUSE program will enter a new phase in november 1999, with the installation at MASURCA of a deuteron accelerator (GENEPI accelerator), developed at the CNRS/IN2P3/ISN of Grenoble. Improved performances are expected (in terms of the quality of the neutron pulse and source intensity), and the use of both (D,D) and (D,T) reactions, will enable to explore different neutron spectra as well as source worths and their ratios to the fission neutron worths. The paper presents the GENEPI accelerator characteristics and monitoring and the experimental configurations defined for the next phase of the MUSE experiments. (author)

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

    International Nuclear Information System (INIS)

    2004-01-01

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

  6. What is done in France with respect to the design, manufacture, management and development of nuclear fuel

    International Nuclear Information System (INIS)

    Brandt, R.; Traccucci, R.; Joly, G.; Gloaguen, A.; Delafosse, J.

    1977-01-01

    What France is undertaking today concerning nuclear fuel is presented under four headings: (1) Design: The analysis of design and that of fuel behaviour is determined by the constructor through the knowledge of phenomena and the evaluation of materials selection and design criteria as well as the calculation of margins; this task is performed with the help of experimental qualifying programmes. With the means at its disposal the Equipment Department of Electricite de France scrutinizes the studies related to the first charges. Thus, design can be proved satisfactory by analysing fuel operation data. Achievements or expectations concerning the fuel supplied by Framatome for CNA and Tihange are given as illustrations. This work is being continued in the study to promote 17x17 (extra-long) fuel. (2) Manufacture: The Quality Assurance of Framatome (supplier of the fuel now being ordered), already applied at the design study level, provides here the important means necessary to ensure the good quality of the products manufactured. EDF's controlling role, as far as the first charges are concerned, today ranges from examining the constructor's manufacturing specifications to investigating at request possible exceptions. (3) Management: EDF's Thermal Production Department implements a system of integrated management: Requirement forecasting; accounting and financial management; permanent control of radioactive material; physical optimization of fuel renewal and control of operating conditions; and analysis of the technological behaviour in the reactor in order to apply experience gained from it to fuel offered by various suppliers. (4) Development: The Atomic Energy Commission has developed fuel for its water reactors according to two techniques: slug fuel and plate fuel. If required both can be considered for power reactors. (author)

  7. A benchmark on computational simulation of a CT fracture experiment

    International Nuclear Information System (INIS)

    Franco, C.; Brochard, J.; Ignaccolo, S.; Eripret, C.

    1992-01-01

    For a better understanding of the fracture behavior of cracked welds in piping, FRAMATOME, EDF and CEA have launched an important analytical research program. This program is mainly based on the analysis of the effects of the geometrical parameters (the crack size and the welded joint dimensions) and the yield strength ratio on the fracture behavior of several cracked configurations. Two approaches have been selected for the fracture analyses: on one hand, the global approach based on the concept of crack driving force J and on the other hand, a local approach of ductile fracture. In this approach the crack initiation and growth are modelized by the nucleation, growth and coalescence of cavities in front of the crack tip. The model selected in this study estimates only the growth of the cavities using the RICE and TRACEY relationship. The present study deals with a benchmark on computational simulation of CT fracture experiments using three computer codes : ALIBABA developed by EDF the CEA's code CASTEM 2000 and the FRAMATOME's code SYSTUS. The paper is split into three parts. At first, the authors present the experimental procedure for high temperature toughness testing of two CT specimens taken from a welded pipe, characteristic of pressurized water reactor primary piping. Secondly, considerations are outlined about the Finite Element analysis and the application procedure. A detailed description is given on boundary and loading conditions, on the mesh characteristics, on the numerical scheme involved and on the void growth computation. Finally, the comparisons between numerical and experimental results are presented up to the crack initiation, the tearing process being not taken into account in the present study. The variations of J and of the local variables used to estimate the damage around the crack tip (triaxiality and hydrostatic stresses, plastic deformations, void growth ...) are computed as a function of the increasing load

  8. Radiation synovectomy: treatment option for haemophilia patients ...

    African Journals Online (AJOL)

    Papers from reputable haematology and radiation medicine journals, as well as conference presentations of the World Federation of Hemophilia were also included. Data selection: The searches for papers, abstracts and reviews were limited to English language, haemophilia, haemarthrosis, synovectomy, RS, ...

  9. Author Details

    African Journals Online (AJOL)

    Saya, Rachel-Aubain. Vol 200 (2004) - Articles Early selection of Eucalyptus clones in retrospective nursery test using growth, morphological and dry matter criteria, in Republic of Congo : scientific paper. Abstract. ISSN: 2070-2639. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians ...

  10. 1977 flywheel technology symposium proceedings. [Fifty-two papers

    Energy Technology Data Exchange (ETDEWEB)

    Chang, G.C.; Stone, R.G. (eds.)

    1978-03-01

    Fifty-two papers, four paper abstracts, and four brief summaries of panel discussions are presented on flywheel energy storage technology. A separate abstract was prepared for each of 41 papers for inclusion in DOE Energy Research Abstracts (ERA). Eleven papers were processed previously for inclusion in the data base. (PMA)

  11. Proceedings of the 1981 linear accelerator conference

    International Nuclear Information System (INIS)

    Jameson, R.A.; Taylor, L.S.

    1982-02-01

    The 1981 Linear Accelerator Conference was held at Bishop's Lodge, Santa Fe, New Mexico, October 19-23, 1981. This publication contains the texts of the invited and contributed papers. Abstracts of individual items from the conference were prepared separately for the data base

  12. Biological physics and synchrotron radiation

    International Nuclear Information System (INIS)

    Filhol, J.M.; Chavanne, J.; Weckert, E.

    2001-01-01

    This conference deals with the applications of synchrotron radiation to current problems in biology and medicine. Seven sessions take stock on the subject: sources and detectors; inelastic scattering and dynamics; muscle diffraction; reaction mechanisms; macromolecular assemblies; medical applications; imaging and spectroscopy. The document presents the papers abstracts. (A.L.B.)

  13. Browse Title Index - African Journals Online

    African Journals Online (AJOL)

    Items 351 - 400 of 506 ... JLM Gonçalves, MCP Wichert, JL Gava, AV Masetto, JC Arthur Junior, MIP Serrano, SLM Mello. Vol 192 (2001), Solar-assisted drying of timber at industrial scale: management paper, Abstract. M Bux, K Bauer, W Mühlbauer, T Conrad. Vol 70, No 1 (2008), Solid-wood production from temperate ...

  14. AFRREV IJAH: An International Journal of Arts and Humanities

    African Journals Online (AJOL)

    IJAH: International Journal of Arts and Humanities, is a Peer Reviewed ... how advanced information technologies further scholarly understanding of traditional topics in the arts and humanities. ... Papers abstract/indexed by major indexing services ... Bibliometrics study: article usage and citation counts metric in trade ...

  15. Biological physics and synchrotron radiation

    Energy Technology Data Exchange (ETDEWEB)

    Filhol, J M; Chavanne, J [European Synchrotron Radiation Facility, 38 - Grenoble (France); Weckert, E [Hasylab at Desy, Hamburg (Germany); and others

    2001-07-01

    This conference deals with the applications of synchrotron radiation to current problems in biology and medicine. Seven sessions take stock on the subject: sources and detectors; inelastic scattering and dynamics; muscle diffraction; reaction mechanisms; macromolecular assemblies; medical applications; imaging and spectroscopy. The document presents the papers abstracts. (A.L.B.)

  16. Author Details

    African Journals Online (AJOL)

    Crafford, J. Vol 193 (2002) - Articles Measuring total economic benefits from water in plantation forestry: application of quasi I-O framework to the Crocodile catchment in South Africa: scientific paper. Abstract. ISSN: 2070-2639. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors ...

  17. Author Details

    African Journals Online (AJOL)

    : management paper. Abstract. ISSN: 2070-2639. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's Partners · Terms and Conditions of Use · Contact AJOL ...

  18. RADIOISOTOPES IN SOIL-PLANT NUTRITION STUDIES. Proceedings of the Symposium held in Bombay, 26 February-2 March 1962

    Energy Technology Data Exchange (ETDEWEB)

    None

    1962-06-01

    A symposium on Radioisotopes in Soil-Plant Nutrition Studies was held at Bombay, Feb. 26 to March 2, 1962. Separate abstracts were prepared for 8 papers. abstracts of 2 papers have appeared previously in NSA. Other papers presented covered various aspects of soil chemistry, soil physics, ion uptake and translocation in soils, biological measurement of soil characteristics, and fertilizer usage. (C.H.)

  19. Calcite twinning strain variations across the Proterozoic Grenville orogen and Keweenaw-Kapuskasing inverted foreland, USA and Canada

    Directory of Open Access Journals (Sweden)

    John P. Craddock

    2017-11-01

    Full Text Available We report the calcite twinning strain results of a traverse across the Grenville orogen from Parry Sound, Ontario (NW to Ft. Ann, New York (SE, including the younger, adjacent Ordovician Taconic allochthon. Fifty four carbonates (marbles, calcite veins, Ordovician limestone were collected resulting in 68 strain analyses on mechanically twinned calcite (n = 2337 grains across the Central Gneiss Belt (CGB; 3 samples, the Central Metasedimentary Belt (CMB; 27 samples, the Central Granulite Terrane (CGT; Adirondack's; 13 samples and the Ottawan Orogenic Lid (OOL; 11 samples. Twinning strains in the greenschist-grade OOL marbles preserve N–S shortening and U-Pb titanite ages (∼1150 Ma; n = 4 document these marbles formed during the Shawinigan (1190–1140 Ma part of the Grenville orogen. From northwest to southeast, the Ottawan (1095–1020 Ma twinning strain is dominantly a layer-parallel shortening fabric oriented N–S (Parry Sound, then becomes parallel to the Grenville thrust direction (NW–SE across the CMB to the Adirondack Highlands where the sub-horizontal shortening strain becomes margin-parallel (SW–NE. Within the regional sample suite there are two areas studied in detail, the Bancroft shear zone (n = 11 and a roadcut on the southeast side of the Adirondack Mountains (Ft. Ann, NY; n = 8. Marbles from the Bancroft shear zone contain calcite grains with 2 sets of twin lamellae (e1 and e2. The better-developed e1 sets (n = 406 record a horizontal fabric oriented NW–SE whereas the younger e2 lamellae (n = 146 preserve a margin-parallel (SW–NE horizontal fabric. Both the e1 and e2 strains record an overprint vertical shortening strain (NEV, perhaps related to extensional orogenic collapse. We also report an Ottawan orogen-aged granoblastic mylonite (1093 Ma, U-Pb zircon; 1102 Ma Ar-Ar biotite in the Keweenaw thrust hanging wall 500 km inboard of the Grenville front and interpret the relations of Grenville

  20. Exchange networks and free shops in Berlin: gifts and commodities in ‘alternative’ consumption experiences Redes de intercâmbio e lojas gratuitas em Berlim: dádiva e mercadoria em experiências “alternativas” de consumo

    Directory of Open Access Journals (Sweden)

    Irene Sabaté Muriel

    2009-05-01

    Full Text Available This paper is based on an ethnography of ‘alternative’ consumption practices in the inner city of the former East Berlin. Non-monetary exchange networks (Tauschringe and ‘free shops’ (Umsonstläden have been examined. In Umsonstläden, the contemporary ideology of the ‘pure’ gift (Parry 1986; Carrier 1995 is at play: objects are freely given and totally alienated from their owners. In turn, Tauschringe sometimes induce gift-giving practices entailing mutual obligation, as a result of frequent exchanges which bring participants socially closer. The ethnographic material I present challenges the suitability of a conceptual gift/commodity divide to examine these experiences, provided that different modalities of gift-giving are articulated with commoditisation trends. Considering this complexity, I propose a re-examination of the role of the gift in ‘alternative’ consumption practices promoted by social movements in Berlin.O artigo baseia-se numa etnografia de práticas de consumo “alternativas” nos bairros centrais da antiga Berlim-Leste. São aqui analisadas as redes de intercâmbio não monetário (Tauschringe e as “lojas gratuitas” (Umsonstläden. As Umsonstläden são enquadradas pela ideologia contemporânea da dádiva “pura” (Parry 1986; Carrier 1995: os objectos são dados gratuitamente e totalmente alienados dos seus possuidores. Já as Tauschringe, por seu lado, induzem por vezes práticas de oferta que implicam obrigações mútuas, como consequência de trocas frequentes que aproximam socialmente os participantes. O material etnográfico apresentado põe em causa a adequação do binómio dádiva/mercadoria à análise dessas experiências, na medida em que diferentes modalidades de oferta se conjugam com tendências para a mercadorização. Face a essa complexidade, o artigo propõe uma revisão da análise do papel da dádiva em práticas de consumo “alternativas” promovidas pelos movimentos sociais em

  1. Radiological impact on the workers, members of the public, and environment from the partial decommissioning of Pakistan Research Reactor-I and its associated radioactive residues.

    Science.gov (United States)

    Ali, A; Orfi, S D; Manzur, H; Aslam, M

    2001-05-01

    The Pakistan Research Reactor-I (PARR-I) is a swimming pool type research reactor originally designed and built for a thermal power of 5 MW using High Enriched Uranium (HEU) fuel. In 1990-1991 the reactor was redesigned, partially decommissioned and recommissioned to operate with Low Enriched Uranium (LEU) fuel at a thermal power of 10 MW. An essential requirement, construction and commissioning of a wet spent fuel storage bay and fabrication of an irradiated fuel transfer cask were completed before actual dismantling of the reactor core. During the partial decommissioning operations, radioactive waste generated included 600 m3 low-level liquid radioactive waste and 14 m3 of solid radioactive waste with an average specific activity of 4.52 Bq ml(-1) and 2.22 kBq g(-1), respectively. External radiation doses of the workers were determined using TLD (NG 6,7) and direct reading dosimeters. The maximum individual external radiation dose received by any worker during this practice was 5 mSv, which was 25% of the annual dose limit of 20 mSv. Detection and measurement of internal contamination was carried out using bioassay techniques. During the whole operation, not a single case of internal contamination was detected. The ambient radiation levels around waste seepage pits are periodically monitored using TLD (G-2 cards) and G. M. radiation survey meters. Underground migration of radioactivity is checked by analyzing seepage water samples taken from boreholes that have been dug at different locations in the vicinity of the radioactive residues. The monitoring around disposal sites containing radioactive residues has been continued during the last 9 y and will be continued in the future. So far, no rise in the environmental gamma radiation dose level and migration of underground radionuclides has been found in the vicinity of these disposal sites. Working personal during the decommissioning of PARR-I have been found to be radiologically safe. Adherence to the ALARA

  2. Improved method to determine the molar volume and compositions of the NaCl-H2O-CO2 system inclusion

    Institute of Scientific and Technical Information of China (English)

    SONG YuCai; HU WenXuan; NI Pei; DUAN ZhenHao; ZHANG XueFeng

    2007-01-01

    On the basis of Parry's method (1986),an improved method was established to determine the molar volume(Vm)and compositions(X)of the NaCl-H2O-CO2(NHC)system inclusion.To use this method,the determination of Vm-X only requires three microthermometric data of a NHC inclusion:partial homogenization temperature(Th,CO2),salinity(s)and total homogenization temperature(Th).Theoretically,four associated equations are needed containing four unknown parameters:Xco2,XNcl,Vm and F (volume fraction of CO2 phase in total inclusion when occurring partial homogenization).When they are released,the Vm-X are determined.The former three equations,only correlated with Th,co2,S and F,have simplified expressions:XCO2=f1(Th,CO2,S,F),XNaCl=f2(Th,CO2,S,F),Vm=f3(Th,CO2,S,F).The last one is the thermodynamic relationship of Xco2,Xnacl,vm and Th:f4(XCO2,XNacl,Vm,Th)=0. Since the above four associated equations are complicated,it is necessary to adopt iterative technique to release them.The technique can be described by:(i)Freely input a F value(0≤F≤1),with Th,co2 and S,into the former three equations.As a result,Xco2,XNacl and the molar volume value recorded as Vm1 are derived.(ii)Input the Xco2 and XNacl gotten in the step above into the last equation,and another molar volume value recorded as Vm2 is determined.(iii) If Vm1 is unequal to Vm2,the calculation will be restarted from"(i)".The iteration is completed until Vm1 is equal to Vm2,which means that the four associated equations are released.Compared to Parry's (1986) solution method,the improved method is more convenient to use,as well as more accurate to determine Xco2.It is available for a NHC inlusion whose partial homogenization temperature is higher than clatherate melting temperature and there are no solid salt crystals in the inclusion at parital homogenization.

  3. Lake sediments as natural seismographs: Earthquake-related deformations (seismites) in central Canadian lakes

    Science.gov (United States)

    Doughty, M.; Eyles, N.; Eyles, C. H.; Wallace, K.; Boyce, J. I.

    2014-11-01

    Central Canada experiences numerous intraplate earthquakes but their recurrence and source areas remain obscure due to shortness of the instrumental and historic records. Unconsolidated fine-grained sediments in lake basins are 'natural seismographs' with the potential to record ancient earthquakes during the last 10,000 years since the retreat of the Laurentide Ice Sheet. Many lake basins are cut into bedrock and are structurally-controlled by the same Precambrian basement structures (shear zones, terrane boundaries and other lineaments) implicated as the source of ongoing mid-plate earthquake activity. A regional seismic sub-bottom profiling of lakes Gull, Muskoka, Joseph, Rousseau, Ontario, Wanapitei, Fairbanks, Vermilion, Nipissing, Georgian Bay, Mazinaw, Simcoe, Timiskaming, Kipawa, Parry Sound and Lake of Bays, encompassing a total of more than 2000 kilometres of high-resolution track line data supplemented by multibeam and sidescan sonar survey records show a consistent sub-bottom stratigraphy of relatively-thick lowermost lateglacial facies composed of interbedded semi-transparent mass flow facies (debrites, slumps) and rhythmically-laminated silty-clays. Mass flows together with cratered ('kettled') lake floors and associated deformations reflect a dynamic ice-contact glaciolacustrine environment. Exceptionally thick mass flow successions in Lake Timiskaming along the floor of the Timiskaming Graben within the seismically-active Western Quebec Seismic Zone (WQSZ), point to a higher frequency of earthquakes and slope failure during deglaciation and rapid glacio-isostatic rebound though faulting continues into the postglacial. Lateglacial faulting, diapiric deformation and slumping of coeval lateglacial sediments is observed in Parry Sound, Lake Muskoka and Lake Joseph, which are all located above prominent Precambrian terrane boundaries. Lateglacial sediments are sharply overlain by relatively-thin rhythmically-laminated and often semi

  4. Direct hits to the head during amateur boxing is associated with a rise in serum biomarkers for brain injury.

    Science.gov (United States)

    Graham, M R; Myers, T; Evans, P; Davies, B; Cooper, S M; Bhattacharya, K; Grace, F M; Baker, J S

    2011-01-01

    Boxing exposes participants to the physiological response to high intensity exercise and also to direct body and brain trauma. Amateur boxing is increasing and females have also been included in the Olympics. The aim of this study is to assess the stress response and possible brain injury incurred during a match by measuring serum biomarkers associated with stress and cellular brain injury before and after combat. Sixteen male amateur boxers were studied retrospectively. The study population was divided into two groups: (a) a group that received predominantly punches to the head (PTH) and (b) a group that received predominantly punches to the body (PTB). Blood samples were taken before and five minutes after each contest. They were analysed for S-100B, neuron-specific enolase (NSE), creatine kinase (CK) and cortisol. The PTH group received direct contacts to the head (not blocked, parried or avoided) and to the body (n=8, age: 17.6 ± 5.3, years; height: 1.68 ± 0.13, meters; mass: 65.4 ± 20.3, kg). The PTB group received punches to the body including blocked and parried punches, but received no direct punches to the head, (n=8, mean ± SD, age: 19.1 ± 3.2 years; height: 1.70 ± 0.75, meters; mass: 68.5 ± 15 kg). Significant increases (P<0.05) were observed between pre- and post-combat serum concentrations in serum concentrations in PTH of S-100B (0.35 ± 0.61 vs. 0.54 ± 0.73, μg.L-1) NSE (19.7 ± 14 vs.31.1 ± 26.6, ng.ml-1) and cortisol (373 ± 202 vs. 756 ± 93, nmol.L-1). Significant increases (P<0.05) of creatine kinase were recorded in both groups. This study demonstrates significant elevations in neurochemical biomarkers in boxers who received direct blows to the head. However, further work is required to quantify this volumetric brain damage and long term clinical sequelae.

  5. EPR becomes reality at Finland's Olkiluoto 3

    International Nuclear Information System (INIS)

    Gueldner, R.; Giese, U.

    2005-01-01

    The EPR is a third-generation pressurized water reactor (PWR). Its development was started in 1992 by Framatome and Siemens within a Franco-German partnership. Since 2001 this work has been continued by Framatome ANP, which was formed when the two companies merged their nuclear businesses. The French company AREVA, world market leader in nuclear technology, holds a 66% share in Framatome ANP, with Siemens owning 34%. From the very start, development of the EPR was focused on improving plant safety and economics even further. The new reactor development was jointly financed together with the leading power utilities of both countries. The first steps towards realization of an EPR nuclear power plant were taken at Olkiluoto, Finland in 2004, consisting of initial preparation of the construction site. By mid-February 2005 the local municipality - Eurajoki - had issued a construction permit, and the Finnish Government a construction license pursuant to the Finnish Nuclear Energy Act. This had been preceded by a preliminary safety assessment prepared by the Finnish Radiation and Nuclear Safety Authority (STUK) for the Finnish Ministry of Trade and Industry in which STUK verified that it did not see any safety-related issues opposing issuance of the nuclear construction license. STUK emphasized that the evolutionary design of the EPR had been further improved by AREVA compared to the previous product lines. Concreting work began this spring and the unit will start commercial operation in 2009. Construction of an EPR has also been given the political go-ahead in France. According to the utility Electricite de France (EDF) the new reactor will be built as a forerunner of a later series at the site of Flamanville in Normandy. Construction is scheduled to begin in 2007. An EPR nuclear power plant has a rated electric capacity of around 1600 MW, depending on specific site conditions. Being the product of intense bilateral cooperation the EPR combines the technological

  6. Demonstration of AC and DC charge control for the LISA test masses

    Science.gov (United States)

    Olatunde, Taiwo Janet

    2018-01-01

    Taiwo Olatunde, Stephen Apple, Andrew Chilton, Samantha Parry, Peter Wass, Guido Mueller, John W. Conklin The residual test mass acceleration in LISA must be below 3 fm/s2/√Hz at all frequencies between 0.1 and 3 mHz. Test mass charge coupled with stray electrical potentials and external electromagnetic fields is a well-known source of acceleration noise. LISA Pathfinder uses Hg lamps emitting mostly around 254 nm to discharge the test masses via photoemission, but a future LISA mission launched around 2030 will likely replace the lamps with newer UV LEDs with lower mass, better power efficiency, smaller size and higher bandwidth. This presentation will discuss charge control demonstrated on the torsion pendulum in AC and DC modes at the University of Florida using latest generation UV LEDs producing light at 240 nm with energy above the work function of pure Au. Initial results of Au quantum efficiency measurements (number of emitted electrons per incident photons) which is critical for bi-polar charge control will also be presented.

  7. Controls of growth phenology vary in seedlings of three, co-occurring ecologically distinct northern conifers.

    Science.gov (United States)

    Green, D Scott

    2007-08-01

    The objective of this study was to investigate the effects of temperature and seed-source elevation on height-growth phenology of three co-occurring and ecologically distinct northern conifers (Pinus contorta Dougl. ex Loud. var. latifolia (lodgepole pine), Picea glauca (Moench) Voss x Picea engelmannii Parry ex Engelm. (interior spruce) and Abies lasiocarpa (Hook.) Nutt. (subalpine fir)). Seed from populations of the three indigenous and co-occurring species was collected across an elevational transect on the southwestern slope of McBride Peak, near Prince George, BC. Collection sites were at elevations of 750 to 1850 m, the latter being close to the tree line. In 2003, seeds were germinated and seedlings raised under favorable growing conditions in a temperature-controlled glasshouse. In 2004, seedlings of each population were grown in natural daylengths at a location within 50 km of the seed collection site both in a temperature-controlled glasshouse and at a nearby field site, and height growth was recorded twice a week throughout the growing season. Species differed in both the date and the accumulated heat sum above 5 degrees C for the initiation and cessation of shoot extension. Growth durations (which integrate growth initiation and growth cessation) were more similar among species in the field than in the glasshouse. This suggests that different mechanisms of phenological control among co-occurring species can result in adaptive "equivalence" under a particular set of climatic conditions.

  8. China’s Three Warfares Strategy Mitigates Fallout From Cyber Espionage Activities

    Directory of Open Access Journals (Sweden)

    Emilio Iasiello

    2016-06-01

    Full Text Available China is engaged in longstanding cyber espionage against the U.S., as well as other nations, to collect sensitive public and private information in support of national objectives laid out in its 12th Five Year Plan. Foreign governments citing China’s malfeasance have rebuked these activities, a claim vehemently denied by Beijing. In response, China is leveraging the “Three Warfares” an integrated three-prong information warfare strategy to combat these accusations by leveraging Media, Legal, and Psychological components designed to influence the international community. While the United States has threatened the imposition of economic sanctions, Beijing has successfully parried consequential actions by arresting U.S.-identified hackers, thereby demonstrating its commitment toward preserving a stable and peaceful cyberspace. These interrelated “Three Warfares” disciplines have targeted the cognitive processes of the U.S. leadership, as well as the international public’s perception of China as a global threat, thereby having successfully forestalled the implementation of any effective punitive or economic deterrence strategy to include the imposition of cyber sanctions.

  9. Molecular adaptation within the coat protein-encoding gene of Tunisian almond isolates of Prunus necrotic ringspot virus.

    Science.gov (United States)

    Boulila, Moncef; Ben Tiba, Sawssen; Jilani, Saoussen

    2013-04-01

    The sequence alignments of five Tunisian isolates of Prunus necrotic ringspot virus (PNRSV) were searched for evidence of recombination and diversifying selection. Since failing to account for recombination can elevate the false positive error rate in positive selection inference, a genetic algorithm (GARD) was used first and led to the detection of potential recombination events in the coat protein-encoding gene of that virus. The Recco algorithm confirmed these results by identifying, additionally, the potential recombinants. For neutrality testing and evaluation of nucleotide polymorphism in PNRSV CP gene, Tajima's D, and Fu and Li's D and F statistical tests were used. About selection inference, eight algorithms (SLAC, FEL, IFEL, REL, FUBAR, MEME, PARRIS, and GA branch) incorporated in HyPhy package were utilized to assess the selection pressure exerted on the expression of PNRSV capsid. Inferred phylogenies pointed out, in addition to the three classical groups (PE-5, PV-32, and PV-96), the delineation of a fourth cluster having the new proposed designation SW6, and a fifth clade comprising four Tunisian PNRSV isolates which underwent recombination and selective pressure and to which the name Tunisian outgroup was allocated.

  10. Hausdorff dimension of unique beta expansions

    International Nuclear Information System (INIS)

    Kong, Derong; Li, Wenxia

    2015-01-01

    Given an integer N ⩾ 2 and a real number β > 1, let Γ β, N be the set of all x=∑ i=1 ∞ d i /β i with d i  ∈ {0, 1, ···, N − 1} for all i ⩾ 1. The infinite sequence (d i ) is called a β-expansion of x. Let U β,N be the set of all x's in Γ β,N which have unique β-expansions. We give explicit formula of the Hausdorff dimension of U β,N for β in any admissible interval [β L , β U ], where β L is a purely Parry number while β U is a transcendental number whose quasi-greedy expansion of 1 is related to the classical Thue–Morse sequence. This allows us to calculate the Hausdorff dimension of U β,N for almost every β > 1. In particular, this improves the main results of Gábor Kallós (1999, 2001). Moreover, we find that the dimension function f(β) = dim H U β,N fluctuates frequently for β ∈ (1, N). (paper)

  11. Pilot-Scale Demonstration of In-Situ Chemical Oxidation ...

    Science.gov (United States)

    A pilot-scale in situ chemical oxidation (ISCO) demonstration, involving subsurface injections of sodium permanganate (NaMnO4), was performed at the US Marine Corp Recruit Depot (MCRD), site 45 (Parris Island (PI), SC). The ground water was originally contaminated with perchloroethylene (PCE) (also known as tetrachloroethylene), a chlorinated solvent used in dry cleaner operations. High resolution site characterization involved multiple iterations of soil core sampling and analysis. Nested micro-wells and conventional wells were also used to sample and analyze ground water for PCE and decomposition products (i.e., trichloroethyelene (TCE), dichloroethylene (c-DCE, t-DCE), and vinyl chloride (VC)), collectively referred to as chlorinated volatile organic compounds (CVOC). This characterization methodology was used to develop and refine the conceptual site model and the ISCO design, not only by identifying CVOC contamination but also by eliminating uncontaminated portions of the aquifer from further ISCO consideration. Direct-push injection was selected as the main method of NaMnO4 delivery due to its flexibility and low initial capital cost. Site impediments to ISCO activities in the source area involved subsurface utilities, including a high pressure water main, a high voltage power line, a communication line, and sanitary and stormwater sewer lines. Utility markings were used in conjunction with careful planning and judicious selection of injection locations. A

  12. Enhancement of safety at nuclear facilities in Pakistan

    International Nuclear Information System (INIS)

    Ahmad, S.A.; Hayat, T.; Azhar, W.

    2006-01-01

    Pakistan is benefiting from nuclear technology mostly in health and energy sectors as well as agriculture and industry and has an impeccable safety record. At the national level uses of nuclear technology started in 1955 resulting in the operation of Karachi Radioisotope Center, Karachi, in December 1960. Pakistan Nuclear Safety Committee (PNSC) was formulated in 1964 with subsequent promulgation of Pakistan Atomic Energy Commission (PAEC) Ordinance in 1965 to cope with the anticipated introduction of a research reactor, namely PARR-I, and a nuclear power plant, namely KANUPP. Since then Pakistan's nuclear program has expanded to include numerous nuclear facilities of varied nature. This program has definite economic and social impacts by producing electricity, treating and diagnosing cancer patients, and introducing better crop varieties. Appropriate radiation protection includes a number of measures including database of sealed radiation sources at PAEC operated nuclear facilities, see Table l, updated during periodic physical verification of these sources, strict adherence to the BSS-115, IAEA recommended enforcement of zoning at research reactors and NPPs, etc. Pakistan is party to several international conventions and treaties, such as Convention of Nuclear Safety and Early Notification, to improve and enhance safety at its nuclear facilities. In addition Pakistan generally and PAEC particularly believes in a blend of prudent regulations and good/best practices. This is described in this paper. (Author)

  13. HPLC determination of caffeine in coffee beverage

    Science.gov (United States)

    Fajara, B. E. P.; Susanti, H.

    2017-11-01

    Coffee is the second largest beverage which is consumed by people in the world, besides the water. One of the compounds which contained in coffee is caffeine. Caffeine has the pharmacological effect such as stimulating the central nervous system. The purpose of this study is to determine the level of caffeine in coffee beverages with HPLC method. Three branded coffee beverages which include in 3 of Top Brand Index 2016 Phase 2 were used as samples. Qualitative analysis was performed by Parry method, Dragendorff reagent, and comparing the retention time between sample and caffeine standard. Quantitative analysis was done by HPLC method with methanol-water (95:5v/v) as mobile phase and ODS as stationary phasewith flow rate 1 mL/min and UV 272 nm as the detector. The level of caffeine data was statistically analyzed using Anova at 95% confidence level. The Qualitative analysis showed that the three samples contained caffeine. The average of caffeine level in coffee bottles of X, Y, and Z were 138.048 mg/bottle, 109.699 mg/bottle, and 147.669 mg/bottle, respectively. The caffeine content of the three coffee beverage samples are statistically different (pcoffee beverage samples were not meet the requirements set by the Indonesian Standard Agency of 50 mg/serving.

  14. Sounding rocket study of auroral electron precipitation

    International Nuclear Information System (INIS)

    McFadden, J.P.

    1985-01-01

    Measurement of energetic electrons in the auroral zone have proved to be one of the most useful tools in investigating the phenomena of auroral arc formation. This dissertation presents a detailed analysis of the electron data from two sounding rocket campaigns and interprets the measurements in terms of existing auroral models. The Polar Cusp campaign consisted of a single rocket launched from Cape Parry, Canada into the afternoon auroral zone at 1:31:13 UT on January 21, 1982. The results include the measurement of a narrow, magnetic field aligned electron flux at the edge of an arc. This electron precipitation was found to have a remarkably constant 1.2 eV temperature perpendicular to the magnetic field over a 200 to 900 eV energy range. The payload also made simultaneous measurements of both energetic electrons and 3-MHz plasma waves in an auroral arc. Analysis has shown that the waves are propagating in the upper hybrid band and should be generated by a positive slope in the parallel electron distribution. A correlation was found between the 3-MHz waves and small positive slopes in the parallel electron distribution but experimental uncertainties in the electron measurement were large enough to influence the analysis. The BIDARCA campaign consisted of two sounding rockets launched from Poker Flat and Fort Yukon, Alaska at 9:09:00 UT and 9:10:40 UT on February 7, 1984

  15. RESEARCH ON THE DEVELOPMENT OF ALTERNATIVE TECHNOLOGIES FOR THE PRODUCTION OF TOMATO SEEDLINGS IN DRĂGANU ARGEŞ

    Directory of Open Access Journals (Sweden)

    Florina Uleanu

    2017-12-01

    Full Text Available This paper aims to find the most efficient techniques for the production of seedlings because it represents one of the greatest concerns of the vegetable growers, being a subject of great interest. A special attention shows determining influence of different pots, plastic or biodegradable, on the growth and development of tomato seedlings. The replanting of the seedlings was carried out in various pots (of polyethylene film, from peat, Jiffy pots, small and big alveolar pallets filled with nutritional mixture. The best growth in height was achieved in seedlings transplanted in polyethylene pots (B1, except for Parris hybrid, the favorable effects on seedlings growth being explained by their better nutritional capacity as a result of the development of a stronger root system. As a type of pot, it is noted that seedlings transplanted into large alveolar pallets formed floral buds before planting in all hybrids studied. The type of pots used to transplant seedlings, and especially their size, positively influences the number of leaves. This work brings to the forefront the influence of different pots of plastic or biodegradable material on the growth and development of tomato seedlings that have been transplanted and maintained in these pots until planting.

  16. [Autologous fat grafting in children].

    Science.gov (United States)

    Baptista, C; Bertrand, B; Philandrianos, C; Degardin, N; Casanova, D

    2016-10-01

    Lipofilling or fat grafting transfer is defined as a technique of filling soft tissue by autologous fat grafting. The basic principle of lipofilling is based on a harvest of adipose tissue, followed by a reinjection after treatment. Lipofilling main objective is a volume defect filling, but also improving cutaneous trophicity. Lipofilling specificities among children is mainly based on these indications. Complications of autologous fat grafting among children are the same as those in adults: we distinguish short-term complications (intraoperative and perioperative) and the medium and long-term complications. The harvesting of fat tissue is the main limiting factor of the technique, due to low percentage of body fat of children. Indications of lipofilling among children may be specific or similar to those in adults. There are two types of indications: cosmetic, in which the aim of lipofilling is correcting a defect density, acquired (iatrogenic, post-traumatic scar) or malformation (otomandibular dysplasia, craniosynostosis, Parry Romberg syndrom, Poland syndrom, pectus excavatum…). The aim of functional indications is correcting a velar insufficiency or lagophthalmos. In the paediatric sector, lipofilling has become an alternative to the conventional techniques, by its reliability, safety, reproducibility, and good results. Copyright © 2016 Elsevier Masson SAS. All rights reserved.

  17. Navigable windows of the Northwest Passage

    Science.gov (United States)

    Liu, Xing-he; Ma, Long; Wang, Jia-yue; Wang, Ye; Wang, Li-na

    2017-09-01

    Artic sea ice loss trends support a greater potential for Arctic shipping. The information of sea ice conditions is important for utilizing Arctic passages. Based on the shipping routes given by ;Arctic Marine Shipping Assessment 2009 Report;, the navigable windows of these routes and the constituent legs were calculated by using sea ice concentration product data from 2006 to 2015, by which a comprehensive knowledge of the sea ice condition of the Northwest Passage was achieved. The results showed that Route 4 (Lancaster Sound - Barrow Strait - Prince Regent Inlet and Bellot Strait - Franklin Strait - Larsen Sound - Victoria Strait - Queen Maud Gulf - Dease Strait - Coronation Gulf - Dolphin and Union Strait - Amundsen Gulf) had the best navigable expectation, Route 2 (Parry Channel - M'Clure Strait) had the worst, and the critical legs affecting the navigation of Northwest Passage were Viscount Melville Sound, Franklin Strait, Victoria Strait, Bellot Strait, M'Clure Strait and Prince of Wales Strait. The shortest navigable period of the routes of Northwest Passage was up to 69 days. The methods used and the results of the study can help the selection and evaluation of Arctic commercial routes.

  18. Optimal management of perimenopausal depression

    Directory of Open Access Journals (Sweden)

    Barbara L Parry

    2010-06-01

    Full Text Available Barbara L ParryDepartment of Psychiatry, University of California, San Diego, USAAbstract: Only recently has the perimenopause become recognized as a time when women are at risk for new onset and recurrence of major depression. Untreated depression at this time not only exacerbates the course of a depressive illness, but also puts women at increased risk for sleep disorders, cardiovascular disease, diabetes, and osteoporosis. Although antidepressant medication is the mainstay of treatment, adjunctive therapy, especially with estrogen replacement, may be indicated in refractory cases, and may speed the onset of antidepressant action. Many, but not all, studies, report that progesterone antagonizes the beneficial effects of estrogen. Although some antidepressants improve vasomotor symptoms, in general they are not as effective as estrogen alone for relieving these symptoms. Estrogen alone, however, does not generally result in remission of major depression in most (but not all studies, but may provide benefit to some women with less severe symptoms if administered in therapeutic ranges. The selective serotonin reuptake inhibitors (SSRIs in addition to estrogen are usually more beneficial in improving mood than SSRIs or estrogen treatment alone for major depression, whereas the selective norepinephrine and serotonin reuptake inhibitors do not require the addition of estrogen to exert their antidepressant effects in menopausal depression. In addition to attention to general health, hormonal status, and antidepressant treatment, the optimal management of perimenopausal depression also requires attention to the individual woman’s psychosocial and spiritual well being.Keywords: menopause, depression, management

  19. Clark T. Sawin historical vignette: what do criminology, Harry Houdini, and King George V have in common with postpartum thyroid dysfunction?

    Science.gov (United States)

    Smallridge, Robert C

    2014-12-01

    The history of postpartum thyroid dysfunction (PPTD) dates back almost two millennia, when Soranus of Ephesus, who practiced obstetrics and neonatology, observed swelling in the necks (presumably goiters) of women after pregnancy. The next reference to PPTD appeared in artwork more than 1000 years later, with many portraits illustrating women with goiter while holding infants. In the early to mid-19th century, Caleb Hillier Parry and Armand Trousseau described postpartum hyperthyroidism, while in the late 1800s, Sir Horatio Bryan Donkin reported the first patient with postpartum hypothyroidism. The modern era of PPTD began with the description in the late 1940s by H.E.W. Roberton of women after delivery reporting hypothyroid symptoms and responding to thyroid extract. The immunologic influence on PPTD was recognized initially by Parker and Beierwaltes in the early 1960s, and the clinical variability and natural history were carefully documented by numerous investigators in the 1970s-1980s. The past two decades have seen further refinements in understanding the prevalence, etiology, and treatment of PPTD. Yet to be determined is the role of screening as a cost-effective measure.

  20. Capillary wave Hamiltonian for the Landau–Ginzburg–Wilson density functional

    International Nuclear Information System (INIS)

    Chacón, Enrique; Tarazona, Pedro

    2016-01-01

    We study the link between the density functional (DF) formalism and the capillary wave theory (CWT) for liquid surfaces, focused on the Landau–Ginzburg–Wilson (LGW) model, or square gradient DF expansion, with a symmetric double parabola free energy, which has been extensively used in theoretical studies of this problem. We show the equivalence between the non-local DF results of Parry and coworkers and the direct evaluation of the mean square fluctuations of the intrinsic surface, as is done in the intrinsic sampling method for computer simulations. The definition of effective wave-vector dependent surface tensions is reviewed and we obtain new proposals for the LGW model. The surface weight proposed by Blokhuis and the surface mode analysis proposed by Stecki provide consistent and optimal effective definitions for the extended CWT Hamiltonian associated to the DF model. A non-local, or coarse-grained, definition of the intrinsic surface provides the missing element to get the mesoscopic surface Hamiltonian from the molecular DF description, as had been proposed a long time ago by Dietrich and coworkers. (paper)

  1. Mineral Analysis of Pine Nuts (Pinus spp.) Grown in New Zealand.

    Science.gov (United States)

    Vanhanen, Leo P; Savage, Geoffrey P

    2013-04-03

    Mineral analysis of seven Pinus species grown in different regions of New Zealand; Armand pine ( Pinus armandii Franch), Swiss stone pine ( Pinus cembra L.), Mexican pinyon ( Pinus cembroides Zucc. var. bicolor Little), Coulter pine ( Pinus coulteri D. Don), Johann's pine ( Pinus johannis M.F. Robert), Italian stone pine ( Pinus pinea L.) and Torrey pine ( Pinus torreyana Parry ex Carrière), was carried out using an inductively coupled plasma optical emission spectrophotometer (ICP-OES) analysis. Fourteen different minerals (Al, B, Ca, Cr, Cu, Fe, K, Mg, Mn, Na, Ni, P, S and Zn) were identified in all seven varieties, except that no Al or Na was found in Pinus coulteri D. Don. New Zealand grown pine nuts are a good source of Cu, Mg, Mn, P and Zn, meeting or exceeding the recommended RDI for these minerals (based on an intake of 50 g nuts/day) while they supplied between 39%-89% of the New Zealand RDI for Fe. Compared to other commonly eaten tree-nuts New Zealand grown pine nuts are an excellent source of essential minerals.

  2. NPL's contribution to the introduction of the caesium second

    Energy Technology Data Exchange (ETDEWEB)

    Whibberley, Peter [National Physical Laboratory, Teddington (United Kingdom). Time and Frequency Group

    2017-09-15

    For centuries timekeeping was the preserve of astronomers. The fundamental unit of time measurement was the day, sub-divided by clocks for everyday use into hours, minutes and seconds. By the early 20th century, clocks were sufficiently stable to indicate that the length of the mean solar day varied, though their lack of intrinsic accuracy (the rate of a clock depended on its mechanical properties) ensured that the Earth's rotation remained the global reference standard for timekeeping. This situation changed fundamentally in June 1955, when Louis Essen and Jack Parry brought the first caesium atomic clock into operation at the National Physical Laboratory, in Teddington, UK. The atomic clock not only provided a much more stable timekeeper than the Earth's rotation; its reference was the frequency of an atomic transition - a fundamental constant of nature, determined by the laws of quantum mechanics. As a result all caesium clocks will run at essentially the same rate, limited only by noise processes and their local environment, regardless of time or place.

  3. USGS integrated drought science

    Science.gov (United States)

    Ostroff, Andrea C.; Muhlfeld, Clint C.; Lambert, Patrick M.; Booth, Nathaniel L.; Carter, Shawn L.; Stoker, Jason M.; Focazio, Michael J.

    2017-06-05

    Project Need and OverviewDrought poses a serious threat to the resilience of human communities and ecosystems in the United States (Easterling and others, 2000). Over the past several years, many regions have experienced extreme drought conditions, fueled by prolonged periods of reduced precipitation and exceptionally warm temperatures. Extreme drought has far-reaching impacts on water supplies, ecosystems, agricultural production, critical infrastructure, energy costs, human health, and local economies (Milly and others, 2005; Wihlite, 2005; Vörösmarty and others, 2010; Choat and others, 2012; Ledger and others, 2013). As global temperatures continue to increase, the frequency, severity, extent, and duration of droughts are expected to increase across North America, affecting both humans and natural ecosystems (Parry and others, 2007).The U.S. Geological Survey (USGS) has a long, proven history of delivering science and tools to help decision-makers manage and mitigate effects of drought. That said, there is substantial capacity for improved integration and coordination in the ways that the USGS provides drought science. A USGS Drought Team was formed in August 2016 to work across USGS Mission Areas to identify current USGS drought-related research and core capabilities. This information has been used to initiate the development of an integrated science effort that will bring the full USGS capacity to bear on this national crisis.

  4. Optimal gasoline tax in developing, oil-producing countries: The case of Mexico

    International Nuclear Information System (INIS)

    Antón-Sarabia, Arturo; Hernández-Trillo, Fausto

    2014-01-01

    This paper uses the methodology of Parry and Small (2005) to estimate the optimal gasoline tax for a less-developed oil-producing country. The relevance of the estimation relies on the differences between less-developed countries (LDCs) and industrial countries. We argue that lawless roads, general subsidies on gasoline, poor mass transportation systems, older vehicle fleets and unregulated city growth make the tax rates in LDCs differ substantially from the rates in the developed world. We find that the optimal gasoline tax is $1.90 per gallon at 2011 prices and show that the estimate differences are in line with the factors hypothesized. In contrast to the existing literature on industrial countries, we show that the relative gasoline tax incidence may be progressive in Mexico and, more generally, in LDCs. - Highlights: • We estimate the optimal gasoline tax for a typical less-developed, oil-producing country like Mexico. • The relevance of the estimation relies on the differences between less-developed and industrial countries. • The optimal gasoline tax is $1.90 per gallon at 2011 prices. • Distance-related pollution damages, accident costs and gas subsidies account for the major differences. • Gasoline tax incidence may be progressive in less developed countries

  5. Casein micelle structure: a concise review

    Directory of Open Access Journals (Sweden)

    Chanokphat Phadungath

    2005-01-01

    Full Text Available Milk is a complex biological fluid with high amount of proteins, lipid and minerals. The function of milk is to supply nutrients such as essential amino acids required for the growth of the newborn. In addition, due to the importance of casein and casein micelles for the functional behavior of dairy products, the nature and structure of casein micelles have been studied extensively. However, the exact structure of casein micelles is still under debate. Various models for casein micelle structure have been proposed. Most of the proposedmodels fall into three general categories, which are: coat-core, subunit (sub-micelles, and internal structure models. The coat-core models, proposed by Waugh and Nobel in 1965, Payens in 1966, Parry and Carroll in 1969, and Paquin and co-workers in 1987, describe the micelle as an aggregate of caseins with outer layer differing in composition form the interior, and the structure of the inner part is not accurately identified. The sub-micelle models, proposed by Morr in 1967, Slattery and Evard in 1973, Schmidt in 1980, Walstra in1984, and Ono and Obata in 1989, is considered to be composed of roughly spherical uniform subunits. The last models, the internal structure models, which were proposed by Rose in 1969, Garnier and Ribadeau- Dumas in 1970, Holt in 1992, and Horne in 1998, specify the mode of aggregation of the different caseins.

  6. Investigating Potential Toxicity of Leachate from Wood Chip Piles Generated by Roadside Biomass Operations

    Directory of Open Access Journals (Sweden)

    John Rex

    2016-02-01

    Full Text Available Roadside processing of wood biomass leaves chip piles of varying size depending upon whether they were created for temporary storage, spillage, or equipment maintenance. Wood chips left in these piles can generate leachate that contaminates streams when processing sites are connected to waterways. Leachate toxicity and chemistry were assessed for pure aspen (Populus tremuloides Michx., lodgepole pine (Pinus contorta Dougl., hybrid white spruce (Picea engelmannii x glauca Parry, and black spruce (Picea mariana (Mill. Britton as well as from two wood chipping sites using mixes of lodgepole pine and hybrid or black spruce. Leachate was generated using rainfall simulation, a static 28-day laboratory assay, and a field-based exposure. Leachate generated by these exposures was analyzed for organic matter content, phenols, ammonia, pH, and toxicity. Findings indicate that all wood chip types produced a toxic leachate despite differences in their chemistry. The consistent toxicity response highlights the need for runoff management that will disconnect processing sites from aquatic environments.

  7. Individua l tree identification in airborne LASER data BY inverse SEARCH window

    Directory of Open Access Journals (Sweden)

    Eric Bastos Gorgens

    2015-03-01

    Full Text Available The local maximum filtering performance is highly dependent of the window size definition. This paper proposes that the window size should be determined by an inverse relationship to the canopy height model, and test the hypothesis that a windowsize inversely proportional will have better performance than the window proportional to the canopy height model. The study area is located in the southeastern region of the State of British Columbia, Canada. The natural vegetation is the boreal type and is characterized by the dominance of two species Picea engelmannii Parry ex. Engelmann (Engelmann spruce and Abies lasiocarpa (Hook. Nutt. (sub-alpine fir. The relief is mountainous with altitudes ranging from 650-2400 meters. 62 plots with 256 square meters were measured in the field. The airborne LiDAR had discrete returns, 2 points per square meter density and small-footprint. The performance of the search windows was evaluated based on success percentage, absolute average error and also compared to the observed values of the field plots. The local maximum filter underestimated the number of trees per hectare for both window sizing methods. The use of the inverse proportional window size has resulted in superior results, particularly for regions with highest density of trees.

  8. AN AMBIVALENT CONRAD IN AN OUTPOST OF PROGRESS

    Directory of Open Access Journals (Sweden)

    Majid SADEGHZADEGAN

    2017-06-01

    Full Text Available The present paper aims to portray the racist and anti-racist dimensions of Joseph Conrad in his short story “An Outpost of Progress” (1897. Conrad’s alleged racist status espoused by thinkers such as Chinua Achebe and Edward Said, particularly in Heart of Darkness, has constantly been the subject of heated debates in literature. A myriad of analogous traces in the short story “An Outpost of Progress” lend Conrad’s voice to a highly racist position while many other anti-racist traces observed in the story could lower the resonance of the same voice, hence an inconclusive ambivalence or a liminal position in Conrad’s tone. This paper is thus divided into two sections. The first section has the racist traces of Conrad in the short story on top of its agenda whereas the second section ventures into the anti-racist footprints of Conrad’s voice in the story. In so doing, this paper sets out to turn to Achebe and Said in arguing for the racist position of Conrad; however, the anti-racist facets of the story will be substantiated via relying on the arguments developed by thinkers such as D. C. R. A. Goonetilleke and Benita Parry. An ironic ambivalence swaying from a racist tone to an anti-racist tone in Conrad’s voice in “An Outpost of Progress” is the conclusive maxim.

  9. Cell-assisted lipotransfer for facial lipoatrophy: efficacy of clinical use of adipose-derived stem cells.

    Science.gov (United States)

    Yoshimura, Kotaro; Sato, Katsujiro; Aoi, Noriyuki; Kurita, Masakazu; Inoue, Keita; Suga, Hirotaka; Eto, Hitomi; Kato, Harunosuke; Hirohi, Toshitsugu; Harii, Kiyonori

    2008-09-01

    Lipoinjection is a promising treatment, but its efficacy in recontouring facial lipoatrophy remains to be established. The objective was to evaluate the efficacy and adverse effects of lipoinjection and supplementation of adipose-derived stem/stromal cells (ASCs) to adipose grafts. To overcome drawbacks of autologous lipoinjection, we have developed a novel strategy called cell-assisted lipotransfer (CAL). In CAL, stromal vascular fraction containing ASCs was freshly isolated from half of an aspirated fat sample and attached to the other half of aspirated fat sample with the fat acting as a scaffold. This process converts relatively ASC-poor aspirated fat into ASC-rich fat. We performed conventional lipoinjection (non-CAL; n=3) or CAL (n=3) on six patients with facial lipoatrophy due to lupus profundus or Parry-Romberg syndrome. All patients obtained improvement in facial contour, but the CAL group had a better clinical improvement score than did the non-CAL patients, although the difference did not reach statistical significance (p=.11). Adipose necrosis was found in one non-CAL case who took perioperative oral corticosteroids. Our results suggest that CAL is both effective and safe and potentially superior to conventional lipoinjection for facial recontouring. The authors have indicated no significant interest with commercial supporters.

  10. Changes in the physico-chemical properties of four lettuce (Lactuca sativa L. varieties during storage

    Directory of Open Access Journals (Sweden)

    María Vargas-Arcila

    2017-05-01

    Full Text Available Lettuce, a popularly consumed leafy vegetable, is well known for its health and nutritional value. Thus, the current study focused on the qualitative changes of four lettuce varieties, namely Alpha, Parris Island, Graziella and Lollo Rossa, stored at 5.5 ºC and 90 % RH for 12 days. The analyzed parameters were water content, total soluble solids (TSS, titrable acidity (TA, vitamin C, total phenols, polyphenoloxidase (PPO, color and texture. Under storage conditions, the studied varieties exhibited different rates of water loss. TSS was found to increase until day 8 of storage, which is also when TA differences were observed. The Graziella variety showed the highest vitamin C levels. Total phenol content decreased significantly during the 12 days of storage. No significant PPO activity changes were found, except for those of the Lollo Rossa variety. Biplot analysis allowed observing not only positive and negative correlations between coordinates L*, a* and b*, but also the separavtion of the green lettuce varieties from the red one, together with color variations depending on leaf position. Although textural changes were recorded at the end of the study, foliage quality was not altered. In short, the studied parameters, which contribute to lettu-ce direct consumption properties, can be said to be variety-dependent and better preserved under refrigeration.

  11. A fixed incore based system for an on line core margin monitoring

    International Nuclear Information System (INIS)

    Mourlevat, J. L.; Carrasco, M.

    2002-01-01

    In order to comply with the needs of Utilities for improvements in the economic competitiveness of nuclear energy, one of the solutions proposed is to reduce the cost of the fuel cycle. To this aim, increasing the lifetime of cycles by introducing so-called low leakage fuel loading patterns to the reactor is a rather promising solution. However, these loading patterns lead to an increase in the core hostspot factors and therefore to a reduction in the core operating margins. For many years FRAMATOME-ANP has developed and proposed solutions aiming at increasing and therefore restoring these margins, namely; the improvement in design methods based on three-dimensional modelling of the core,on kinetic representation of transients and on neutron-thermohydraulic coupling, or the improvement in the fuel with the introduction of intermediate mixing girds. A third approach is to improve the core instrumentation associated with the system for monitoring the core operating limits: it is this approach that is described in this presentation. The core operating limits monitoring function calls on realtime knowledge of the power distribution. At present time, for most of the PWRs operated in the world, this knowledge is based on the measurement of the axial power distribution made by two-section neutron detectors located outside the pressure vessel. This kind of detectors is only able to provide the operators with a rustic picture of the axial power distribution through the axial dissymmetry index so called axial-offset. During normal core operation operators have to control the axial power distribution that means to keep the axial-offset value inside a pre-determined domain of which the width is a function of the mean power level. This pre-determined domain is calculated or checked during the nuclear design phase of the reload and due to th emethodology used to calculate it, a consderable potential for improving the core operating margin does ewxist. This the reason why

  12. Promethee experiment and analysis

    International Nuclear Information System (INIS)

    Jean-Philippe Gaillard; Jean-Benoit Ritz; Christelle Vurpillot-Le Maitre; Jan-Patrice Simoneau; Bernard Duret

    2005-01-01

    Full text of publication follows: The thermal conditions of containers and storage rooms is one of the decisive aspects governing the various concepts for spent fuel assemblies interim storage. In case of vertical dry storage, current numerical models are insufficiently validated against representative experiments, especially for turbulent flow of air in an annuli where usual turbulence modelling developed for forced convection flows are not well adapted to mixed convection flows. For these reasons, EDF, CEA and Framatome are currently carrying out a basic model qualification program, launched in 1998 the experimental loop for axial flow is called PROMETHEE. The main features of the experimental vessel are near a scale 1 canister: height 5 m, diameter 90 cm, air gap thickness 10 cm. Radiative thermal exchange between canister and containment vessel being essential to be well known, emissivity of the walls have been measured. Motion of air along the canister may be natural or modified using an external fan, the tests presented control the boundary conditions and investigate the effect of the electrical power supplied (from 5 kW to 20 kW), the input and output 3D effect and the efficiency of the external wind. During the steady state and transient experiment, temperature profile of walls and air are carried out. In parallel detailed 2D and 3D thermal hydraulics calculation with the tools of the different partners (EDF: Code-Saturne, Framatome: Star-cd and CEA: TRIO and FLOTRAN) have been submitted to the same boundary conditions. The Star-cd software is a general purpose code for fluid mechanics and thermal engineering. Full coupled convection - conduction - radiation heat transfers are modelled. A set of parametric calculations has been performed: Different mesh sizes and different turbulence models (variants of the standard k-epsilon model) have been investigated. From the benchmark, the experimental-calculation comparisons results of the profile temperature and

  13. Promethee experiment and analysis

    Energy Technology Data Exchange (ETDEWEB)

    Jean-Philippe Gaillard [CEA/DEN/DTEC - Centre de Valrho / Marcoule, BP 17171, 30207 Bagnols sur Ceze Cedex (France); Jean-Benoit Ritz [EDF R and D, Dept SEVE, Groupe E15 Avenue des Renardieres, BP 46, F77818 Moret sur Loing (France); Christelle Vurpillot-Le Maitre [EDF R and D, Dept MFTT, Groupe I83, 6 Quai Watier BP 49, 78401 Chatou Cedex (France); Jan-Patrice Simoneau [Framatome-ANP (France); Bernard Duret [CEA/DEN/DTN, CEA Grenoble, 38054 Grenoble Cedex (France)

    2005-07-01

    Full text of publication follows: The thermal conditions of containers and storage rooms is one of the decisive aspects governing the various concepts for spent fuel assemblies interim storage. In case of vertical dry storage, current numerical models are insufficiently validated against representative experiments, especially for turbulent flow of air in an annuli where usual turbulence modelling developed for forced convection flows are not well adapted to mixed convection flows. For these reasons, EDF, CEA and Framatome are currently carrying out a basic model qualification program, launched in 1998 the experimental loop for axial flow is called PROMETHEE. The main features of the experimental vessel are near a scale 1 canister: height 5 m, diameter 90 cm, air gap thickness 10 cm. Radiative thermal exchange between canister and containment vessel being essential to be well known, emissivity of the walls have been measured. Motion of air along the canister may be natural or modified using an external fan, the tests presented control the boundary conditions and investigate the effect of the electrical power supplied (from 5 kW to 20 kW), the input and output 3D effect and the efficiency of the external wind. During the steady state and transient experiment, temperature profile of walls and air are carried out. In parallel detailed 2D and 3D thermal hydraulics calculation with the tools of the different partners (EDF: Code-Saturne, Framatome: Star-cd and CEA: TRIO and FLOTRAN) have been submitted to the same boundary conditions. The Star-cd software is a general purpose code for fluid mechanics and thermal engineering. Full coupled convection - conduction - radiation heat transfers are modelled. A set of parametric calculations has been performed: Different mesh sizes and different turbulence models (variants of the standard k-epsilon model) have been investigated. From the benchmark, the experimental-calculation comparisons results of the profile temperature and

  14. The EPR - a safe and competitive solution for future energy needs

    International Nuclear Information System (INIS)

    Fischer, U.; Bouteille, F.; Leverenz, R.

    1999-01-01

    NPI, Siemens and Framatome, in co-operation with EDF and the major German Utilities, started the development of the European Pressurized Water Reactor (EPR) as an evolutionary approach. After a careful evaluation of the potential of passive safety features, this way was concluded to be superior compared to a 'revolutionary' approach. The vast majority of advanced reactor designs being developed today is of the evolutionary type. The advantages to base an advanced design on the feedback of operation experience of the more than 100 nuclear power plants designed and constructed by Siemens and Framatome are outstanding. This view is shared by the German and French safety authorities which defined their preference for an evolutionary design early at the beginning of their co-operation for the definition of a common safety approach for future nuclear power plants to be built in Germany and France. In their first common set of recommendations, they gave a clear guideline regarding their point of view for requirements posed to the next generation of nuclear power plants: (1) Preference for an evolutionary design in order to derive a maximum benefit from experience; (2) Significant safety improvements by reduction of core meltdown probability and improvement of the confinement function of the containment under accident conditions; (3) Improvement of operating conditions regarding radiation protection, maintenance and human errors. Besides the French-German co-operation of vendors, utilities and authorities, the European utilities co-operate on a much broader basis for the establishment of the European Utilities' Requirements (EUR). During the development of the basic design, the EPR was continuously assessed against these EUR and it was concluded that the EPR complies with these requirements. At the end of the basic design phase at the end of 1997, all information necessary to file a preliminary safety analysis report and a reliable bill of quantities was elaborated. With

  15. French studies on blow-down accident in light water reactors

    International Nuclear Information System (INIS)

    Pelce, J.

    1977-01-01

    The effects on fuel elements and containment buildings resulting from a rapid blow-down accident and the effectiveness of proposed emergency systems are currently being evaluated in France, using the so-called first generation computer codes. Some of these were developed by the constructing organization Framatome for the design of actual power plants; others were developed by the Nuclear Safety Division to back-up related safety studies. These codes are considered to be inadequate and for several years a large effort has been made jointly by EDF and safety authorities, and with the technical assistance of CEA, to make a significant improvement in the methods of assessment. Framatome also participates in this work to some extent. A more physical method is proposed. In particular, selected models are supported by a quite comprehensive experimental programme which is mainly analytical in nature, as follows: (1) Basic analysis, using experiments which are planned or in progress, such as CANON, MOBY-DICK, SUPER MOBY-DICK, REBECA (critical flow at the break and between sub-compartments of the containment building), ECOTRA (condensation on inner walls), TAPIOCA (phase separation at small cracks), EPIS (water and steam mixing during emergency injection), EDGAR (fuel cladding behavior). (2) More intricate or semi-integral analysis such as OMEGA and ERSEC (tests on in-core heat transfer during blow-down and rewetting), both of which are in progress, in-pile PHEBUS loop due to start operating in 1977 (fuel behavior during the accident), pump tests (EVA, POMPE). Future methods of assessing the reactor itself will include the physical models thus perfected: A first code, (CLYSTERE) has been written and can be used. Although it has not been validated experimentally, it can already evaluate the effect of some physical phenomena on the development of the accident. Work is being done on reconstructing the general flow chart of this code in order to improve the conditions of use, in

  16. Game-Changer: The Illusion of War Without Risk

    Science.gov (United States)

    2017-04-28

    War. Cambridge, MA: Harvard University Press, 1985. _____. A History of Strategy: From Sun Tzu to William S. Lind. Kuovola, Finland: Castalia House...Selected Bibliography 24 iii Paper Abstract In the late 1980s and early 1990s, the “Revolution in Military Affairs” (RMA) argued...SELECTED BIBLIOGRAPHY Books Bernstein, Peter L. Against the Gods: The Remarkable Story of Risk. New York: John Wiley & Sons, Inc., 1998

  17. Essential aspects and concepts of the energy debate

    International Nuclear Information System (INIS)

    Kotte, U.

    1985-01-01

    The paper abstracted intends to elucidate the structures of modern energy supply and explains a number of concepts arising in the energy debate. Among others, the paper discusses the different energy sources, the relation between per capita income and primary energy consumption, the development of primary energy consumption classified by energy sources, economic growth and electric power consumption in the Federal Republic of Germany and end use energy consumption classified by different groups of consumers. (DG) [de

  18. The Hualien Large-Scale Seismic Test for soil-structure interaction research

    International Nuclear Information System (INIS)

    Tang, H.T.; Stepp, J.C.; Cheng, Y.H.

    1991-01-01

    A Large-Scale Seismic Test (LSST) Program at Hualien, Taiwan, has been initiated with the primary objective of obtaining earthquake-induced SSI data at a stiff soil site having similar prototypical nuclear power plant soil conditions. Preliminary soil boring, geophysical testing and ambient and earthquake-induced ground motion monitoring have been conducted to understand the experiment site conditions. More refined field and laboratory tests will be conducted such as the state-of-the-art freezing sampling technique and the large penetration test (LPT) method to characterize the soil constitutive behavior. The test model to be constructed will be similar to the Lotung model. The instrumentation layout will be designed to provide data for studies of SSI, spatial incoherence, soil stability, foundation uplifting, ground motion wave field and structural response. A consortium consisting of EPRI, Taipower, CRIEPI, TEPCO, CEA, EdF and Framatome has been established to carry out the project. It is envisaged that the Hualien SSI array will be ready to record earthquakes by the middle of 1992. The duration of the recording scheduled for five years. (author)

  19. The yawning chasm of French nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The financial problems of the nuclear power industry in France are explained. Cogema, the waste reprocessing company ventured into the French financial futures market and lost money. It is trying to sue its brokers over this disaster. Framatome, the State reactor manufacturer is trying to diversify into aeronautics, electronics and foodstuffs. The electric utility EdF is sliding into debt and, with no price rise allowed, this situation will get worse. Theoretically EdF should be delivering cheap electricity from nuclear power stations. However, French electricity prices are not significantly cheaper than those of Germany and the United Kingdom. The generating capacity will increase greatly over the next few years. The availability of existing plants is also improving. In spite of efforts to export its electricity (about 10% is exported) EdF seem unable to make its extra electricity cheaper and is heavily in debt. The fast breeder programme has also not lived up to expectations due to a sodium leak at Superphenix. (U.K.)

  20. Post test analyses of Revisa benchmark based on a creep test at 1100 Celsius degrees performed on a notched tube

    International Nuclear Information System (INIS)

    Fischer, M.; Bernard, A.; Bhandari, S.

    2001-01-01

    In the Euratom 4. Framework Program of the European Commission, REVISA Project deals with the Reactor Vessel Integrity under Severe Accidents. One of the tasks consists in the experimental validation of the models developed in the project. To do this, a benchmark was designed where the participants use their models to test the results against an experiment. The experiment called RUPTHER 15 was conducted by the coordinating organisation, CEA (Commissariat a l'Energie Atomique) in France. It is a 'delayed fracture' test on a notched tube. Thermal loading is an axial gradient with a temperature of about 1130 C in the mid-part. Internal pressure is maintained at 0.8 MPa. This paper presents the results of Finite Element calculations performed by Framatome-ANP using the SYSTUS code. Two types of analyses were made: -) one based on the 'time hardening' Norton-Bailey creep law, -) the other based on the coupled creep/damage Lemaitre-Chaboche model. The purpose of this paper is in particular to show the influence of temperature on the simulation results. At high temperatures of the kind dealt with here, slight errors in the temperature measurements can lead to very large differences in the deformation behaviour. (authors)