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Sample records for areva nc cadarache

  1. Taking Human and organizational factors into account in AREVA NC Cadarache dismantling projects

    International Nuclear Information System (INIS)

    AREVA NC Cadarache fabricated MOX fuel (fuel assemblies made with a mixture of uranium and plutonium oxides) and FBR fuel (fast breeder reactor) for 40 years. In 2003, commercial fuel fabrication was stopped and the plant began implementing a plan to remove the nuclear material and clean up its two production buildings and laboratory. The objective is to reduce the radiological activity in the process facilities to IAEA level 2 and transferred them back to the owner French Atomic Energy Commission (CEA). The type of facilities to be dismantled (glove boxes, tanks, etc.) and the products involved (uranium and plutonium), in the form of powder, require a high degree of manual operation. Human and Organizational Factors (HOF) therefore play a key role in the depth defense concept. (author)

  2. Intensive post operation clean out (Poco) in AREVA NC Cadarache dismantling projects: economic value and sustainable development

    International Nuclear Information System (INIS)

    After fabricating plutonium fuels for 40 years (Fast Breeder Reactor, MOX), commercial operations at the AREVA NC Cadarache plant ended in 2003 and post operation clean out of its production buildings and laboratory started. AREVA objective is to achieve IAEA level 2 cleanup of the process facilities and transfer them to their owner, the French Atomic Energy Commission (CEA). There are two main opposite dismantling scenarios: very limited cleanup to optimize man power, or intensive cleanup of the facilities to optimize the quantity of long lived level waste as much as possible. Economic and environmental considerations lead the choice between these two options. (author)

  3. Report on transparency and nuclear safety, Cadarache 2011, Volume 1 + Volume 2 INB 32 and 54 Areva NC

    International Nuclear Information System (INIS)

    For respectively different sites all situated in Cadarache, the CEA Centre on the one hand, and the AREVA nuclear base installation INB 32 and 54 on the other hand, these volumes propose a presentation of their activities and installations, a description of measures regarding safety and radiation protection, a description of significant events regarding nuclear safety and radiation protection, a presentation and discussion of results of measurements of releases and of their impact on the environment, and a description of the different radioactive wastes stored on the concerned site

  4. Report on transparency and nuclear safety 2013 - Cadarache CEA centre - Tome 1. INB 32 (ATPu) et 54 (LCP) AREVA NC - Tome 2

    International Nuclear Information System (INIS)

    A first volume proposes a presentation of the Cadarache CEA centre, of its activities and installations, gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. It also reports significant events related to safety and to radiation protection which occurred in 2013 and have been declared to the ASN. It discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. It addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre, indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and on the environment. Nature and quantities of warehoused wastes are specified. The second volume concerns some specific installations (INB 32 or ATPu, and INB 54 or LPC) which belong to AREVA NC. The same topics are addressed: presentation of the facilities, arrangements regarding safety and radiation protection, significant events related to safety and radiation protection, measurements of effluents and their impact on the environment, warehoused wastes. Remarks and recommendations of the CHSCT are given

  5. Areva

    International Nuclear Information System (INIS)

    Areva and EDF have signed an important contract for the supply of enriched uranium on a long term basis. The contract amounts to 5 milliard euros and is for Areva the highest contract ever signed in this field of activities, this contract will be satisfied through the output of the future Georges-Besse-2 enrichment plant that is being built. Areva and Nuclear Power Corporation of India Limited (NPCIL) have signed a draft agreement for the construction of 2 EPR at least and their supply in nuclear fuel for all along their operating life. Siemens has announced its decision to withdraw from the capital of Areva-NP and has expressed its decision to create a new society dedicated to nuclear activities with the Russian public group Rosatom. Areva, Mitsubishi Heavy Industries Limited (MHI), Mitsubishi Materials Corporation (MMC) and Mitsubishi Corporation (MC) have signed a shareholder pact concerning the creation of a new society dedicated to the development, design, fabrication and trading of nuclear fuels. The capital of this new society, named Mitsubishi Nuclear Fuel Company is shared between MHI 35%, MMC 30%, Areva 30% and MC 5%. Areva has filed an application to the NRC (American Nuclear Regulatory Commission) for licensing the construction and operation of a uranium enrichment plant at Eagle Rock in Idaho. (A.C.)

  6. AREVA decommissioning strategy and programme

    International Nuclear Information System (INIS)

    As with any industrial installation, a nuclear facility has an operating life that requires accounting for its shutdown. In compliance with its sustainable development commitments, AREVA accounts this via its own decommissioning resources to value and make sites fit for further use. These capabilities guarantee the reversibility of the nuclear industry. Thus, the nuclear site value development constitutes an important activity for AREVA, which contributes to the acceptance of nuclear in line with the AREVA continuous policy of sustainable development which is to be fully responsible from the creation, during the operation, to the dismantling of its facilities in all respects with safety, local acceptance and environment. AREVA has already performed a large variety of operation during the life-time of its installations such as heavy maintenance, equipment replacement, upgrading operation. Nowadays, a completely different dimension is emerging with industrial decommissioning operations of nuclear fuel cycle installations: enrichment gaseous diffusion plant, fuel assembly plants, recycling and reprocessing facilities. These activities constitute a major know-how for AREVA. For this reason, the group decided, beginning of 2008, to gather 4 projects in one business unit called Nuclear Site Value Development - a reprocessing plant UP2 400 on AREVA La Hague site, a reprocessing plant UP1 on AREVA Marcoule site, a MOX fuel plant on Cadarache and 2 sites (SICN Veurey and Annecy) that handled GCR fuel fabrication). The main objectives are to enhance the feed back, to contribute to performance improvements, to value professionals and to put innovation forward. The following article will describe in a first part the main decommissioning programmes managed by AREVA NC Nuclear Site Value Development Business Unit. The second part will deal with strategic approaches. A more efficient organization with integration of the supply chain and innovation will be part of the main drivers

  7. Former radioactive waste storage sites: the case of the AREVA NC La Hague plant; Les anciens sites d'entreposage de dechets radioactifs: le cas de l'usine AREVA NC de La Hague

    Energy Technology Data Exchange (ETDEWEB)

    Houdre, Th. [Autorite de Surete Nucleaire, chef de la Division de Caen, 75 - Paris (France)

    2011-02-15

    Unlike AREVA NC's new UP2-800 and UP3 plants at La Hague, where the waste is conditioned in-line, the majority of waste produced while its first UP2-400 plant was still in service was stored without final packaging, at installations that no longer meet the safety requirements currently applicable. ASN believes that such storage facilities pose major safety problems. These problems are mainly related to the fact that little is known about the exact condition of certain storage facilities and the waste they contain, nor how they will evolve over time, as well as to former facility design and the inadequacy of early leak detection systems. Operations to recover this waste are technically complicated and require considerable resources and investment. As a result, the main issue as far as ASN is concerned is to ensure that the deadlines declared by AREVA are met, given that they are often dependent on the development of waste recovery procedures that do not as yet exist. For several years now, in view of the considerable delays affecting the majority of waste recovery projects, ASN has enforced the binding provisions set out under the TSN Act to set a schedule for the recovery of this old waste by prescribed dates. This situation serves to consolidate ASN's actions in requiring operators to assess, for all projects, the amount of waste generated, and to take measures for it to be processed and packaged as and when it is produced. (author)

  8. TAO2000 V2 computer-assisted force feedback tele-manipulators used as maintenance and production tools at the AREVA NC-La Hague fuel recycling plant

    International Nuclear Information System (INIS)

    During a 15-year joint research program, French Atomic Energy Agency Interactive Robotics Laboratory (CEA LIST) and AREVA have developed several remote operation devices, also called tele-robots. Some of them are now commonly used for maintenance operations at the AREVA NC (Nuclear Cycle) La Hague reprocessing plant. Since the first maintenance operation in 2005, several other successful interventions have been realized using the industrial MA23/RX170 tele-manipulation system. Moreover, since 2010, the through-the-wall tele-robot named MT200 TAO based on the slave arm of the MSM MT200 (La CalheneTM), has been evaluated in an active production cell at the AREVA NC La Hague fuel recycling plant. Although these evaluations are ongoing, the positive results obtained have led to an update and industrialization program. All these developments are based on the same generic control platform, called TAO2000 V2. TAO2000 V2 is the second release of the CEA LIST core software platform dedicated to computer aided force-feedback tele-operation (TAO is the French acronym for computer aided tele-operation). This paper presents all these developments resulting from the joint research program CEA LIST/AREVA. The TAO2000 V2 controller is first detailed, and then two maintenance operations using the industrial robot RX170 are presented: the removal of the nuclear fuel dissolver wheel rollers and the cleanup of the dissolver wheel inter-bucket spaces. Finally, the new MT200 TAO system and its evaluations at the AREVA NC La Hague facilities are discussed. (authors)

  9. Year 2005. GRNC's appreciation of the dose estimates presented in the annual environmental monitoring report of Areva-NC La Hague facility. Third GRNC viewpoint. Detailed report

    International Nuclear Information System (INIS)

    The 'Groupe Radioecologie Nord Cotentin' (GRNC) has carried out a very thorough evaluation of the assessment of doses due to discharges from the Cap de la Hague nuclear site carried out by Areva NC, the site operators. The group has looked at all aspects of the assessment methods and data to ensure that they agree with the results presented in the 2005 annual environmental report of the operator. The computer tool, ACADIE, developed to assess the doses, has been used by the GRNC members to carry out their own calculations. This document comprises the detailed report of the GRNC and its synthesis. The detailed report includes: 1 - critical analysis of the 2005 source term, the data transmitted by Areva NC (status of atmospheric effluents, status of liquid effluents at sea, fuel data, presentation of the work progress of the Areva NC working group), the history of liquid and gaseous effluents between 1966 and 2005; 2 - detailed comparison between model and 2005 measurements; 3 - detail of the 2005 efficient dose calculations. (J.S.)

  10. Global expertise of the ten-year environmental situation of AREVA N.C..2. part: environmental impact at the level of catchment basins and surveillance evaluation

    International Nuclear Information System (INIS)

    The second step of the expertise of the ten-year environmental assessment 1994-2003 of Areva NC allowed to complete the work on the themes and the sites that were not treated during the first step. The analysis concerned the impacts on the mine installations of the mine division of La Crouzille and more particularly of impacts observed since the sites refitting. The detail of this analysis and the results to which it allowed to achieve are the object of this present report. (N.C.)

  11. Year 2006. GRNC's appreciation of the dose estimates presented in the annual environmental monitoring report of Areva-NC La Hague facility. Forth GRNC viewpoint. Detailed report

    International Nuclear Information System (INIS)

    The 'Groupe Radioecologie Nord Cotentin' (GRNC) has carried out a very thorough evaluation of the assessment of doses due to discharges from the Cap de la Hague nuclear site carried out by Areva NC, the site operators. The group has looked at all aspects of the assessment methods and data to ensure that they agree with the results presented in the 2006 annual environmental report of the operator. The computer tool, ACADIE, developed to assess the doses, has been used by the GRNC members to carry out their own calculations. This document comprises the detailed report of the GRNC and its synthesis. The detailed report includes: 1 - a critical analysis of the 2006 source term; a note about the uranium content in liquid effluents; the data transmitted by Areva NC (status of atmospheric effluents, status of liquid effluents at sea, fuel data); the data transmitted by the IRSN - the French institute of radiation protection and nuclear safety (status of the radioactive effluents of Areva La Hague facility); the history of liquid and gaseous effluents between 1966 and 2006; 2 - detailed comparison between model and 2006 measurements; critical analysis of 14C and tritium data available for the Nord Cotentin and the English Channel area; 3 - detail of the 2006 efficient dose calculations; presentation of the environmental dispersion of tritium and of its effects on living organisms. (J.S.)

  12. Global expertise of the ten-year environmental assessment (1993-2004) of AREVA NC.3. part: reuse of deads in the public field

    International Nuclear Information System (INIS)

    The present document corresponds to the third and last phase of the global critical analysis of the ten-year environmental assessment. It has for objective to evaluate the knowledge on the conditions of reuse, in the public area, of deads coming from the sites of Limousin and to propose an exploratory analysis of conceivable actions to complete this knowledge in order to better identify the sectors and, or, the potentially risk uses. At this day, the knowledge on the transfer of deads and their use in the public field rests on the data recorded in a register implemented by Areva Nc from 1984. According to the transfers anterior to 1984, the situation of knowledge especially about the places of destination and purpose are poor. The analysis of Areva NC data allowed to I.R.S.N. to identify the areas of improvement of knowledge. The first one consists in achieving information concerning deads occurring before 1984. the second one aims to check that every use of deads in the 1984-1995 period are compatible with the exposure levels. (N.C.)

  13. Qualification of a laser cutting process for nuclear dismantling operations AREVA NC BU Valorisation - CEA/DPAD - IRSN/DSU/SERAC

    International Nuclear Information System (INIS)

    A major decommissioning project is under way on the Marcoule French Atomic Site (CEA) at the UP1 reprocessing plant where AREVA plays the role of prime contractor. Due to severe radiological levels on certain cells, these require remote operations. The cutting tools commonly used today are mainly mechanical such as grinders, saws and hydraulic shears. Nowadays, the feed-back shows that the implementation of these mechanical techniques: *?Is the main factor of mechanical failures of the remote arms. *?Requires a lot of spare parts (saw blades, discs...) The future cutting operations to be done in the UP1 reprocessing plant needs to be more industrial and productive. That is why CEA and AREVA NC are evaluating a new cutting process based on a laser set up on a remote arm. The laser cutting is already widely used in none nuclear environment and the goal is to evaluate if this thermal process may be used in nuclear installations with existing remote control arms. (authors)

  14. ITER at Cadarache; ITER a Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-06-15

    This public information document presents the ITER project (International Thermonuclear Experimental Reactor), the definition of the fusion, the international cooperation and the advantages of the project. It presents also the site of Cadarache, an appropriate scientifical and economical environment. The last part of the documentation recalls the historical aspect of the project and the today mobilization of all partners. (A.L.B.)

  15. Near-field krypton-85 measurements in stable meteorological conditions around the AREVA NC La Hague reprocessing plant: estimation of atmospheric transfer coefficients

    International Nuclear Information System (INIS)

    The aim of this work was to study the near-field dispersion of 85Kr around the nuclear fuel reprocessing plant at La Hague (AREVA NC La Hague – France) under stable meteorological conditions. Twenty-two 85Kr night-time experimental campaigns were carried out at distances of up to 4 km from the release source. Although the operational Gaussian models predict for these meteorological conditions a distance to plume touchdown of several kilometers, we almost systematically observed a marked ground signal at distances of 0.5–4 km. The calculated atmospheric transfer coefficients (ATC) show values (1) higher than those observed under neutral conditions, (2) much higher than those proposed by the operational models, and (3) higher than those used in the impact assessments. - Highlights: • Measurements of 85Kr in air around reprocessing plant. • Measurement in stable meteorological conditions. • Determination of Atmospheric Transfer Coefficients (ATC). • Comparison with operational models. • ATC in stable conditions are higher than data from models

  16. Radiation protection at the Cadarache research center

    International Nuclear Information System (INIS)

    This article recalls the French law about radiation protection and its evolution due to the implementation of the 2013/59-EURATOM directive that separates the missions of counsel from the more operative missions of the person appointed as 'competent in radiation protection'. The organisation of the radiation protection of the Cadarache research center is presented. The issue of sub-contracting and the respect of an adequate standard of radioprotection is detailed since 2 facilities operated by AREVA are being dismantled on the site. (A.C.)

  17. Report on transparency and nuclear safety - Cadarache CEA centre - 2012

    International Nuclear Information System (INIS)

    A first volume proposes a presentation of the Cadarache CEA centre, of its activities and installations, gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. It also reports significant events related to safety and to radiation protection which occurred in 2012 and have been declared to the ASN. It discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. It addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre, indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and on the environment. Nature and quantities of warehoused wastes are specified. The second volume concerns some specific installations (INB 32 or ATPu, and INB 54 or LPC) which belong to AREVA NC. The same topics are addressed: presentation of the facilities, arrangements regarding safety and radiation protection, significant events related to safety and radiation protection, measurements of effluents and their impact on the environment, warehoused wastes. Remarks and recommendations of the CHSCT are given

  18. ITER at Cadarache

    International Nuclear Information System (INIS)

    This public information document presents the ITER project (International Thermonuclear Experimental Reactor), the definition of the fusion, the international cooperation and the advantages of the project. It presents also the site of Cadarache, an appropriate scientifical and economical environment. The last part of the documentation recalls the historical aspect of the project and the today mobilization of all partners. (A.L.B.)

  19. Global expertise of the ten-year environmental situation of AREVA N.C.1. part: storage of Bellezane and environmental impact at the level of the Ritord catchment basin

    International Nuclear Information System (INIS)

    The first step of the expertise of the ten-year environmental assessment of Areva Nc was focused on the storage of mine residues of Bellezane and on the environmental impact of mine exploitation at the level of the Ritord watershed, these two aspects being appeared as a priority as regard to the different concerns and topical. The I.R.S.N. analysis consisted in checking that the impacts associated to the presence of residues are correctly controlled. The specificity of the storage system face to the water control rest on the capacity of water collect that have circulated at the residues contact and on their treatment before release. Concerning the exposure by emission in atmosphere, the characteristics of the roofing, particularly its thickness, allow to reduce significantly the residues contribution to the ambient gamma radiation and radon emission. The measured dose rate appear linked to the radiological content of deads themselves and rocks constituting the surrounding landscape. (N.C.)

  20. Applications of learning based systems at AREVA group

    International Nuclear Information System (INIS)

    As part of its work on advanced information systems, AREVA is exploring the use of computerized tools based on 'machine learning' techniques. Some of these studies are being carried out by EURIWARE - continuing on from previous work done by AREVA NC - focused on the supervision of complex systems. Systems based on machine learning techniques are one of the possible solutions being investigated by AREVA: knowing that the stakes are high and involve better anticipation and control and high financial considerations. (authors)

  1. Enforcement of control decree for radiation protection devices on the Cadarache center

    International Nuclear Information System (INIS)

    On the Cadarache center there are nearly 1800 mobile devices and 800 fixed. The periodic calibration checks are performed by type with the same sources on every installation of the Center. A commune methodology was developed by type of device. It is presented in the form of cards with a phasing of operations as a picture. (N.C.)

  2. Areva 2005 annual report

    International Nuclear Information System (INIS)

    This annual report contains information on AREVA's objectives, prospects and strategies, particularly in Chapters 4 and 7, as well as contains information on the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the annual report and persons responsible for auditing the financial statements; 2 - Information pertaining to the transaction; 3 - General information on the company and share capital: Information on AREVA, Information on share capital and voting rights, Investment certificate trading, Dividends, Organizational chart of the AREVA group, Equity interests, Shareholders' agreements; 4 - Information on company operations, 5 - New developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, AREVA group energy businesses, Front End Division, Reactors and Services Division, Back End Division, Transmission and Distribution Division, Major Contracts, The Group's principal sites, AREVA's customers and suppliers, Human resources, Sustainable Development and Continuous Improvement, Capital spending programs, Research and development, intellectual property and brand name programs, Risk and insurance; 6 - Assets - Financial position - financial performance: Analysis of and comments on the Group's financial position and performance, Human Resources report 2005, Environmental report, Consolidated financial statements, Notes to the consolidated financial statements, AREVA SA Financial statements 2005, Notes to the corporate financial statements; 7 - Corporate governance: Composition and functioning of administrative bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual General Meeting of Shareholders of May 2, 2006; 8 - Recent developments and outlook: Events subsequent to year-end closing for 2005, Outlook

  3. Areva, reference document 2006

    International Nuclear Information System (INIS)

    This reference document contains information on the AREVA group's objectives, prospects and development strategies, particularly in Chapters 4 and 7. It contains information on the markets, market shares and competitive position of the AREVA group. Content: - 1 Person responsible for the reference document and persons responsible for auditing the financial statements; - 2 Information pertaining to the transaction (Not applicable); - 3 General information on the company and its share capital: Information on AREVA, on share capital and voting rights, Investment certificate trading, Dividends, Organization chart of AREVA group companies, Equity interests, Shareholders' agreements; - 4 Information on company operations, new developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, The energy businesses of the AREVA group, Front End division, Reactors and Services division, Back End division, Transmission and Distribution division, Major contracts, The principal sites of the AREVA group, AREVA's customers and suppliers, Sustainable Development and Continuous Improvement, Capital spending programs, Research and development programs, intellectual property and trademarks, Risk and insurance; - 5 Assets - Financial position - Financial performance: Analysis of and comments on the group's financial position and performance, 2006 Human Resources Report, Environmental Report, Consolidated financial statements, Notes to the consolidated financial statements, AREVA SA financial statements, Notes to the corporate financial statements; 6 - Corporate Governance: Composition and functioning of corporate bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual Combined General Meeting of Shareholders of May 3, 2007; 7 - Recent developments and future prospects: Events subsequent to year-end closing for 2006, Outlook; 8 - Glossary; 9 - Table of concordance

  4. Areva, annual report 2004

    International Nuclear Information System (INIS)

    This annual report contains information on AREVA objectives, prospects and strategies, particularly in chapters 4 and 7. This information is a not meant as a presentation of past performance data and should not be interpreted as a guarantee that events or data set forth herein are assured or that objectives will be met. Forward looking statements made in this document also address known and unknown risks, uncertainties and other factors that could, were they to translate into fact, cause AREVA future financial performance, operating performance and production to differ significantly from the objectives presented or suggested herein. Those factors include, in particular, changes in international, economic or market conditions, as well as risk factors presented in Section 4.14.3. Neither AREVA nor the AREVA group is committing to updating forward looking statements or information contained in the annual report. This annual report contains information on the markets, market shares and competitive position of the AREVA group. Unless otherwise indicated, all historical data and forward looking information are based on Group estimates (source: AREVA) and are provided as examples only. To AREVA knowledge, no report is available on the AREVA group markets that is sufficiently complete or objective to serve as a sole reference source. The AREVA group developed estimates based on several sources, including in-house studies and reports, statistics provided by international organizations and professional associations, data published by competitors and information collected by AREVA subsidiaries. The main sources, studies and reports used include (i) the International Atomic Energy Agency (IAEA), the International Energy Agency (IEA), the World Nuclear Association (WNA), the Nuclear Energy Institute (NEA), Nuclear Assurance Corporation (NAC), the European Atomic Energy Community (Euratom) and the Commissariat a l'Energie Atomique (CEA) for the nuclear business; and (ii) the

  5. Areva, annual report 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This annual report contains information on AREVA objectives, prospects and strategies, particularly in chapters 4 and 7. This information is a not meant as a presentation of past performance data and should not be interpreted as a guarantee that events or data set forth herein are assured or that objectives will be met. Forward looking statements made in this document also address known and unknown risks, uncertainties and other factors that could, were they to translate into fact, cause AREVA future financial performance, operating performance and production to differ significantly from the objectives presented or suggested herein. Those factors include, in particular, changes in international, economic or market conditions, as well as risk factors presented in Section 4.14.3. Neither AREVA nor the AREVA group is committing to updating forward looking statements or information contained in the annual report. This annual report contains information on the markets, market shares and competitive position of the AREVA group. Unless otherwise indicated, all historical data and forward looking information are based on Group estimates (source: AREVA) and are provided as examples only. To AREVA knowledge, no report is available on the AREVA group markets that is sufficiently complete or objective to serve as a sole reference source. The AREVA group developed estimates based on several sources, including in-house studies and reports, statistics provided by international organizations and professional associations, data published by competitors and information collected by AREVA subsidiaries. The main sources, studies and reports used include (i) the International Atomic Energy Agency (IAEA), the International Energy Agency (IEA), the World Nuclear Association (WNA), the Nuclear Energy Institute (NEA), Nuclear Assurance Corporation (NAC), the European Atomic Energy Community (Euratom) and the Commissariat a l'Energie Atomique (CEA) for the nuclear business; and (ii

  6. AREVA group overview; Presentation du groupe AREVA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-02-08

    This document presents the Group Areva, a world nuclear industry leader, from a financial holding company to an industrial group, operating in two businesses: the nuclear energy and the components. The structure and the market of the group are discussed, as the financial assets. (A.L.B.)

  7. Areva reference document 2007

    International Nuclear Information System (INIS)

    This reference document contains information on the AREVA group's objectives, prospects and development strategies, particularly in Chapters 4 and 7. It contains also information on the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the reference document and persons responsible for auditing the financial statements; 2 - Information pertaining to the transaction (not applicable); 3 - General information on the company and its share capital: Information on Areva, Information on share capital and voting rights, Investment certificate trading, Dividends, Organization chart of AREVA group companies, Equity interests, Shareholders' agreements; 4 - Information on company operations, new developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, The energy businesses of the AREVA group, Front End division, Reactors and Services division, Back End division, Transmission and Distribution division, Major contracts 140 Principal sites of the AREVA group, AREVA's customers and suppliers, Sustainable Development and Continuous Improvement, Capital spending programs, Research and Development programs, Intellectual Property and Trademarks, Risk and insurance; 5 - Assets financial position financial performance: Analysis of and comments on the group's financial position and performance, Human Resources report, Environmental report, Consolidated financial statements 2007, Notes to the consolidated financial statements, Annual financial statements 2007, Notes to the corporate financial statements; 6 - Corporate governance: Composition and functioning of corporate bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual Ordinary General Meeting of Shareholders of April 17, 2008; 7 - Recent developments and future prospects: Events subsequent to year-end closing for 2007, Outlook; Glossary; table of concordance

  8. Energy. Saving 'Private' Areva

    International Nuclear Information System (INIS)

    While Areva keeps on loosing money (billions of euros for 2014), the saving of this company is at stake. Staff is already planned to be reduced in La Hague, and other staff reductions might occur after the failure of a previous strategic plan. Various activities could be sold (dismantling, mining). The article outlines the difficult relationships between Areva and EDF and the problems also faced by EDF. Some actors think that Areva should remain independent from EDF in order to be free to compete on international bidding. The rapprochement between these two companies is said to be necessary for the Ministry but seems very difficult to achieve

  9. Areva - 2011 Annual results

    International Nuclear Information System (INIS)

    Areva's backlog established at 45.6 billion euros at the end of 2011, significantly increasing at the end of a year marked by the Fukushima accident, confirms the commercial dynamism of the group alongside its customers and reinforces the visibility on its future business level. In a difficult context, the slight decline in revenue in 2011 demonstrates the robustness of Areva's integrated model, resting mainly on recurring business generated in relation to Areva's customers' nuclear installed base, and benefiting from the development of Areva's renewable energies operations. Free operating cash flow before tax, although down over the whole year in 2011, improved in the second half, showing the first effects of Areva's stronger focus on cash generation and debt management. After the success of Areva's bond issue in September 2011, the Group's liquidity remains high at the end of 2011. The Areva teams are now dedicating all of their efforts to the deployment of the 'Action 2016' strategic action plan, which had already yielded its first positive results at the end of 2011, with an improvement in the cost structure of Areva's operations, an increase in order intake, and the launch of several disposals of minority interests. Summary of the 2011 financial results: - Backlog: euro 45.6 bn, +3.1% vs. 2010, i.e +6.7% over 3 months; - Revenue: euro 8.872 bn, i.e -2.6% vs. 2010; - Operating income: - euro 1.923 bn; - Net income attributable to equity owners of the parent: - euro 2.424 bn; - EBITDA: euro 1.068 bn ( euro 420 m excluding Siemens impact); - Free operating cash flow before tax: - euro 2.397 bn (- euro 1.366 bn excluding Siemens impacts), improvement over the second half; - Decrease in net debt of euro 124 m for the year; - Significant drop in general and administrative expenses, with a noticeable reduction between the first and the second half; - Launch of several disposals of minority interests

  10. Remediation of Areva Miramas site - 59312

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: Objectives: The objectives of this project is to remediate the former facility by performing all operations useful and necessary enabling a final withdrawal of CEA and AREVA NC companies. The desired end state is a remediated site for a new industrial use Environmental Context: The various studies have demonstrated and confirmed the presence of soil contaminations. The types and ranges of pollution could clearly be attributed to different historical activities: metals; mercury and organic compounds. However, due to the different constraints (Mercury regulation, urban proximity, slick...) and to a particular sensitivity (AREVA operator, site located in a urban area), the project cannot be limited to the strict regulatory requirements Description of operations: The operations concerns the remediation of approximately 100 000 m3 of soil and the decommissioning of facilities. Soil remediation focuses on two major pollutants: mercury and organo-nitro compounds, located in areas well identified

  11. 2006 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It proposes a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation), for which the significant events occurred on the 19. of January and on the 6. of November 2006. For these installations, release measurements concern gaseous and liquid releases

  12. 2008 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It proposes a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation) for which significant events occurred on the 18. and on the 21. of November 2008. For these installations, release measurements concern gaseous and liquid releases

  13. 2007 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It provides a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. It reports the recommendations expressed by the CHSCT (committee on hygiene, security and working conditions) after the 2006 report. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation), for which the significant events occurred on the 13. of March and on the 25. of May 2007. For these installations, release measurements concern gaseous and liquid releases

  14. 2009 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety (safety organisation, general measures, measures related to various risks, inspections, control of emergency situations, audits and second level control, measures in basic nuclear installations) and radioprotection (organisation, significant facts, dosimeter results). It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of measurements of releases and of their impact on the environment (chemical and radiological assessment). Then after a description of measures to limit the volume of stored radioactive wastes and their impact on health and on the environment, tables indicate the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation) for which a significant event occurred on the 6 October 2009. For these installations, release measurements concern gaseous and liquid releases

  15. Areva in 2006

    International Nuclear Information System (INIS)

    This document is the 2006 activity report of the Areva group and presents the 2006 highlights of the nuclear division (front end of the nuclear cycle, pressurized water reactors, treatment and recycling of used nuclear fuel) and of the Transmission and Distribution division. Content: Message from the Chairman of the Supervisory Board; Message from the Chief Executive Officer; the World in 2006; Areva 2006 highlights; business review; key data; Areva around the World; policy of continuous innovation; five years of sustainable development; governance; Continuous improvement; Financial performance; Innovation; Customer satisfaction; Commitment to employees; Environmental protection; Risk management and prevention; Dialogue and consensus building; Community involvement; corporate governance; organization of the group; Share information and shareholder relations; glossary; learn more

  16. Areva: 2014 annual results

    International Nuclear Information System (INIS)

    The scale of the net loss for 2014 illustrates the twofold challenge confronting AREVA: continuing stagnation of the nuclear operations, lack of competitiveness and difficulties in managing the risks inherent in large projects. The group understands how serious this situation is. A comprehensive strategic review of operations was undertaken beginning in November 2014 and is being carried out without compromise. As a result, AREVA is now able to announce a solid transformation plan that sets a challenging but economically realistic course for its teams. First, AREVA will refocus on its core business: mastery of key nuclear processes essential to operators around the globe. This strategic redeployment will lead to the revision of certain goals, whether in the management of new reactor projects or in renewable energies. AREVA's objective is to achieve excellence as a high value-added supplier of products and services. Secondly, AREVA, whose resources had been marshaled to support a spurt of growth in nuclear power, must now adapt to new market realities and become competitive once again. The group's most urgent task is recovery and securing its future by immediately launching a far-reaching competitiveness plan founded on organizational simplification, quality of operations, and a completely revamped approach to managing risk in large projects. Last but not least, AREVA must ensure sustainable financing for its activities. A financing plan will be clarified before publication of the half-year financial statements. This document presents the key financial data of the group, its strategic road-map and its operating and financing plans

  17. Areva: experiences in outage services

    International Nuclear Information System (INIS)

    As the world leader in the nuclear industry, Areva is firmly committed to the safe and reliable operation of the Spanish nuclear power plants. Following this commitment, Areva has established the subsidiary Areva NP Services Spain as a local platform to provide nuclear services for the Spanish nuclear power plants. being integrated and supported by the global Areva Group, Areva NP Services Spain is able to offer services solutions to all customers demands while maintaining close and sustainable relationships with them. This integration also allows the Spanish personnel of Areva to employ their skills by working in multinational teams in international projects. This article will present the capacities, and the most important recent national and international project performed by Areva NP Services Spain in the field of outage services. (Author)

  18. AREVA group overview

    International Nuclear Information System (INIS)

    This document presents the Group Areva, a world nuclear industry leader, from a financial holding company to an industrial group, operating in two businesses: the nuclear energy and the components. The structure and the market of the group are discussed, as the financial assets. (A.L.B.)

  19. The 2003 essential. AREVA

    International Nuclear Information System (INIS)

    This document presents the essential activities of the Areva Group, a world nuclear industry leader. This group proposes technological solutions to produce the nuclear energy and to transport the electric power. It develops connection systems for the telecommunication, the computers and the automotive industry. Key data on the program management, the sustainable development activities and the different divisions are provided. (A.L.B.)

  20. AREVA in India

    International Nuclear Information System (INIS)

    India is the sixth largest energy consumer in the world and its demand is rising rapidly. To support its economic growth, estimated to be 8% on average over the last three years and to ensure access to electricity for all, the country foresees massive investments in its power sector over the next five years. India is therefore an essential market for the AREVA Group, where its Transmission and Distribution division plays a leading role on the strategic grid modernization market. This document presents: 1 - the economic situation in India: Key figures, Growth, India's growing need for electricity, India's energy sources and policy: current mix, driving role of the State, the financial reorganization of the SEBs, the 'Mega-Power' projects, the electricity act, the rural electrification program, the Investments. 2 - Civil nuclear energy: a strong potential for development; 3 - India's transmission and distribution network: the power challenge of the transmission network, the efficiency challenge of the distribution network. 4 - AREVA T and D in India: AREVA T and D profile, Areva's presence in India, market share, T and D customers and flagship projects

  1. AREVA 2009 reference document

    International Nuclear Information System (INIS)

    This Reference Document contains information on the AREVA group's objectives, prospects and development strategies. It contains information on the markets, market shares and competitive position of the AREVA group. This information provides an adequate picture of the size of these markets and of the AREVA group's competitive position. Content: 1 - Person responsible for the Reference Document and Attestation by the person responsible for the Reference Document; 2 - Statutory and Deputy Auditors; 3 - Selected financial information; 4 - Risks: Risk management and coverage, Legal risk, Industrial and environmental risk, Operating risk, Risk related to major projects, Liquidity and market risk, Other risk; 5 - Information about the issuer: History and development, Investments; 6 - Business overview: Markets for nuclear power and renewable energies, AREVA customers and suppliers, Overview and strategy of the group, Business divisions, Discontinued operations: AREVA Transmission and Distribution; 7 - Organizational structure; 8 - Property, plant and equipment: Principal sites of the AREVA group, Environmental issues that may affect the issuer's; 9 - Analysis of and comments on the group's financial position and performance: Overview, Financial position, Cash flow, Statement of financial position, Events subsequent to year-end closing for 2009; 10 - Capital Resources; 11 - Research and development programs, patents and licenses; 12 -trend information: Current situation, Financial objectives; 13 - Profit forecasts or estimates; 14 - Administrative, management and supervisory bodies and senior management; 15 - Compensation and benefits; 16 - Functioning of corporate bodies; 17 - Employees; 18 - Principal shareholders; 19 - Transactions with related parties: French state, CEA, EDF group; 20 - Financial information concerning assets, financial positions and financial performance; 21 - Additional information: Share capital, Certificate of incorporation and by-laws; 22 - Major

  2. AREVA in China

    International Nuclear Information System (INIS)

    China has a great need for secure, safe, and economic energy supplies that combat the greenhouse effect and global warming. Since January 2002, China, the most heavily populated country with more than 1.3 billion inhabitants in a territory of 9.5 million km2 (17 times larger than France), has a nuclear capacity of 9 GWe with 11 nuclear plants on line. Forecasts of electricity consumption report a need for 900 to 1,000 GWe per year through 2020, and at this time the country's objective is to increase nuclear generated electricity from 1% to 4% of its total output. This means a need for additional 30 GWe, which is the equivalent of twenty 1,500 MWe reactors. In addition to nuclear power, China is pushing renewable energy. With the passage of the 2005 Renewable Energy Law, China's government imposed a national renewable energy requirement that is expected to boost the use of renewable energy capacity from 10 to 12 percent by 2020, up from 3% in 2003. This law requires power operators to buy electricity from alternative energy providers and gives economic incentives to these providers. Consequently, China is expanding its interests in renewable energy sources including wind and bio-energies, among others. It is in this context that AREVA, a world expert in energy, creates and offers solutions to generate, transmit, and distribute electricity for China. Based on its long experience and global presence, AREVA has become the worldwide leader for nuclear energy in the areas of construction, equipment, and services for nuclear power plants, and for the whole nuclear fuel cycle. AREVA is also a world leader in electrical power-grid equipment and systems. This document presents: China's need for energy; the Sources of China's energy mix; the challenges of China's nuclear program; AREVA's action in supporting China's ambitious nuclear program; the strong opportunities in renewable energy; and the high potential market for AREVA's T and D Division

  3. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    A reasonable assumption for the estimated new build market for the next 25 years is over 340 GWe net. The number of prospect countries is growing almost each day. To address this new build market, AREVA is developing a comprehensive portfolio of reactors intended to meet a wide range of power requirements and of technology choices. The EPR reactor is the flagship of the fleet. Intended for large power requirements, the four first EPRs are being built in Finland, France and China. Other countries and customers are in view, citing just two examples: the Usa where the U.S. EPR has been selected as the technology of choice by several U.S utilities; and the United Kingdom where the Generic Design Acceptance process of the EPR design submitted by AREVA and EDF is well under way, and where there is a strong will to have a plant on line in 2017. For medium power ranges, the AREVA portfolio includes a boiling water reactor and a pressurized water reactor which both offer all of the advantages of an advanced plant design, with excellent safety performance and competitive power generation cost: -) KERENA (1250+ MWe), developed in collaboration with several European utilities, and in particular with Eon; -) ATMEA 1 (1100+ MWe), a 3-loop evolutionary PWR which is being developed by AREVA and Mitsubishi. AREVA is also preparing the future and is deeply involved into Gen IV concepts. It has developed the ANTARES modular HTR reactor (pre-conceptual design completed) and is building upon its vast Sodium Fast Reactor experience to take part into the development of the next prototype. (author)

  4. Continuously tritium monitoring of the pipe of liquid effluents at the Cea Cadarache; Controle en continu du tritium de la conduite des effluents liquides du CEA Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    Pira, Y

    2004-07-01

    This report is oriented toward the radiation protection of environment that is an essential component of radiation protection. It is necessary to detect any solid, liquid or gaseous abnormal release and to find its origin. The present study bears on a detection instrument in continuously to find tritium in liquid effluents of the Cea Cadarache. After having study the functioning principle of this device, an evaluation of its performances has been realised ( back noise, yield, detection limit) and to a checking in real conditions of utilization. (N.C.)

  5. The Areva Group

    International Nuclear Information System (INIS)

    This document provides information on the Areva Group, a world nuclear industry leader, offering solutions for nuclear power generation, electricity transmission and distribution and interconnect systems to the telecommunications, computer and automotive markets. It presents successively the front end division including the group business lines involved in producing nuclear fuel for electric power generation (uranium mining, concentration, conversion and enrichment and nuclear fuel fabrication); the reactors and services division which designs and builds PWR, BWR and research reactors; the back end division which encompasses the management of the fuel that has been used in nuclear power plants; the transmission and distribution division which provides products, systems and services to the medium and high voltage energy markets; the connectors division which designs and manufactures electrical, electronic and optical connectors, flexible micro circuitry and interconnection systems. Areva is implemented in Europe, north and south america, africa and asia-pacific. (A.L.B.)

  6. AREVA fatigue concept

    International Nuclear Information System (INIS)

    Modern state-of-the-art fatigue monitoring approaches gain in importance as part of the ageing management of nuclear power plant components. Consequently, lots of operators have to deal with demanding security requirements to ensure the safe operation of power plants. AREVA disposes of a long tradition in the development of fatigue and structural health monitoring solutions. Nuclear power plant applications require the qualified assessment of measured thermo-mechanical loads. The core challenge is the identification and qualified processing of realistic load-time histories. The related methodological requirements will be explained in detail within this contribution. In terms of the nuclear industry, the ageing management of power plant components is nowadays a main issue for all actors: states, regulatory agencies, operators, designers or suppliants. As regards fatigue assessment of nuclear components stringent safety standards imply the consideration of new parameters in the framework of the fatigue analysis process: new design fatigue curves, consideration of environmental fatigue (EAF) parameters and stratification effects. In this general context AREVA developed the integral approach AREVA Fatigue Concept (AFC) with new tools and methods in order to live up to operators’ expectations: Simplified Fatigue Estimation (SFE), Fast Fatigue Evaluation (FFE) and Detailed Fatigue Check (DFC). Based on real measured thermal loads (FAMOSi Local Measurements) and superposed mechanical loads the Fast Fatigue Evaluation (FFE) process allows a highly automated and reliable data processing to evaluate cumulative usage factors of mechanical components. Calculation and management of results are performed within the software frontend FAMOSi, thus impact of operating cycles on components in terms of stress and fatigue usage can be taken into account in order to plan optimized decisions relating to the plant operation or maintenance activities. The paper mainly describes the

  7. Areva, reference document 2006; Areva, document de reference 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This reference document contains information on the AREVA group's objectives, prospects and development strategies, particularly in Chapters 4 and 7. It contains information on the markets, market shares and competitive position of the AREVA group. Content: - 1 Person responsible for the reference document and persons responsible for auditing the financial statements; - 2 Information pertaining to the transaction (Not applicable); - 3 General information on the company and its share capital: Information on AREVA, on share capital and voting rights, Investment certificate trading, Dividends, Organization chart of AREVA group companies, Equity interests, Shareholders' agreements; - 4 Information on company operations, new developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, The energy businesses of the AREVA group, Front End division, Reactors and Services division, Back End division, Transmission and Distribution division, Major contracts, The principal sites of the AREVA group, AREVA's customers and suppliers, Sustainable Development and Continuous Improvement, Capital spending programs, Research and development programs, intellectual property and trademarks, Risk and insurance; - 5 Assets - Financial position - Financial performance: Analysis of and comments on the group's financial position and performance, 2006 Human Resources Report, Environmental Report, Consolidated financial statements, Notes to the consolidated financial statements, AREVA SA financial statements, Notes to the corporate financial statements; 6 - Corporate Governance: Composition and functioning of corporate bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual Combined General Meeting of Shareholders of May 3, 2007; 7 - Recent developments and future prospects: Events subsequent to year-end closing for 2006, Outlook; 8 - Glossary; 9 - Table of concordance.

  8. Enriched uranium workshops towards decommissioning CEA Cadarache

    International Nuclear Information System (INIS)

    The author presents the post operational clean-out following the shut down of the ATUE nuclear facility implemented in the Cadarache research Center (France) and preceding the dismantling operations. ATUE was constructed in 1965, in the support of the fuel cycle industry, to develop the dry process of UF6 to UO2 conversion and the wet process with step of nitric acid solution, solvent purification by exchange columns, ammonium precipitation and hydrogen reduction. The dismantling organization, methods and technology are also presented and discussed. In a last part the author highlights some important points of the project. (A.L.B.)

  9. Remote Participation at JET from DRFC Cadarache

    International Nuclear Information System (INIS)

    The DRFC at the CEA/Cadarache has participated in the EFDA-JET Programme via the Task Agreement for Profile Control Studies in 1999 and via the EFDA-JET agreement in 2000. Several physicists have been seconded to Culham to work JET and many others have participated in the program 'at distance'. This task has necessitated careful consideration of working methods, often with 'ad-hoc' remote working solutions, but has led to a clear identification of the technical needs for Remote Participation (RP) for the new European Fusion Development Agreement (EFDA). We have contributed substantial input into the working groups evaluating the technical needs of RP

  10. Cadarache - 20 years of plutonium fuels

    International Nuclear Information System (INIS)

    The qualitative and quantitative evolution of plutonium used is reviewed; more particularly, the isotopic composition of plutonium handled at the plutonium fuel fabrication plant of Cadarache has been considerably changing during these 20 last years. The evolution of fast neutron reactor fuel assemblies explains why the fabrication unit has to. The installations have been modified, as also the fuel assembly fabrication process. Changes can be classified in 3 categories: the transformations related to mass evolution, those related more particularly to the plutonium isotopic composition, finally those related to the waste treatment process. These transformations concerned workshops, apparatus and equipments, the reinforcement of protections, criticality accident prevention, and safeguards

  11. AREVA annual results 2009

    International Nuclear Information System (INIS)

    AREVA expanded its backlog and increased its revenues compared with 2008, on strong installed base business and dynamic major projects, fostering growth in operating income of 240 million euros. As announced previously, Areva is implementing a financing plan suited to its objectives of profitable growth. The plan was implemented successfully in 2009, including the conclusion of an agreement, under very satisfactory terms, to sell its Transmission and Distribution business for 4 billion euros, asset sales for more than 1.5 billion euros, and successful bond issues of 3 billion euros. The plan will continue in 2010 with a capital increase, the completion of asset disposals and cost reduction and continued operational performance improvement programs. Areva bolstered its Renewable Energies business segment by supplementing its offshore wind power and biomass businesses with the acquisition of Ausra, a California-based leader in concentrated solar power technology. Despite the sale of T and D, Areva is maintaining its financial performance outlook for 2012: 12% average annual revenue growth to 12 billion euros in 2012, double digit operating margin and substantially positive free operating cash flow. Annual results 2009: - For the group as a whole, including Transmission and Distribution: Backlog: euros 49.4 bn (+2.5%), Revenues: euros 14 bn (+6.4%), Operating income: euros 501 m (+20.1%); - Nuclear and Renewable Energies perimeter: Backlog: euros 43.3 bn (+1.8%), Strong revenue growth: +5.4% to euros 8.5 bn, Operating income before provision for the Finnish project in the first half of 2009: euros 647 m, Operating income: euros 97 m, for a euros 240 m increase from 2008; - Net income attributable to equity holders of the parent: euros 552 m, i.e. euros 15.59 per share; - Net debt: euros 6,193 m; - Pro-forma net debt, including net cash to be received from the sale of T and D in 2010: euros 3,022 m; - Dividend of euros 7.06 per share to be proposed during the Annual

  12. Areva in Niger

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-02-01

    Niger is the second poorest country in the world but it has natural resources underground in the form of uranium ores deposits. This uranium is currently mined by two companies incorporated under Nigerian law: Somair and Cominak, operated by the principal shareholder Areva (through its subsidiary Cogema). After a presentation of Somair and Cominak key figures, this document details the working conditions and radiological protection, the environmentally friendly operations, the production traceability, the local economic development, the strengthening of the health care system and the development of the infrastructure. (A.L.B.)

  13. Areva in Niger

    International Nuclear Information System (INIS)

    Niger is the second poorest country in the world but it has natural resources underground in the form of uranium ores deposits. This uranium is currently mined by two companies incorporated under Nigerian law: Somair and Cominak, operated by the principal shareholder Areva (through its subsidiary Cogema). After a presentation of Somair and Cominak key figures, this document details the working conditions and radiological protection, the environmentally friendly operations, the production traceability, the local economic development, the strengthening of the health care system and the development of the infrastructure. (A.L.B.)

  14. Areva reference document 2007; Areva document de reference 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This reference document contains information on the AREVA group's objectives, prospects and development strategies, particularly in Chapters 4 and 7. It contains also information on the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the reference document and persons responsible for auditing the financial statements; 2 - Information pertaining to the transaction (not applicable); 3 - General information on the company and its share capital: Information on Areva, Information on share capital and voting rights, Investment certificate trading, Dividends, Organization chart of AREVA group companies, Equity interests, Shareholders' agreements; 4 - Information on company operations, new developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, The energy businesses of the AREVA group, Front End division, Reactors and Services division, Back End division, Transmission and Distribution division, Major contracts 140 Principal sites of the AREVA group, AREVA's customers and suppliers, Sustainable Development and Continuous Improvement, Capital spending programs, Research and Development programs, Intellectual Property and Trademarks, Risk and insurance; 5 - Assets financial position financial performance: Analysis of and comments on the group's financial position and performance, Human Resources report, Environmental report, Consolidated financial statements 2007, Notes to the consolidated financial statements, Annual financial statements 2007, Notes to the corporate financial statements; 6 - Corporate governance: Composition and functioning of corporate bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual Ordinary General Meeting of Shareholders of April 17, 2008; 7 - Recent developments and future prospects: Events subsequent to year-end closing for 2007, Outlook; Glossary; table of

  15. Areva 2005 annual report; Areva rapport annuel 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This annual report contains information on AREVA's objectives, prospects and strategies, particularly in Chapters 4 and 7, as well as contains information on the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the annual report and persons responsible for auditing the financial statements; 2 - Information pertaining to the transaction; 3 - General information on the company and share capital: Information on AREVA, Information on share capital and voting rights, Investment certificate trading, Dividends, Organizational chart of the AREVA group, Equity interests, Shareholders' agreements; 4 - Information on company operations, 5 - New developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, AREVA group energy businesses, Front End Division, Reactors and Services Division, Back End Division, Transmission and Distribution Division, Major Contracts, The Group's principal sites, AREVA's customers and suppliers, Human resources, Sustainable Development and Continuous Improvement, Capital spending programs, Research and development, intellectual property and brand name programs, Risk and insurance; 6 - Assets - Financial position - financial performance: Analysis of and comments on the Group's financial position and performance, Human Resources report 2005, Environmental report, Consolidated financial statements, Notes to the consolidated financial statements, AREVA SA Financial statements 2005, Notes to the corporate financial statements; 7 - Corporate governance: Composition and functioning of administrative bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual General Meeting of Shareholders of May 2, 2006; 8 - Recent developments and outlook: Events subsequent to year-end closing for 2005, Outlook.

  16. AREVA 2010 Reference document

    International Nuclear Information System (INIS)

    After a presentation of the person responsible for this document, and of statutory auditors, this report proposes some selected financial information. Then, it addresses, presents and comments the different risk factors: risk management and coverage, legal risk, industrial and environmental risk, operational risk, risks related to major projects, liquidity and market risk, and other risk. Then, after a presentation of the issuer, it proposes a business overview (markets for nuclear and renewable energies, AREVA customers and suppliers, strategy, activities), a presentation of the organizational structure, a presentation of AREVA properties, plants and equipment (sites, environmental issues), an analysis and comment of the group's financial position and performance, a presentation of its capital resources, an overview of its research and development activities, programs, patents and licenses. It indicates profit forecast and estimates, presents the administrative, management and supervisory bodies, and compensation and benefits amounts, reports of the functioning of corporate bodies. It describes the human resource company policy, indicates the main shareholders and transactions with related parties. It proposes financial information concerning assets, financial positions and financial performance. This document contains its French and its English versions

  17. AREVA - 2013 Reference document

    International Nuclear Information System (INIS)

    This Reference Document contains information on the AREVA group's objectives, prospects and development strategies, as well as estimates of the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the Reference Document; 2 - Statutory auditors; 3 - Selected financial information; 4 - Description of major risks confronting the company; 5 - Information about the issuer; 6 - Business overview; 7 - Organizational structure; 8 - Property, plant and equipment; 9 - Situation and activities of the company and its subsidiaries; 10 - Capital resources; 11 - Research and development programs, patents and licenses; 12 - Trend information; 13 - Profit forecasts or estimates; 14 - Management and supervisory bodies; 15 - Compensation and benefits; 16 - Functioning of the management and supervisory bodies; 17 - Human resources information; 18 - Principal shareholders; 19 - Transactions with related parties; 20 - Financial information concerning assets, financial positions and financial performance; 21 - Additional information; 22 - Major contracts; 23 - Third party information, statements by experts and declarations of interest; 24 - Documents on display; 25 - Information on holdings; Appendix 1: report of the supervisory board chairman on the preparation and organization of the board's activities and internal control procedures; Appendix 2: statutory auditors' reports; Appendix 3: environmental report; Appendix 4: non-financial reporting methodology and independent third-party report on social, environmental and societal data; Appendix 5: ordinary and extraordinary general shareholders' meeting; Appendix 6: values charter; Appendix 7: table of concordance of the management report; glossaries

  18. AREVA 2010 annual results

    International Nuclear Information System (INIS)

    Areva's 44-billion euro backlog at the end of 2010 gives the group excellent visibility, enabling it to confirm its outlook for 2012: 12 billion euros in revenue, double-digit operating margin and significantly positive free operating cash flow. Revenue rose by 575 million euros in 2010, or 6.7%, in comparison to 2009 and operating income excluding particular items improved by 201 million euros, nearly 2 points of revenue. In the past two years, Areva has raised 7.1 billion euros and secured its liquidity to ensure its development. In 2011, Areva is going to simplify the group's capital structure by listing ordinary shares of AREVA. At that time, the group may launch the employee share-holding plan, something it has ardently sought for several years as a way for its employees to share in AREVA's growth. The consolidated backlog stood at 44.204 billion euros at December 31, 2010, up 2.0% compared with that at December 31, 2009. The group's consolidated revenue came to 9.104 billion euros in 2010, up 6.7% on a reported basis and 5.1% like-for-like compared with 2009. Excluding particular items, operating income rose by 1.9 point, going from 3.9% in 2009 to 5.8% in 2010, giving operating income of 532 million euros (331 million euros in 2009). Net income attributable to equity owners of the parent came to 883 million euros in 2010, an increase of 331 million euros compared with 2009. Operating cash flow before capex was 923 million euros, an increase of 548 million euros compared with 2009, when it was 375 million euros, due to the visible improvement in EBITDA and working capital requirement. The change in gross capex (excluding acquisitions) from 1.780 billion euros in 2009 to 1.966 billion euros in 2010 is due to the ramp-up of construction programs, particularly in Enrichment. In 2010, almost 60% of the group's capital spending was on sites in France. The acquisitions made in Renewable Energies in 2010 in the amount of 210 million euros (100% of Ausra and the

  19. Areva - 2011 Reference document

    International Nuclear Information System (INIS)

    After having indicated the person responsible of this document and the legal account auditors, and provided some financial information, this document gives an overview of the different risk factors existing in the company: law risks, industrial and environmental risks, operational risks, risks related to large projects, market and liquidity risks. Then, after having recalled the history and evolution of the company and the evolution of its investments over the last five years, it proposes an overview of Areva's activities on the markets of nuclear energy and renewable energies, of its clients and suppliers, of its strategy, of the activities of its different departments. Other information are provided: company's flow chart, estate properties (plants, equipment), an analysis of its financial situation, its research and development policy, the present context, profit previsions or estimations, management organization and operation

  20. The Cadarache 1 MV porcelain SINGAP bushing

    International Nuclear Information System (INIS)

    The 1 MV bushing is considered as one of the most technically challenging components of the ITER neutral beam injectors, necessitating the design and manufacture of large ceramic insulators beyond the range of current industrial production. The ITER radiation environment and the fact that the bushing forms part of the tritium barrier demand a component of great reliability and safety. An R and D task has been launched for the fabrication of a prototype bushing based on the SINgle GAP, SINGle APerture (SINGAP) 1 MeV accelerator being developed in the EU. We present the design of this prototype, which is to be tested at Cadarache, and compare it with the SINGAP bushing proposed for the ITER injectors

  1. Nuclear. Areva, a French fission

    International Nuclear Information System (INIS)

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

  2. Report transparency and nuclear safety 2007 CEA Cadarache; Rapport transparence et securite nucleaire 2007 CEA Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

  3. AREVA: Growing Engineers through Education

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Liz [AREVA Inc, 3315 Old Forest Road, 24501 Lynchburg - Virginia (United States)

    2008-07-01

    The demand for engineers is of global proportions, and the need for engineers at AREVA has never been greater. The availability of qualified resources is of strategic concern to the company as it meets the energy challenges of the 21. century. The nuclear energy company will require up to 800 additional engineers by 2011 to support the growth of the business, especially in the area of new nuclear plants. Competition for college graduates at engineering schools is intense and talented students are moving away from central Virginia to pursue degrees at engineering universities. The cost to recruit new engineers from other areas is increasing. In response to these challenges, AREVA and area businesses, the University of Virginia (U.Va.) and the Central Virginia Community College (CVCC) have formed a partnership to provide undergraduate engineering education at the two-year college in Lynchburg. The program allows students to earn an engineering associate's degree at CVCC and then complete their bachelor of science through U.Va.'s School of Engineering and Applied Science. Students can earn a prestigious engineering degree from U.Va. while still in Lynchburg. Nearly 150 students are in the program, including 50 AREVA employees. Flexible courses are arranged for AREVA employees who work at nuclear power plants during outages. AREVA also sponsors interns who learn on the job in close mentor-ships with engineers while studying engineering. These students have the advantage of getting to know AREVA and can work effectively part time during studies and immediately upon graduation as an engineer. Students with family ties prefer to stay in central Virginia, and the strong bonds they form with AREVA during their studies increase loyalty to the company. AREVA is 'Growing Its Own Engineers' starting in middle and high school and through this unique college program in order to meet tomorrow's demand for resources. (author)

  4. AREVA: Growing Engineers through Education

    International Nuclear Information System (INIS)

    The demand for engineers is of global proportions, and the need for engineers at AREVA has never been greater. The availability of qualified resources is of strategic concern to the company as it meets the energy challenges of the 21. century. The nuclear energy company will require up to 800 additional engineers by 2011 to support the growth of the business, especially in the area of new nuclear plants. Competition for college graduates at engineering schools is intense and talented students are moving away from central Virginia to pursue degrees at engineering universities. The cost to recruit new engineers from other areas is increasing. In response to these challenges, AREVA and area businesses, the University of Virginia (U.Va.) and the Central Virginia Community College (CVCC) have formed a partnership to provide undergraduate engineering education at the two-year college in Lynchburg. The program allows students to earn an engineering associate's degree at CVCC and then complete their bachelor of science through U.Va.'s School of Engineering and Applied Science. Students can earn a prestigious engineering degree from U.Va. while still in Lynchburg. Nearly 150 students are in the program, including 50 AREVA employees. Flexible courses are arranged for AREVA employees who work at nuclear power plants during outages. AREVA also sponsors interns who learn on the job in close mentor-ships with engineers while studying engineering. These students have the advantage of getting to know AREVA and can work effectively part time during studies and immediately upon graduation as an engineer. Students with family ties prefer to stay in central Virginia, and the strong bonds they form with AREVA during their studies increase loyalty to the company. AREVA is 'Growing Its Own Engineers' starting in middle and high school and through this unique college program in order to meet tomorrow's demand for resources. (author)

  5. Areva and Energy Constellation create a commune society to launch the EPR in Usa

    International Nuclear Information System (INIS)

    The Group Areva and Constellation energy have announced the creation of a society, Unistar Nuclear to launch the first park of new generation type reactor. The american group Bechtel Power Company will help their union by bringing its expertise in building. (N.C.)

  6. TJ-II operation tracking from Cadarache

    International Nuclear Information System (INIS)

    The TJ-II remote participation system was designed to follow the TJ-II discharge production, even allowing the physicist in charge of operation to be in a remote location. The system has been based on both web servers and Java technology. These elements were chosen due to its open character, security properties, platform independence and technological maturity. Web pages and Java applications permit users to access experimental systems, data servers and the operation logbook. Security resources are provided by the PAPI system, a distributed authentication and authorization system. The TJ-II remote participation tools have allowed us to command and follow the stellarator operation from Cadarache. Over 1,000 digitizer channels and more than 20 diagnostic control systems were remotely available from web pages for monitoring/programming purposes. One Java application provided on-line information about the acquisition status of channels and acquisition cards. A second Java application showed temporal evolution signals that were refreshed in an automated way on the screen after each shot. A third Java application provided access to the operation logbook. In addition to these tools, we used the VRVS video conferencing system (FUSION community, X-Point room) and the EFDA Messenger Service for instant messaging (Jabber client). (Author)

  7. TJ-II operation tracking from Cadarache

    International Nuclear Information System (INIS)

    The TJ-II remote participation system was designed to follow the TJ-II discharge production, even allowing the physicist in charge of operation to be in a remote location. The system has been based on both web servers and Java technology. These elements were chosen due to its open character, security properties, platform independency and technological maturity. Web pages and Java applications permit users to access experimental systems, data servers and the operation logbook. Security resources are provided by the PAPI system, a distributed authentication and authorization system. The TJ-II remote participation tools have allowed us to command and follow the stellarator operation from Cadarache. Over 1,000 digitizer channels and more than 20 diagnostic control systems were remotely available from web pages for monitoring/programming purposes. One Java application provided on-line information about the acquisition status of channels and acquisition cards. A second Java application showed temporal evolution signals that were refreshed in an automated way on the screen after each shot. A third Java application provided access to the operation logbook. In addition to these tools, we used the VRVS videoconferencing system (FUSION community, X-Point room) and the EFDA Messenger Service for instant messaging (Jabber client). (author)

  8. AREVA in Mongolia - Press kit

    International Nuclear Information System (INIS)

    Mongolia is going through a crucial period in its history and setting up a strategic policy for uranium. The choices that are being made will affect the country and its future. Mongolia, since the mid-2000's, has benefited from significant mining development that has nourished the strong growth of the country. The giant Oyu Tolgoi (gold and copper) and Tavan Tolgoi (coal) deposits are the symbols of this mining potential. Uranium in particular has a major strategic role. The exploration programmes have revealed the presence of exploitable resources. On 26 February 2013, the Professional Council of Mineral Resources with the Ministry of Mines officially classified the Zoovch Ovoo deposit's with more than 50 000 tons of uranium. Following classification of the deposit of Dulaan Uul in 2011, the Zoovch Ovoo classification makes Mongolia officially one of the top 10 countries with the largest uranium resources. Mongolia has set about making the uranium industry a centrepiece of its strategy and its policy of independence. This new approach is founded in the Nuclear Energy Act adopted in the summer of 2009. The Mongolian State wants to create a uranium industry that makes Mongolia a nuclear fuel supplier for the Asian market. The choice of partners with whom the country associates to mine the uranium deposits is therefore important. Agreements have notably entered into with France, through AREVA which is a public company, as well as with Russia, China, Japan and India. AREVA has been present in Mongolia since 1997. AREVA is today represented in Mongolia by AREVA Mongol, its 100% subsidiary. AREVA Mongol carries out its exploration activities through Cogegobi and will manage its mining licences through AREVA Mines LLC. AREVA holds several exploration licences in Mongolia covering over 9,000 km2 in the provinces of Dornogobi and Sukbaatar, where COGEGOBI is conducting its drilling programmes. This first phase has led to the first project-development steps (hydrogeological

  9. The 2003 essential. AREVA; L'essentiel 2003. AREVA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document presents the essential activities of the Areva Group, a world nuclear industry leader. This group proposes technological solutions to produce the nuclear energy and to transport the electric power. It develops connection systems for the telecommunication, the computers and the automotive industry. Key data on the program management, the sustainable development activities and the different divisions are provided. (A.L.B.)

  10. Areva - 2008 results: yet another year of growth for AREVA

    International Nuclear Information System (INIS)

    This paper summarizes the 2008 financial results of the Areva group: Backlog: 48.2 billion euros, up 21.1%; Revenue: 13.2 billion euros, up 10.4%; Operating income: - Operating income excluding provision on OL3 contract in Finland: 1,166 million euros, i.e. operating margin of 8.9%; - Additional provision on OL3 contract of 749 million euros; - Operating income: 417 million euros, i.e. operating margin of 3.2%. Net income attributable to equity holders of the parent: 589 million euros, i.e. euros 16.62 per share; Net debt of 3.45 billion euros before recognition of the SIEMENS put; Dividend of euros 7.05 to be proposed during the Annual General Meeting of Shareholders of April 30, 2009. After publication of these figures Siemens announced its decision to withdraw from AREVA NP

  11. Press kit. Areva in China

    International Nuclear Information System (INIS)

    The results achieved in the nuclear energy field illustrate the exemplary nature of the cooperation between France and China. Over 20 years, China has developed the nuclear technology for generating electricity, using the expertise and knowledge of the AREVA Group. AREVA has been present in China since 1986 and now employs 3,500 staff there. The group supplied the nuclear islands for 4 reactors at Daya Bay and Ling Ao as well as technology and equipment for 4 more reactors at the Qinshan II and Tianwan plants. AREVA has developed an ambitious program for transferring technology to the Chinese industry and developing local skills. The group's objective is to remain China's partner of choice in terms of its nuclear program. During an official visit to France in June 2004, China's Vice Premier Zeng Peiyan said he was in favor of 'overall and long-lasting cooperation between China and France in the field of nuclear energy'. AREVA took the opportunity to sign two letters of intent for cooperation over technology from its next generation of nuclear reactors. Electricity consumption forecasts report a need for 900 GW through 2020 and the country's objective is to increase nuclear-generated electricity from 1% to 4% of its total output (36 GW: the equivalent of around twenty 1,500 MWe reactors). An official decision to build 4 new reactors was announced in July 2004 and a further decision concerning another 4 reactors is expected in the near future. Various construction sites are being considered, mainly along the country's eastern coast. An official decision to build four duplicate reactors was announced n July 2004. In addition to these four duplicate reactors to be built on existing sites, China has decided to build four 3. generation reactors at Yangjiang and Sanmen. An international call for tender was launched on September 28, 2004. AREVA will reply to the tender by offering its EPR model. AREVA also aims to expand its Chinese operations into exploring and extracting

  12. Areva - 2008 results: yet another year of growth for AREVA; Areva - Resultats 2008: une nouvelle annee de croissance pour AREVA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-02-15

    This paper summarizes the 2008 financial results of the Areva group: Backlog: 48.2 billion euros, up 21.1%; Revenue: 13.2 billion euros, up 10.4%; Operating income: - Operating income excluding provision on OL3 contract in Finland: 1,166 million euros, i.e. operating margin of 8.9%; - Additional provision on OL3 contract of 749 million euros; - Operating income: 417 million euros, i.e. operating margin of 3.2%. Net income attributable to equity holders of the parent: 589 million euros, i.e. euros 16.62 per share; Net debt of 3.45 billion euros before recognition of the SIEMENS put; Dividend of euros 7.05 to be proposed during the Annual General Meeting of Shareholders of April 30, 2009. After publication of these figures Siemens announced its decision to withdraw from AREVA NP.

  13. Areva at September 30, 2015:

    International Nuclear Information System (INIS)

    After the phase of strategic choices and definition of competitiveness objectives, AREVA entered the phase of operational execution of its transformation plan. Despite a still depressed market environment, the Group is beginning to measure the first results of its efforts to restore its financial situation. Thanks to the actions undertaken, the cash consumption pace was sharply slowed down compared to what had been anticipated. In summary: Rise in revenue to euro 2.947 bn: +10.3% vs. September 2014 (+8.7% like for like); - Backlog of euro 31.595 bn; - Discontinued operations, including AREVA NP: - Revenue of euro 2.732 bn: -7.5% vs. September 2014, - Backlog of euro 12.872 bn. Progress on the transformation plan in the third quarter: - Social dialogue: signature of the group agreement on the employment plan and submittal of documents describing the group's reorganization plans to employee representation bodies as part of a job-saving plan; - Continued deployment of actions for operational performance; - Strategic partnership with EDF: finalization of due diligence for the sale of AREVA NP; - Decisions on capital increase taken before the end of 2015

  14. Annual report 2001. A (AREVA) for.

    International Nuclear Information System (INIS)

    This annual report 2001, on the group Areva, provides data and information on the Areva emerges, overview of operations, sustainable development policy, research and development programs, nuclear power activities (front-end, reactors and services back-end divisions), components (connectors division and STMicroelectronics, human resources, share data and the financial report. (A.L.B.)

  15. Reference document 2001. A (AREVA) for.

    International Nuclear Information System (INIS)

    This reference document 2001, on the group Areva, provides data and information on the Areva emerges, overview of operations, sustainable development policy, research and development programs, nuclear power activities (front-end, reactors and services back-end divisions), components (connectors division and STMicroelectronics, human resources, share data and financial information (financial report 2001, financial report first-half 2002). (A.L.B.)

  16. Areva. 2005 half year report; Areva. Rapport semestriel 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    With manufacturing facilities in over 40 countries and a sales network in over 100, AREVA offers customers technological solutions for nuclear power generation and electricity transmission and distribution. The group also provides interconnect systems to the telecommunications, computer and automotive markets. This half-year report of Areva group presents the key financial data of the group for the first half of 2005: 1 - Highlights of the period; 2 - Transition to the International Financial Reporting Standards: Group's application of IFRS, Impact of IAS 32 and 39 adoption on the Group's financial statements; 3 - Key data: summary data, summary data by business Division, backlog, income statement, review by business Division, cash flow statement, balance sheet items; 4 - events subsequent to the half-year-end; 5 - consolidated financial statements: statutory Auditors' report on the 2005 half-year financial statements - period from January 1 to June 30, 2005, consolidated income statement, consolidated balance sheet, consolidated cash flow statement, change in consolidated shareholders' equity, data by business Division and region, notes to the consolidated financial statements; 6 - Outlook.

  17. Sharing Experiences within AREVA D and D Project Portfolio: Four Illustrations - 13049

    Energy Technology Data Exchange (ETDEWEB)

    Chabeuf, Jean-Michel; Varet, Thierry [AREVA Site Value Development Business Unit, La Hague Site (France); AREVA Site Value Development Business Unit, La Hague Site

    2013-07-01

    Over the past ten years, AREVA has performed D and D operations on a wide range of nuclear sites, such as Marcoule and La Hague recycling plants, to Cadarache MOX fuel fabrication plant or Veurey and Annecy metallic Uranium machining plants. Each site is different from the other but some lessons can be shared through this D and D portfolio. In that respect, knowledge management is one of AREVA D and D Technical Department main missions. Four illustrations demonstrate the interest of knowledge share. Waste management is one of the key activities in D and D; It requires a specific characterization methodology, adapted logistics, and optimized waste channels, all of which have been developed over the years by AREVA teams on the site of Marcoule while they are rather new to La Hague, whose main activity remains fuel reprocessing despite the launch of UP2 400 D and D program. The transfer of know how has thus been organized over the past two years. Plasma cutting has been used extensively in Marcoule for years, while prohibited on the site of La Hague following questions raised about the risks associated wit Ruthenium sublimation. La Hague Technical Department has thus developed an experimental protocol to quantify and contain the Ruthenium risk, the result of which will then be applied to Marcoule where the Ruthenium issue has appeared in recent operations. Commissioning and operating fission products evaporators is a rather standard activity on UP2 800 and UP3, while the associated experience has been decreasing in Marcoule following final shutdown in 1998. When the French atomic Energy commission decided to build and operate a new evaporator to concentrate rinsing effluents prior to vitrification in 2009, AREVA La Hague operators were mobilized to test and commission the new equipment, and train local operators. Concrete scabbling is the final stage prior to the free release of a nuclear facility. In the context of Veurey and Annecy final cleanup and declassification

  18. Sharing Experiences within AREVA D and D Project Portfolio: Four Illustrations - 13049

    International Nuclear Information System (INIS)

    Over the past ten years, AREVA has performed D and D operations on a wide range of nuclear sites, such as Marcoule and La Hague recycling plants, to Cadarache MOX fuel fabrication plant or Veurey and Annecy metallic Uranium machining plants. Each site is different from the other but some lessons can be shared through this D and D portfolio. In that respect, knowledge management is one of AREVA D and D Technical Department main missions. Four illustrations demonstrate the interest of knowledge share. Waste management is one of the key activities in D and D; It requires a specific characterization methodology, adapted logistics, and optimized waste channels, all of which have been developed over the years by AREVA teams on the site of Marcoule while they are rather new to La Hague, whose main activity remains fuel reprocessing despite the launch of UP2 400 D and D program. The transfer of know how has thus been organized over the past two years. Plasma cutting has been used extensively in Marcoule for years, while prohibited on the site of La Hague following questions raised about the risks associated wit Ruthenium sublimation. La Hague Technical Department has thus developed an experimental protocol to quantify and contain the Ruthenium risk, the result of which will then be applied to Marcoule where the Ruthenium issue has appeared in recent operations. Commissioning and operating fission products evaporators is a rather standard activity on UP2 800 and UP3, while the associated experience has been decreasing in Marcoule following final shutdown in 1998. When the French atomic Energy commission decided to build and operate a new evaporator to concentrate rinsing effluents prior to vitrification in 2009, AREVA La Hague operators were mobilized to test and commission the new equipment, and train local operators. Concrete scabbling is the final stage prior to the free release of a nuclear facility. In the context of Veurey and Annecy final cleanup and declassification

  19. AREVA 2010 annual results; AREVA resultats annuels 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    Areva's 44-billion euro backlog at the end of 2010 gives the group excellent visibility, enabling it to confirm its outlook for 2012: 12 billion euros in revenue, double-digit operating margin and significantly positive free operating cash flow. Revenue rose by 575 million euros in 2010, or 6.7%, in comparison to 2009 and operating income excluding particular items improved by 201 million euros, nearly 2 points of revenue. In the past two years, Areva has raised 7.1 billion euros and secured its liquidity to ensure its development. In 2011, Areva is going to simplify the group's capital structure by listing ordinary shares of AREVA. At that time, the group may launch the employee share-holding plan, something it has ardently sought for several years as a way for its employees to share in AREVA's growth. The consolidated backlog stood at 44.204 billion euros at December 31, 2010, up 2.0% compared with that at December 31, 2009. The group's consolidated revenue came to 9.104 billion euros in 2010, up 6.7% on a reported basis and 5.1% like-for-like compared with 2009. Excluding particular items, operating income rose by 1.9 point, going from 3.9% in 2009 to 5.8% in 2010, giving operating income of 532 million euros (331 million euros in 2009). Net income attributable to equity owners of the parent came to 883 million euros in 2010, an increase of 331 million euros compared with 2009. Operating cash flow before capex was 923 million euros, an increase of 548 million euros compared with 2009, when it was 375 million euros, due to the visible improvement in EBITDA and working capital requirement. The change in gross capex (excluding acquisitions) from 1.780 billion euros in 2009 to 1.966 billion euros in 2010 is due to the ramp-up of construction programs, particularly in Enrichment. In 2010, almost 60% of the group's capital spending was on sites in France. The acquisitions made in Renewable Energies in 2010 in the amount of 210 million euros

  20. Areva. 2005 half year report

    International Nuclear Information System (INIS)

    With manufacturing facilities in over 40 countries and a sales network in over 100, AREVA offers customers technological solutions for nuclear power generation and electricity transmission and distribution. The group also provides interconnect systems to the telecommunications, computer and automotive markets. This half-year report of Areva group presents the key financial data of the group for the first half of 2005: 1 - Highlights of the period; 2 - Transition to the International Financial Reporting Standards: Group's application of IFRS, Impact of IAS 32 and 39 adoption on the Group's financial statements; 3 - Key data: summary data, summary data by business Division, backlog, income statement, review by business Division, cash flow statement, balance sheet items; 4 - events subsequent to the half-year-end; 5 - consolidated financial statements: statutory Auditors' report on the 2005 half-year financial statements - period from January 1 to June 30, 2005, consolidated income statement, consolidated balance sheet, consolidated cash flow statement, change in consolidated shareholders' equity, data by business Division and region, notes to the consolidated financial statements; 6 - Outlook

  1. The ITER management advisory committee (MAC) meeting in Cadarache

    International Nuclear Information System (INIS)

    The ITER management advisory committee meeting was held on 8 March in Cadarache, France. The main topics were the ITER EDA Status Report in the period between the ITER Meeting in Yokohama (October 1990) and February 1999. In particular, the management advisory committee shares the director's concern about the uncertainties against which the whole project operates at present. They also noted that the definition of an appropriate framework for continued US involvement in on-going projects is a very important issue

  2. Meeting of the ITER CTA Project Board at Cadarache

    International Nuclear Information System (INIS)

    The meeting of the ITER CTA Project Board took place on the occasion of the N4 Meeting at Cadarache, France on 3-4 June 2002. The Project Board members and experts from Canada, EU, Japan and Russian Federation and the International Team attended the meeting. The parts informed each other of the latest developments concerning the ITER project in their respective countries, among them, offers for ITER potential site from the EU and Japan

  3. Report transparency and nuclear safety 2007 CEA Cadarache

    International Nuclear Information System (INIS)

    This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

  4. Areva at March 31, 2016

    International Nuclear Information System (INIS)

    In the first quarter of 2016, AREVA generated consolidated revenue of 826 million euros, a decrease of 0.8% (-2.2% like for like) compared with the same period in 2015, due in particular to the schedule of uranium deliveries. Foreign exchange had a positive impact of 12 million euros over the period. At March 31, 2016, the group's backlog reached 33.6 billion euros, up sharply compared to December 31, 2015 (29 billion euros), and represented eight years of revenue. It reflects in particular multi-year commercial agreements signed with EDF in early 2016. The order intake for the first quarter of 2016 totaled 6.1 billion euros, a strong increase in relation to the first quarter of 2015 (0.3 billion euros)

  5. Areva and sustainable development 2003 summary report

    International Nuclear Information System (INIS)

    This document is a summary of the 2003 report on the sustainable development of the world nuclear industry leader, Areva. The 2002 report helped establish the status of Areva entities sustainable development performance and identity areas for improvement. The 2003 report presents the continuous improvement process, including accomplishments and projects initiated as well as difficulties encountered and ground yet to be covered. Two new tools support this process. The Areva Way self assessment model allows each unit to assess its own performance against the sustainable development commitments and the Areva values charter lays down ethical principles of action and rules of conduct. Over the coming months, the Group will devote considerable effort to extending the sustainable development initiative to the activities resulting from the acquisition of Alstom Transmission and Distribution operations in early 2004. (A.L.B.)

  6. Report on responsible growth. AREVA in 2008

    International Nuclear Information System (INIS)

    All over the world, AREVA supplies its customers with solutions for carbon-free power generation and electricity transmission and distribution. With its knowledge and expertise in these fields, the group has a leading role to play in meeting the world's energy needs. Ranked first in the global nuclear power industry, AREVA's unique integrated offering covers every stage of the fuel cycle, reactor design and construction, and related services. In addition, the group is expanding its operations in renewable energies. AREVA is also a world leader in electricity transmission and distribution and offers its customers a complete range of solutions for greater grid stability and energy efficiency. Sustainable development is a core component of the group's industrial strategy. Its 75,000 employees work every day to make AREVA a responsible industrial player that is helping to supply ever cleaner, safer and more economical energy to the greatest number of people. Sustainable development is a keystone of AREVA's industrial strategy for achieving growth that is profitable, socially responsible and respectful of the environment. To translate this choice into reality, AREVA integrates sustainable development into its management practices via a continuous improvement initiative revolving around ten commitments: customer satisfaction, financial performance, governance, community involvement, environmental protection, innovation, continuous improvement, commitment to employees, risk management and prevention, dialogue and consensus building. This document is Areva's 2008 report on responsible growth. After the Messages from the Chairman of the Supervisory Board and from the Chief Executive Officer, the report presents the Key data and Highlights of the period, the Corporate governance, the Organization of the group, the Share information and shareholder relations, the uranium reserves, the growing energy demand and the World's population demographic growth, Areva's actions to

  7. AREVA and sustainable development - 2003 report

    International Nuclear Information System (INIS)

    The first report helped establish the status of Areva entities sustainable development performance and identify areas for improvement. This second report will report on the continuous improvement process, including accomplishments and projects initiated as well as difficulties encountered and ground yet to be covered. It includes, the Areva role in key sustainable development issues, the commitments and the governance, the risk management, the economic responsibility, the social responsibility and the environmental responsibility. (A.L.B.)

  8. Technical Aspect of Shielded SIMS Installation in CEA Cadarache

    International Nuclear Information System (INIS)

    A shielded IMS 6f has been installed in the LECA facility, CEA Cadarache France. The nuclearization was performed by CAMECA Company, which sells the standard IMS 6f. Working on nuclear materials requires in depth modifications of the apparatus itself. Despite these modifications, the shielded SIMS has the same level of performance as the standard apparatus. The design of the modified apparatus is presented and the safety aspects are emphasised. The shielded SIMS should be allowed to handle irradiated samples at the end of 2001. (Author)

  9. Annual report 2001. A (AREVA) for..; Rapport annuel 2001. A (AREVA) comme..

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This annual report 2001, on the group Areva, provides data and information on the Areva emerges, overview of operations, sustainable development policy, research and development programs, nuclear power activities (front-end, reactors and services back-end divisions), components (connectors division and STMicroelectronics, human resources, share data and the financial report. (A.L.B.)

  10. Reference document 2001. A (AREVA) for..; Document de reference 2001. A (AREVA) comme..

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This reference document 2001, on the group Areva, provides data and information on the Areva emerges, overview of operations, sustainable development policy, research and development programs, nuclear power activities (front-end, reactors and services back-end divisions), components (connectors division and STMicroelectronics, human resources, share data and financial information (financial report 2001, financial report first-half 2002). (A.L.B.)

  11. Fuel Services Germany - AREVA NP

    International Nuclear Information System (INIS)

    AREVA NP has over 30 years of nuclear fuel inspection and repair experience. Our service staff is trained regularly and holds a long lasting experience in their field of work. Our services comprise all activities within examinations of lead test assemblies, all necessary inspections and tests of fuel assemblies and other core components during an outage, reconstitution of fuel assemblies for further use in the reactor and activities within the disposal of fuel assemblies and core components. Furthermore we deliver facilities and systems that are necessary for the above mentioned services. These are in particular facilities for inspections, sipping, repair and for disposal (e.g. conditioning equipment, facility for encapsulation of leaking fuel rods). Continuous research and development guarantee that the applied facilities always comply with the latest state of the art. They are suitable for a variety of fuel assembly designs of AREVA's and external supplier's latest and conventional technology. The facilities are applicable in different BWR-, PWR and VVER nuclear power plants. Inspections in PWR- and BWR Plants: - Measurements with contact and contact less measuring methods of fuel assemblies, fuel rods, fuel channels and other core components; - High-definition video inspections; - Mast-, In-core- and Box-sipping to detect defective fuel assemblies; - Support (e.g. measurements on site) for post irradiation examinations; - Sampling of material (e.g. taking CRUD or material probes) and fuel rod preparation for hot cell examination. Repair in PWR- and BWR Plants: - Exchange of defective fuel rods of a fuel assembly for further use in the reactor and preparation of the fuel assembly or defective fuel rod for disposal; - Reconstitution of fuel assemblies with damaged structure parts (spacer, springs, upper-and lower end fitting). We offer products that meet the requirements of pressure-tightness under water (e. g. for use in the fuel storage pool), that are

  12. EDF, Areva: 2006 trading results

    International Nuclear Information System (INIS)

    In 2006, EDF achieved a turnover of 58.9 billion euros, it means a 15.4% increase compared to the previous year. The EDF's policy has been to decrease its debts by 3.7 billion euros to reach 14.9 billion euros and to invest 3.8 billion euros in France and 2.1 billion euros abroad. 2.8 billion euros have been affected to the dismantlement of nuclear facilities. The EDF company achieved a net trading result of 4.2 billion euros (+47.3%). The agreement signed between EDF and the French government imposes that the electricity tariffs do not increase above the inflation rate from 2006 till 2020. In 2006, the Areva group achieved a turnover of 10.863 billion euros (+7.3%) despite the important financial reserve imposed by the delay in the construction of the EPR reactor in Finland. The trading result has decreased by 26.1% to reach 407 million euros. On the 31. december 2006 the order book reached 25.627 billion euros (+24.6%). (A.C.)

  13. AREVA in the United States

    International Nuclear Information System (INIS)

    civilian nuclear power program, which had been wound down by the Carter Administration in 1979. More than 30 projects are underway, of which almost half are the subject of a Construction and Operating License (COL) application to the NRC. According to the report published in February 2007 by the EPRI, installed nuclear power in the United States could have increased by 64 GWe in 2030 and by 24 GWe in 2020. The document presents Areva's position in the US market for nuclear products and services, AREVA's integrated offer covering the entire nuclear energy cycle, AREVA's support in the revival of the U.S. nuclear sector, and the forward-thinking approach for AREVA's T and D division

  14. Status of safety at Areva group facilities. 2006 annual report

    International Nuclear Information System (INIS)

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

  15. Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA

    International Nuclear Information System (INIS)

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

  16. Areva will work the Imouraren mine

    International Nuclear Information System (INIS)

    Areva has signed an agreement with the government of Niger about the exploitation of the Imouraren uranium mine. The agreement settles a capital share of 66.65% for Areva and 33.35% for the Niger state. The production is assessed to be 5000 tonnes a year for 35 years and about 1400 jobs will be created. The initial investment amounts to 1.2 milliard euros and the production will begin in 2012. The Imouraren mine will enable Niger to double its present uranium production and to rank second worldwide as an uranium producer. Areva has been operating 2 mines in Niger for 40 years, one located at Arlit, the other one at Akokan, the 2 mines production reached 2260 tonnes of uranium in 2006. (A.C.)

  17. Areva. Half-year 2015 results

    International Nuclear Information System (INIS)

    This document presents the financial statements of Areva Group for the period ended June 30, 2015. During the first half, AREVA made determining decisions in refocusing on its core business, the nuclear fuel cycle direction. The group has announced an ambitious competitiveness plan, is engaged in strong social dialogue with its social partners, and has worked to improve the management of its large projects, which up to now have weighed heavily on its financial trajectory. It pursued its strategic roadmap for its refocusing and the redefinition of the partnership with EDF. The agreements found with EDF represent very significant progress. The group also worked on its financing plan whose aim is to allow AREVA to refinance its mid-term needs on the markets. Content: Key figures, Highlights of the period, Transformation plan (Performance plan, Strategic roadmap, Financing plan, Financial outlook)

  18. Report on transparency and nuclear safety 2014 - Cadarache CEA centre

    International Nuclear Information System (INIS)

    This document proposes, first, a presentation of the Cadarache CEA centre, of its activities and installations, gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. Then it reports significant events related to safety and to radiation protection which occurred in 2014 and have been declared to the ASN. Next, it discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. Finally, it addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre, indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and on the environment. Nature and quantities of warehoused wastes are specified. Remarks and recommendations of the CHSCT are given

  19. Processing of radioactive effluents in Cadarache research centre

    International Nuclear Information System (INIS)

    French Atomic Energy Commission (Commissariat a l'Energie Atomique - CEA) is studying the design of a new plant for processing liquid aqueous radioactive effluents produced on Cadarache Research Centre. Effluents to be processed are low and medium activity effluents, with, for some of them, important concentrations of actinides, and which lead to the production of A and B category solid wastes, according to the French legislation, and suitable for final disposal. The objectives in terms of minimization of discharge's activity level and solid waste production have guided a selection of processes and their arrangement, in order to optimise decontamination and volume concentration factors. Seeded-ultrafiltration and vitrification with cold crucible melter are part of the selected processes for which developments are in progress in CEA for application to the characteristics of the project. (authors)

  20. Tenth ITER negotiations and related meetings [Cadarache, France, September 2005

    International Nuclear Information System (INIS)

    With the issue of ITER siting settled at the Ministerial Meeting for ITER in Moscow of 28 June 2005, detailed joint work towards all the other aspects of the agreement on the implementation of the ITER international fusion energy research project resumed as delegations from China, the European Union, Japan, the Republic of Korea, the Russian Federation and the United States of America met at the agreed site of Cadarache in the period 7-15 September 2005 for intensive working sessions culminating in the tenth official meeting of the ITER Negotiators. The major advances made were reported to the Tenth Official Meeting of the Negotiators on 12 September at which all delegations reiterated their intention to proceed together with the construction of ITER at the earliest date, and expressed their satisfaction on progress made in defining the process for designation of top ITER officials. In particular, the delegations expressed the wish to see Japan identify suitably qualified candidate(s) to be designated as Nominee Director General. In a separate meeting, the ITER delegates had an informal exchange with a delegation from India on India's interest in the possibility of participating in ITER. The Committee took a number of organizational decisions aimed at preparing for the start of construction. In particular it was agreed to establish, under the Transitional Arrangements, an ITER Joint Work Site at Cadarache. This now provides the institutional frame to start assembling international personnel and to undertake joint technical work at the ITER Site. In addition, the CEA was mandated to represent ITER, in collaboration with the International Team, in the public debate now in progress in France and in the regulatory and licensing process until the ITER Organization itself will be in a position to take the role over

  1. Figures and information on nuclear safety and radiation protection on the Tricastin AREVA site

    International Nuclear Information System (INIS)

    This report presents and briefly comments figures concerning the environment (water consumption, greenhouse gas emissions, liquid releases in a canal, radioactive and hazardous industrial wastes), radiological impact and radiation protection (computed dose for a reference group, computed maximum dose for the reference group, radiological exposures of workers), nuclear safety (number of events, controls and audits), production (quantities of various materials) and transport (flows of radioactive products) for the whole Tricastin site for which only some general data are indicated, and more precisely the various installations and establishments it comprises: AREVA NC Pierrelatte, COMURHEX Pierrelatte, EURODIF Production, FBFC Pierrelatte, SET, SOCATRI

  2. Areva at September 30, 2014

    International Nuclear Information System (INIS)

    Over the first nine months of 2014, AREVA generated consolidated revenue of 5.558 billion euros, a decrease of 14.3% (-12.9% like for like) compared to the same period in 2013. In the nuclear operations, revenue totaled 5.453 billion euros over the first 9 months of 2014, versus 6.330 billion euros for the first 9 months of 2013, a 13.9% decrease (-13.1% like for like). Revenue in the Front End BG rose 13.2% (+13.8% like for like). Revenue in the Mining, Reactors and Services and Back End BGs declined 44.8% (-43.5% like for like), 7.7% (-6.5% like for like) and 24.0% (-24.3% like for like) respectively. Foreign exchange had a negative impact of 54 million euros over the period, while consolidation scope had a negative impact of 46 million euros. Third quarter 2014 revenue came to 1.669 billion euros, a 15.3% decrease (-14.1% like for like) compared to the third quarter of 2013. Consolidation scope had a negative impact of 28 million euros over the period, while foreign exchange had practically no impact. Revenue in the nuclear operations amounted to 1.655 billion euros in the 3. quarter of 2014, a drop of 14.2% compared to the 3. quarter of 2013 (-14.3% like for like). Over the first 9 months of 2014, revenue in France came to 2.645 billion euros, a 3.2% decrease compared to the first 9 months of 2013. Over the same period, revenue from international operations totaled 2.913 billion euros, a drop of 22.3% compared to the first 9 months of 2013. At September 30, 2014, the group's backlog was 46.076 billion euros, an increase of 11.4% compared to September 30, 2013 (41.365 billion euros). This is a record level for the nuclear operations since the group's creation. It should be noted that the backlog does not include all of the umbrella agreement signed with EDF, announced on October 2, 2014, for the supply of design and fuel fabrication services for the French nuclear reactors from 2015 to 2021. It should also be noted that it does not include the amount of

  3. AREVA and sustainable development - 2003 report; Rapport developpement durable 2003 - AREVA

    Energy Technology Data Exchange (ETDEWEB)

    Lauvergeon, A

    2003-07-01

    The first report helped establish the status of Areva entities sustainable development performance and identify areas for improvement. This second report will report on the continuous improvement process, including accomplishments and projects initiated as well as difficulties encountered and ground yet to be covered. It includes, the Areva role in key sustainable development issues, the commitments and the governance, the risk management, the economic responsibility, the social responsibility and the environmental responsibility. (A.L.B.)

  4. Areva group. Result, first half 2004

    International Nuclear Information System (INIS)

    Areva, a world nuclear industry leader, provides by this document information and key data on the performance and detailed financial data of the first half 2004. The transmission and distribution integration plan 2004-2006 is also detailed. (A.L.B.)

  5. 1. half results 2003 - AREVA group

    International Nuclear Information System (INIS)

    This financial presentation of the Areva group, the world nuclear industry leader, results for the first half 2003 highlights the good level of activity, the negotiations with URENCO in final stages concerning the enrichment, the revision of estimates and negotiations underway concerning the dismantling and the operating income positive in Q2 2003 concerning the connectors division. (A.L.B.)

  6. Export Control in the AREVA Group

    International Nuclear Information System (INIS)

    After the Second World War the nuclear technology was mostly considered inappropriate for the export. It remains strictly regulated today, but the development of the civil applications urged states to facilitate the peaceful uses while establishing a strict control in the domains of the internal security and the nuclear proliferation. AREVA decided to set up an Export Control program applied to all the products and in all the countries where the group operates. AREVA can export products or make transfer of technology considered as sensitive for the non-proliferation and the risks linked to the terrorism. This sensitiveness results from the nature of the products or from the country of destination and in certain cases both of them. AREVA has set up an Export Control program and an interactive e-learning training within the Group to make exports of sensitive products, raw materials and technologies more secure. The subject is rather complex, the regulations are constantly evolving, and becoming familiar with them is necessarily a gradual process, but it must be made in-depth, hence the idea of regular training sessions. The implementation of the Export Control in the AREVA Group declines in four fundamental stages: -) Policy and procedure; -) Appointment of Export Control Officers (ECO); -) Training; and -) Audit and Self Assessment. The training program is composed by the following elements: Ethics (Value Charter) of the Group, Non-proliferation, international regulations and more particularly those that are applicable in Europe (Germany and France) and in the United States. Particular attention is devoted to the Export Control practice in China, Japan and India. (A.C.)

  7. Areva in 2007, growth and profitability

    International Nuclear Information System (INIS)

    This annual report 2007, presents the AREVA Group activities during the year. It contents the messages of the Chairman and Chief executive officer, the solutions offered by the group for CO2 free power generation and reliable electricity transmission and distribution, the governance, the financial performance, the innovation, the environmental protection, the risk management and prevention, the audit's report and key data for the year 2007. (A.L.B.)

  8. AREVA net income: 649 million euros

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-03-15

    This document presents the financial statements for 2006 of Areva group: net income: 649 million euros; backlog up by 24.6% to 25.6 billion euros; steady growth of sales revenue: + 7.3%1 to 10.863 billion euros; operating income of 407 million euros: excellent divisional performance and constitution of a significant provision for the OL3 project in Finland; dividend proposed to Annual General Meeting of Shareholders: 8.46 euros per share.

  9. AREVA net income: 649 million euros

    International Nuclear Information System (INIS)

    This document presents the financial statements for 2006 of Areva group: net income: 649 million euros; backlog up by 24.6% to 25.6 billion euros; steady growth of sales revenue: + 7.3%1 to 10.863 billion euros; operating income of 407 million euros: excellent divisional performance and constitution of a significant provision for the OL3 project in Finland; dividend proposed to Annual General Meeting of Shareholders: 8.46 euros per share

  10. The IRSN Institute of radiation protection and nuclear safety Cadarache Center

    International Nuclear Information System (INIS)

    The research programs of the IRSN in the Cadarache Center concern the nuclear safety (reactor safety, nuclear fuels behavior during accidents, fires in nuclear installations), the protection and the control of radioactive materials, the human and the environment protection. The programs are presented and discussed. This presentation includes also the regional impact of the Institute at Cadarache (economical impact, relations with the universities and international meetings). (A.L.B.)

  11. Areva - 2012 Annual Report. Forward looking energy

    International Nuclear Information System (INIS)

    After an interview of the Chief Executive Officer, a presentation of the company's governance and organization, and a brief overview of its strategy (with its five pillars: safety and security, operation and customers, economic competitiveness, technology and innovation, people), this report indicates and presents the various projects across the world. It outlines the main activities and objectives: preservation of nuclear and occupational safety, service to customer over the long term, fuel supply security, expertise, sustainability of nuclear power, contribution to the energy mix of tomorrow. It outlines the belief of Areva in the future of nuclear and renewable energies (brief presentations of activities and examples in different countries and in different domains), describes how Areva offers comprehensive solutions for power generation with less carbon, and indicates the distribution of revenues by business group and by geographic area. It comments a year of mining operations, the activities concerning the front end of the fuel cycle, those related to reactors and nuclear services, to recycling (fuel recycling, site dismantling and reuse, material storage and disposal), to the booming business of renewable energies, to engineering services. The report proposes some key figures concerning greenhouse gas emissions, environmental footprint, occupational safety, and radiation protection within the group. It outlines the importance of innovation in terms of investment, personnel and patents. It comments the activities related to nuclear safety and to the control of the environment. It outlines the human resource policy, evokes the activity of the Areva foundation. A summarized presentation of financial statements is given

  12. Reliability innovations for AREVA NP BWR fuel

    International Nuclear Information System (INIS)

    AREVA NP is a supplier of nuclear fuel assemblies and associated core components to light water reactors worldwide, representing today more than 185,000 fuel assemblies on the world market including more than 63,000 fuel assemblies for boiling water reactors (BWRs). ATRIUM trademark 10 fuel assemblies have been supplied to a total of 32 BWR plants worldwide resulting in an operating experience over 20,250 fuel assemblies. ATRIUM trademark 10XP and ATRIUM trademark 10XM are AREVA NP's most recent fuel assembly designs featuring improved fuel utilization and achieving high margins to operating limits while maintaining very good reliability. Nevertheless, fuel failures are still encountered in all modern and advanced fuel assembly designs leading to significant operating limitations or unplanned shutdowns of nuclear power plants. The majority of fuel failures in BWR plants are caused by debris fretting, with PCI induced failures being a second leading cause. AREVA NP runs programs to study these root causes and to develop product solutions as part of the continuous improvement process within the Zero Tolerance for Failure (ZTF) initiative. The focus of the ZTF initiative is to further upgrade BWR fuel assembly reliability to achieve the goal of failure free fuel. In the following, two major product improvements are described that will significantly contribute to this goal: - Improved FUELGUARD trademark Lower Tie Plate - Chamfered Fuel Pellet Design (orig.)

  13. Large N_c

    OpenAIRE

    Jenkins, Elizabeth E.

    2009-01-01

    The 1/N_c expansion of QCD with N_c=3 has been successful in explaining a wide variety of QCD phenomenology. Here I focus on the contracted spin-flavor symmetry of baryons in the large-N_c limit and deviations from spin-flavor symmetry due to corrections suppressed by powers of 1/N_c. Baryon masses provide an important example of the 1/N_c expansion, and successful predictions of masses of heavy-quark baryons continue to be tested by experiment. The ground state charmed baryon masses have all...

  14. Areva group. Result, first half 2004; Resultats du 1. semestre 2004. Groupe Areva

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-09-01

    Areva, a world nuclear industry leader, provides by this document information and key data on the performance and detailed financial data of the first half 2004. The transmission and distribution integration plan 2004-2006 is also detailed. (A.L.B.)

  15. 1. half results 2003 - AREVA group; Resultats du 1. semestre 2003 - groupe AREVA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-10-01

    This financial presentation of the Areva group, the world nuclear industry leader, results for the first half 2003 highlights the good level of activity, the negotiations with URENCO in final stages concerning the enrichment, the revision of estimates and negotiations underway concerning the dismantling and the operating income positive in Q2 2003 concerning the connectors division. (A.L.B.)

  16. AREVA sustainable development indicators guidelines; Guide methodologique des indicateurs developpement durable AREVA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-12-01

    These guidelines set out the procedures used to measure and report the sustainable development and continuous progress data and indicators used within the Areva Group. It defines the scope of the guide, the list of indicators, the measurement and calculation procedures, the internal and external audits. (A.L.B.)

  17. Areva in China - Press kit April 2013

    International Nuclear Information System (INIS)

    increasingly key market for the AREVA Group. AREVA, which is focused on and committed to both nuclear and renewable energies, supports the Chinese utilities to reach the ambitious targets set by their government. This document summarizes the present activities of Areva in China: 1 - More than 30 years of cooperation with China: Key Dates; AREVA Group in China and partnerships with the Chinese Nuclear Industry; 2 - Chinese energy and policies: Economy and Energy in China, Nuclear energy in China, Overview of the Chinese nuclear fleet, Renewable energies in China; 3 - Activities in China: Mining, Front-End, Reactors and Services, Back-End, Renewable Energies; 4 - Taishan 1 and 2 EPRTM project: General Description, Scope of AREVA, AREVA Supply Chain, Key Milestones, Progress of Taishan 1 and 2, at the end of 2012

  18. Areva - Press release from the Supervisory Board

    International Nuclear Information System (INIS)

    During its meeting held on December 12, 2011, devoted in particular to the examination of the 2011 closing estimates, the AREVA Executive Board indicated that it expected to book a provision of 1.46 billion euros (2.025 billion US dollars) in the company's accounts for fiscal year 2011 for impairment of assets for the reporting entity UraMin, a mining company acquired by AREVA in 2007, which, given the provision booked in 2010 (426 million euros), brings the value of these assets on the AREVA balance sheet down to 410 million euros. Given the size of these provisions, the Supervisory Board decided to make three of its members, meeting as an ad hoc committee, in charge of analyzing the terms of acquisition of this company, as well as the key decisions made in this reporting entity up to 2011 and, based on the outcome of these analyses, to recommend to it any appropriate measures in AREVA's interest. This committee reported on its work during the Supervisory Board meeting held on February 14, 2012. In light of this report, the Supervisory Board found that the fairness and reliability of the financial statements of previous years were not in question. Nevertheless, considering the malfunctions raised, the Board considers it appropriate to thoroughly review AREVA's governance in order to ensure that decisions concerning large acquisitions or investments be reviewed and validated in the future under conditions ensuring better legal and financial security and enabling a more transparent dialogue between management and the Supervisory Board. It thus asked the Executive Board to recommend, at the next General Meeting of Shareholders, that the by-laws of the company be modified to make the Supervisory Board's prior approval of investments, stake acquisitions and acquisitions mandatory above a threshold of 20 million euros. It also decided to set up a business ethics committee within the Supervisory Board responsible for ensuring that rules of conduct are properly applied

  19. Areva as of December 31, 2011

    International Nuclear Information System (INIS)

    In 2011, AREVA's consolidated revenue came to 8.872 billion euros, down slightly (-2.6%) compared with 2010 (-1.2% like for like). The decrease in revenue in nuclear operations was partially offset by significant growth in the renewable energies business. Foreign exchange and changes in the scope of consolidation had respectively a negative impact of 113 million euros and 16 million euros over the period. Revenue totaled 2.922 billion euros in the fourth quarter of 2011, stable compared with the fourth quarter of 2010 (-0.5% on a reported basis and -0.5% like for like). Foreign exchange had a negligible impact during the period. Led by nuclear operations, the group's backlog was 45.6 billion euros at December 31, 2011, up 3.1% year on year and 6.7% in relation to September 30, 2011. Order cancellations since Fukushima were limited to 464 million euros as of December 31, 2011. In accordance with the requirements of IFRS 8, AREVA's business segment information is presented for each operating Business Group (BG), which is the level of information examined by the group's governance bodies. Subsequent to the establishment of a subsidiary combining all of the group's mining operations, data for the Mining Business Group are now reported separately from those of the Front End Business Group. Data used for comparisons with 2010 were restated to reflect this new organization. The business segment information therefore corresponds to AREVA's five operating Business Groups: Mining, Front End, Reactors and Services, Back End and Renewable Energies

  20. AREVA Technical Days (ATD) session 1: Energy outlook and presentation of the Areva Group; AREVA Technical Days (ATD) session 1: enjeux energetiques et presentation du groupe AREVA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This first session deals with energy challenges and nuclear, public acceptance of nuclear power, mining activities, chemistry activities, enrichment activities, fuel assembly, reactors and services activities, nuclear measurements activities, reprocessing and recycling activities, logistics activities and connectors activities. (A.L.B.)

  1. AREVA Business and Strategy overview April, 2010

    International Nuclear Information System (INIS)

    This document is a series of slides presenting AREVA's activities in the framework of CO2-free power generation: 2005-2009 Group Performance; 2010-2012 Development Plan (Build 1/3 of the new nuclear generating capacity, Secure the fuel cycle for current and future customers, Expand renewable energies offering, Ensure strong profitable growth in the T and D Division); Performances and objectives by division (Front-End, Mines and Enrichment, Reactors and Service, renewable energies, Back-End); latest key financial results; Appendices (Financial, Nuclear power, Mining business details, Conversion/Enrichment/Fuel business details, Reactors and Services business details, Back-End business details, Renewable business details)

  2. AREVA and sustainable development. 2002 report

    International Nuclear Information System (INIS)

    The performance indicators in this report reflect the major sustainable development impacts and challenges that Areva is facing as a group due to the very nature of its operations. They chose the calendar year as reporting period, from January 1 to December 31. This report covers all of the group operations in France and abroad. This report presents an overview of the major financial, social and environmental challenges facing the group. This report is a companion document to the annual activity report. (A.L.B.)

  3. Seismic risk and safety of nuclear installations. A look at the Cadarache Centre; Risque sismique et surete des installations nucleaires. Regards sur le Centre de Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    Verrhiest-Leblanc, G.; Chevallier, A. [Autorite de Surete Nucleaire 75 - Paris (France)

    2010-11-15

    After a brief recall of some important seismic events which occurred in the past in the south-eastern part of France, the authors indicate the nuclear installations present in this region. They outline the difference between requirements for a usual building and for basic nuclear installations. They indicate laws and regulations which are to be applied to these installations like to any hazardous industrial installation. They describe the seismic risk as it has been determined for the Cadarache area, and evoke the para-seismic design of new nuclear installations which are to be built in Cadarache and actions for a para-seismic reinforcement of existing constructions. Finally, they evoke organisational aspects (emergency plans) and the approach for a better information and transparency about the seismic risk

  4. Environmental monitoring in the area of the Cadarache Nuclear Studies Centre

    International Nuclear Information System (INIS)

    The Cadarache Centre is part of the French nuclear programme providing for extensive development of research and hence of personnel and installations. It is essentially a centre for testing prototype reactors intended for use in power stations or for ship propulsion. In addition, experimental studies are carried out in connection with reactor structural materials and fuel elements. Various studies related to reactor physics, radiation protection, plant biology, etc. are also undertaken. This article describes the Cadarache site and the monitoring programme to assess the levels of radioactivity released from it.

  5. AREVA in the Republic of South Africa

    International Nuclear Information System (INIS)

    South Africa opted to develop its electricity production sector in a safe and competitive manner using CO2 free technologies in order to support its economic and social growth. The country's ambitious energy program aims to create a lasting nuclear sector generating 20 GW of electricity by 2025 mainly from super modern water reactors and PBMRs. South Africa wishes to become a world player in the nuclear energy field, thus reinforcing its position as one of the major world producers of energy. In the strategic plan for the development of a national nuclear policy unveiled in July 2007, the government's objective is to create the suitable conditions for a nuclear industry based on the most modern technologies and promote an ambitious new builds construction program. By 2030, nuclear energy should provide 30% of electricity in South Africa, from a fleet of PWRs and PBMRs. In 2007, ESKOM's Board of Directors approved a plan to re-launch the construction of electrical plants in South Africa, to reach around 80 GW by 2025 and including the construction of an additional 20 GW of nuclear-based capacity. This nuclear revival program provides for the construction of PWR nuclear power plant generating a total of 3 GWe to 3,5 GWe, to go online as of 2016, and the consideration of a fleet of PWR power plants up to 20,000 MWe in total to gradually go on line through 2025. Five sites have already been identified for the new power stations and the nuclear company to build the power plants will be selected in 2008. AREVA's Evolutionary Power Reactor (EPR) and Westinghouse's AP 1000 have been pre-selected. The Government aims to achieve the objective of encourage the participation of Public entities such as the South African Nuclear Energy Corporation (NECSA) in the uranium value chain. Such public entities shall be used to store the secured uranium supplies, as well as participate in the local beneficiation. NECSA, as the state's body responsible for research and development in the

  6. AREVA signs a contract for completing Angra 3

    International Nuclear Information System (INIS)

    AREVA has signed a contract for the completion of the Angra-3 reactor with the Eletrobas Eletronuclear Brasilian company. Angra-3 is a PWR-type reactor with an output electric power of 1405 MW and located in the Rio-de-Janeiro state. AREVA will provide engineering assistance, some components of the primary loop and the digit control and instrumentation system of the reactor. AREVA will also provide assistance for performing final commissioning tests. The contract worth amounts to 1.25 billions euros. Angra 3 will comply with the post-Fukushima standards of the Brasilian Nuclear Safety Authority. (A.C.)

  7. AREVA Logistics Business Unit Transportation Risk Management Initiative

    International Nuclear Information System (INIS)

    A safe, secure and reliable transportation organization is a key component for the success of the nuclear industry. With the forecasted increase of radioactive material transport flows in future and the changing environment, AREVA Logistic Business Unit (L-BU) must ensure that safety and security risks are minimized but also ensure of the chain supply for its various facilities (mines, conversion, enrichment, fuel manufacturing, reprocessing, etc). AREVA L-BU Unit is implementing a transportation risk management initiative for the radioactive shipments of the AREVA group across all the Business Unit involved in shipments of radioactive and nuclear materials. The paper will present the four main components of the risk management. (authors)

  8. Experience of Areva in fuel services for PWR and BWR

    International Nuclear Information System (INIS)

    AREVA being an integrated supplier of fuel assemblies has included in its strategy to develop services and solutions to customers who desire to improve the performance and safety of their fuel. These services go beyond the simple 'after sale' services that can be expected from a fuel supplier: The portfolio of AREVA includes a wide variety of services, from scientific calculations to fuel handling services in a nuclear power plant. AREVA is committed to collaborate and to propose best-in-class solutions that really make the difference for the customer, based on 40 years of Fuel design and manufacturing experience. (Author)

  9. AREVA first half 2007 sales revenue

    International Nuclear Information System (INIS)

    The AREVA group's backlog as of June 30, 2007 was euros 33.5 billion, up 31% compared with that of December 31, 2006. On average, the Group's backlog increased by more than 20% annually over the last three years. It is now at the highest level since AREVA was established in 2001. All divisions contributed to this performance: - The Front End division signed in particular a major enrichment contract with KHNP (South Korea), a fuel supply contract with EDF covering the 2008-2012 period and other significant contracts with Japanese and Swedish utilities. - The Reactors and Services division added the Flamanville 3 EPR, ordered by EDF, to the backlog. Flamanville 3 is AREVA's 100. reactor order. - The Back End division also concluded a major contract with Sogin to treat used fuel stored at Italian nuclear sites. - The Transmission and Distribution division continued to record strong growth. New orders were up 24% compared with the first half of 2006 (+25.1% like-for-like). Important contracts were signed in the Middle East, Russia and with large industrial users of electricity. First half 2007 sales revenue was up 6.7% (+6.4% like-for-like) to euros 5373 million, compared with euros 5036 million for the first half of 2006. Major developments in the first half of 2007 include: - Sales revenue was down 2.8% to euros 1342 million in the Front End division (-3.6% like-for- like) due to uneven distribution of deliveries in the Fuel business unfavorable during the period. This timing issue has no impact on projected annual growth. The division continues to benefit from a gradual price increase for long-term uranium supply contracts. - Sales revenue was up 4.8% to euros 1154 million in the Reactors and Services division (+3% like-for-like). The Services business unit, especially, was a major contributor to growth on all its markets after a 2006 fiscal year marked by a weak demand. The start of construction of a second EPR reactor for EDF, Flamanville 3, also contributed to

  10. Areva - Nuclear Safety Policy 2013-2016

    International Nuclear Information System (INIS)

    The objectives of Areva's Nuclear Safety Policy cover three areas: 1 - Safety of facilities: - Establish a group wide process to maintain the regulatory compliance of facilities and to ensure the execution of improvements required by periodic reviews of safety. - Put in place proactive measures to reduce source terms present in facilities, and in particular with regard to fire, operational waste and legacy waste on AREVA sites. - Ensure the performance of arrangements and activities central to risk prevention, in particular in the areas of containment, criticality safety and radiological protection through compliance with the associated safety requirements. - Strengthen the emergency planning arrangements to be implemented in case of accidents and test these through regular exercises. 2 - Operational Safety: - Develop and verify the level of safety culture of our staff and subcontractors and increase the presence of operational managers on the ground. - Improve the requirements and responsibilities within documentation associated with operations and interventions on the basis of a significant involvement of our staff and subcontractors. - Implement robust and formal risk prevention processes to manage temporary or transitional situations, uncommon situations, or specific risks, including but not limited to parallel activities, administrative lockout/tag-out, working with naked flames, gamma radiation, work in a radioactive environment. - Integrate human and organizational factors (HOF) in the analysis of safety-related modifications of facilities; undertake detailed reviews of the causes of all significant events inside the group and improve the communication and implementation of operating experience within all group entities. - 3 Safety Management: - Maintain an organization based on clear principles of shared responsibility and delegation of authority, and have in place a robust process to assess the impact on safety of any organizational change. - Strengthen

  11. Areva's water chemistry guidebook with chemistry guidelines for next generation plants (AREVA EPRTM reactors)

    International Nuclear Information System (INIS)

    Over the years, AREVA globally has maintained a strong expertise in LWR water chemistry and has been focused on minimizing short-term and long-term detrimental effects of chemistry for startup, operation and shutdown chemistry for all key plant components (material integrity and reliability, promote optimal thermal performances, etc.) and fuel. Also AREVA is focused on minimizing contamination and equipment/plant dose rates. Current Industry Guidelines (EPRI, VGB, etc.) provide utilities with selected chemistry guidance for the current operating fleet. With the next generation of PWR plants (e.g. AREVA's EPRTM reactor), materials of construction and design have been optimized based on industry lessons learned over the last 50+ years. To support the next generation design, AREVA water chemistry experts, have subsequently developed a Chemistry Guidebook with chemistry guidelines based on an analysis of the current international practices, plant operating experience, R and D data and calculation codes now available and/or developed by AREVA. The AREVA LWR chemistry Guidebook can be used to help resolve utility and safety authority questions and addresses regulation requirement questions/issues for next generation plants. The Chemistry Guidebook provides water chemistry guidelines for primary coolant, secondary side circuit and auxiliary systems during startup, normal operation and shutdown conditions. It also includes conditioning and impurity limits, along with monitoring locations and frequency requirements. The Chemistry Guidebook Guidelines will be used as a design reference for AREVA's next generation plants (e.g. EPRTM reactor). (authors)

  12. Areva - First half 2008 sales revenue

    International Nuclear Information System (INIS)

    As of June 30, 2008, AREVA's backlog stood at 38.1 billion euro, for 13.6% growth since June 30, 2007, with 9.9% growth in Nuclear and 40.7% growth in Transmission and Distribution. In Nuclear, the backlog came to 32.3 billion euro as of the end of June 2008. In the front end of the cycle, AREVA signed multi-year contracts in the first half of the year with Japanese and American utilities and with EDF, for a combined total of more than 1 billion euro. Of note in the back end of the cycle is the contract AREVA signed with the U.S. Department of Energy to build a MOX fuel fabrication facility. In Transmission and Distribution, the backlog came to 5.8 billion euro as of the end of period. A total of 3.2 billion euro in orders was booked in the first half, an increase of 20.0% year-on-year. The division won several important contracts, most notably a contract with Dubai Electricity (more than 130 million euro), a contract with National Grid and RTE for the renovation of the IFA 2000 grid interconnection between France and Great Britain (more than 60 million euro), and, in the industrial field, a contract with Rio Tinto Alcan (close to 65 million euro). The group cleared revenue of 6.2 billion euro in the first half of 2008, up 14.8% (+16.4% like-for-like) compared with the first half of 2007. Sales outside France were up 14.3% to 4.2 billion euro or 68.6% of total sales; the latter were stable compared with the first half of 2007. All businesses were up, with growth of 15.9% in Nuclear operations (+19.1% LFL1) - particularly in Reactors and Services (+31.3% LFL1) - and 13.0% growth in Transmission and Distribution operations (+12.0% LFL T 1). Foreign exchange had a negative impact of 155 million euro, primarily due to the change in the U.S. dollar in relation to the euro. Changes in the consolidated group had a positive impact of 97 million euro, mainly reflecting acquisitions in the Transmission and Distribution division and in Renewable Energies. Sales revenue for

  13. AREVA in 2007, growth and profitability

    International Nuclear Information System (INIS)

    This document is the 2007 activity report of the Areva group, the nuclear division of which is Number 1 worldwide in the front end of the nuclear cycle, in pressurized water reactors (in terms of installed capacity), and in the treatment and recycling of used nuclear fuel. The Transmission and Distribution division is Number 1 worldwide in market management software and grid management software, number 2 in high voltage products, and number 3 in medium voltage products. Content: Message from the Chairman of the Supervisory Board; Message from the Chief Executive Officer; Key data; 2007 highlights; Corporate governance; Organization of the group; Share information and shareholder relations; Solutions for CO2-free power generation; Solutions for reliable electricity transmission and distribution; Governance; Continuous improvement; Financial performance; Innovation; Customer satisfaction; Commitment to employees; Environmental protection; Risk management and prevention; Dialogue and consensus building; Community involvement; Auditors' report; Reporting methodology; Data verified in 2007; Glossary; and 'to learn more' references

  14. Areva: clinical trials for a new treatment to fight cancer; Areva: essais cliniques pour un nouveau traitement contre le cancer

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2011-01-15

    Areva Med, the branch of Areva dedicated to nuclear medicine, has been agreed by the American Food and Drug Administration to begin the validation of a new treatment to fight cancer. This treatment is called alpha radio-immunotherapy and is based on the use of Pb{sup 212}. The validation phase aims at testing its efficiency on patients and will start in 2011 and will last 2 years. Areva has developed a process to extract Pb{sup 212} from thorium coming from ancient industrial activities. (A.C.)

  15. Areva - 2014 Half-year results

    International Nuclear Information System (INIS)

    The group posted a net loss in the first half of the year. This is the consequence of losses recorded in renewable operations, additional project-related provisions, asset write-downs and a nuclear market environment that has still deteriorated. Areva's backlog has strengthened thanks to the signing of the agreement through 2020 with EDF for used fuel treatment and MOX fuel production. Though it has a short-term adverse impact on the group's results, it provides these operations with long-term visibility and strengthens our strategic partnership with EDF. Despite a decline in revenue that was greater than anticipated, the group achieved positive free operating cash flow, an increase compared with the first half of 2013. The success of Areva's recovery actions partially offset the downturn in activity. These actions will be reinforced in the second half of the year to adapt to market conditions. The group continues to restructure its operations in renewable energies by entering into partnerships in promising markets, such as offshore wind and energy storage, and by discontinuing loss-making operations, such as concentrated solar power. 2014 Half-year results: - Backlog: euro 44.9 bn (euro +3.5 bn vs. 12/31/2013 thanks to the treatment-recycling agreement with EDF); - Negative net income attributable to equity owners of the parent (euro -694 m): Losses in discontinued renewable activities (euro -373 m), One-off impact of treatment-recycling agreement with EDF (euro -95 m), Provisions and assets impairment: - Positive free operating cash flow despite lower activity level: Revenue: euro 3.889 bn (-12.4% LFL), EBITDA: euro 256 m (euro -231 m vs. H1 2013), Free operating cash flow: euro 98 m (euro +256 m vs. H1 2013); - Strengthened recovery actions in an unfavorable economic environment: 2015 cost reduction objective secured and raised to euro 1.2 bn by 2016, Capital expenditure reduced over 2014-16; - Revised financial outlook

  16. Research and test reactor fuel treatment at AREVA NC la Hague

    International Nuclear Information System (INIS)

    The La Hague plant has a long successful history of treatment power reactor spent fuel. To accommodate a new contract, the process needed to be adapted to fuel from Research Test Reactors (RTR) taking into account the dimensional characteristics, the chemical composition and the high uranium enrichment of RTR fuel. Several treatment options resulted have been studied and proposed. The chosen approach for the detailed design consists of dissolving the RTR fuel in a dissolution pit in one line of dissolver facility (T1B). The process was designed for small RTR fuel elements composed of aluminium and uranium alloy. 'Taxi' baskets containing the RTR fuel elements are transferred from the fuel storage pools, to the feed cell in T1B. The fuel elements are loaded into canisters and transferred to a rack in the general maintenance cell. The RTR fuel canisters are picked up one by one and the fuel element is dropped into a transfer tube leading to the dissolution pit. The RTR dissolution process is fundamentally different from the continuous power reactor fuel dissolution process and is done in batches. The RTR fuel elements are completely dissolved in nitric acid. It appeared that the dissolution rate is higher than expected allowing more flexibility in operation. At the end of a batch, the solution is drained from the dissolver and diluted with UOX solutions from line T1A. The resulting UOX/RTR mixture complies with the specifications for downstream processing operations, including high level waste vitrification, where aluminium is incorporated into glass in accordance with specified limits. The innovative nature of the process, demanded by the special characteristics of the RTR fuel, required a major qualification program. The main objectives of the qualification program were to validate the dissolver pit concept, to verify basic RTR process data for the T1B production environment and to acquire data showing control of the process. The first active batch dissolution was successfully performed in 2005. About 2 tons of RTR fuel have been reprocessed by the end of 2006

  17. Commissioning of Nuclear Power Plants. The AREVA approach

    International Nuclear Information System (INIS)

    Georges Mateo, Fellow Expert at AREVA, closed the last day of conferences by detailing deeply the different phases of NPPs commissioning. He insisted on the skills required to be a Commissioning engineer and on the carrier opportunities that it offers

  18. Areva 2009 responsible growth report: more energy, less CO2

    International Nuclear Information System (INIS)

    This document is the 2009 annual responsible growth report of AREVA which presents itself as having consolidated its leadership position in its original business of nuclear power while expanding considerably in renewable energies (wind, solar, bio-energies and hydrogen/storage) to become a leading provider of solutions for carbon-free power generation. The main chapters of the report are: the group and its strategy, Areva's nuclear power solutions (is nuclear a sustainable energy source?, supply, technological excellence, safety, recycling and waste, acceptability, non-proliferation), Areva's renewable energy solutions (how much of the energy mix should be renewable?, rising demand, competitiveness and efficiency, responsible development), Areva's human resources (gender balance, health and safety, diversity and opportunity, hiring and training). Data and balanced scorecard for sustainable development are also given

  19. An Information Building on Radioactivity and Nuclear Energy for the French CEA Cadarache Research Center - 13492

    International Nuclear Information System (INIS)

    The CEA Cadarache research center is one of the 10 research centers of the French Alternative Energies and Atomic Energy Commission (CEA). Distributed throughout various research platforms, it focuses on nuclear fission, nuclear fusion, new energy technologies (hydrogen, solar, biomass) and fundamental research in the field of vegetal biology. It is the most important technological research and development centers for energy in Europe. Considering the sensitive nature of nuclear activities, the questions surrounding the issue of radioactive waste, the nuclear energy and the social, economic and environmental concerns for present and future generations, the French Government asked nuclear actors to open communication and to give all the information asked by the Local Information Commission (CLI) and the public [1]. In this context, the CEA Cadarache has decided to better show and explain its expertise and experience in the area of nuclear energy and nuclear power plant design, and to make it available to stakeholders and to the public. CEA Cadarache receives each year more than 9000 visitors. To complete technical visits of the research facilities and laboratories, a scientific cultural center has been built in 2011 to inform the public on CEA Cadarache research activities and to facilitate the acceptance of nuclear energy in a way suited to the level of knowledge of the visitors. A modern interactive exhibition of 150 m2 allows visitors to find out more about energy, CEA Cadarache research programs, radioactive waste management and radiological impact on the research center activities. It also offers an auditorium for group discussions and for school groups to discover science through enjoyment. This communication center has received several thousand visitors since its opening on October 2011; the initial results of this experience are now available. It's possible to explain the design of this exhibition, to give some statistics on the number of the visitors, their

  20. The Areva Group back-end division - challenges and prospects

    International Nuclear Information System (INIS)

    This document presents the Areva Group back-end division challenges and prospects. Areva, a world nuclear industry leader, analyzes in this document, the high-profile mix of complementary activities of the nuclear energy industry, concerning the back-end division the full range of services for the end of the fuel cycle, the fuel cycle back-end markets, the economic and financial associated considerations. (A.L.B.)

  1. The Areva Group back-end division - challenges and prospects; Le pole aval dans le groupe Areva - enjeux et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-06-01

    This document presents the Areva Group back-end division challenges and prospects. Areva, a world nuclear industry leader, analyzes in this document, the high-profile mix of complementary activities of the nuclear energy industry, concerning the back-end division the full range of services for the end of the fuel cycle, the fuel cycle back-end markets, the economic and financial associated considerations. (A.L.B.)

  2. Literature survey 'Impact of the Cadarache Centre activity on the environment'. Survey performed by the CRIIRAD laboratory for the Cadarache's CLI

    International Nuclear Information System (INIS)

    After a presentation of the Cadarache Centre installations and activities, this document reports a literature survey based on the documents provided by the Centre and related to dismissals and incidents since the beginning of the Centre activity, and to environment control during some critical periods. Several issues are discussed: the radioactive atmospheric effluents and their impact, the control of underground waters, the control of surface water environment (impact of liquid radioactive effluents and monitoring of run-off waters), soil and food chain monitoring. For each of these themes, control and monitoring data are analysed

  3. Areva - Press release from the Supervisory Board; Areva - Communique de presse du Conseil de Surveillance

    Energy Technology Data Exchange (ETDEWEB)

    Marie, Patricia; Briand, Pauline; Floquet-Daubigeon, Fleur; Michaut, Maxime; Scorbiac, Marie de; Repaire, Philippine du

    2012-02-14

    During its meeting held on December 12, 2011, devoted in particular to the examination of the 2011 closing estimates, the AREVA Executive Board indicated that it expected to book a provision of 1.46 billion euros (2.025 billion US dollars) in the company's accounts for fiscal year 2011 for impairment of assets for the reporting entity UraMin, a mining company acquired by AREVA in 2007, which, given the provision booked in 2010 (426 million euros), brings the value of these assets on the AREVA balance sheet down to 410 million euros. Given the size of these provisions, the Supervisory Board decided to make three of its members, meeting as an ad hoc committee, in charge of analyzing the terms of acquisition of this company, as well as the key decisions made in this reporting entity up to 2011 and, based on the outcome of these analyses, to recommend to it any appropriate measures in AREVA's interest. This committee reported on its work during the Supervisory Board meeting held on February 14, 2012. In light of this report, the Supervisory Board found that the fairness and reliability of the financial statements of previous years were not in question. Nevertheless, considering the malfunctions raised, the Board considers it appropriate to thoroughly review AREVA's governance in order to ensure that decisions concerning large acquisitions or investments be reviewed and validated in the future under conditions ensuring better legal and financial security and enabling a more transparent dialogue between management and the Supervisory Board. It thus asked the Executive Board to recommend, at the next General Meeting of Shareholders, that the by-laws of the company be modified to make the Supervisory Board's prior approval of investments, stake acquisitions and acquisitions mandatory above a threshold of 20 million euros. It also decided to set up a business ethics committee within the Supervisory Board responsible for ensuring that rules of conduct are

  4. Areva as of December 31, 2011; Areva au 31 decembre 2011

    Energy Technology Data Exchange (ETDEWEB)

    Marie, Patricia; Briand, Pauline; Michaut, Maxime; Scorbiac, Marie de; Repaire, Philippine du

    2012-01-26

    In 2011, AREVA's consolidated revenue came to 8.872 billion euros, down slightly (-2.6%) compared with 2010 (-1.2% like for like). The decrease in revenue in nuclear operations was partially offset by significant growth in the renewable energies business. Foreign exchange and changes in the scope of consolidation had respectively a negative impact of 113 million euros and 16 million euros over the period. Revenue totaled 2.922 billion euros in the fourth quarter of 2011, stable compared with the fourth quarter of 2010 (-0.5% on a reported basis and -0.5% like for like). Foreign exchange had a negligible impact during the period. Led by nuclear operations, the group's backlog was 45.6 billion euros at December 31, 2011, up 3.1% year on year and 6.7% in relation to September 30, 2011. Order cancellations since Fukushima were limited to 464 million euros as of December 31, 2011. In accordance with the requirements of IFRS 8, AREVA's business segment information is presented for each operating Business Group (BG), which is the level of information examined by the group's governance bodies. Subsequent to the establishment of a subsidiary combining all of the group's mining operations, data for the Mining Business Group are now reported separately from those of the Front End Business Group. Data used for comparisons with 2010 were restated to reflect this new organization. The business segment information therefore corresponds to AREVA's five operating Business Groups: Mining, Front End, Reactors and Services, Back End and Renewable Energies

  5. Areva half-year report june 30, 2006; Areva rapport semestriel 30 juin 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document is the half-year financial report of the Areva group for 2006. It presents: 1 - Highlights of the period; 2 - Key data: Summary data, Segment reporting, Backlog, Income statement, Review by business division, Cash flow, Balance sheet data; 3 - Outlook; 4 - Events subsequent to the half-year end; 5 - Consolidated financial statements: Statutory auditors' report on the interim consolidated financial statements for the period January 1, 2006 to June 30, 2006, Consolidated income statement, Consolidated balance sheet, Consolidated cash flow statement, Consolidated statement of changes in equity, Segment reporting, Notes to the consolidated financial statements.

  6. AREVA Technical Days (ATD) session 1: Energy outlook and presentation of the Areva Group

    International Nuclear Information System (INIS)

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This first session deals with energy challenges and nuclear, public acceptance of nuclear power, mining activities, chemistry activities, enrichment activities, fuel assembly, reactors and services activities, nuclear measurements activities, reprocessing and recycling activities, logistics activities and connectors activities. (A.L.B.)

  7. Areva half-year report June 30, 2008; Areva rapport semestriel 30 juin 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This document is the half-year financial report of the Areva group for 2008. It presents: 1 - the highlights of the period: key data (Summary data, Segment reporting, Backlog, Income statement, Review by division, Cash flow, Balance sheet data); Outlook; 2 - the events subsequent to half-year closing; 3 - the consolidated financial statements: Statutory Auditors' report on half-year 2008 information for the period January 1, 2008 to June 30, 2008, Consolidated income statement, Consolidated balance sheet, Consolidated cash flow statement, Consolidated statement of change in equity, Segment reporting, Notes to the consolidated financial statements for the period ending June 30, 2008.

  8. AREVA and sustainable development. 2002 report; AREVA et le developpement durable. Rapport 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    The performance indicators in this report reflect the major sustainable development impacts and challenges that Areva is facing as a group due to the very nature of its operations. They chose the calendar year as reporting period, from January 1 to December 31. This report covers all of the group operations in France and abroad. This report presents an overview of the major financial, social and environmental challenges facing the group. This report is a companion document to the annual activity report. (A.L.B.)

  9. Areva - first half 2007 financial results

    International Nuclear Information System (INIS)

    This document presents the financial statements of Areva group for the first half of 2007 as submitted by the Executive Board: Sales revenue: euro 5.373 billion, up by 6.7%; Operating income: euro 207 million, i.e. 3.9% operating margin, up 1.6 point compared with H1 2006; Consolidated net income: euro 295 million, i.e. euro 8.31 per share in H1 2007 against euro 6.92 per share in H1 2006, a 20% increase. All Group performance indicators were up the first half of 2007. Growth was robust and profitability strengthened significantly in terms of both operating income and net income. Consolidated sales revenue rose 6.7% for the first half of 2007 alone, after growth of more than 7% in 2006. This positive trend will continue: the backlog grew by 31% in the first half to more than euro 33 billion, compared with euro 26 billion six months ago and euro 21 billion at year-end 2005. Business is up sharply in the Transmission and Distribution division, which had operating margin of 8.7% in the first half of the year

  10. AREVA in 2007, growth and profitability

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This document is the 2007 activity report of the Areva group, the nuclear division of which is Number 1 worldwide in the front end of the nuclear cycle, in pressurized water reactors (in terms of installed capacity), and in the treatment and recycling of used nuclear fuel. The Transmission and Distribution division is Number 1 worldwide in market management software and grid management software, number 2 in high voltage products, and number 3 in medium voltage products. Content: Message from the Chairman of the Supervisory Board; Message from the Chief Executive Officer; Key data; 2007 highlights; Corporate governance; Organization of the group; Share information and shareholder relations; Solutions for CO{sub 2}-free power generation; Solutions for reliable electricity transmission and distribution; Governance; Continuous improvement; Financial performance; Innovation; Customer satisfaction; Commitment to employees; Environmental protection; Risk management and prevention; Dialogue and consensus building; Community involvement; Auditors' report; Reporting methodology; Data verified in 2007; Glossary; and 'to learn more' references.

  11. AREVA - first half 2005 sales figures

    International Nuclear Information System (INIS)

    First half 2005 sales for the AREVA group were up 1.1% to 5,396 million euros and 2.6% like-for-like, compared with 5,339 million euros for the same period in 2004.The change in foreign exchange rates had a negative impact of nearly (34) million euros between these two periods, which was much less than between the first half of 2003 and the same period in 2004. Sales are up 1.1% compared with the first half of 2004 (up 2.6% like-for-like); the euros (17.3) M impact of IFRS adoption is limited to the Front End division; Energy is up: Nuclear Power: up 4.4% (up 5.5% like-for-like), driven by the Front End and Reactors and Services divisions; T and D: down 3.9% (-2.1% like-for-like) due to the one time peak observed in early 2004; Connectors sales are stable (+0.3% like-for-like): Automotive performed well, while the communication market continued to be a difficult one

  12. Integral needs for MOX powders: state of the art at Cea Cadarache on MOX fuel experiments

    International Nuclear Information System (INIS)

    Several experimental programmes have been conducted at CEA connected with the use of MOX in commercial PWR or innovative concepts, such as high conversion light water reactors (HCLWRs) and at various moderation ratios. Measurements of integral parameters of interest were performed using fission chambers and gamma-scanning techniques, or by oscillation techniques. This paper presents an overview of the experimental programmes performed at the EOLE and MINERVE facilities located at CEA Cadarache. (author)

  13. Influence of high-permeability discs in an axisymmetric model of the Cadarache dynamo experiment

    Science.gov (United States)

    Giesecke, A.; Nore, C.; Stefani, F.; Gerbeth, G.; Léorat, J.; Herreman, W.; Luddens, F.; Guermond, J.-L.

    2012-05-01

    Numerical simulations of the kinematic induction equation are performed on a model configuration of the Cadarache von-Kármán-sodium dynamo experiment. The effect of a localized axisymmetric distribution of relative permeability μr that represents soft iron material within the conducting fluid flow is investigated. The critical magnetic Reynolds number Rmc for dynamo action of the first non-axisymmetric mode roughly scales like Rmcμr - Rmc∞∝μ-1/2r, i.e. the threshold decreases as μr increases. This scaling law suggests a skin effect mechanism in the soft iron discs. More important with regard to the Cadarache dynamo experiment, we observe a purely toroidal axisymmetric mode localized in the high-permeability discs which becomes dominant for large μr. In this limit, the toroidal mode is close to the onset of dynamo action with a (negative) growth rate that is rather independent of the magnetic Reynolds number. We qualitatively explain this effect by paramagnetic pumping at the fluid/disc interface and propose a simplified model that quantitatively reproduces numerical results. The crucial role of the high-permeability discs in the mode selection in the Cadarache dynamo experiment cannot be inferred from computations using idealized pseudo-vacuum boundary conditions (H × n = 0).

  14. 'Action 2016': AREVA's strategic action plan

    International Nuclear Information System (INIS)

    On December 13, 2011, Luc Oursel, CEO, and Pierre Aubouin, Chief Financial Officer presented the group's strategic plan for the period 2012-2016. The plan has been drawn up collectively and is based on a thorough-going analysis and a realistic assessment of perspectives for all group activities and associated resources. Development of nuclear and renewable energies: the fundamentals are unchanged. In this context, the German decision remains an isolated case and the great majority of nuclear programs around the world have been confirmed. More conservative in its projections than the International Energy Agency, the group expects growth of 2.2% annually, reaching 583 GW of installed nuclear capacity by 2030, against 378 GW today. However, the Fukushima accident will lead to delays in launching new programs. 'Action 2016' plan aims to consolidate AREVA's leadership in nuclear energy and become a leading player in renewable energy. The group's strategic action plan 'Action 2016' is based on the following strategic choices: - commercial priority given to value creation, - selectivity in investments, - strengthening of the financial structure. These demand an improvement in the group's performance by 2015. This plan makes nuclear safety a strategic priority for the industrial and commercial performance of the group. This ambitious performance plan for the period 2012-2016 will give the group the wherewithal to withstand a temporary slowdown in the market resulting from the Fukushima accident and to deliver safe and sustainable growth of the business. The plan sets out the strategic direction for the group's employees for the years ahead: taking advantage of the expected growth in nuclear and renewable energies, targeted investment programs, and return to self-financing as of 2014

  15. AREVA HTR concept for near-term deployment

    Energy Technology Data Exchange (ETDEWEB)

    Lommers, L.J., E-mail: lewis.lommers@areva.com [AREVA Inc., 2101 Horn Rapids Road, Richland, WA 99354 (United States); Shahrokhi, F. [AREVA Inc., Lynchburg, VA (United States); Mayer, J.A. [AREVA Inc., Marlborough, MA (United States); Southworth, F.H. [AREVA Inc., Lynchburg, VA (United States)

    2012-10-15

    This paper introduces AREVA's High Temperature Reactor (HTR) steam cycle concept for near-term industrial deployment. Today, nuclear power primarily impacts only electricity generation. The process heat and transportation fuel sectors are completely dependent on fossil fuels. In order to impact this energy sector as rapidly as possible, AREVA has focused its HTR development effort on the steam cycle HTR concept. This reduces near-term development risk and minimizes the delay before a useful contribution to this sector of the energy economy can be realized. It also provides a stepping stone to longer term very high temperature concepts which might serve additional markets. A general description of the current AREVA steam cycle HTR concept is provided. This concept provides a flexible system capable of serving a variety of process heat and cogeneration markets in the near-term.

  16. Proceedings of the Areva Technical Days. Session 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document presents the proceedings of the Areva technical days, presented during the session 5 the 9 and 10 december 2004, at Istanbul. It deals with the operations of the transmission and distribution division. With manufacturing facilities in over 40 countries and a sales network in over 100, Areva offers customers technological solutions for nuclear power generation and electricity transmission and distribution (the Group also provides interconnect systems to the telecommunications, computer and automotive markets). It provides five topics: a general presentation of Areva, the strategic stakes for transmission and distribution by world-zone, economic and strategic stakes of business unit products, business unit systems and business unit automation. (A.L.B.)

  17. Proceedings of the Areva Technical Days. Session 5

    International Nuclear Information System (INIS)

    This document presents the proceedings of the Areva technical days, presented during the session 5 the 9 and 10 december 2004, at Istanbul. It deals with the operations of the transmission and distribution division. With manufacturing facilities in over 40 countries and a sales network in over 100, Areva offers customers technological solutions for nuclear power generation and electricity transmission and distribution (the Group also provides interconnect systems to the telecommunications, computer and automotive markets). It provides five topics: a general presentation of Areva, the strategic stakes for transmission and distribution by world-zone, economic and strategic stakes of business unit products, business unit systems and business unit automation. (A.L.B.)

  18. Responsible Development of AREVA's Mining Activities - Report 2012

    International Nuclear Information System (INIS)

    By defining AREVA's strategy and policies, this report aims to demonstrate the company's performance in the key areas of mining activity responsibility: ethics and governance, social report, the environment, occupational health and safety, community involvement, commitments to stakeholders. The data given cover the assets for which AREVA acts as operator in uranium mining activities: exploration, project development, production and rehabilitation. The consolidated data target activities in France, Canada, Niger, Kazakhstan, Mongolia, Gabon and Namibia. Activities in the Central African Republic and those linked to La Mancha no longer fall within the scope of this report (sale of assets in 2012). This report is the third edition of this annual exercise

  19. Responsible Development of Areva's Mining Activities. 2010 report

    International Nuclear Information System (INIS)

    After a map indicating the location of the main Areva's mining sites, this report provides several key figures and data and discusses the evolution of this activity which is part of the business core of the AREVA company. It gives a statement of values and principles, governance and commitments related to this activity. In order to report this activity, it addresses several topics: reduction of industrial risks, protection of workers and populations, rational consumption of water and energy resources, biodiversity preservation, management over time of waste rock and mining tailings, sustainable integration into territories, and contribution to social development. This document is proposed in French and in English

  20. Areva half-year report june 30, 2007; Areva rapport semestriel 30 juin 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Information provided in this document concerns the AREVA group as a whole. It presents the highlights and Key data of the first half of 2007, the outlook, the events subsequent to half-year closing, and the Consolidated financial statements. Contents: 1 - Highlights of the period; 2 - Key data: Summary data, Segment reporting, Backlog, Income statement, Review by division, Cash flow, Balance sheet data; 3 - Outlook; 4 - Events subsequent to half-year closing; 5 - Consolidated financial statements: Statutory Auditors' report on half-year information for the period January 1, 2007 to June 30, 2007, Consolidated income statement, Consolidated balance sheet, Consolidated cash flow statement, Consolidated statement of change in equity, Segment reporting, Notes to the consolidated financial statements for the period ending June 30, 2007.

  1. Areva - First half 2008 sales revenue; Areva - Chiffre d'affaires du 1. semestre 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    As of June 30, 2008, AREVA's backlog stood at 38.1 billion euro, for 13.6% growth since June 30, 2007, with 9.9% growth in Nuclear and 40.7% growth in Transmission and Distribution. In Nuclear, the backlog came to 32.3 billion euro as of the end of June 2008. In the front end of the cycle, AREVA signed multi-year contracts in the first half of the year with Japanese and American utilities and with EDF, for a combined total of more than 1 billion euro. Of note in the back end of the cycle is the contract AREVA signed with the U.S. Department of Energy to build a MOX fuel fabrication facility. In Transmission and Distribution, the backlog came to 5.8 billion euro as of the end of period. A total of 3.2 billion euro in orders was booked in the first half, an increase of 20.0% year-on-year. The division won several important contracts, most notably a contract with Dubai Electricity (more than 130 million euro), a contract with National Grid and RTE for the renovation of the IFA 2000 grid interconnection between France and Great Britain (more than 60 million euro), and, in the industrial field, a contract with Rio Tinto Alcan (close to 65 million euro). The group cleared revenue of 6.2 billion euro in the first half of 2008, up 14.8% (+16.4% like-for-like) compared with the first half of 2007. Sales outside France were up 14.3% to 4.2 billion euro or 68.6% of total sales; the latter were stable compared with the first half of 2007. All businesses were up, with growth of 15.9% in Nuclear operations (+19.1% LFL1) - particularly in Reactors and Services (+31.3% LFL1) - and 13.0% growth in Transmission and Distribution operations (+12.0% LFL T 1). Foreign exchange had a negative impact of 155 million euro, primarily due to the change in the U.S. dollar in relation to the euro. Changes in the consolidated group had a positive impact of 97 million euro, mainly reflecting acquisitions in the Transmission and Distribution division and in Renewable Energies. Sales revenue

  2. FCC-NG: the Areva safe fresh fuel shipping cask to deliver the future EPRtm reactors - 141

    International Nuclear Information System (INIS)

    AREVA as a worldwide PWR fuel provider has to have a fleet of fresh UO2 shipping casks being agreed within a lot of countries and to accommodate foreseen EPRTM Nuclear Power Plants fuel buildings. To reach this target the AREVA NP Fuel Sector together with TN International (a subsidiary of AREVA NC) decided to develop an up to date shipping cask gathering experience feedback of the today fleet and an improved safety allowing the design to comply with international regulations (NRC and IAEA) and other local foreign Safety Authorities requirements. Based on pre design features a safety case was set up to highlight safety margins. Criticality hypothetical accidental assumptions were defined: - Preferential flooding, - Fuel rod array expansion (so called 'bird caging' effect), - Fuel sliding, - Neutron absorber penalty, - ... The French criticality code package CRISTAL is used to check several configuration Keff and derived safety margins. The CRISTAL code package relies on a wide validation process helping defining uncertainties as required by regulations in force. The shipping cask, containing two fuel assemblies, is designed to maximize fuel isolation inside the cask and with neighboring ones even for large array configuration cases. Few and proven industrial products are used: - Stainless steel for the structural frame, - Balsa wood for impact limiters, - BORAR resin as neutron absorber. The cask is designed to handle mainly the EPRTM fuel assembly type and may be extended to other contents such as APWR fuel assembly type. After a brief presentation of the computer codes and the description of the shipping cask, the CRISTAL calculation results as well as the allowances for biases and uncertainties will be discussed. (authors)

  3. A worldwide fuel strategy by AREVA

    International Nuclear Information System (INIS)

    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 HTPTM alloy as the reference material for cladding tubes, guide thimbles, and grids, -- Gradual incorporation of the valuable high-stiffiness MONOBLOCtM 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

  4. AREVA Technical Days (ATD) session 4: operations of the front-end division of the nuclear fuel cycle; AREVA Technical Days (ATD) session 4: les activites du pole Amont

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This fourth session deals with the strategic and financial significance of the Areva mining operations, the Areva chemistry business, the Areva enrichment business and the Areva fuel business. (A.L.B.)

  5. AREVA's social licensing experience in Northern Saskatchewan, Canada

    International Nuclear Information System (INIS)

    Full text: The Athabasca Basin area in the northern part of the Province of Saskatchewan has for many years been the world's leading uranium producing region. The current generation of projects date back to the 1970s, and in addition to a strong record for safety and environmental protection, have featured a complementary focus on social considerations. AREVA Resources Canada Inc. is the majority owner and operator of two of these projects. The Cluff Lake Project operated from 1981 to 2002, and is well advanced with decommissioning. McClean Lake Operation commenced operation in 1999 and has a lengthy future. This paper will discuss the development of these projects from the perspective of obtaining and maintaining a 'social licence'. It will briefly describe the physical and socioeconomic environment, and the main public policy decisions underlying the approach to social licensing. It will then describe the various socioeconomic programs, including the challenges and successes in their implementation. It will conclude with a brief look at future challenges and opportunities. The socioeconomic programs are supported by our joint venture partners, and AREVA Resources Canada supports similar programs in projects where we have a minority joint venture interest. Overall, the experience of AREVA Resources Canada in northern Saskatchewan reflects the AREVA Group's approach to sustainable development, tailored to the specific local environment of our projects. (author)

  6. Wind power: Areva acquires a 51% stake in Multibrid

    International Nuclear Information System (INIS)

    AREVA announced the acquisition of a 51% stake in Multibrid, a designer and manufacturer of multi-megawatt off-shore wind turbines based in Germany. With this acquisition, AREVA has entered into a joint venture with Prokon Nord, a German off-shore wind turbine and biomass plant developer and current owner of Multibrid. This transaction values Multibrid at euro 150 million. AREVA plans to rapidly further develop Multibrid's activities by giving the company access to its industrial resources, financial base and international commercial network. In return, Multibrid will provide AREVA with its leading-edge technology which, developed for 5 MW turbines, can achieve a very high output while reducing operating costs thanks to a simplified maintenance system. With this stake in Multibrid, AREVA aims to increase its presence on the offshore wind market that meets land settlement requirements and that should grow significantly in the years to come (from 300 MW in Europe today to an expected 1400 MW by 2011). As an exclusive supplier of Prokon Nord, Multibrid will participate in projects such as Borkum West (30 MW), the first offshore project in Germany, Borkum West 2 (400 MW), and Cote d'Albatre (105 MW), the first offshore wind farm project in France. The stake in Multibrid strengthens AREVA's strategic positioning on the CO2-free energy market, thanks to complementary solutions ranging from nuclear technologies to renewables. A number of recent achievements illustrate this strategy: - bio-energy (crucial energy supply in numerous rural areas): delivery of turnkey biomass power plants; ongoing construction of 10 plants in India, Thailand and Brazil; future development plans in fast-growing regions, such as Latin America; - wind power: Multibrid adds to the Group's stake in REpower and to its partnership with Suzlon for which AREVA is the number one supplier of transmission and distribution solutions for wind power; - hydrogen and fuel cells: design and manufacture of power

  7. Results of a large scale neutron spectrometry and dosimetry comparison exercise at the Cadarache moderator assembly

    International Nuclear Information System (INIS)

    Eurados Working Group 7 recently organised a large-scale comparison of neutron spectrometry and dosimetry measurements at the IPSN/SDOS laboratory of the CEA Cadarache Research Centre in France. A large number of participants took part with a range of instruments including spectrometers, tissue-equivalent proportional counters, personal dosemeters, and survey instruments. The neutron field used for the exercise was a primarily low energy neutron spectrum similar to those which have been measured recently around nuclear facilities. This paper presents the results of the measurements and attempts to draw conclusions about the accuracy attainable with the various devices, their advantages and drawbacks, and potential problems. (author)

  8. Influence of high permeability disks in an axisymmetric model of the Cadarache dynamo experiment

    OpenAIRE

    A. Giesecke; Nore, C.; Stefani, F.; Gerbeth, G.; Léorat, J.; Herreman, W; Luddens, F.; Guermond, J.-L

    2011-01-01

    Numerical simulations of the kinematic induction equation are performed on a model configuration of the Cadarache von-K\\'arm\\'an-Sodium dynamo experiment. The effect of a localized axisymmetric distribution of relative permeability {\\mu} that represents soft iron material within the conducting fluid flow is investigated. The critical magnetic Reynolds number Rm^c for dynamo action of the first non-axisymmetric mode roughly scales like Rm^c({\\mu})-Rm^c({\\mu}->infinity) ~ {\\mu}^(-1/2) i.e. the ...

  9. French fission products experiments performed in Cadarache and Valduc. Results comparison

    International Nuclear Information System (INIS)

    Cofunded by Cogema, two complementary experimental programmes on burn up credit (BUC) related to fission products (FPs) are performed by CEA and IRSN at Cadarache and Valduc. After shortly recalling the main characteristics of each experiment, a first comparison of some results is presented, especially the energy range in which most part of cross section absorption are qualified. Both experiments exhibit great quality and accurate results, giving a high degree of confidence to the whole experimental French process of qualification devoted to BUC. (author)

  10. AREVA Technical Days (ATD) session 4: operations of the front-end division of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This fourth session deals with the strategic and financial significance of the Areva mining operations, the Areva chemistry business, the Areva enrichment business and the Areva fuel business. (A.L.B.)

  11. Nuclear renaissance in the reactor training of Areva

    International Nuclear Information System (INIS)

    Because of the perspectives of new builds, a significant increase in the number of design, construction and management personnel working in AREVA, their clients and sub-contractors has been estimated for the next future. In order to cope with the challenge to integrate newly hired people quickly and effectively into the AREVA workforce, a project - 'Training Task Force (TTF)' - was launched in 2008. The objective was to develop introductory and advanced courses and related tools harmonized between AREVA Training Centers in France, Germany and USA. First, a Global Plants Introductory Session (GPIS) was developed for newly hired employees. GPIS is a two weeks training course introducing in a modular way AREVA and specifically the activities and the reactors technical basics. As an example, design and operation of a nuclear power plant is illustrated on EPRTM. Since January 2009, these GPIS are held regularly in France, Germany and the US with a mixing of employees from these 3 regions. Next, advanced courses for more experienced employees were developed: - Advanced EPRTM, giving a detailed presentation of the EPRTM reactor design; - Codes and Standards; - Technical Nuclear Safety. Finally, feasibility studies on a Training Material Management (TMM) system, able to manage the training documentation, and on a worldwide training administration tool, were performed. The TTF project was completed mid of 2009; it transferred their recurrent activities to a new AREVA training department. This unit now consists of the French, German and US Reactors Training Centers. In particular, all courses developed by the TTF are now implemented worldwide with an opening to external trainees. The current worldwide course catalogue includes training courses for operation and maintenance personnel as well as for managers, engineers and non technical personnel of nuclear operators, suppliers, safety authorities and expert organizations. Training delivery is supported effectively by tools

  12. Nuclear renaissance in the reactor training of Areva

    Energy Technology Data Exchange (ETDEWEB)

    De Braquilanges, Bertrand [Reactor Training Center/France Manager, La Tour Areva - 1, place Jean Millier - 92084 Paris - La Defense (France); Napior, Amy [Reactor Training Center/USA Manager, 1300 Old Graves Mill Road - Lynchburg VA, 2450 (United States); Schoenfelder, Christian [Reactor Training Center/Germany Manager, Kaiserleistrasse 29 - 63067 Offenbach (Germany)

    2010-07-01

    Because of the perspectives of new builds, a significant increase in the number of design, construction and management personnel working in AREVA, their clients and sub-contractors has been estimated for the next future. In order to cope with the challenge to integrate newly hired people quickly and effectively into the AREVA workforce, a project - 'Training Task Force (TTF)' - was launched in 2008. The objective was to develop introductory and advanced courses and related tools harmonized between AREVA Training Centers in France, Germany and USA. First, a Global Plants Introductory Session (GPIS) was developed for newly hired employees. GPIS is a two weeks training course introducing in a modular way AREVA and specifically the activities and the reactors technical basics. As an example, design and operation of a nuclear power plant is illustrated on EPRTM. Since January 2009, these GPIS are held regularly in France, Germany and the US with a mixing of employees from these 3 regions. Next, advanced courses for more experienced employees were developed: - Advanced EPR{sup TM}, giving a detailed presentation of the EPR{sup TM} reactor design; - Codes and Standards; - Technical Nuclear Safety. Finally, feasibility studies on a Training Material Management (TMM) system, able to manage the training documentation, and on a worldwide training administration tool, were performed. The TTF project was completed mid of 2009; it transferred their recurrent activities to a new AREVA training department. This unit now consists of the French, German and US Reactors Training Centers. In particular, all courses developed by the TTF are now implemented worldwide with an opening to external trainees. The current worldwide course catalogue includes training courses for operation and maintenance personnel as well as for managers, engineers and non technical personnel of nuclear operators, suppliers, safety authorities and expert organizations. Training delivery is supported

  13. Areva 2007 results: accelerated growth and significantly improved profitability

    International Nuclear Information System (INIS)

    The AREVA group recorded accelerated growth and increased profitability in 2007, meeting both of its objectives for the year. The group made strategic inroads in fast growing markets. AREVA's integrated model met with record success in China, where GGNPC acquired two EPR nuclear islands in a combined order including both the reactors and the fuel, and the creation of a joint venture in engineering. Its T and D division was awarded the largest contract of its history in Qatar, making it the leader in a region where T and D was not even present a few years ago. For more than three years, AREVA has built up its capacity to meet surging demand in the nuclear power and T and D markets through an active policy of research and development and by capitalizing on the diversity and strength of its partnerships. Areva hired 8,600 people in 2006 and 11,500 people in 2007; this represents an investment in recruitment, training and integration of approximately euro 200 million per year. For 2008, the group foresees a further increase in its backlog, sales revenue and operating income. The Areva Group financial statements for 2007 are summarized below: - Backlog: euro 39.8 billion, up 55%; - Sales revenue: euro 11.9 billion, up 9.8% (up 10.4% like-for-like); - Operating income: euro 751 million, i.e. 6.3% operating margin, up 2.6 points compared with 2006; - Net income attributable to equity holders of the parent: euro 743 million (euro 20.95 per share), up from euro 649 million in 2006 (euro 18.31 per share); - Net debt: euro 1.954 billion, linked to the acquisition of UraMin; - Dividend: euro 6.77, to be proposed to the Annual General Meeting of Shareholders convening on April 17, 2008

  14. Phenomenology of large Nc QCD

    International Nuclear Information System (INIS)

    These lectures are designed to introduce the methods and results of large Nc QCD in a presentation intended for nuclear and particle physicists alike. Beginning with definitions and motivations of the approach, we demonstrate that all quark and gluon Feynman diagrams are organized into classes based on powers of 1/Nc. We then show that this result can be translated into definite statements about mesons and baryons containing arbitrary numbers of constituents. In the mesons, numerous well-known phenomenological properties follow as immediate consequences of simply counting powers of Nc, while for the baryons, quantitative large Nc analyses of masses and other properties are seen to agree with experiment, even when 'large' Nc is set equal to its observed value of 3. Large Nc reasoning is also used to explain some simple features of nuclear interactions. (author)

  15. Pro Engineerin NC-ohjelmointi

    OpenAIRE

    Tervo, Toni

    2003-01-01

    Insinöörityön ensisijaisena tavoitteena oli selvittää NC-ohjelman luonti Pro Engineerillä ja dokumentoida prosessi. Työssä tutustuttiin Pro Engineerin Manufacture-toimintoon, jonka avulla työstöratojen määrittely sekä niiden simulointi on mahdollista. Toissijaisena tavoitteena oli luoda NC-ohjelma valitulle kappaleelle ja yrittää koneistaa se koulun NC-koneella. Työssä selvitettiin NC-ohjelman luonnin kaikista vaiheista tärkeimmät asiat toimivan ohjelman luomiseksi. Ensimmäisessä vaiheessa...

  16. Influence of high permeability disks in an axisymmetric model of the Cadarache dynamo experiment

    CERN Document Server

    Giesecke, A; Stefani, F; Gerbeth, G; Léorat, J; Herreman, W; Luddens, F; Guermond, J -L

    2011-01-01

    Numerical simulations of the kinematic induction equation are performed on a model configuration of the Cadarache von-K\\'arm\\'an-Sodium dynamo experiment. The effect of a localized axisymmetric distribution of relative permeability {\\mu} that represents soft iron material within the conducting fluid flow is investigated. The critical magnetic Reynolds number Rm^c for dynamo action of the first non-axisymmetric mode roughly scales like Rm^c({\\mu})-Rm^c({\\mu}->infinity) ~ {\\mu}^(-1/2) i.e. the threshold decreases as {\\mu} increases. This scaling law suggests a skin effect mechanism in the soft iron disks. More important with regard to the Cadarache dynamo experiment, we observe a purely toroidal axisymmetric mode localized in the high permeability disks which becomes dominant for large {\\mu}. In this limit, the toroidal mode is close to the onset of dynamo action with a (negative) growth-rate that is rather independent of the magnetic Reynolds number. We qualitatively explain this effect by paramagnetic pumping...

  17. Cadarache, January 17, 2012. A nuclear crisis exercise with a seismic dimension

    International Nuclear Information System (INIS)

    As France is a region with a moderate seismicity, the new French seismic zoning indicates that the Cadarache CEA centre and the surrounding communities are located in a region exhibiting a seismicity which is greater than the metropolitan average. Therefore, a project of organizing a nuclear crisis exercise emerged with taking this seismic risk into account. This exercise took place on the 17 January 2012. This article presents its objectives which addressed the ability of public authorities and of the operator to manage a nuclear accident caused by an earthquake and its consequences in terms of civilian security and nuclear safety. The article also briefly presents the Cadarache centre within its seismic environment, and how the seismic risk had been taken into account when designing and dimensioning some of its installations. It also evokes the ASN prescriptions made after the decennial safety inspections. Several actors, institutions and organizations have been involved in the exercise and in its preparation, and this preparation had some consequences on the awareness of local authorities on the seismic risk. The adopted scenario is briefly presented as well as the performance of simulations. The main lessons learned are briefly discussed

  18. Areva - first half 2007 financial results; Areva - resultats du 1. semestre 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document presents the financial statements of Areva group for the first half of 2007 as submitted by the Executive Board: Sales revenue: euro 5.373 billion, up by 6.7%; Operating income: euro 207 million, i.e. 3.9% operating margin, up 1.6 point compared with H1 2006; Consolidated net income: euro 295 million, i.e. euro 8.31 per share in H1 2007 against euro 6.92 per share in H1 2006, a 20% increase. All Group performance indicators were up the first half of 2007. Growth was robust and profitability strengthened significantly in terms of both operating income and net income. Consolidated sales revenue rose 6.7% for the first half of 2007 alone, after growth of more than 7% in 2006. This positive trend will continue: the backlog grew by 31% in the first half to more than euro 33 billion, compared with euro 26 billion six months ago and euro 21 billion at year-end 2005. Business is up sharply in the Transmission and Distribution division, which had operating margin of 8.7% in the first half of the year.

  19. AREVA - first half 2005 sales figures; AREVA - chiffre d'affaires du 1. semestre 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    First half 2005 sales for the AREVA group were up 1.1% to 5,396 million euros and 2.6% like-for-like, compared with 5,339 million euros for the same period in 2004.The change in foreign exchange rates had a negative impact of nearly (34) million euros between these two periods, which was much less than between the first half of 2003 and the same period in 2004. Sales are up 1.1% compared with the first half of 2004 (up 2.6% like-for-like); the euros (17.3) M impact of IFRS adoption is limited to the Front End division; Energy is up: Nuclear Power: up 4.4% (up 5.5% like-for-like), driven by the Front End and Reactors and Services divisions; T and D: down 3.9% (-2.1% like-for-like) due to the one time peak observed in early 2004; Connectors sales are stable (+0.3% like-for-like): Automotive performed well, while the communication market continued to be a difficult one.

  20. Decree of January 11, 2016 bearing homologation of the decision nr 2015-DC-0536 by the Nuclear Safety Authority of December 22, 2015 defining threshold values of releases in the environment of liquid and gaseous effluents from base nuclear installations nr 33 (UP2-400), 38 (STE2 et AT1), 47 (ELAN II B), 80 (HAO), 116 (UP3-A), 117 (UP2-800) and 118 (STE3 effluent processing station) exploited by AREVA NC on the La Hague site (Manche district)

    International Nuclear Information System (INIS)

    After having mentioned the various related and reference legal texts, this legal publication specifies the various threshold values which must be applied to liquid and gaseous releases of nuclear installations located in La Hague for a better control and management of pollutions and of the impact of these installations on the environment. Threshold values are thus specified for various compounds and species, and the document also mentions AREVA's publications which indicate the actual release levels and state that these levels are within the accepted limits

  1. Status of safety at Areva group facilities. 2007 annual report

    International Nuclear Information System (INIS)

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

  2. Responsible Development of Areva's Mining Activities. Report 2011

    International Nuclear Information System (INIS)

    After a presentation of the approach to responsibility adopted by AREVA to be a responsible mining stake holder (charter of values, implemented policies, risk prevention and management, best practices), this report gives an overview of mining activities (international presence, production in constant increase) with a focus on uranium mining which is the core business (the different phases are briefly presented: exploration, project development, mining, site decommissioning). It outlines personnel qualification and commitment, actions and policy in the field of personnel health and safety. It addresses the environmental policy: key levers, environmental management system, examples throughout the entire mining life cycle, changes in site consumptions and emissions, promotion of biodiversity. The next part concerns Areva's social commitment (dialogue, development aid in mining territories). Then, performance is expressed in terms of indicators for these different issues (teams, environmental policy, social involvement)

  3. Logistics of the research reactor fuel cycle: AREVA solutions

    International Nuclear Information System (INIS)

    The AREVA Group Companies offer comprehensive solutions for the entire fuel cycle of Research Reactors comply with IAEA standards. CERCA and Cogema Logistics have developed a full partnership in the front end cycle. In the field of uranium CERCA and Cogema Logistics have the long term experience of the shipment from Russia, USA to the CERCA plant.. Since 1960, CERCA has manufactured over 300,000 fuel plates and 15,000 fuel elements of more than 70 designs. These fuel elements have been delivered to 40 research reactors in 20 countries. For the Back-End stage, Cogema and Cogema Logistics propose customised solutions and services for international shipments. Cogema Logistics has developed a new generation of packaging to meet the various needs and requirements of the Laboratories and Research Reactors all over the world, and complex regulatory framework. Comprehensive assistance dedicated, services, technical studies, packaging and transport systems are provided by AREVA for every step of research reactor fuel cycle. (author)

  4. Environmental, social, and corporate report 2012 - Cezus Ugine (Areva)

    International Nuclear Information System (INIS)

    CEZUS, a subsidiary of AREVA, is the global leader in the market for zirconium, the metal used, among other things, for nuclear fuel cladding. CEZUS's operations are distributed over six sites. The site in Ugine handles production of ingots and transformation of zirconium, titanium, tantalum, and hafnium into semi-finished products. This document shows details of the CEZUS Ugine facility and its 2012 initiatives on: consumption and waste management, risk management, environmental and safety management, social and corporate responsibilities

  5. Environmental, social, and corporate report 2012 - Cezus Paimboeuf (Areva)

    International Nuclear Information System (INIS)

    CEZUS, a subsidiary of AREVA, is the global leader in the market for zirconium, the metal used, among other things, for fuel cladding in the heart of nuclear reactors. CEZUS's operations are distributed over six sites. The site in Paimboeuf, in the Loire-Atlantique department, fabricates zirconium-alloy cladding tubes and guide tubes. This document shows details of the CEZUS Paimboeuf facility and its 2012 initiatives on: consumption and waste management, risk management, environmental and safety management, social and corporate responsibilities

  6. Areva 2006 figures - Economic, social, societal and environmental data

    International Nuclear Information System (INIS)

    This document presents the 2006 economic, social, societal and environmental data of the Areva Group. Content: 1 - Improvement initiative: Continuous improvement, Innovation, stakeholder relations, local economic development, Financial performance; 2 - Commitment to employees: Health and safety, Radiation protection, Radiological impacts, Technological risks, employees and training; 3 - Environment: Water, Energy, Gaseous releases, Liquid releases, Conventional waste, Radioactive waste; 4 - Reporting and performance indicators: Reporting methodology, Auditors' report, Social indicators, Environmental indicators

  7. Areva. Nine-month 2007 sales revenue and data

    International Nuclear Information System (INIS)

    The main information concerning the nine-month 2007 financial data of the Areva group is a steady growth of 9-month sales revenue, at euro 8.066 billion (+6.8% like-for-like), including euro 2.692 billion in the 3. quarter, i.e. +7.6% like-for-like. The group confirms its strong sales revenue growth objective for 2007

  8. Environmental, social, and corporate report 2012 - Cezus Rugles (Areva)

    International Nuclear Information System (INIS)

    CEZUS, a subsidiary of AREVA, is the global leader in the zirconium market, the metal used, among other things, for fuel assembly tube cladding in the heart of nuclear reactors. CEZUS's operations are distributed over six sites: the Rugles site manufactures flat products originated from the pilgering of rectangular billets. This document shows details of the CEZUS Rugles facility and its 2012 initiatives on: consumption and waste management, risk management, environmental and safety management, social and corporate responsibilities

  9. Environmental, social, and corporate report 2012 - Cezus Jarrie (Areva)

    International Nuclear Information System (INIS)

    CEZUS, an AREVA group subsidiary, is the global leader in the market for nuclear-grade zirconium. Zirconium is a metal used for fuel cladding, among other applications. CEZUS operates at six sites; the Jarrie site in the Isere department of France produces zirconium sponge. This document shows details of the CEZUS Jarrie facility and its 2012 initiatives on: consumption and waste management, risk management, environmental and safety management, social and corporate responsibilities

  10. Environmental, social, and corporate report 2010 - Cezus Ugine (Areva)

    International Nuclear Information System (INIS)

    CEZUS, a subsidiary of AREVA, is the global leader in the market for zirconium, the metal used, among other things, for nuclear fuel cladding. CEZUS's operations are distributed over six sites. The site in Ugine handles production of ingots and transformation of zirconium, titanium, tantalum, and hafnium into semi-finished products. This document shows details of the CEZUS Ugine facility and its 2010 initiatives on: consumption and waste management, risk management, environmental and safety management, social and corporate responsibilities

  11. Dose constraint implementation in AREVA group: an optimization tool

    International Nuclear Information System (INIS)

    AREVA offers customers reliable technology solutions for CO2 free power generation and electricity transmission and distribution. The group counts 68000 employees worldwide and for its nuclear activities there are about 33.000 people who work under ionizing radiation. Risk management and prevention is one of the ten engagements of the sustainable development policy of AREVA, to establish and maintain the highest level of nuclear and occupational safety in all of the group's operations to preserve public and worker health, and to protect the environment. The implementation of these engagements is founded on a voluntary continuous improvement program, AREVA Way: objectives, common for the all entities, are laid down in the policies documents. Indicators are defined and a common reporting method for each indicator and the result of performance self-assessment is set up. AREVA chose to federate the whole of the nuclear entities around a common policy, the Nuclear Safety Charter, implemented at the beginning of 2005. This charter sets up principles of organization, action and engagements of transparency. Regarding radiation protection, the Charter reaffirms the engagement to limit in the installations of the group, at a level as low as reasonably possible, the exposure of the workers, through the implementation of the ALARA principle and the implementation of a continuous improvement policy. This approach, basically different from the simple respect of imposed limits, radically modifies the dynamics of progress. In the activities of engineering, the optimization of protection against radiation is also integrated in the design, by taking account the experience feedback of the operational activities. This determination of constraints is taken on all levels of the organization. Thus sustainable development performance indicators and especially those relating to protection against radiation are discussed between the managers in charge of Units Business and the Top managers

  12. Areva. 2007 figures economic, social, societal and environmental data

    International Nuclear Information System (INIS)

    This document presents the 2007 economic, social, societal and environmental data of the Areva Group. Content: 1 - Improvement initiative: Continuous improvement, Innovation; 2 - Financial performance: 2007 results; 3 - Commitment to employees: Stakeholder relations, Health and safety, Radiation protection, Radiological impacts, Technological risks, Workforce, Workforce and training; 4 - Environment: Water, Energy, Gaseous releases, Liquid releases, Conventional waste, Radioactive waste; 5 - Reporting and performance indicators: Reporting methodology, Auditors' report, Social indicators, Environmental indicators

  13. Areva - Results for the first half of 2009

    International Nuclear Information System (INIS)

    Areva Group's results for the first half of 2009 can be summarized as follows: - Backlog of 48,876 million euro: +28% compared to June 30, 2008; - Sales revenue of 6,522 million euro: + 6% compared to the first half of 2008; - Operating income before additional provision for the Finnish OL3 project: 566 million euro, representing an operating margin of 8.7%; - Operating income: 16 million euro; - Net income attributable to equity holders of the parent: 161 million euro, or 4.55 euro per share; - Net debt of 6,414 million euro; - AREVA capital increase and opening of capital to strategic and industrial partners and launch of an open call for bids for the T and D activity; - Granting of a long-term Standard and Poor's 'A' rating and confirmation of the short-term 'A1' rating - stable outlook. Based on the consolidation scope as at June 30, 2009, AREVA anticipates for the financial year 2009: - strong growth in the backlog; - strong growth in sales revenue; - operating income close to that of the financial year 2008. The document includes the transparencies of the presentation of the first half 2009 results

  14. AREVA in Niger, a long term uranium producer

    International Nuclear Information System (INIS)

    Full text: Niger ranks number three amongst uranium producing countries and holds the fourth world resources. Niger Uranium story started fifty years ago and AREVA is its first partner since. AREVA/COGEMA inherited the exploration programs conducted by former 'Bureau Minier de la France d'Outre-mer' and 'Commissariat a l'Energie Atomique' in the early sixties. Arlit's deposits came out of that. In association with other partners (Niger government through ONAREM, Japan and Spain), uranium production started in 1967 with joint venture company SOMAIR followed by COMINAK. That partnership stands sound through the 1980-2003 market depression and production rate never slows since. Near by prospects allow extension and keeping activities ahead as it is the case now where the two companies have more than ten years production assured reserves. New major project is also on hand with more than 100 000 tons of uranium. AREVA/COGEMA foresaw the current market upraise when it launched a large exploration program three years ago in its previous allotted area. Regulatory agreement is underway for more prospecting areas allocation. More decades of uranium production resources are expected. This long partnership is supported by a sustainable development commitment in a hard to live desert area: health care, school, training, water supply, energy and employment. (author)

  15. Web software for the control and management of radiation protection devices in the Cadarache site

    International Nuclear Information System (INIS)

    This series of slides presents how to use a new software dedicated to the management of the periodical controls that have to be performed on the equipment involved in radiation protection. This software is ready to be dispatched on the CEA site of Cadarache. This software gives information on: the device to be controlled, the controls that have to be performed, the procedures to follow to make the test, the equipment necessary for the test particularly the need for radioactive sources, the maintenance of the device, the previous measurements and in the end the device's conformity. An evaluation of the conformity of all the devices present in a building or an area or of a particular type can be easily obtained. (A.C.)

  16. Evolution of ITER Tritium Confinement strategy and adaptation to Cadarache site conditions and French regulatory requirements

    International Nuclear Information System (INIS)

    The ITER Nuclear Buildings include the Tokamak, Tritium and Diagnostic Buildings (Tokamak Complex) and the Hot Cell and Low Level Radioactive Waste Buildings (Hot Cell Complex). The Tritium Confinement strategy of the Nuclear Buildings comprises key features of the atmosphere and vent detritiation systems and the heating, ventilation and air conditioning systems. The designs developed during the ITER EDA (engineering design activities) for these systems need to be adapted to the specific conditions of the Cadarache site and modified to conform with the regulatory requirements applicable to installations nucleaires de base (INB) - basic nuclear installations - in France. The highest priority for such adaptation has been identified as the Tritium Confinement of the Tokamak Complex and the progress in development of a robust, coherent design concept compliant with French practice is described in the paper

  17. NOCHAR Polymers: An Aqueous and Organic Liquid Solidification Process for Cadarache LOR (Liquides Organiques Radioactifs) - 13195

    International Nuclear Information System (INIS)

    To handle the Very Low Level Waste (VLLW) and the Low Level Waste (LLW) in France, two options can be considered: the incineration at CENTRACO facility and the disposal facility on ANDRA sites. The waste acceptance in these radwaste routes is dependent upon the adequacy between the waste characteristics (physical chemistry and radiological) and the radwaste route specifications. If the waste characteristics are incompatible with the radwaste route specifications (presence of significant quantities of chlorine, fluorine, organic component etc or/and high activity limits), it is necessary to find an alternative solution that consists of a waste pre-treatment process. In the context of the problematic Cadarache LOR (Liquides Organiques Radioactifs) waste streams, two radioactive scintillation cocktails have to be treated. The first one is composed of organic liquids at 13.1 % (diphenyloxazol, mesitylene, TBP, xylene) and water at 86.9 %. The second one is composed of TBP at 8.6 % and water at 91.4 %. They contain chlorine, fluorine and sulphate and have got alpha/beta/gamma spectra with mass activities equal to some kBq.g-1. Therefore, tritium is present and creates the second problematic waste stream. As a consequence, in order for disposal acceptance at the ANDRA site, it is necessary to pre-treat the waste. The NOCHAR polymers as an aqueous and organic liquid solidification process seem to be an adequate solution. Indeed, these polymers constitute an important variety of products applied to the treatment of radioactive aqueous and organic liquids (solvent, oil, solvent/oil mixing etc) and sludge through a mechanical and chemical solidification process. For Cadarache LOR, N910 and N960 respectively dedicated to the organic and aqueous liquids solidification are considered. With the N910, the organic waste solidification occurs in two steps. As the organic liquid travels moves through the polymer strands, the strands swell and immobilise the liquid. Then as the

  18. Corium behaviour research at CEA Cadarache. The PLINIUS prototypic corium experimental platform

    International Nuclear Information System (INIS)

    In the hypothetical case of a Light Water Reactor severe accident, the reactor core could melt and form with structure materials, and eventually concrete, a complex mixture called corium. The knowledge of corium behaviour is one of the key to increase the safety of the nuclear reactors. In the framework of severe accident studies, CEA has undertaken for many years a large RandD program devoted to this topic. At CEA-Cadarache, a specific platform, called PLINIUS, has been developed and is dedicated to studies of prototypic corium (i.e. with uranium dioxide). In this paper, the PLINIUS platform four facilities and the experiments on corium behaviour are described.(author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

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

  20. Areva. 2007 figures economic, social, societal and environmental data; Areva. Chiffres 2007 donnees economiques, sociales, societales et environnementales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document presents the 2007 economic, social, societal and environmental data of the Areva Group. Content: 1 - Improvement initiative: Continuous improvement, Innovation; 2 - Financial performance: 2007 results; 3 - Commitment to employees: Stakeholder relations, Health and safety, Radiation protection, Radiological impacts, Technological risks, Workforce, Workforce and training; 4 - Environment: Water, Energy, Gaseous releases, Liquid releases, Conventional waste, Radioactive waste; 5 - Reporting and performance indicators: Reporting methodology, Auditors' report, Social indicators, Environmental indicators.

  1. SIGNIFICANT NATURAL HERITAGE AREAS (NC)

    Science.gov (United States)

    The North Carolina Department of Environment and Natural Resources, Division of Parks and Recreation, Natural Heritage Program in cooperation with the NC Center for Geographic Information & Analysis, developed the Significant Natural Heritage Areas digital data to determine the a...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

  3. EPR by Areva. The path of greatest certainty

    International Nuclear Information System (INIS)

    AREVA's Evolutionary Power Reactor (EPR) is the first Generation III+ reactor design currently being built to answer the world's growing demand for clean and reliable electricity generation. Already under construction in Finland, France and China, the EPR is also being considered by America, United Kingdom, South Africa and other countries for the development of their nuclear fleet. The EPR is now clearly destined to become the mainstay of standardized, efficient reactor fleets around the globe. AREVA's EPR incorporates unbeatable know-how provided by an uninterrupted track record of reactor building activities and backed by decades of feedback experience from operating PWRs, including the most recent. The EPR is a Franco-German initiative which benefited from the stringent scrutiny of safety authorities from both countries, at each stage of the project. The EPR has already secured construction licenses from two of the world's most demanding safety authorities in France and Finland and is currently in line for a design certification and a combined construction and operating license (COL) in the USA. It is also taking part in the licensing process recently launched in the United Kingdom. Europe's leading utilities have granted the EPR their approval under the 'European Utilities Requirements' and have further expressed individual interest in the design and performance of the EPR for their businesses. AREVA is the only Gen III+ reactor constructor in the world with ongoing building experience. To date, AREVA is the only vendor who has the necessary field experience that future customers can benefit: - Detailed design completed; - Experience feedback from 87 PWR; - 3 projects going on; - Continuous PWR experience in design and construction. Close to 100% of the EPR primary circuit heavy components are sourced directly from AREVA's integrated plants. Engineering, manufacturing, services and fuel cycle management are totally integrated and mastered by AREVA. From its

  4. Teach NC Basics Step by Step.

    Science.gov (United States)

    Schroeder, Roger

    1978-01-01

    Rapid expansion of numerical control (NC) machining in industry has created the need for inclusion of NC basic concepts in the industrial education curriculum. The author describes an NC unit in an industrial technology class and the program sheet and NC worksheet that he developed for machining a product. (MF)

  5. KROTOS FCI experimental programme at CEA Cadarache: new features and status

    Energy Technology Data Exchange (ETDEWEB)

    Bonnet, J.M.; Bullado, Y.; Journeau, C.; Fouquart, P.; Piluso, P.; Sergeant, C.; Magallon, D. [CEA-Cadarache, DTN/STRI/LMA, Bat 708, BP1, 13108 Saint Paul lez Durance cedex (France)

    2005-07-01

    Full text of publication follows: KROTOS facility has been operated by the European Commission at JRC-Ispra for many years until 1999 as part of the FARO/KROTOS programme. The programme had to be stopped at JRC due to new EC priorities, and an agreement was concluded with CEA to transfer the KROTOS facility and know-how to Cadarache to continue investigating the pending FCI issues. By this agreement, CEA became owner of the facility. The main objective of the KROTOS programme at CEA Cadarache is understanding the role of melt properties in steam explosion propagation and energetics and, in particular, steam explosion behaviour of prototypical corium melts. Possible influence of physicochemical processes on explosiveness will also be explored. Actually, analysis of alumina debris produced at Ispra have shown that formation of metastable phases and chemical reaction with water at high temperature may play a significant role in enhancing heat transfer to water in the explosion phase. In order to reach the objective, steam explosion experiments are performed in well characterised conditions for a large spectrum of conditions and melt compositions of interest for both in- and ex-vessel situations. A trigger is applied as a rule. Advanced technology and instrumentation is used to reduce uncertainties on initial conditions and characterise the various phases of an explosion, with emphasis on high energy X-ray cinematography to qualify pre-mixing. This advanced instrumentation will enable the measurement of detailed variables to consolidate the qualification of the FCI codes. The use of high energy X-rays made it necessary to construct a new building to house the facility and its components. The facility should newly become operative early 2005. Main improvements with respect to Ispra concern melt delivery, hydrogen measurement and X-ray imaging. Preliminary studies have demonstrated that identification of the pre-mixture-water interface and coherent melt jet core, and

  6. Alternative large Nc baryons and holography

    International Nuclear Information System (INIS)

    In gauge theories in the limit of a large number Nc of colors baryons are usually described as heavy solitonic objects with mass of order Nc. We discuss an alternative large Nc description both directly in the field theory as well as using holography. In this alternative large Nc limit at least some of the baryons behave like mesons, that is they stay light even at large Nc and their interactions vanish in that limit. For Nc=3 these alternative large Nc baryons are equivalent to the standard baryons. In the holographic description it is manifest that the Regge slopes of mesons and alternative baryons are degenerate.

  7. Alternative large Nc baryons and holography

    CERN Document Server

    Hoyos-Badajoz, Carlos

    2009-01-01

    In gauge theories in the limit of a large number Nc of colors, baryons are usually described as heavy solitonic objects with mass of order Nc. We discuss an alternative large Nc description both directly in the field theory as well as using holography. In this alternative large Nc limit at least some of the baryons behave like mesons, that is they stay light even at large Nc and their interactions vanish in that limit. For Nc=3 these alternative large Nc baryons are equivalent to the standard baryons. In the holographic description it is manifest that the Regge slopes of mesons and alternative baryons are degenerate.

  8. 'Action 2016': AREVA's strategic action plan to improve performance

    International Nuclear Information System (INIS)

    On December 12, 2011, Luc Oursel, Executive Officer of AREVA, and Pierre Aubouin, Chief Financial Executive Officer, presented the group's 'Action 2016' strategic action plan based on an in-depth analysis of the market's outlook. This document makes, first, a Detailed presentation of the 'Action 2016' plan and then presents the group's financial outlook: - Full-year 2011 immediate accounting consequences of the new market environment: operating losses expected in 2011; - 2012-2013 transition period Objective: self-finance capex in cumulative terms; - 2014-2016: safe growth and cash generation, free operating cash flow at break-even beginning in 2013, above euro 1 bn per year beginning in 2015

  9. Areva half-year report June 30, 2008

    International Nuclear Information System (INIS)

    This document is the half-year financial report of the Areva group for 2008. It presents: 1 - the highlights of the period: key data (Summary data, Segment reporting, Backlog, Income statement, Review by division, Cash flow, Balance sheet data); Outlook; 2 - the events subsequent to half-year closing; 3 - the consolidated financial statements: Statutory Auditors' report on half-year 2008 information for the period January 1, 2008 to June 30, 2008, Consolidated income statement, Consolidated balance sheet, Consolidated cash flow statement, Consolidated statement of change in equity, Segment reporting, Notes to the consolidated financial statements for the period ending June 30, 2008

  10. Environmental, social, and corporate report 2009 - Cezus Montreuil- Juigne (Areva)

    International Nuclear Information System (INIS)

    CEZUS, a subsidiary of AREVA, is the global leader in the market for zirconium, the metal used, among other things, for the cladding on fuel assembly tubes. CEZUS's operations are distributed over six sites. The site in Montreuil-Juigne, in western France, pilgers zirconium and titanium alloy tubes and blanks for the fabrication of fuel assembly tubes. This document shows details of the CEZUS Montreuil-Juigne facility and its 2009 initiatives on: consumption and waste management, risk management, environmental and safety management, social and corporate responsibilities

  11. Areva half-year report june 30, 2006

    International Nuclear Information System (INIS)

    This document is the half-year financial report of the Areva group for 2006. It presents: 1 - Highlights of the period; 2 - Key data: Summary data, Segment reporting, Backlog, Income statement, Review by business division, Cash flow, Balance sheet data; 3 - Outlook; 4 - Events subsequent to the half-year end; 5 - Consolidated financial statements: Statutory auditors' report on the interim consolidated financial statements for the period January 1, 2006 to June 30, 2006, Consolidated income statement, Consolidated balance sheet, Consolidated cash flow statement, Consolidated statement of changes in equity, Segment reporting, Notes to the consolidated financial statements

  12. Flow modelling in fractured aquifers, development of multi-continua model (direct and inverse problems) and application to the CEA/Cadarache site

    International Nuclear Information System (INIS)

    This research thesis concerns the modelling of aquifer flows under the CEA/Cadarache site. The author reports the implementation of a numerical simulation tool adapted to large scale flows in fractured media, and its application to the Cadarache nuclear site. After a description of the site geological and hydrogeological characteristics, the author presents the conceptual model on which the modelling is based, presents the inverse model which allows a better definition of parameters, reports the validation of the inverse approach by means of synthetic and semi-synthetic cases. Then, he reports experiments and simulation of the Cadarache site

  13. Research Reactor Business at AREVA TA: Status and Perspectives

    International Nuclear Information System (INIS)

    Research reactors offer essential support for a country's nuclear power generation industry. They have for many years now provided this support in countless ways: They have made it possible to test new developments, to act as the forerunners for pressurised water reactor operations, for qualifying components, training operators as well as allowing the production of radioactive elements for medical or industrial purposes and they have also be used to perform tests on materials. In a word, they have definitively made a difference in our everyday life. For some forty years now, through its various iterations, AREVA TA has taken part in, or led the design and production of more than twenty research reactors and today, within AREVA, has the leading role in energies that generate lower CO2 emissions and in the range of engineering specialties and services offered by the group in this field, alongside CERCA, the world leader in the supply of fuel for research reactors. All of this, in a competitive worldwide market that is more than ever dominated by the need to meet the expectations of the general public. (author)

  14. Logistics of the research reactor fuel cycle: AREVA solutions

    International Nuclear Information System (INIS)

    Full text: The AREVA Group Companies offer comprehensive solutions for the entire fuel cycle of Research Reactors comply with IAEA standards. CERCA and COGEMA LOGISTICS have developed a full partnership in the front end cycle In the field of uranium CERCA and COGEMA LOGISTICS have the long term experience of the shipment from Russia, USA to the CERCA plant. Since 1960, CERCA has manufactured over 300,000 fuel plates and 15,000 fuel elements of more than 70 designs. These fuel elements have been delivered to 40 research reactors in 20 countries. For the Back-End stage, COGEMA and COGEMA LOGISTICS propose customised solutions and services for international shipments. COGEMA LOGISTICS has developed a new generation of packaging to meet the various needs and requirements of the Laboratories and Research Reactors all over the world, and complex regulatory framework.Comprehensive assistance dedicated, services, technical studies, packaging and transport systems are provided by AREVA for every step of research reactor fuel cycle. (author)

  15. AREVA invests 610 million euro in new uranium conversion plants

    International Nuclear Information System (INIS)

    AREVA today announced the launch of the Comurhex II project which will see the group build new uranium conversion facilities on the Malvesi site in Narbonne and Tricastin. Through this 610 million euro investment, AREVA aims to maintain its position as world no. 1 for conversion within a context of global nuclear energy. COMURHEX II integrates technological innovations from major R and D programs and return of experience from processes in operation for over forty years. Nuclear safety and reducing the impact on the environment were top priorities when designing the project. These future facilities will also lead to major savings of water and energy consumption and reduce effluents. The groundwork of the Comurhex II project has taken 150,000 hours of engineering over the past three years. Four hundred people will work on the site which will be launched in summer 2007. First industrial production is scheduled for 2012, based on 15,000 metric tons of uranium per year. This figure may be increased to 21,000 tons to meet market requirements

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

    International Nuclear Information System (INIS)

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

  17. LWR Fuel Gas Characterization at CEA Cadarache LECA-STAR Hot Laboratory

    International Nuclear Information System (INIS)

    The aim to improve LWR fuel behaviour led CEA to improve its PIE capacities in term of test devices and characterization techniques in the shielded hot cells of the LECA-STAR facility, located in Cadarache. A presentation of these capacities is made, focusing on gas characterization : - annealing test devices used for transient simulations. These devices are test facilities allowing to simulate a very large range of conditions (temperature, atmosphere, pressure etc); - characterization techniques : optical microscopy, for microstructure characterizations on polished samples; scanning electron microscopy (SEM) used both on polished samples and on fractographs; Electron Probe Micro-Analyzer (EPMA) for quantitative elementary analysis and elementary mappings; Secondary Ion Mass Spectrometer (SIMS), for isotopic analysis, mapping depth profiles and gas measurements. It shows an overview of their main applications for the study of fuel behaviour under nominal operating conditions but also under simulated accidental conditions and storage conditions. Two detailed examples of the use of these techniques working together on the same samples, are then presented, focusing on fission gas characterizations. The first one is a 72 GW.d.t-1 high burnup UO2 PWR fuel for which detailed characterizations have been performed before and after a LOCA type condition annealing test. The second one is a 35 GW.d.t-1 UO2 PWR fuel for which these characterizations have been done before and after a ramp test at 100 W.cm-1.min-1 up to a 90 s maximum power hold time at 520 W.cm-1. In both cases, the complementarities of these various techniques show the interest of such detailed characterizations. (author)

  18. Areva half-year report june 30, 2007

    International Nuclear Information System (INIS)

    Information provided in this document concerns the AREVA group as a whole. It presents the highlights and Key data of the first half of 2007, the outlook, the events subsequent to half-year closing, and the Consolidated financial statements. Contents: 1 - Highlights of the period; 2 - Key data: Summary data, Segment reporting, Backlog, Income statement, Review by division, Cash flow, Balance sheet data; 3 - Outlook; 4 - Events subsequent to half-year closing; 5 - Consolidated financial statements: Statutory Auditors' report on half-year information for the period January 1, 2007 to June 30, 2007, Consolidated income statement, Consolidated balance sheet, Consolidated cash flow statement, Consolidated statement of change in equity, Segment reporting, Notes to the consolidated financial statements for the period ending June 30, 2007

  19. AREVA NP Liner Repair Strategy with Adhesive Technology

    International Nuclear Information System (INIS)

    AREVA has developed a repair method for sealing leakages in austenitic stainless steel liners, especially in nuclear power plants. This technology is either a repair, when applied after failures already occurred, or a prophylaxis, when applied before failures occurred. Leakages of stainless steel pool liners can be classified into basically four mechanisms: Mechanical impact, mechanical stress, weld failures and corrosion. Damage from mechanical impact like dropping tools or equipment can be usually recognized and localized immediately. In such situations no extensive leak detection needs to be performed. Contrary to the mechanical damage, it is more difficult to localize damages due to mechanical stress, such as load changes or thermal stress. Load changes occur when a stainless steel pool is repeatedly filled and drained, thermal stress occurs when a pool is exposed to temperature gradients. Those two preconditions are given in reactor cavities (RC). Mechanical stress usually promotes other pre-existing defects. According to the experience of AREVA the weld failures are not a common root cause for leakages, found after several years of operation. They are due to the standard testing procedure in which all weld seams are checked (with e.g. Penetrate Testing (PT) for example). If failures are detected, they are repaired during the commissioning. The main root cause for leakages found after several years of operation is corrosion. Corrosion failures themselves are mainly caused by stress corrosion cracking (SCC). SCC needs certain preconditions to initiate: Mechanical stress must exist; a corrosion initiating element (e.g. chlorine) above a limiting concentration is necessary as well as a heat affected zone (HAZ). In the HAZ, which is exists near weld seams, the microstructure of the stainless steel has changed. This leads to a higher susceptibility to SCC. Those preconditions for SCC cannot be found at the front side of the liner (water side), because the water

  20. The nuclear data, A key component for reactor studies, Overview of AREVA NP needs and applications

    Science.gov (United States)

    Ravaux, Simon; Demy, Pierre-Marie; Rechatin, Clément

    2016-03-01

    The quality of the nuclear data is essential for AREVA NP. Indeed, many AREVA NP activities such as reactor design, safety studies or reactor instrumentation use them as input data. So, the nuclear data can be considered as a key element for AREVA NP. REVA NP's contribution in the improvement of the nuclear data consists in a joint effort with the CEA. It means a financing and a sharing of information which can give an orientation to the future research axis. The aim of this article is to present the industrial point of view from AREVA NP on the research on nuclear data. Several examples of collaborations with the CEA which have resulted in an improvement of the nuclear data are presented.

  1. AREVA: Operating performance shows distinct improvement; Results heavily impacted by the cost of remedial measures

    International Nuclear Information System (INIS)

    The 2015 results illustrate the progress AREVA made in 2015 and open up favorable prospects for 2016 and the following years in view of its fundamentals. The group's competitiveness plan had a very positive impact on its costs and cash, despite the heavy net loss situation which continues and in a market environment that remained difficult in 2015. Half of this loss of 2 billion Euro is due to additional provisions for OL3 and half to provisions for restructuring and impairment related to market conditions. Concerning the group's liquidity, 2016 is funded and the capital increase which will be launched in the coming months will enable AREVA to gradually regain the group's positive profile. A new phase awaits the Group in 2016 with clarity and confidence in the implementation of the restructuring announced in 2015 and in particular the autonomy of AREVA NP and the creation of New AREVA

  2. An effective and sustainable D&D concept. Competencies and experiences of AREVA

    International Nuclear Information System (INIS)

    Business Unit created in 2008 to manage nuclear sites dismantling projects for AREVA and external clients through: Assistance during post-closure phase /deregulation; D&D planning and assistance; Project- and Site-Management; Decontamination; Dismantling; Waste management

  3. The nuclear data, A key component for reactor studies, Overview of AREVA NP needs and applications

    Directory of Open Access Journals (Sweden)

    Ravaux Simon

    2016-01-01

    Full Text Available The quality of the nuclear data is essential for AREVA NP. Indeed, many AREVA NP activities such as reactor design, safety studies or reactor instrumentation use them as input data. So, the nuclear data can be considered as a key element for AREVA NP. REVA NP’s contribution in the improvement of the nuclear data consists in a joint effort with the CEA. It means a financing and a sharing of information which can give an orientation to the future research axis. The aim of this article is to present the industrial point of view from AREVA NP on the research on nuclear data. Several examples of collaborations with the CEA which have resulted in an improvement of the nuclear data are presented.

  4. Track record of the AREVA NP Nuclear Fuel in the United States of America

    International Nuclear Information System (INIS)

    Having its American, German and French legacy, AREVA NP has been and is supplying nuclear fuel assemblies and associated core components to PWR and BWR reactors around the world. To develop its action on the world market, AREVA NP has organized its activities on its major locations in Europe (France, Germany and Belgium) and in the USA. Also AREVA NP is strongly represented in the other nuclear countries (Asia, Eastern Europe, South America, South Africa and remaining European countries). Today AREVA NP has supplied more than 110,000 PWR and 51,000 BWR fuel assemblies to the world market. In the USA, AREVA NP has produced about 28,000 PWR fuel assemblies. Representing almost a quarter of the PWR American fuel market, AREVA NP is currently supplying or starting to supply 22 reactors from its 2 manufacturing plants located at Lynchburg (VA) and Richland (WA). This supply is currently based on HTP and Mark-BW designs, which have been distributed to all types of the US reactors and satisfy the NRC requirements. Also they are prepared for the current development of reactors, including AREVA NP's EPR reactor. At the time being our US PWR fuel takes the advantage of the thorough review performed on all our products, in order to keep the most proven and best performance features and allow US to better respond to each customer need. We propose the AGORA products with enough flexibility and variants to offer customized products, well suited to each customer's needs. These products incorporate a set of common characteristics and associated features, which are: · the use of the M5R alloy, as cladding material and as structural material. · a welded structure comprising the HMP alloy 718 bottom end grid, the MONOBLOC guide thimbles and the ROBUST FUELGUARD as lower tie plate. AREVA NP's fuel activities are supported by their engineering, manufacturing and fuel services which enable AREVA NP to provide utilities with licensed fuel design, a complete fuel package and suitable

  5. Role and contribution of AREVA NP GmbH and Siemens for completion of Belene NPP

    International Nuclear Information System (INIS)

    The content of the presentation includes: 1.Experience of AREVA NP / Siemens - participation in modernization and new building of NPP with VVER-1000: modernization of NPP Kozloduy Units 5 and 6 and contribution for NPP Tianwan Units 1 and 2; 2. AREVA NP / Siemens Contribution for Belene NPP: electrical systems; safety I and C; operational I and C; Heating-Ventilation-Air conditioning (HVAC); Hydrogen recombination; 3. Joint commitment for Belene

  6. Transmission and Distribution: AREVA takes further action to reinforce its presence in China

    International Nuclear Information System (INIS)

    Following the recent opening of its new gas-insulated switchgear factory last month in Suzhou, China, AREVA's Transmission and Distribution (T and D) division has announced additional actions to increase its market share in the country. The division has just signed an agreement to form a 50/50 joint venture with the Chinese company, Sunten Electric Co. Ltd., a leading manufacturer of distribution transformers, whose 2006 annual sales reached circa euro 120 million. Through this joint venture, AREVA T and D will become No 1 in China for dry-type transformers, Sunten Electric Co. Ltd.'s specialization. AREVA T and D has also established a partnership with the China Electric Power Research Institute (C-EPRI), a leading Chinese organization specialized in electrical technologies. Under the agreement, C-EPRI will be the official licensee for AREVA T and D's H-400 high-voltage direct current (HVDC) Thyristor valves in China. The partnership will enable AREVA T and D to enter the fast-growing domestic HVDC market. The T and D sector in China represents 24% of the worldwide transmission and distribution market. AREVA T and D's turnover in China, where demand for T and D equipment is growing strongly, should significantly contribute to the division's objective to reach euro 5 billion in sales by 2010

  7. Rapport d'étude : La perception des risques majeurs par les riverains du CEA de Cadarache

    OpenAIRE

    Lopez, Alexia; Régner, Isabelle; Schleyer-Lindenmann, Alexandra

    2015-01-01

    Ce rapport d'étude vient répondre aux interrogations de son commanditaire, la CLI (Commission Local d'Information) du CEA (Commissariat à l'énergie Atomique) de Cadarache. Il s'organise en trois partie : une première partie établit un état des lieux des connaissances des risques majeurs par les habitants. Les risques majeurs officiellement recensés sont : le risque feu de forêt, le risque inondation, le risque sismique, le risque de mouvement de terrain, le risque de rupture de barrage, et le...

  8. The giant superconducting magnet system of 10,000 tons mass for fusion experiment at Cadarache, France

    International Nuclear Information System (INIS)

    The International Thermonuclear Experimental Reactor (ITER) being built at Cadarache, France has many unique features and is one of the biggest scientific adventures in the history of science and technology. Seven partners (India, EU, US, China, Japan, Korea and Russia) have made an International Organization situated at Cadarache, France to provide direction and co-ordination for R and D and construction of this project. The R and D labs and manufacturing industries are spread in these seven partner countries. Components manufactured in these countries will be transported to Cadarache in France for assembly. Institute for Plasma Research, Bhat, Gandhinagar, Gujarat is coordinating this project activities on behalf of India. The magnet system, required for confinement and control of plasma leading to fusion reaction in ITER is one of the key systems of this project. There are 18 TF (Toroidal Field) Coils, 6 PF (Poloidal Field) coils, 6 CS (Central Solenoid) coils and 18 correction coils (CC), all of which are of superconducting type. All TF and CS coils have Nb3Sn superconductor and all PF and CC coils have NbTi superconductor. Each TF coil has height 15 m and width 9 m and 330 tons mass. The biggest PF coil has diameter 24 m and 300 tons mass. The total mass of these superconducting magnet systems is about 10000 tons. Use of Nb3Sn superconductor for manufacturing superconducting cables for successful use had not reached a matured stage earlier and this project gave a thrust for significant R and D activities worldwide and now due to this project, it is a matured and reliable technology. The jacketing and manufacturing of long cables need up to about 760 m long special infrastructure at Industry. The special building built for PF coil winding at ITER, Cadarache site is of size 250 m X 45 m. All these coils are made using cable-in-conduit conductors (CICC). These long CICCs have to carry current as high as 68 kA in case of TF coils. Due to this high current and

  9. AREVA announces US$ 7.75 Per share friendly cash offer for UraMin

    International Nuclear Information System (INIS)

    AREVA and UraMin Inc. ('UraMin') entered on June 15, 2007 into an agreement in respect of AREVA's friendly cash offer for 100% of the share capital of UraMin. UraMin is listed in London (AIM) and Toronto (TSX). AREVA (Euronext Paris) already owns 5.5% of UraMin's share capital. This cash offer of AREVA will be made through its indirect wholly-owned subsidiary CFMM Development ('AREVA') based on a price of US$ 7.75 per UraMin share. The total offer consideration amounts to more than USD 2.5 billion for 100% of the fully diluted share capital of UraMin. This represents a premium of 21% over UraMin 20-day weighted average trading price ending on June 8, 2007. The UraMin Board of Directors, after consulting with its financial advisors, has determined that the offer is fair and in the best interest of the UraMin shareholders and it has resolved to recommend acceptance of the Offer. BMO Capital Markets has provided an opinion that the offer is fair, from a financial point of view, to the UraMin shareholders. In connection with the offer, all directors and certain other shareholders representing approximately 25% of the outstanding UraMin shares (calculated on a fully diluted basis) have entered into lock-up agreements with AREVA pursuant to which they have agreed to tender all their UraMin shares to AREVA's offer. The support agreement entered into between AREVA and UraMin provides for, among other things, in case a superior proposal is accepted by UraMin, a right to match in favour of AREVA. The support agreement also includes a break up fee in favour of AREVA of US$ 75 million under certain circumstances. Concurrently with the closing of the proposed offer, UraMin will declare a dividend payable in shares of the capital of Niger Uranium Limited held by UraMin (where permitted by law) or a cash equivalent of the value of such shares

  10. Areva - Half year financial report June 30, 2009

    International Nuclear Information System (INIS)

    This half-year financial report contains statements on the objectives, prospects and growth areas for the AREVA group. It gives a view of the net worth, the financial position and the income of the company and all the companies included in consolidation. It presents the major events that occurred during the first six months of the fiscal year, of their effect on the financial statements and of the main transactions between related parties. It gives a description of the main risks and main uncertainties for the remaining six months of the financial year. Content: 1 - Half-year business report: Significant events, Summary data, Segment reporting, Backlog, Income statement, Review by division, Cash flow, Balance sheet items, Events subsequent to closing, Outlook; 2 - Statutory auditors' report on the financial information for the 2009 half-year - period January 1 to June 30, 2009: Condensed consolidated financial statements at June 30, 2009, Consolidated income statement, Consolidated comprehensive income, Consolidated balance sheet, Consolidated cash flow statement, Consolidated statement of changes in equity, Segment reporting, Notes to the consolidated financial statements for the period ending June 30, 2009

  11. LWR core safety analysis with Areva's 3-dimensional methods

    International Nuclear Information System (INIS)

    The quality of the safety analysis strongly affects the confidence in the operational safety of a reactor. To ensure the highest quality, it is essential that the methodology consists of appropriate analysis tools and an extensive validation base. Sophisticated 3-dimensional core models ensure that all physical effects relevant for safety are treated and the results are reliable and conservative. The validation base includes measurement campaigns in test facilities and comparisons of the predictions of steady state and transient measured data gathered from plants during many years of operation. Thus, the core models achieve reliable and comprehensive results for a wide range of applications. As an example an overview of the application experience as well as the validation base of AREVA's 3-dimensional codes is given. The importance and necessity of the comprehensive 3-dimensional methodology is illustrated with examples of a BWR and PWR safety analysis. For BWR transient application the analysis of regional power oscillations is considered and regarding the PWR safety analysis an example referring to fast enthalpy rise and the maximum fuel temperature caused by a rod ejection accident is shown. (orig.)

  12. Areva 2007 results: accelerated growth and significantly improved profitability; Areva resultats 2007: acceleration de la croissance et hausse significative de la profitabilite

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-02-15

    The AREVA group recorded accelerated growth and increased profitability in 2007, meeting both of its objectives for the year. The group made strategic inroads in fast growing markets. AREVA's integrated model met with record success in China, where GGNPC acquired two EPR nuclear islands in a combined order including both the reactors and the fuel, and the creation of a joint venture in engineering. Its T and D division was awarded the largest contract of its history in Qatar, making it the leader in a region where T and D was not even present a few years ago. For more than three years, AREVA has built up its capacity to meet surging demand in the nuclear power and T and D markets through an active policy of research and development and by capitalizing on the diversity and strength of its partnerships. Areva hired 8,600 people in 2006 and 11,500 people in 2007; this represents an investment in recruitment, training and integration of approximately euro 200 million per year. For 2008, the group foresees a further increase in its backlog, sales revenue and operating income. The Areva Group financial statements for 2007 are summarized below: - Backlog: euro 39.8 billion, up 55%; - Sales revenue: euro 11.9 billion, up 9.8% (up 10.4% like-for-like); - Operating income: euro 751 million, i.e. 6.3% operating margin, up 2.6 points compared with 2006; - Net income attributable to equity holders of the parent: euro 743 million (euro 20.95 per share), up from euro 649 million in 2006 (euro 18.31 per share); - Net debt: euro 1.954 billion, linked to the acquisition of UraMin; - Dividend: euro 6.77, to be proposed to the Annual General Meeting of Shareholders convening on April 17, 2008.

  13. Heavy baryons in the large Nc limit

    CERN Document Server

    Albertus, C; Fernando, I P; Goity, J L

    2015-01-01

    It is shown that in the large Nc limit heavy baryon masses can be estimated quantitatively in a 1/Nc expansion using the Hartree approximation. The results are compared with available lattice calculations for different values of the ratio between the square root of the string tension and the heavy quark mass tension independent of Nc. Using a potential adjusted to agree with the one obtained in lattice QCD, a variational analysis of the ground state spin averaged baryon mass is performed using Gaussian Hartree wave functions. Relativistic corrections through the quark kinetic energy are included. The results provide good estimates for the first sub-leading in 1/Nc corrections.

  14. AREVA - 2012 annual results: significant turnaround in performance one year after launching the Action 2016 plan

    International Nuclear Information System (INIS)

    One year after launching Areva's Action 2016 strategic plan, the first results are in. AREVA is ahead of schedule in executing its recovery plan. While pursuing its efforts in the management of a few difficult projects (such as OL3), Areva group was able to return to a virtuous performance cycle rooted in strong growth in nuclear order intake and good progress on its cost reduction program. Commercially, despite the difficult economic environment, AREVA was able to capitalize on its leadership in the installed base and on its long-term partnerships with strategic customers, beginning with EDF, with which AREVA renewed a confident and constructive working relationship. Areva has secured 80% of its objective of one billion euros of savings by the end of 2015 to improve its competitiveness. The group also continued efforts to optimize working capital requirement and control the capital expenditure trajectory. Together, these results enabled AREVA to exceed the objectives set for 2012 for two key indicators of its strategic plan: EBITDA and free operating cash flow. Nearly 60% of the 2.1 billion euros devoted to capital expenditures for future growth in 2012 were funded by operations, a quasi-doubled share compared to 2011. Areva's floor target for asset disposals was achieved one year ahead of schedule, also helping the Group to control its net debt, which remained below 4 billion euros. In 2013, Areva is continuing to implement the Action 2016 plan to keep its turnaround on track. In summary: - Backlog renewed over the year 2012 to euro 45.4 bn thanks to the increase in nuclear order intake; - Sales revenue growth: euro 9.342 bn (+5.3% vs. 2011), led by nuclear and renewables operations; - Very sharp upturn in EBITDA: euro 1.007 bn (+euro 586 m vs. 2011) - Very net improvement in free operating cash flow: -euro 854 m (+euro 512 m vs. 2011); - Back to positive reported operating income: euro 118 m (+euro 1.984 bn vs. 2011); - 2012-2013 floor target for asset disposals

  15. A new generation of codes and methods supporting AREVA fuel products

    International Nuclear Information System (INIS)

    This paper provides an overview of the recent main codes and methods developments in AREVA NP covering PWR as well as BWR applications. The domains of neutronics, core thermal-hydraulics and fuel rod thermal-mechanics are covered. The paper demonstrates how advanced Codes and Methods (C and M) support the fuel product development using increased analytical modeling of the basic principal phenomena (reducing empiricism), enabling better understanding of the physical mechanisms and more efficient (shorter) development cycles. The new AREVA NP C and M are largely based on first principles modeling with an extremely broad international verification and validation data base (achieved by merging and globally using the multiple data bases existing in AREVA NP), which enables AREVA NP and its customers to access easier licensing processes in a more and more changing safety regulations environmental (new safety criteria, requests for enlarged qualification databases, statistical applications, first principle physics..). In this context, the advanced codes and methods represent the key to avoiding penalties on products, operational limits, or the methodologies themselves. Making the link to the host country of ICONE19, not only gives this paper an outlook on the new AREVA NP methods but it also exhibits the BWR methodologies Mitsubishi Nuclear Fuels Co., Ltd. is reviewing and preparing for application in Japan. (author)

  16. Kazakhstan: A new source of uranium for AREVA (COGEMA)

    International Nuclear Information System (INIS)

    Kazakhstan is one of the ten largest countries in the world and number two in terms of world uranium resources. AREVA (COGEMA) has made a significant investment in uranium mining operations in Kazakhstan. The creation of KATCO, a joint venture with Kazatomprom the state owned corporation responsible for uranium production in Kazakhstan, will enable AREVA to increase and diversify its uranium supplies. Why Kazakhstan? Kazakhstan hosts 16% of the world's total uranium reserves. The large orebodies are amenable to low cost In Situ Leaching (ISL) extraction. Joint venture partner Kazatomprom possesses local know how and experience in ISL mining for uranium. The country has a high potential for industrial development and opportunities exist for foreign companies to create joint ventures. Kazakhstan has the best risk rating for a central Asia country. The uranium potential of Kazakhstan lies within six uranium provinces. Four of them correspond to past production or dormant resources. The Chu-Saryssu and Syr-Darya basins found in the southern part of the country are two large uranium districts with abundant resources. KATCO's project is located in the south of Kazakhstan about 200km northwest of Shymkent and approximately 800km west of Almaty. KATCO 's reserves are hosted by the Muyunkum Deposit, which is found in the uranium-rich Chu-Saryssu Basin, located 50km north of of the village of Taukent. The Muyunkum Deposit has a length of 75km and width of 30km. The depth of the mineralized horizons vary from 220m at the north and 520m at the south. Three ore bodies have been identified: Muyunkum South, Muyunkum Centre and Muyunkum North (Tortkuduk). At a regional scale, uranium is controlled by four major roll-front systems. Mineralization is hosted by fine to medium grained sandstones of the Uyuk and Upper Kanjugan formations which are confined between clay layers. COGEMA began exploration in Kazakhstan in 1994 and KATCO was formed in 1996 to explore and mine the Muyunkum

  17. Areva revenue and data for the first quarter of 2008

    International Nuclear Information System (INIS)

    First quarter 2008 revenue was up 12.1% year-on-year, to 2.769 billion euros. Like-for-like (at constant exchange rates and consolidation scope), growth came to 14.5%. Foreign exchange had a negative impact of 2.5%, or -69 million euros, mainly due to currency translation tied to the US dollar drop compared with the euro. The consolidation scope had a positive impact of +0.7% or 18 million euros, chiefly as a result of the consolidation of VEI Distribution (specializing in medium voltage distribution) and Passoni and Villa (world leader in the manufacture of high voltage bushings) in the Transmission and Distribution division. The main growth engines for first quarter revenue were the Reactors and Services division and the Back End division, with growth of 29.7% (+36.8% LFL1) and 13.8% (+14.1% LFL1) respectively. Outside France, revenue rose to 1.857 billion euros, compared with 1.753 billion euros in the first quarter of 2007. This represents 67% of total revenue. As a reminder, the group points out that: - revenue can vary significantly from one quarter to the next in the nuclear businesses, and quarterly operations should therefore not be taken as a reliable basis for annual projections; - the foreign exchange impact mentioned in this release comes from the translation of subsidiary accounts into the group's unit of account, and primarily reflects the US dollar in relation to the euro. AREVA also points out that its foreign exchange hedging policy for commercial operations aims to shield profitability from fluctuations in exchange rates in relation to the euro

  18. Our energies have a future. A future without CO2. Areva in 2005

    International Nuclear Information System (INIS)

    This document is the sustainable development and 2005 annual report altogether of Areva group. It presents first the challenges of energy for economical development, the climate change threat and the sustainability of nuclear power in particular with respect to radioactive wastes management and power blackouts. Then follows a presentation of Areva's 10 commitments for sustainable development (governance and continuous improvement, financial performance, innovation, customer satisfaction, commitment to employees, risk management and prevention, environmental protection, dialogue and consensus building, community involvement). The annual report presents: the 2005 highlights, Areva around the world, key data, corporate governance, organisation of the group, share information and shareholder relations, business review (front end division, reactors and services division, back end division, transmission and distribution division), financial report and glossary. (J.S.)

  19. Mammalian Mitochondrial ncRNA Database

    OpenAIRE

    Anandakumar, Shanmugam; Vijayakumar, Saravanan; Arumugam, Nagarajan; Gromiha, M. Michael

    2015-01-01

    Mammalian Mitochondrial ncRNA is a web-based database, which provides specific information on non-coding RNA in mammals. This database includes easy searching, comparing with BLAST and retrieving information on predicted structure and its function about mammalian ncRNAs. Availability The database is available for free at http://www.iitm.ac.in/bioinfo/mmndb/

  20. Hemisphere jet mass distribution at finite Nc

    Directory of Open Access Journals (Sweden)

    Yoshikazu Hagiwara

    2016-05-01

    Full Text Available We perform the leading logarithmic resummation of nonglobal logarithms for the single-hemisphere jet mass distribution in e+e− annihilation including the finite-Nc corrections. The result is compared with the previous all-order result in the large-Nc limit as well as fixed-order perturbative calculations.

  1. Prediction of Long Term Corrosion Behaviour in Nuclear Waste Systems. Proceedings of an International Workshop, Cadarache, France, 2002

    International Nuclear Information System (INIS)

    This 36. book of the European Federation of Corrosion series contains the proceedings of the International Workshop on 'Prediction of Long Term Corrosion Behaviour in Nuclear Waste Systems' that took place in Cadarache, France in November 2001. The EFC Working Party on Nuclear Corrosion, which sponsored this Workshop, had already considered in 1991 that the long term integrity of Radioactive Waste storage was a crucial problem in the development of nuclear energy for electricity production. At that time, it was realized that public opinion on Nuclear Energy, was concerned not only with the risk of a nuclear accidents but also with the safety of long term storage of high level nuclear wastes. The nuclear community and the public demanded that any technical barrier for preventing long term radionuclides from entering the biosphere should be effective and guaranteed for 10,000 or more. The integrity of the waste containers, particularly their resistance to possible internal and external corrosion, is the most important aspect of this requirement. For the last ten years, the importance of programmes on long term corrosion on nuclear waste canisters has become of major significance to the international community. The Cadarache Workshop included reports on these programmes from eight countries. These approached the long term corrosion tests, but also by the development of the necessary deterministic and empirical models for extrapolating the behaviour of the selected materials. The difficulties involved in developing such models of corrosion behaviour and in demonstrating their validity has been underlined many times. The Proceedings contains in all an Introduction by Professor G. Beranger and 33 papers grouped in four parts as follows: 1 - R and D corrosion programmes (5 papers); 2 - Laboratory and in situ testing (11 papers); 3 - Historical and archaeological analogues (5 papers); and 4 - Fundamental issues, models and prediction

  2. Heavy baryons in the large Nc limit

    Science.gov (United States)

    Albertus, C.; Ruiz Arriola, E.; Fernando, I. P.; Goity, J. L.

    2015-11-01

    It is shown that in the large Nc limit heavy baryon masses can be estimated quantitatively in a 1 /Nc expansion using the Hartree approximation. The results are compared with available lattice calculations for different values of the ratio between the square root of the string tension and the heavy quark mass √{ σ} /mQ. These estimates implement important 1 /Nc corrections and assume a string tension independent of Nc. Using a potential adjusted to agree with the one obtained in lattice QCD, a variational analysis of the ground state spin averaged baryon mass is performed using Gaussian Hartree wave functions. Relativistic corrections through the quark kinetic energy are included. The results provide good estimates for the first sub-leading in 1 /Nc corrections.

  3. Annual report 2014. Report on subcontracting within the AREVA group in France

    International Nuclear Information System (INIS)

    This report presents quantitative data and actions undertaken by the AREVA group regarding subcontracting in its nuclear activities in France in 2014. After a presentation of AREVA, it addresses innovative practices in the 'commissioner-supplier' relationship, describes how the subcontracting option corresponds to an industrial choice, describes how subcontracting is supervised through an operational acquisition process, how abilities and training of external interveners are controlled, how operations performed by external interveners are prepared and accompanied. It outlines how issues related to health, safety and security are addressed exactly the same way for all interveners, and finally comments how observations made by the different stakeholders are sources of progress

  4. AREVA in 2013: a 7% growth for nuclear activities, more than expected

    International Nuclear Information System (INIS)

    AREVA's consolidated turnover reached 9240 millions euros in 2013, it means a 4% rise compared to 2012. This achievement is mainly due to nuclear activities (+7.1%) while the turnover of the renewable energies sector is down by 24.7%. At the end of 2013 the order-book reached 41.6 billions euros and the total of the orders over 2013 reached 7.6 billions euros, not including the orders that concern the EPR project at Hinkley Point in Great-Britain. The article details and comments the economic figures for each sector of AREVA activities

  5. Press kit. Cooperation between Areva and South Africa in the nuclear energy field

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    This document presents the nuclear industry business developed by Areva in South Africa. The first part offers general information on the country (political context, economy which fuels African growth, social situation and South Africa in search of sustainable development). An other part deals with the electricity supply (predominance of coal and the issue of global warming, electricity for everyone. The last parts detail the nuclear energy development (the new PBMR reactor project, the exploitation of all nuclear technology) and how Areva consolidates its presence in South Africa. (A.L.B.)

  6. Press kit. Cooperation between Areva and South Africa in the nuclear energy field

    International Nuclear Information System (INIS)

    This document presents the nuclear industry business developed by Areva in South Africa. The first part offers general information on the country (political context, economy which fuels African growth, social situation and South Africa in search of sustainable development). An other part deals with the electricity supply (predominance of coal and the issue of global warming, electricity for everyone. The last parts detail the nuclear energy development (the new PBMR reactor project, the exploitation of all nuclear technology) and how Areva consolidates its presence in South Africa. (A.L.B.)

  7. Areva T and D market opportunities after the US and EU Blackouts

    International Nuclear Information System (INIS)

    This document presents the events on the transmission systems during August 2003 in Usa and in September 2003 in Italy. The author analyzes the causes of the blackouts (small margins in transmission system, not adequate control, weaknesses in interconnections between regions), the market opportunity arising out of the blackouts, the economic regulatory and environmental structure/issues today and developments, the scenario for Areva after the blackout (the market size today and in the future) and Areva strength in relation to blackout. (A.L.B.) opportunities

  8. Areva. Nine-month 2007 sales revenue and data; Areva. Informations et chiffre d'affaires relatifs au neuf premiers mois de l'exercice 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-10-15

    The main information concerning the nine-month 2007 financial data of the Areva group is a steady growth of 9-month sales revenue, at euro 8.066 billion (+6.8% like-for-like), including euro 2.692 billion in the 3. quarter, i.e. +7.6% like-for-like. The group confirms its strong sales revenue growth objective for 2007.

  9. Logistics of the research reactor fuel cycle: AREVA solutions

    International Nuclear Information System (INIS)

    The fuel cycle for Research Reactors and Laboratories is an integral part of the fuel cycle of Power Reactors. Due to the type of material (uranium enriched up to 93%) the shipment must comply with the international regulation for dangerous goods, IAEA standards and National and International laws for physical protection. The AREVA Group Companies offer comprehensive solutions. CERCA and COGEMA LOGISTICS have developed a full partnership in the front end cycle: - In the field of uranium (HEU and LEU) CERCA and COGEMA LOGISTICS have the long term experience of the shipment from Russia, USA to the CERCA plant. This cooperation includes providing the packages such as TNTM-BGC, TNTMUO2, technical assistance on sites and door-to-door transportation logistics. - Since 1960, CERCA has manufactured over 300,000 fuel plates and 15,000 fuel elements of more than 70 designs. These fuel elements have been delivered to 40 research reactors in 20 countries. - Following the fuel fabrication, CERCA and COGEMA LOGISTICS provide transport services from CERCA plant to the reactor in Europe or abroad. Most of the fuel deliveries are performed with the CERCA 01 package. It has been developed in cooperation between both companies, complies with IAEA 96, and can be used for multimodal transportation. Examples will be provided, such as transports to Japan and within Europe, using CERCA package for fresh fuel, TNTMUO2 or TNTMF-XI for powders and pellets, or TNTM-BGC for HEU. For the Back-End stage, COGEMA and COGEMA LOGISTICS propose customized solutions and services for international shipments, in a complex regulatory framework. COGEMA LOGISTICS has developed a new generation of packaging to meet the various needs and requirements of the Laboratories and Research Reactors all over the world. 4 TNTM-MTR casks, which can be equipped with 6 different types of basket allowing a capacity from 4 to 68 fuel elements, and 2 TNTM-106 casks with two different lengths of cavity (2200 mm and 2000 mm

  10. AREVA revenue and data for the first nine months of 2008

    International Nuclear Information System (INIS)

    This public information sheet presents financing data of the group AREVA for the first nine months of 2008. It shows a high increase of the revenue (12,9%). The data are detailed for each activity sector, front end, reactors and services, back end, transmission and distribution. Consolidated revenue for the years 2007 are also provided. (A.L.B.)

  11. Investments in new nuclear fuel cycle facilities. AREVA long term supply insurance approach

    International Nuclear Information System (INIS)

    As a leading provider of technological solutions for nuclear power generation and electricity transmission, the AREVA group and its partners can offer a unique range of products and services from one single step to a fully integrated fuel supply, as requested by its customers. At the core of AREVA, the Front end division is an essential part of the overall fuel supply chain. To address its customers' needs for their existing and future nuclear power plants, the AREVA group has already launched and is further planning very significant investments to build new facilities in the front end, based on the most advanced technologies: - in conversion: the Comurhex 2 project is now approved and started. - in enrichment: our 3 billion euros GB II centrifuge plants project is well on its construction schedule, now allowing us to start a project in the USA based upon the same design. - We are also investing in fuel fabrication at our existing plants in Europe and in the US. Current uranium market evolutions put natural uranium supply under pressure: we are also investing in mining, - Canada, Kazakhstan, Niger, Namibia, South Africa, etc - and also in exploration. Because AREVA is convinced of a fast growing future for nuclear power generation, it has proactively opted to massively invest in the fuel cycle facilities of the 21st century in order to be prepared to fulfil its customer needs. (author)

  12. AREVA's fuel assemblies addressing high performance requirements of the worldwide PWR fleet

    International Nuclear Information System (INIS)

    Taking advantage of its presence in the fuel activities since the start of commercial nuclear worldwide operation, AREVA is continuing to support the customers with the priority on reliability, to: >participate in plant operational performance for the in core fuel reliability, the Zero Tolerance for Failure ZTF as a continuous improvement target and the minimisation of manufacturing/quality troubles, >guarantee the supply chain a proven product stability and continuous availability, >support performance improvements with proven design and technology for fuel management updating and cycle cost optimization, >support licensing assessments for fuel assembly and reloads, data/methodologies/services, >meet regulatory challenges regarding new phenomena, addressing emergent performance issues and emerging industry challenges for changing operating regimes. This capacity is based on supplies by AREVA accumulating very large experience both in manufacturing and in plant operation, which is demonstrated by: >manufacturing location in 4 countries including 9 fuel factories in USA, Germany, Belgium and France. Up to now about 120,000 fuel assemblies and 8,000 RCCA have been released to PWR nuclear countries, from AREVA European factories, >irradiation performed or in progress in about half of PWR world wide nuclear plants. Our optimum performances cover rod burn ups of to 82GWD/tU and fuel assemblies successfully operated under various world wide fuel management types. AREVA's experience, which is the largest in the world, has the extensive support of the well known fuel components such as the M5'TM'cladding, the MONOBLOC'TM'guide tube, the HTP'TM' and HMP'TM' structure components and the comprehensive services brought in engineering, irradiation and post irradiation fields. All of AREVA's fuel knowledge is devoted to extend the definition of fuel reliability to cover the whole scope of fuel vendor support. Our Top Reliability and Quality provide customers with continuous

  13. Developing talent at AREVA: Investing in people and building our future

    International Nuclear Information System (INIS)

    AREVA employs 65,000 people today and will recruit 12,000 new employees worldwide in 2008 to support business strategy. The group forecasts that recruitment needs will significantly rise to 40,000 by 2012, representing 50% of the workforce. In order to meet the challenges of rapid international expansion and a highly competitive talent market, AREVA has developed initiatives to accelerate its investment in people, to reinforce recruitment and retain high quality talents and valuable skills and knowledge. The group human resources department's mission is based on shaping talents for sustainable business performance. It established its five-point human resources policy, Talent Builder, to attract, develop, retain, reward and mobilize employees across all businesses. In the context of a global talent market, dynamic recruitment programs are implemented to attract top talent. A global Campus Management program builds on relationships with colleges and universities to attract the future generation of engineers and managers. Talent development initiatives include processes and management tools, such as the People Review to identify and nurture key skills and talents, a group-wide integration program, professional training, and priority to internal mobility. AREVA places particular importance to diversity, a keystone of HR policy, and a socio-economic lever of development. The rich variety of people and cultures in the group reflect the markets, customers and the civil society in which AREVA operates. The group is actively committed to equal opportunities for all. The European agreement on equal opportunities in the workplace sets out measures for promoting gender equality and professional career paths, with the principal themes of recruitment, career development, training, remuneration and parental support. In addition, the WE network of men and women was set up with the support of Anne Lauvergeon, Chief Executive of AREVA with the objectives of promoting gender equality

  14. Developing talent at AREVA: Investing in people and building our future

    Energy Technology Data Exchange (ETDEWEB)

    Vivien, Philippe [Human Resources AREVA (France)

    2008-07-01

    AREVA employs 65,000 people today and will recruit 12,000 new employees worldwide in 2008 to support business strategy. The group forecasts that recruitment needs will significantly rise to 40,000 by 2012, representing 50% of the workforce. In order to meet the challenges of rapid international expansion and a highly competitive talent market, AREVA has developed initiatives to accelerate its investment in people, to reinforce recruitment and retain high quality talents and valuable skills and knowledge. The group human resources department's mission is based on shaping talents for sustainable business performance. It established its five-point human resources policy, Talent Builder, to attract, develop, retain, reward and mobilize employees across all businesses. In the context of a global talent market, dynamic recruitment programs are implemented to attract top talent. A global Campus Management program builds on relationships with colleges and universities to attract the future generation of engineers and managers. Talent development initiatives include processes and management tools, such as the People Review to identify and nurture key skills and talents, a group-wide integration program, professional training, and priority to internal mobility. AREVA places particular importance to diversity, a keystone of HR policy, and a socio-economic lever of development. The rich variety of people and cultures in the group reflect the markets, customers and the civil society in which AREVA operates. The group is actively committed to equal opportunities for all. The European agreement on equal opportunities in the workplace sets out measures for promoting gender equality and professional career paths, with the principal themes of recruitment, career development, training, remuneration and parental support. In addition, the WE network of men and women was set up with the support of Anne Lauvergeon, Chief Executive of AREVA with the objectives of promoting gender

  15. AREVA ''Sustainable Cycle Solutions''

    International Nuclear Information System (INIS)

    capabilities are on track to expand in some countries there will be a growing need, to move forward efficiently, to smartly mix proven and evolving solutions (recycling, on site dry storage, pools, centralized storage, advanced technologies). These shall be combined in an optimized manner taking into account key criteria related to non proliferation, minimization of environmental impact, economics, fleet performance, responsibility towards future generations... The recommendations from Safety Authorities to deepen the question of very long term dry storage have also reactivated the debate about the available options for the short and long terms, including recycling, which is therefore likely to play an increasing role, especially if flexibility is required to ensure a cost-effective fast reactor ramp-up. Such an approach is aimed at meeting needs that may differ, even diverge depending on the concerned stakeholders. The paper will in particular illustrate how AREVA 'Sustainable Cycle Solutions' may optimize fuel cycle schemes for the short and longer terms and fulfill the stakeholders' needs. It will also pinpoint the related limits and conditions that have to be met to fulfill the above mentioned criteria. (author)

  16. Areva 2009 responsible growth report: more energy, less CO{sub 2}; Areva rapport de croissance responsable 2009: plus d'energie moins de CO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This document is the 2009 annual responsible growth report of AREVA which presents itself as having consolidated its leadership position in its original business of nuclear power while expanding considerably in renewable energies (wind, solar, bio-energies and hydrogen/storage) to become a leading provider of solutions for carbon-free power generation. The main chapters of the report are: the group and its strategy, Areva's nuclear power solutions (is nuclear a sustainable energy source?, supply, technological excellence, safety, recycling and waste, acceptability, non-proliferation), Areva's renewable energy solutions (how much of the energy mix should be renewable?, rising demand, competitiveness and efficiency, responsible development), Areva's human resources (gender balance, health and safety, diversity and opportunity, hiring and training). Data and balanced scorecard for sustainable development are also given

  17. AREVA NP decontamination concept for decommissioning. A comprehensive approach based on over 30 years experience

    International Nuclear Information System (INIS)

    Decontamination prior to Decommissioning and Dismantlement is imperative. Not only does it provide for minimization of personnel dose exposure but also maximization of the material volume available for free release. Since easier dismantling techniques in lower dose areas can be applied, the licensing process is facilitated and the scheduling and budgeting effort is more reliable. The most internationally accepted approach for Decontamination prior to Decommissioning projects is the Full System Decontamination (FSD). FSD is defined as the chemical decontamination of the primary cooling circuit, in conjunction with the main auxiliary systems. AREVA NP has long-term experience with Full System Decontamination for return to service of operating nuclear power plants as well as for decommissioning after shutdown. Since 1976, AREVA NP has performed over 500 decontamination applications and, from 1986, Decontaminations prior to Decommissioning projects which comprise virtually all NPP designs and plant conditions were performed: NPP designs: HPWR, PWR, and BWR by AREVA, Westinghouse, ABB and GE. Decontaminations performed shortly after final shutdown or several years later, and even after re-opening Safe Enclosure. High Alpha inventory and or low gamma/alpha ratio. Main Coolant chemistry (e.g., with and without Zn injection during operation). Fifteen Decontaminations prior to Decommissioning Projects have been performed successfully to date and the sixteenth FSD is now in the detailed engineering phase and is scheduled to commence late 2010. AREVA NP has developed a fully comprehensive approach for decontamination based on the CORD® (Chemical Oxidation Reduction Decontamination) Family, applied using the in-house designed decontamination equipment AMDATM (Automatic Modular Decontamination Appliance). Based on the vast experience of AREVA NP in the field of decontamination, the Decontamination Concept for Decommissioning was developed. This concept ensures that the

  18. A methodology for fast and accurate decay heat calculations for in-pool used fuel assemblies developed at AREVA La Hague reprocessing facility

    International Nuclear Information System (INIS)

    The evaluation of the decay heat released from used fuels stored in an interim storage pool is a crucial issue for safety and operation. This paper presents a methodology developed at the AREVA NC La Hague reprocessing facility in order to perform a fast and accurate assessment of the decay heat for a pool containing a large variety of fuel assemblies with different features (kind of reactor, initial composition, number of irradiation cycles, operating power, outage length) and cooling times ranging from 6 months to 60 years. The key aspect of the methodology relies on the fact that, for cooling times higher than 6 months, only a very short number of isotopes significantly contribute to the overall decay heat. The methodology uses results from calculations performed by the industrial depletion code CESAR and takes benefit from the experimental validation of CEA reference depletion package DARWIN. A full CESAR calculation at a given cooling time for each assembly allows building up a reference database: for any cooling time higher than the reference one, a simplified on-line calculation involving less than 30 isotopes is performed, and all approximations made are covered by the mean of biases relying on pre-evaluated coefficients. Results for an application to a 10,000-used-fuel-assembly interim storage pool are given. (author)

  19. AREVA: from speech to reality / The example uranium mines in Niger

    International Nuclear Information System (INIS)

    This document presents the activities of AREVA in Niger in the field of uranium production on different sites. It recalls the interventions by the CRIIRAD in support of a local NGO, the reactions of AREVA and some means of intimidation used by this company. It outlines, criticizes and discusses the contamination of water resources and, therefore their degradation, the contamination of air by radioactive dusts and gases from the production sites, the retailing of contaminated scrap metals, and the dispersal of radioactive materials in the environment (including a hospital), and also the outdoor storage of radioactive materials. It mentions some accidents which occurred during radioactive material transport, relates uranium exploitation with the greenhouse gas effect. It stresses that public hygiene is insufficient. It discusses the current prospecting works, and finally identifies guarantees to be obtained and urgent actions to be undertaken

  20. Concept and operational experience of the Areva DMT process for preventive maintenance of steam generators

    International Nuclear Information System (INIS)

    The AREVAs DMT process is a preventive chemical cleaning of the steam generators (SG) that provides the required features to keep the SG in good operative conditions. -Very low carbon steel corrosion -Innocuous towards stainless steel and nickel base alloys -Inherently safe process -Efficient magnetite dissolution -No use of CMR (i.e Carcinogenic, Mutagenic and toxic to Reproduction) Chemicals (e. g. Hydrazine) -No ammonia emissions -Easy decomposition of waste Several applications have been performed world-wide over the last 5 years. The results were fully satisfying in all the above stated points. The removal of up to 800 kg of dry deposits per SG was realized. A positive effect on fouling factor was observed, showing that AREVAs DMT process is a safe, easy and successful way to maintain the steam generators in excellent operative conditions. (Author)

  1. Monitoring of the radiological environmental impact of the AREVA site of Tricastin

    International Nuclear Information System (INIS)

    Set up at the beginning of the site's operations, in 1962, the monitoring of the radiological environmental impact of the AREVA site of Tricastin has evolved over time to meet more specifically the multiple objectives of environmental monitoring: to prove the respect of the commitments required by the authorities, to be able to detect a dysfunction in the observed levels, to enable the assessment of impacts of industrial activities, to ensure the balance between environmental quality and the use made by the local population and to inform the public of the radiological state of the environment. Thousands of data were acquired on the radioactivity of all environmental compartments as well as on the functioning of local ecosystems. Today, the Network of Environmental Monitoring of AREVA Tricastin goes beyond the requirements of routine monitoring to provide innovative solutions for monitoring the radioactivity (especially for uranium) in the environment. (author)

  2. AREVA LOCA and non-LOCA realistic methodology development strategy based on CATHARE

    International Nuclear Information System (INIS)

    The CATHARE code developed since 1979 by AREVA, Cea, EDF and IRSN is one of the major thermal-hydraulic system codes worldwide. The paper gives an overview of CATHARE 2 Version 2.5 based realistic methodologies elaborated by AREVA for LOCA and non-LOCA and the underlying process (called DRM) applied for that purpose, the special features and improvements implemented in the code to handle additional needs and possible future requirements for industrial applications such as the effect of high Burn-up on fuel and cladding behaviour during LOCAs, coupling with core thermal-hydraulics, 3-dimensional core physics and instrumentation and control, capability to account for asymmetric reactor coolant system flow transients by means of dedicated vessel mixing matrices, second order numerical resolution scheme for boron front propagation for non-LOCA transients. (Author)

  3. First half 2006 financial results; Resultats du 1er semestre 2006 Groupe Areva

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-09-15

    Areva provides technological solutions for highly reliable nuclear power generation and electricity transmission and distribution. The group is the world leader in nuclear power and the only company to cover all industrial activities in this field. This Press release presents the first half 2006 financial results: the overall performance and the performance by division (front end, reactors and services, back end, transmission and distribution). (A.L.B.)

  4. Does multinationals socially responsible in Sub-Sahara Africa? Case of AREVA in Niger

    OpenAIRE

    Youssoufou, Hamadou Daouda

    2014-01-01

    Societal actions in terms of CSR of the French nuclear group in Niger contrast with stakeholders charges against him (pollution, degradation of the environment, groundwater contamination, etc.) and certain realities observed on the field (armed conflict, poverty, social inequalities, disintegration of the local economy). This paper proposes to shed light on the issues and controversies related to the practice of CSR in Africa in general, those related to Areva group in Niger in...

  5. MFFF project in Savannah River: AREVA's role in the project - construction status

    International Nuclear Information System (INIS)

    Within the framework of a bilateral agreement between the USA and the Russian federation during the 90s (Start agreement), both parties decided to eliminate 34 metric tons of surplus weapon-grade plutonium each. On the American side, the Department of Energy (DOE) is in charge of implementing the agreement. In 1999, the DOE signed a contract with DCS (Duke, Cogema, Stone and Webster), to design, build and operate a facility, MFFF, that would transform the American weapon-grade plutonium in MOX fuel. This plant, located in Savannah River in South Carolina, will fabricate civil fuel to be loaded in existing US commercial reactors. AREVA signed technology transfer with the DOE, allowing MFFF to be an US copy of AREVA's fuel recycling facilities (La Hague for material purification and MELOX for fuel fabrication). 10 years after the signing of the initial agreement, project is now a reality. Shaw AREVA MOX services, that succeeded to the former DCS, undertook building the MFFF plant the 1. of August 2007. Process equipments are being achieved and testing has begun. From the beginning of the project, AREVA mobilized the best of its expertise to ensure its success. Engineering and operating teams integrate their experience of recycling technologies in the SA MOX Project to carry out the technology transfer. The presentation will trace history of the project and set various stages from its beginning. It will focus on the progress of construction and develop the last prospects of the project. A first feedback of the execution of the technology transfer from France to the USA will be presented. (authors)

  6. Waste Estimates for a Future Recycling Plant in the US Based Upon AREVA Operating Experience - 13206

    International Nuclear Information System (INIS)

    Estimates of process and secondary wastes produced by a recycling plant built in the U.S., which is composed of a used nuclear fuel (UNF) reprocessing facility and a mixed oxide (MOX) fuel fabrication facility, are performed as part of a U.S. Department of Energy (DOE) sponsored study [1]. In this study, a set of common inputs, assumptions, and constraints were identified to allow for comparison of these wastes between different industrial teams. AREVA produced a model of a reprocessing facility, an associated fuel fabrication facility, and waste treatment facilities to develop the results for this study. These facilities were divided into a number of discrete functional areas for which inlet and outlet flow streams were clearly identified to allow for an accurate determination of the radionuclide balance throughout the facility and the waste streams. AREVA relied primarily on its decades of experience and feedback from its La Hague (reprocessing) and MELOX (MOX fuel fabrication) commercial operating facilities in France to support this assessment. However, to perform these estimates for a U.S. facility with different regulatory requirements and to take advantage of some technological advancements, such as in the potential treatment of off-gases, some deviations from this experience were necessary. A summary of AREVA's approach and results for the recycling of 800 metric tonnes of initial heavy metal (MTIHM) of LWR UNF per year into MOX fuel under the assumptions and constraints identified for this DOE study are presented. (authors)

  7. Areva, Chalon/St-Marcel site, Environment, social and societal report for 2010-2011

    International Nuclear Information System (INIS)

    After a brief indication of Areva's activities and a map locating Areva's implantations, and the distribution of turnover and personnel in the different continents, a brief recall of safety commitments, and a presentation of the activity of the Reactors and Services Business Group (turnover, personnel, number of reactors in charge), this report briefly presents the different AREVA sites in Burgundy, and more precisely the Chalon/St-Marcel site which comprises a technical centre and a plant of production of heavy components. The activities of the technical centre concern welding technology, nuclear fusion, corrosion and chemistry, fluid and structure mechanics, and technologies related to the development of new energies and to the environment. Fields of intervention and clients are evoked. The activity of the plant of production of heavy components (vapor generators, pressurizers, vessels, etc.) and some characteristics of these components are presented. The environmental aspect is then addressed: evolution of resource consumption (gas, water, electricity, paper), and of releases (greenhouse gases, used waters, waste management). The social aspect comprises social relationships, health (involved actors, prevention, safety, evolution of labour accidents), ability and job management (training, career management, education). The societal commitments have been acknowledged by several labels related to social inclusion and local activities, support of sporting and cultural activities

  8. Participation in the IAEA Coordinated Research Project Fumex III: Final Report of AREVA NP

    International Nuclear Information System (INIS)

    After the Coordinated Research Project (CRP) FUMEXII, participants asked for a new exercise within an IAEA CRP. This CRP started in December 2008 in Vienna with the first Research Coordination Meeting (RCM). The CRP is titled ''Improvement of Computer Codes Used for Fuel Behaviour Simulation FUMEX III''. The object of FUMEX III were the improvement of fuel rod performance codes for modeling high burnup phenomena in modern fuel. This includes transient behavior, as well as mechanical interaction between pellet and cladding and, in progression to the FUMEX II exercise, fission gas release during various conditions (steady state, load follow, transient). AREVA NP agreed on participating in this exercise under the IAEA research agreement no. 15369 and expressed interest in the modeling of pelletclad mechanical interactions as well as fission gas release under steady state and transient conditions. In this exercise AREVA NP used its new global fuel rod code GALILEO, which is still under development (formerly known under the project name COPERNIC 3). During a Consultants Meeting potential topics and a proposed selection of cases have been prepared, which were discussed during the 1st Research Coordination Meeting (RCM) in Vienna in December 2008. During the discussions a number of additional cases motivated by the participants have been identified. Finally, a case table has been agreed upon, which included several cases for the different topics. Most of the cases have been based on the International Fuel Performance Experiments (IFPE) database, but additional cases have been provided during the exercise (e.g., the AREVA idealized case

  9. Waste Estimates for a Future Recycling Plant in the US Based Upon AREVA Operating Experience - 13206

    Energy Technology Data Exchange (ETDEWEB)

    Foare, Genevieve; Meze, Florian [AREVA E and P, SGN - 1, rue des Herons, 78182 Montigny-le-Bretonneux (France); Bader, Sven; McGee, Don; Murray, Paul [AREVA Federal Services LLC, 7207 IBM Drive, Mail Code CLT- 1D, Charlotte NC 28262 (United States); Prud' homme, Pascal [AREVA NC SA - 1, place Jean Millier, 92084 Paris La Defense CEDEX (France)

    2013-07-01

    Estimates of process and secondary wastes produced by a recycling plant built in the U.S., which is composed of a used nuclear fuel (UNF) reprocessing facility and a mixed oxide (MOX) fuel fabrication facility, are performed as part of a U.S. Department of Energy (DOE) sponsored study [1]. In this study, a set of common inputs, assumptions, and constraints were identified to allow for comparison of these wastes between different industrial teams. AREVA produced a model of a reprocessing facility, an associated fuel fabrication facility, and waste treatment facilities to develop the results for this study. These facilities were divided into a number of discrete functional areas for which inlet and outlet flow streams were clearly identified to allow for an accurate determination of the radionuclide balance throughout the facility and the waste streams. AREVA relied primarily on its decades of experience and feedback from its La Hague (reprocessing) and MELOX (MOX fuel fabrication) commercial operating facilities in France to support this assessment. However, to perform these estimates for a U.S. facility with different regulatory requirements and to take advantage of some technological advancements, such as in the potential treatment of off-gases, some deviations from this experience were necessary. A summary of AREVA's approach and results for the recycling of 800 metric tonnes of initial heavy metal (MTIHM) of LWR UNF per year into MOX fuel under the assumptions and constraints identified for this DOE study are presented. (authors)

  10. Areva - 2013 annual results: breakeven free operating cash flow objective reached despite a difficult environment

    International Nuclear Information System (INIS)

    The Areva group reached a major milestone in 2013 in turning performance around by meeting a key objective of its Action 2016 plan: the return to breakeven of free operating cash flow. For the first time since 2005, cash generated by the Group's operations allowed it to fully fund strategic capital expenditures essential to the group's profitable growth. To achieve this result, Areva built on robust growth in nuclear operations, on contributions from its cost reduction plan and on strict management of capital spending. However, two projects launched in the previous decade (OL3 and a power plant modernization) and the Renewable Energies business impacted negatively the group's 2013 net income. On the Renewable Energies market, in a situation marked by a reduction of capital spending by customers, AREVA anticipated the consolidation required in the sector by implementing industrial partnerships such as the joint venture project with Gamesa, which aims to create a European champion in offshore wind. Similar initiatives were undertaken in solar energy and energy storage. The Group continues to implement the Action 2016 plan to pursue its recovery. While the economic environment remains uncertain and projects launched in the previous decade remain a burden, the Group forecasts further performance improvement and significant growth in cash flow generation by the end of the plan

  11. Treatment of Fukushima contaminated waters TEPCO selected Areva and Veolia solution

    International Nuclear Information System (INIS)

    The Actiflo-RadTM system successfully contributed to treat the contaminated wastewaters from the damaged Fukushima Daiichi nuclear power plant. The decontamination system jointly designed by AREVA and Veolia Water treated about 77 500 m3 of high activity wastewater (∼106 Bq/cm3), combining radionuclides adsorbents developed by AREVA and the know-how of Veolia in water treatment for the settlement of the adsorbed radioactive elements, producing sludge with a weight concentration of 80 g/L. Both companies delivered the treatment facility quickly with an efficient joint organization - in a very complex environment. Assembled on Fukushima site - badly damaged by the tsunami following the earthquake of March 11th - the system was designed, built and started in a record time of 2 month 1/2, instead of several years in a classical nuclear engineering project. The Actiflo-RadTM was a key equipment to achieve a stable situation of reactors, allowing treated water to be reused for core cooling. Commissioned with the on-site support of Veolia experts, the system reduced by 10 000 the Cs-activity of the wastewater even with significant salt content (seawater diluted twice) at a flow-rate slightly below the design value of 50 m3/hr. The implemented technologies are already used separately on AREVA sites (la Hague, fuel reprocessing plant) and for many water treatment projects by Veolia all over the world (ActifloTM and MultifloTM processes, using lamellar settling devices - in addition, the first one making use of micro-sand for a better floc quality). The complete treatment process selected by TEPCO features a physico-chemical treatment and water desalination, in five steps. After de-oiling, wastewater is primarily decontaminated through zeolite columns (Kurion process). This pre-decontaminated water is then treated on the AREVA-Veolia two stages system; at each stage, more than 30 minutes contact time with radionuclides adsorbents is needed, adsorbed radioactive particles

  12. Carbon Nanotubes Investigated by N@C60 and N@C70 Spin Probes

    Science.gov (United States)

    Corzilius, B.; Gembus, A.; Dinse, K.-P.; Simon, F.; Kuzmany, H.

    2005-09-01

    Nitrogen atoms encapsulated in C60 can be used to detect small deviations from spherical symmetry via deformation-induced non-vanishing Zero-Field-Splitting (ZFS). In this context, experiments were performed by using these electronic quartet spin probes to investigate single wall carbon nanotubes. Time-fluctuating ZFS interaction would be indicative for rotational and/or translational degrees of freedom. Using pulsed EPR techniques, spin relaxation rates of N@C60 and also of N@C70 molecules with inherent static ZFS were measured. The analysis of their temperature dependence gave information about the dynamics of N@C60 and N@C70 molecules confined to the inside of the tubes.

  13. Adjacent Nucleotide Dependence in ncRNA and Order-1 SCFG for ncRNA Identification

    OpenAIRE

    Wong, Thomas K. F.; Lam, Tak-Wah; Sung, Wing-Kin; Yiu, Siu-Ming

    2010-01-01

    Background: Non-coding RNAs (ncRNAs) are known to be involved in many critical biological processes, and identification of ncRNAs is an important task in biological research. A popular software, Infernal, is the most successful prediction tool and exhibits high sensitivity. The application of Infernal has been mainly focused on small suspected regions. We tried to apply Infernal on a chromosome level; the results have high sensitivity, yet contain many false positives. Further enhancing Infer...

  14. (Special Issue STEP-NC) Enabling feedback of process data by use of STEP-NC

    OpenAIRE

    Wosnik, Michael; Kramer, Christian; Selig, Andreas; Klemm, Peter

    2006-01-01

    Abstract Today?s Computer Aided Process Planning (CAPP) systems are performing NC programming with insufficient consideration of real machine capabilities and resulting workpiece characteristics. Computer Numerical Controls (CNCs) receive no information about actual workpiece characteristics and applied manufacturing processes. Machine and process observation are not closely coupled to the actual executed machining workingstep. STEP-NC addresses these problems by aiming at the avai...

  15. NC/NG与ADN的相互作用%Interaction of NG/NC with ADN

    Institute of Scientific and Technical Information of China (English)

    张腊莹; 衡淑云; 刘子如; 张皋; 赵凤起; 谭惠民

    2009-01-01

    用高压差示扫描量热法(PDSC),热重-微商热重法(TG-DTG),研究了双基粘合剂(NC/NG体系)与二硝酰胺铵(ADN)之间的相互作用.结果表明,(NC/NG)/ADN体系中NG的分解峰由NC/NG中的207.0 ℃提前至159.8 ℃,在高压下该分解峰温提前至153.6 ℃.NC/ADN的分解峰温比NG/ADN提前了4.8 ℃,而且大部分的ADN没有被NG加速而提前分解,表明NC对ADN的作用比NG更强烈.此外,还用真空安定性试验(VST)评价了NC/NG与ADN的相容性,混合体系的净增放气量大于11 mL,属于严重不相容,证明在90 ℃下NC/NG与ADN之间也存在强烈的相互作用.

  16. Recent developments in post-irradiation examination techniques for water reactor fuel. Proceedings of a technical committee meeting held in Cadarache, France, 17-21 October 1994

    International Nuclear Information System (INIS)

    At the invitation of the Government of France, following a proposal of the International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) the IAEA convened a Technical Committee meeting from 14 to 21 October 1994 in Cadarache to discuss recent technical advances and improvements in the field of post-irradiation examination (PIE) of fuel used in nuclear power plants. Fifty participants representing 14 countries attended the meeting and 30 papers were presented and discussed during five technical sessions. Working Groups composed of the session chairmen and authors of papers prepared summaries of each session including conclusions and recommendations for future work. Refs, figs and tabs

  17. The key role of critical mock-up facilities for neutronic physics assessment of advanced reactors: an overview of Cea Cadarache tools

    International Nuclear Information System (INIS)

    The Experimental Physics section of CEA Cadarache operates three critical facilities devoted to neutronic studies of advanced reactors (EOLE, MINERVE and MASURCA) covering a large scope of interests. These include 100% MOX core in ABWR qualification, knowledge improvement of basic nuclear data for heavy nuclides for new options of the fuel cycle - especially the multi-recycling of plutonium - and accelerator-driven systems neutronic behaviour for transmutation studies. The paper describes these facilities, the scientific programmes associated and the progressive improvement of experimental techniques, the aim being to significantly reduce the uncertainties regarding the evaluation of the physical parameters. (authors)

  18. Our energies have a future. A future without CO{sub 2}. Areva in 2005; Nos energies ont de l'avenir. Un avenir sans CO{sub 2}. Areva en 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document is the sustainable development and 2005 annual report altogether of Areva group. It presents first the challenges of energy for economical development, the climate change threat and the sustainability of nuclear power in particular with respect to radioactive wastes management and power blackouts. Then follows a presentation of Areva's 10 commitments for sustainable development (governance and continuous improvement, financial performance, innovation, customer satisfaction, commitment to employees, risk management and prevention, environmental protection, dialogue and consensus building, community involvement). The annual report presents: the 2005 highlights, Areva around the world, key data, corporate governance, organisation of the group, share information and shareholder relations, business review (front end division, reactors and services division, back end division, transmission and distribution division), financial report and glossary. (J.S.)

  19. AREVA in Gabon. Inquiry report on the situation of workers of the COMUF, Gabonese subsidy of the AREVA-COGEMA group

    International Nuclear Information System (INIS)

    After a recall of the development of uranium mining activities by the COMUF Company which is now a subsidy company of the AREVA-COGEMA group, and a presentation of the inquiry, this document reports the inquiry performed in Gabon about the medical issue (with notably inadequate security measures) and about the environmental issue related to the site rehabilitation. It also reports the analysis of questionnaires sent to ex-workers in Gabon, as well as of testimonies obtained from expatriates who are suffering from health problems. The report discusses the possibilities to take legal actions for different reasons: unintentional injuries and homicide, endangering the life of others, or inexcusable error. In conclusion the report outlines that the risk was known, that there was no information about it, and that people were deliberately maintained in ignorance

  20. AREVA Adhesive Technology. A method to mitigate and/or prevent leaks in pools with stainless steel liners Georg Kramer AREVA GmbH IBOC-G

    International Nuclear Information System (INIS)

    Repair methods with conventional welding technique are not promising as a preventative measure mostly due to cost and time issues. With the provided repair method, the AREVA adhesive technology, it is possible to stop existing leaks and work as a prophylactic measure against future penetration from the concrete side of the pool. This technique can cover the failure mechanisms from weld failures over corrosion to mechanical stresses. Another advantage of the adhesive technology is the possibility of using remote-controlled underwater repair methods which are particularly beneficial in the repair of leaks in spent fuel pools. Extensive laboratory testing and longstanding successful experience in nuclear power plants have proved the suitability of the adhesive technology as active and proactive methods to minimize leakages in pools.

  1. AREVA Adhesive Technology. A method to mitigate and/or prevent leaks in pools with stainless steel liners Georg Kramer AREVA GmbH IBOC-G

    Energy Technology Data Exchange (ETDEWEB)

    Kraemer, G.

    2013-07-01

    Repair methods with conventional welding technique are not promising as a preventative measure mostly due to cost and time issues. With the provided repair method, the AREVA adhesive technology, it is possible to stop existing leaks and work as a prophylactic measure against future penetration from the concrete side of the pool. This technique can cover the failure mechanisms from weld failures over corrosion to mechanical stresses. Another advantage of the adhesive technology is the possibility of using remote-controlled underwater repair methods which are particularly beneficial in the repair of leaks in spent fuel pools. Extensive laboratory testing and longstanding successful experience in nuclear power plants have proved the suitability of the adhesive technology as active and proactive methods to minimize leakages in pools.

  2. AREVA Back-End Possibilities for the Used Fuel of Research Test Reactors

    International Nuclear Information System (INIS)

    One of the major issues faced by the Research and Test Reactor (RTR) operators is the back end management of the used fuel elements. RTR used fuel for both HEU and LEU types are problematic for storing and disposal as their Aluminium cladding degrades leading to activity release, possible loss of containment and criticality concerns. Thus, direct disposal of RTR used fuel, (without prior treatment and conditioning) is in this respect hardly suitable. In the same manner, long term interim storage of RTR used fuel has to take into account the issue of fuel corrosion. Treating RTR used fuel allows separating the content into recyclable materials and residues. It offers many advantages as compared to direct disposal such as the retrieval of valuable fissile material, the reduction of radio-toxicity and a very significant reduction of the volume of the ultimate waste package (reduction factor between 30 and 50). In addition, the vitrification of the residues provides a package that has been specifically designed to ensure long term durability for long term interim storage as well as final disposal (99% of the activity is encapsulated into a stable matrix). RTR fuel treatment process was developed several decades ago by AREVA with now thirty years of experience at an industrial level. The treatment process consists in dissolving the whole assembly (including the Al cladding) in nitric acid and then diluting it with standard Uranium Oxide fuel dissolution liquor prior to treatment with the nominal Tributylphosphate solvent extraction process. A wide range of RTR spent fuel has already been treated in the AREVA facilities. First, at the Marcoule plant over 18 tons of U-Al type RTR fuel from 21 reactors in 11 countries was processed. The treatment activities are now undertaken at the La Hague plant where 17 tons of RTR used fuel from Australia Belgium, and France aligned for treatment. In June 2005, AREVA started to treat at La Hague ANSTO's Australian RTR used fuel from

  3. Call for tender - Areva-Alstom: watershed in wind energy - Technological duel on the open sea

    International Nuclear Information System (INIS)

    The author comments the answers to a call for tender made by the French government and concerning five offshore wind farm sites (Le Treport, Fecamp, Courseulles sur Mer, Saint-Brieuc and Saint-Nazaire). As they are present within the three consortiums, Areva and Alstom should provide the wind turbines. This would result in the construction by Alstom of two blade and mast factories and two turbine and pad factories. For both companies, this market of 500 to 600 turbines is an opportunity. Many jobs are at stake. They push themselves forward for their experience or their innovation capacity. But their wind turbines will be based on foreign (Spanish or German) technology

  4. AREVA solutions to licensing challenges in PWR and BWR reload and safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Curca-Tivig, Florin [AREVA GmbH, Erlangen (Germany)

    2016-05-15

    Regulatory requirements for reload and safety analyses are evolving: new safety criteria, request for enlarged qualification databases, statistical applications, uncertainty propagation.. In order to address these challenges and access more predictable licensing processes, AVERA is implementing consistent code and methodology suites for PWR and BWR core design and safety analysis, based on first principles modeling and extremely broad verification and validation data base. Thanks to the high computational power increase in the last decades methods' development and application now include new capabilities. An overview of the main AREVA codes and methods developments is given covering PWR and BWR applications in different licensing environments.

  5. Areva new fuel designs; increased reliability, operating margins and operating efficiency

    International Nuclear Information System (INIS)

    AREVA is continuously working on the improvement of the fuel design to address immediate and future needs of the utilities. This improvement process regularly leads to incremental changes but also to breakthrough changes addressing the next needs of the market. Since a few years now, the improvements of the fuel design and licensing benefit from the improvement and upgrade in codes and methods and computational capabilities. Changes in design are sustained by these more powerful and phenomenological tools which secure and fasten the fuel design optimization and its implementation. (Author)

  6. Left in the dust. AREVA's radioactive legacy in the desert towns of Niger

    International Nuclear Information System (INIS)

    In one of the poorest countries in the world, ranking last in the Human Development Index of the United Nations Development Programme (UNDP), where more than 40% of children are underweight for their age, water and access to improved water sources is scarce and almost three quarters of the population are illiterate, the French nuclear giant AREVA extracts precious-and deadly-natural resources, earning billions for its Fortune 500 corporation, and leaving little behind but centuries of environmental pollution and health risks for the citizens of Niger. (authors)

  7. Excited Baryon Spectroscopy in the Large $N_c$ Limit

    CERN Document Server

    Goity, J L

    1996-01-01

    The leading in 1/N_c spin-flavor symmetry breaking mass splittings, of order N_c^0, in excited non-strange Baryons are shown to be given, up to two-body operators, by three different effective Hamiltonians: Thomas precession spin-orbit, spin-isospin tensor, and spin-orbit with isospin exchange. Explicit expressions for their matrix elements between low excited Baryons are obtained, and the structure of the mass splittings in large N_c is established to first order of perturbation theory. The problem of extending the large N_c results to the real world with N_c=3 is briefly addressed.

  8. Three-nucleon forces in the 1/Nc expansion

    CERN Document Server

    Phillips, Daniel R

    2013-01-01

    The operator structures that can contribute to three-nucleon forces are classified in the 1/Nc expansion. At leading order in 1/Nc a spin-flavor independent term is present, as are the spin-flavor structures associated with the Fujita-Miyazawa three-nucleon force. Modern phenomenological three-nucleon forces are thus consistent with this O(Nc) leading force, corrections to which are suppressed by a power series in 1/Nc^2. A complete basis of operators for the three-nucleon force, including all independent momentum structures, is given explicitly up to next-to-leading order in the 1/Nc expansion.

  9. Joining the Nuclear Renaissance with the Engineering Business Unit of AREVA

    Energy Technology Data Exchange (ETDEWEB)

    Hubert, Nathalie; Menguy, Stephane [SGN, AREVA Group, 1 rue des Herons, 78182 Saint-Quentin en Yvelines Cedex (France); Valery, Jean-Francois [AREVA NC, AREVA Group, Tour AREVA, 1 place de la Coupole, 92084 Paris La Defense Cedex (France)

    2008-07-01

    The reality of the nuclear renaissance is no longer a question. All over the world, new nuclear plants are going to be deployed; the whole fuel cycle has to be adjusted to fulfil their needs, the front-end to produce the fuel and the back-end to properly manage radioactive waste. AREVA fuel cycle engineering teams have been involved in the design of a variety of industrial plants covering the entire fuel cycle for 50 years. The consistency of the French nuclear policy has been a major factor to acquire and renew the competencies and workforce of AREVA Engineering Business Unit. Our partnership with our customers, French ones but also Japanese, Americans and from other countries, has led us to develop a comprehensive approach of the services that we can deliver, in order to give them the best answer. SGN teams have been involved in the R and D phases in order to take into account the industrialisation aspects as early as possible, and our work does not end with the delivery of the plants; it includes assistance to the operators to optimise and keep their facilities in line with the changing rules and constraints, which ensures the integration of a wide operational experience feedback and the ability to design flexible facilities. This paper will present through our experience how this global approach has been developed and continuously improved and how we are preparing our teams to be ready to answer to the coming needs. (authors)

  10. An effective and sustainable D and D concept - competencies and experiences of AREVA

    International Nuclear Information System (INIS)

    The decommissioning and dismantling (D and D) projects - as large projects generally - are influenced by a variety of different topics. Strategy and planning are very demanding as they are defining the costs of the project for a long period of time. Addressing the political and legal framework is key as D and D projects depending on final disposal concepts usually handled by governmental organizations. If the conditions as described are fulfilled, i.e. contractor and customer collaborate already during the licensing process and the project starts with a fast minimization of the radiological inventory, the overall project duration will be reduced. Again, this offers an enormous potential to save costs. Moreover, remaining operational systems can be reduced much earlier and replaced by mobile operating systems due to the loss of radioactive inventory. AREVA as a major company in the nuclear business has a lot of experience from New Builds-, Service- and D and D projects worldwide. The presentation on the ECED Conference will also give some examples and will demonstrate the competencies and experiences AREVA gained in the last years. (author)

  11. The AREVA integrated and sustainable concept of fatigue design, monitoring and re-assessment

    International Nuclear Information System (INIS)

    Prevention of fatigue damage of components is an important topic with respect to safety and availability of a nuclear power plant. The issue of fatigue monitoring should be of primary interest throughout service life. Based on the changing general framework, i.e. planning of new plants with a projected lifetime of 60 years and the lifetime extension of existing plants AREVA is focussing R and D activities on improved detection methods. Primary objective is the realistic determination of the actual usage level of reactor components. The fatigue monitoring is supposed to enhance cost optimization and minimize inspection frequency. Fatigue monitoring should be implemented at the beginning of start-up period since the high loads during this phase introduce a significant contribution to the usage level. AREVA recommends the use of the FAMOS (fatigue monitoring system) for the assessment of the realistic transient loads and the data processing with respect to fatigue evaluation. Every 10 years the actual usage levels should be evaluated in detail according to the standards, based on measured load data. The fatigue evaluation is usually performed using finite element analyses taking into account the transient temperature loads at the component, dependent on the component demands based on elastic or elasto-plastic material behaviour. Potential problematic areas can be identified reliably. Direct measurement of fatigue damage, refined analysis concepts (short crack fracture mechanics, and ratcheting simulation) are supposed to support the concept

  12. Joining the Nuclear Renaissance with the Engineering Business Unit of AREVA

    International Nuclear Information System (INIS)

    The reality of the nuclear renaissance is no longer a question. All over the world, new nuclear plants are going to be deployed; the whole fuel cycle has to be adjusted to fulfil their needs, the front-end to produce the fuel and the back-end to properly manage radioactive waste. AREVA fuel cycle engineering teams have been involved in the design of a variety of industrial plants covering the entire fuel cycle for 50 years. The consistency of the French nuclear policy has been a major factor to acquire and renew the competencies and workforce of AREVA Engineering Business Unit. Our partnership with our customers, French ones but also Japanese, Americans and from other countries, has led us to develop a comprehensive approach of the services that we can deliver, in order to give them the best answer. SGN teams have been involved in the R and D phases in order to take into account the industrialisation aspects as early as possible, and our work does not end with the delivery of the plants; it includes assistance to the operators to optimise and keep their facilities in line with the changing rules and constraints, which ensures the integration of a wide operational experience feedback and the ability to design flexible facilities. This paper will present through our experience how this global approach has been developed and continuously improved and how we are preparing our teams to be ready to answer to the coming needs. (authors)

  13. The nuclear renaissance and AREVA's reactor designs for the 21st century. EPR and SWR-1000

    International Nuclear Information System (INIS)

    Hydro and nuclear energy are the most environmentally benign way of producing electricity on a large scale. Nuclear generated electricity releases 38 times fewer greenhouse gases than coal, 27 times fewer than oil and 15 times fewer than natural gas [9]. On a global scale nuclear power annually saves about 10% of the global CO2 emission. European nuclear power plants save amount of CO2 emissions corresponding with the annual emission of CO2 from all European passenger cars [16]. Also, that is approximately twice the total estimated quantity to be avoided in Europe under the Kyoto Protocol during the period 2008-2012. In respect to main drivers - such as concerns of the global warming effect, population growth, and future energy supply shortfall, low operating costs, reduced dependence on imported gas - it is clear that 30 new nuclear reactors currently being constructed in 11 countries and another 35 and more planed during next 10 years confirm the nuclear renaissance. Participation in the construction of 100 reactors out of 443 worldwide operated in January 2006 and supplying fuel to 148 of them AREVA helps meet the 21st century's greatest challenges: making energy available to all, protecting the planet, and acting responsibly towards future generations. With EPR and SWR-1000, AREVA NP has developed advanced design concepts of Generation III+ nuclear reactors which fully meet the most stringent requirements in terms of nuclear safety, operational reliability and economic performance. (author)

  14. AREVA revenue and data for the first nine months of 2008; AREVA informations et chiffre d'affaires relatifs aux neuf premiers mois de l'exercice 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This public information sheet presents financing data of the group AREVA for the first nine months of 2008. It shows a high increase of the revenue (12,9%). The data are detailed for each activity sector, front end, reactors and services, back end, transmission and distribution. Consolidated revenue for the years 2007 are also provided. (A.L.B.)

  15. Environmental assessment, continual improvement and adaptive management within the AREVA sustainable development framework

    International Nuclear Information System (INIS)

    COGEMA Resources Inc. (which is part of the AREVA Group) is a Canadian company with its head office in Saskatoon, Saskatchewan. It owns and operates mining and milling facilities in northern Saskatchewan, which produce uranium concentrate. The McClean Lake Operation commenced production in 1999 and its environmental management system represents an integrated approach to environmental assessment, continual improvement and adaptive management based on operational results. In Canada, sustainable development is promoted through the application of the Canadian Environmental Assessment Act (CEAA). Environmental Assessment (EA) is a planning tool, which incorporates environmental considerations before irrevocable decisions are taken. The basic tenet of the Act is the determination of whether the potential environmental effects of a project are adverse, significant and likely, taking into consideration mitigation measures. Thus, project planning and design entails an iterative process that incorporates mitigation measures to minimize potentially significant adverse effects. As part of the EA process conservative approaches are taken to predict potential effects. Several important elements are generated through the EA process including: a set of environmental effects predictions, a compliance and environmental effects monitoring program, a follow-up program to address uncertainties in the prediction of environmental effects, and the identification of contingency measures that could be implemented should non-conservative assumptions be identified in the original assessment framework. The challenge is to integrate each of these elements into the environmental management framework of the operating facility and develop an iterative mechanism to evaluate operational performance relative to what was originally predicted. In Saskatchewan, a requirement of operational licenses is the periodic evaluation of the 'Status of the Environment' surrounding operational facilities. These

  16. Potential Applications for Nuclear Energy besides Electricity Generation: AREVA Global Perspective of HTR Potential Market

    International Nuclear Information System (INIS)

    Energy supply is increasingly showing up as a major issue for electricity supply, transportation, settlement, and process heat industrial supply including hydrogen production. Nuclear power is part of the solution. For electricity supply, as exemplified in Finland and France, the EPR brings an immediate answer; HTR could bring another solution in some specific cases. For other supply, mostly heat, the HTR brings a solution inaccessible to conventional nuclear power plants for very high or even high temperature. As fossil fuels costs increase and efforts to avoid generation of Greenhouse gases are implemented, a market for nuclear generated process heat will develop. Following active developments in the 80's, HTR have been put on the back burner up to 5 years ago. Light water reactors are widely dominating the nuclear production field today. However, interest in the HTR technology was renewed in the past few years. Several commercial projects are actively promoted, most of them aiming at electricity production. ANTARES is today AREVA's response to the cogeneration market. It distinguishes itself from other concepts with its indirect cycle design powering a combined cycle power plant. Several reasons support this design choice, one of the most important of which is the design flexibility to adapt readily to combined heat and power applications. From the start, AREVA made the choice of such flexibility with the belief that the HTR market is not so much in competition with LWR in the sole electricity market but in the specific added value market of cogeneration and process heat. In view of the volatility of the costs of fossil fuels, AREVA's choice brings to the large industrial heat applications the fuel cost predictability of nuclear fuel with the efficiency of a high temperature heat source free of greenhouse gases emissions. The ANTARES module produces 600 MWth which can be split into the required process heat, the remaining power drives an adapted prorated

  17. The CEA Cadarache site. Additional safety assessment with respect to the accident which occurred in the Fukushima-Daiichi nuclear power station

    International Nuclear Information System (INIS)

    After a presentation of some characteristics of the CEA Cadarache site (internal and external industrial environment, crisis management organization at the CEA level and at the local level), this document reports the identification of structures and equipment concerned by crisis management (site support functions, critical structures and equipment concerned by additional safety assessments). Then, it addresses the different risks: earthquake (sizing of critical structures and equipment, margin assessment), flooding (possible origins, alarm measures), other extreme natural events (extreme meteorological conditions, extreme earthquake with induced flooding, forest fire), and loss of electric supplies and of cooling systems. The last parts address the organization of accident management in situation typically related to additional safety management), and subcontracting conditions and practices

  18. Efficient known ncRNA search including pseudoknots

    OpenAIRE

    Yuan Cheng; Sun Yanni

    2013-01-01

    Abstract Background Searching for members of characterized ncRNA families containing pseudoknots is an important component of genome-scale ncRNA annotation. However, the state-of-the-art known ncRNA search is based on context-free grammar (CFG), which cannot effectively model pseudoknots. Thus, existing CFG-based ncRNA identification tools usually ignore pseudoknots during search. As a result, dozens of sequences that do not contain the native pseudoknots are reported by these tools. When pse...

  19. 复合离子镀膜技术制备Cr+Ti+TiNC/TiNC+C/DLC膜性能研究%Properties of Cr+Ti+TiNC/TiNC+C/DLC films prepared by composite ion plating

    Institute of Scientific and Technical Information of China (English)

    马胜歌; 于大洋; 杨宏伟; 张以忱

    2008-01-01

    结合中频孪生靶非平衡磁控溅射、电弧离子镀和霍尔离子源辅助沉积三种工艺,制备了Cr+Ti+TiNC/TiNC+C/DLC硬质膜.硬质膜呈深黑色,表面比较光滑,顶层为掺N的类金刚石(Diamond-like Carbon,DLC)膜,中间层为含C的TiNC,底层为含Ti和Cr的TiNC,力学性能良好.

  20. Radioactive waste storage at the CEA Centre in Cadarache; transfer from the -storage yard- to the CEDRA facility: an illustration of changes in the safety requirements

    International Nuclear Information System (INIS)

    A lot of changes have been made to the nuclear waste storage and disposal strategy over the last few years thanks to technological progress and changes in the requirements applicable in the sector. In this article, the authors present a concrete example of the actions undertaken, at the request of the French Nuclear Safety Authority (ASN), by the CEA Centre at Cadarache, regarding the Cadarache Centre waste storage facility (BNI 56), a facility which was originally intended as a permanent repository for solid waste. Commissioned in 1969, BNI 56 is made up of various trenches and pits which no longer meet current ASN requirements. To clean up these trenches, a legacy from the past, now requires considerable resources and involves many problems, especially due to uncertainty surrounding the nature, activity levels, packaging and volume of this waste. ASN ensures that the CEA will fully assume its overriding responsibility in the matter and implement safe, rigorous and transparent management solutions for all the waste. The BNI 56 trenches are an ongoing and concrete example of the difficulties inherent in recovering waste from storage and dismantling former facilities the design of which failed to take such aspects into account. This waste is now being repackaged so that it can be stored at a new basic nuclear installation called CEDRA (packaging and storage of radioactive waste) which complies with the safety requirements currently in force. This facility, commissioned in 2006, is intended for the storage of Type B solid radioactive waste for a period of 50 years pending construction of a deep geological repository or long-term storage facility. (authors)

  1. Large N_c confinement and turbulence

    CERN Document Server

    Blaizot, Jean-Paul

    2008-01-01

    We suggest that the transition that occurs at large $N_c$ in the eigenvalue distribution of a Wilson loop has a turbulent origin. We arrived at this conclusion by studying the complex-valued inviscid Burgers-Hopf equation that corresponds to the Makeenko-Migdal loop equation, and we demonstrate the appearance of a shock wave in the spectral flow of the Wilson loop eigenvalues. This picture supplements that of the Durhuus-Olesen transition with a particular realization of disorder. The critical behavior at the formation of the shock allows us to infer exponents that have been measured recently in lattice simulations by Narayanan and Neuberger in $d=2$ and $d=3$. Our analysis leads us to speculate that the universal behavior observed in these lattice simulations might be a generic feature of confinement, also in $d=4$ Yang-Mills theory.

  2. Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2012

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

  3. The AREVA customized chemical cleaning C3-concept as part of the steam generator asset management

    International Nuclear Information System (INIS)

    with various chemical cleaning methods and their world wide applications AREVA has developed the 'C3' Customized Chemical Cleaning concept. This concept covers the entire range of steam generator chemical cleaning. With this approach, also specific problems like removal of sludge piles from tube sheet can be adequately addressed. At European PWRs the above presented overall approach was applied successfully in 2009 and 2010. Prior to the chemical cleaning the steam generator status was investigated and evaluated in a common approach of all relevant AREVA departments. For example, as a result of one plant specific evaluation, a hard sludge problem was identified combined with denting indications mainly on the tube sheet. Based on this SG assessment and the expected amount of deposits an individually tailored and site specific cleaning approach was developed in close cooperation with the plant operator. Prior to the chemical cleaning an inner bundle lancing was performed to mechanically weaken the hard deposits, which allows deep penetration of the cleaning agent into the deposits. The chemical cleaning methodology for this site specific SG problem was the AREVA DART HT process selected from the C3 toolbox. The DART HT process allows an efficient removal of hard deposits, while keeping the average corrosion below 50 μm. After the chemical cleaning a subsequent tube sheet lancing was performed, effectively removing the chemically softened deposits. This approach removed the targeted amount of deposits, thus eliminating the hard sludge denting of tubes at the tube sheet. This paper describes the joint approach of the plant operator and AREVA for the on-site chemical cleaning to the improve steam generator condition. (authors)

  4. Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2014

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2014, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  5. Burn-up credit applications for UO2 and MOX fuel assemblies in AREVA/COGEMA

    International Nuclear Information System (INIS)

    For the last seven years, AREVA/COGEMA has been implementing the second phase of its burn-up credit program (the incorporation of fission products). Since the early nineties, major actinides have been taken into account in criticality analyses first for reprocessing applications, then for transport and storage of fuel assemblies Next year (2004) COGEMA will take into account the six main fission products (Rh103, Cs133, Nd143, Sm149, Sm152 and Gd155) that make up 50% of the anti-reactivity of all fission products. The experimental program will soon be finished. The new burn-up credit methodology is in progress. After a brief overview of BUC R and D program and COGEMA's application of the BUC, this paper will focus on the new burn-up measurement for UO2 and MOX fuel assemblies. It details the measurement instrumentation and the measurement experiments on MOX fuels performed at La Hague in January 2003. (author)

  6. Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2013

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2013, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  7. Areva - Environmental, social and societal report 2014, Zirconium sites: Jarrie, Ugine, Rugles, Montreuil-Juigne, Paimboeuf

    International Nuclear Information System (INIS)

    This report first gives an overview of Areva's zirconium-related activities: those integrated into the nuclear fuel cycle, industrial activities distributed among five production sites (Jarrie, Ugine, Rugles, Montreuil-Juigne, Paimboeuf) with an indication of the various products produced on each site (from zirconia to tubes and sheets). The history and activities of these five plants are briefly described. The next part addresses issues related to health, safety, and the environment: health and safety at work, risk prevention and management, improvement of environmental performance (consumption management, waste control and management), material flows and their management modes in the different plants (indication of input products, activities, output products, and destination). The last part addresses social and societal issues: recruiting, training, ability management, actions for local economic development

  8. The French approach through the SMR consortium (CEA, EDF, AREVA, DCNS)

    International Nuclear Information System (INIS)

    The SMR (Small Modular Reactor) is a new range of nuclear reactors characterized by a low output power (less than 300 MWe) and a standardized modular factory-based construction. Moderate capital costs make this type of reactor very attractive for medium-size power utilities or small countries. A consortium made around the CEA and its industrial partners (EDF, AREVA and DCNS) has performed economic and technical feasibility studies. It appears that the competitiveness of SMR require power production costs around 100 euros/MWh and that SMR will be based on PWR technology with a power output of 150 MWe per unit. 2 types of SMR are proposed: a terrestrial unit and an immersed unit. The concept of the immersed SMR, called Flexblue, is based on an unlimited access to a cold sink (the ocean) and a complete modularity. In both types the standard of safety appears to be high. (A.C.)

  9. Status of safety in nuclear facilities - 2012. AREVA General Inspectorate Annual report

    International Nuclear Information System (INIS)

    After a message from the Areva's Chief Executive Officer and a message from the senior Vice President of safety, health, security, sustainable development, a text by the inspector general comments the key safety results (events, dose levels, radiological impacts), the inspection findings, the areas of vigilance (relationship with the ASN, the management of the criticality risk, and facility compliance), some significant topics after the Fukushima accident. Then this report addresses the status of nuclear safety and radiation protection in the group's facilities and operations. It more specifically addresses the context and findings (lessons learned from the inspections, operating experience from event, employee radiation monitoring, environmental monitoring), crosscutting processes (safety management, controlling facility compliance, subcontractor guidance and management, crisis management), specific risks (criticality risk, fire hazards, transportation safety, radioactive waste management, pollution prevention, liability mitigation and dismantling), and areas for improvement and outlook

  10. The Areva integrated and sustainable concept of fatigue design, monitoring and re-assessment

    International Nuclear Information System (INIS)

    Avoiding fatigue-induced damage to components of nuclear power plant technology is an important prerequisite for maintaining plant safety and increasing availability. Fatigue monitoring is an integral part of plant aging and lifetime management. Against this background and changing framework conditions, such as design and construction of new nuclear power plants for 60 years of operation, life extension of existing plants, and the attention to be paid to media-induced effects, improving methods of detection is one of the main concerns of Areva's R and D work. The key objective is to determine more realistically the current degree of fatigue of power plant components. The integral and multi-step procedure proposed contributes to both cost optimization and inspection cycle minimization. Fatigue monitoring should start as early as in the commissioning phase, as the high loads and stresses arising at that stage already contribute significantly to the level of fatigue. Areva recommends using the FAMOS (Fatigue Monitoring System) system to determine the real transient loads and stresses and process them for purposes of a first quick fatigue assessment. On a medium-term basis, the current levels of fatigue are to be determined by means of a detailed code-based fatigue analysis. The input data in that case are the real loads and stresses measured, where the temperature transients are specified from the perspective of experts in systems technology. Fatigue is demonstrated on the basis of finite-element analyses taking into account transient temperature field loads and stresses affecting a component as well as primary loads and stresses. In this way, potential problem areas can be identified reliably which, in turn, helps reduce inspection cost. (orig.)

  11. Preparation and EPR characterization of N@C60 and N@C70 based peapods

    Science.gov (United States)

    Corzilius, B.; Gembus, A.; Weiden, N.; Dinse, K.-P.

    2005-09-01

    Using the quartet spin of encased nitrogen atoms as an electron paramagnetic resonance (EPR) probe, it is possible to examine the fullerene/nanotube interactions in a peapod. A purification method is developed which allows low temperature filling of nanotubes with endohedral fullerenes. The paramagnetic impurities of undoped single wall carbon nanotubes (SWNT) are characterized via EPR resulting in a broad superparamagnetic signal of the remaining catalyst particles and a rather narrow signal of carbonaceous material. Comparison of EPR spectra of several nitrogen endohedral doped peapods with their analogues obtained in a solid fullerene matrix shows a significant broadening of N@C60 and N@C70 EPR signals. This broadening is related to a non-vanishing zero-field splitting caused by deformation of the fullerene cage upon encapsulation.

  12. NC10 bacteria in marine oxygen minimum zones

    DEFF Research Database (Denmark)

    Padilla, Cory C; Bristow, Laura A; Sarode, Neha;

    2016-01-01

    . rRNA and mRNA transcripts assignable to NC10 peaked within the OMZ and included genes of the putative nitrite-dependent intra-aerobic pathway, with high representation of transcripts containing the unique motif structure of the nitric oxide (NO) reductase of NC10 bacteria, hypothesized to...

  13. Areva revenue and data for the first quarter of 2008; Areva informations et chiffre d'affaires relatifs au 1. trimestre de l'exercice 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    First quarter 2008 revenue was up 12.1% year-on-year, to 2.769 billion euros. Like-for-like (at constant exchange rates and consolidation scope), growth came to 14.5%. Foreign exchange had a negative impact of 2.5%, or -69 million euros, mainly due to currency translation tied to the US dollar drop compared with the euro. The consolidation scope had a positive impact of +0.7% or 18 million euros, chiefly as a result of the consolidation of VEI Distribution (specializing in medium voltage distribution) and Passoni and Villa (world leader in the manufacture of high voltage bushings) in the Transmission and Distribution division. The main growth engines for first quarter revenue were the Reactors and Services division and the Back End division, with growth of 29.7% (+36.8% LFL1) and 13.8% (+14.1% LFL1) respectively. Outside France, revenue rose to 1.857 billion euros, compared with 1.753 billion euros in the first quarter of 2007. This represents 67% of total revenue. As a reminder, the group points out that: - revenue can vary significantly from one quarter to the next in the nuclear businesses, and quarterly operations should therefore not be taken as a reliable basis for annual projections; - the foreign exchange impact mentioned in this release comes from the translation of subsidiary accounts into the group's unit of account, and primarily reflects the US dollar in relation to the euro. AREVA also points out that its foreign exchange hedging policy for commercial operations aims to shield profitability from fluctuations in exchange rates in relation to the euro.

  14. Concept and operational experience of the Areva DMT process for preventive maintenance of steam generators; Concepto y experiencia operacional del proceso DMT de Areva para el mantenimiento preventivo de generadores de vapor

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, S.; Gaspar, J. D.; Potier, P.; Jones, D.

    2015-07-01

    The AREVAs DMT process is a preventive chemical cleaning of the steam generators (SG) that provides the required features to keep the SG in good operative conditions. -Very low carbon steel corrosion -Innocuous towards stainless steel and nickel base alloys -Inherently safe process -Efficient magnetite dissolution -No use of CMR (i.e Carcinogenic, Mutagenic and toxic to Reproduction) Chemicals (e. g. Hydrazine) -No ammonia emissions -Easy decomposition of waste Several applications have been performed world-wide over the last 5 years. The results were fully satisfying in all the above stated points. The removal of up to 800 kg of dry deposits per SG was realized. A positive effect on fouling factor was observed, showing that AREVAs DMT process is a safe, easy and successful way to maintain the steam generators in excellent operative conditions. (Author)

  15. AREVA Technical Days (ATD) session 3: operations of the reactors and services division, technical and economic aspects; AREVA Technical Days (ATD) session 3: les activites du pole reacteurs et services, aspects techniques et economiques

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This third session deals with the reactors technologies basics, the EPR and SWR 1000 issues and outlook, the nuclear systems of the future, the business opportunities and business models. (A.L.B.)

  16. AREVA Technical Days (ATD) session 3: operations of the reactors and services division, technical and economic aspects

    International Nuclear Information System (INIS)

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This third session deals with the reactors technologies basics, the EPR and SWR 1000 issues and outlook, the nuclear systems of the future, the business opportunities and business models. (A.L.B.)

  17. CSR and Sustainable Development: Multinationals are they Socially Responsible in Sub-Saharan Africa? The case of Areva in Niger

    OpenAIRE

    Daouda, Youssoufou Hamadou

    2014-01-01

    The purpose of this paper is to contribute in understanding issues related to Corporate Social Responsibility (CSR) in Sub-Saharan Africa. The paper demonstrates that even though multinationals strategies participate with economic and social development, there still is much to do given environmental, social and economic expectations. The case of Areva discussed here illustrates the discrepancy that exists between such companies’ CSR strategies and the local conditions in which they evolve (ar...

  18. AREVA's toolbox for long-term best performance and reliable operation of nuclear steam generators

    International Nuclear Information System (INIS)

    Long-term integrity and high performance of major plant systems and components are of uppermost importance for the successful operation of any power plant. AREVA's experience gathered with water-steam cycle chemistry treatments in more than 40 years yields the conclusion: Accumulation of corrosion products in SGs may result in local overheating and enrichment of impurities up to critical levels. This can lead to several degradation phenomena of the structural materials of the SGs. Therefore, minimization of corrosion product generation and prevention of deposit accumulation is required. The objective of AREVA's asset management program is to support operators by minimizing corrosion damage and performance losses of water-steam cycle systems and components and thereby to maximize the availability and economic performance of the plant. Such asset management program is in principle a closed cycle process. It is based on control, corrective and preventive measures. The objective of control measure is deriving a widespread assessment of the corrosion status of the steam-water cycle which yields to weak points and identifying the best suited corrective and/or preventive measures. In the subsequent steps appropriate measures which improve the current status or counteract on identified issues are identified and applied. Corrective measures, likes mechanical and/or chemical cleaning are targeting the minimization of negative influence on plant performance caused by corrosion in the steam-water cycle. Complementary to corrective measures are preventive ones, like optimization of pH strategy and AREVA's FFA technology could by applied. They are focusing on the origin of corrosion product generation. AREVA is offering a toolbox for long-term best performance and reliable operation of NPPs. (author)

  19. Positive parity pentaquark towers in large Nc QCD

    CERN Document Server

    Pirjol, D; Pirjol, Dan; Schat, Carlos

    2006-01-01

    We construct the complete set of positive parity pentaquarks, which correspond in the quark model to {\\bar s} q^{Nc+1} states with one unit of orbital angular momentum L=1. In the large Nc limit they fall into the K=1/2 and K=3/2 irreps (towers) of the contracted SU(4)c symmetry. We derive predictions for the mass spectrum and the axial couplings of these states at leading order in 1/Nc. The strong decay width of the lowest-lying positive parity exotic state is of order O(1/Nc), such that this state is narrow in the large Nc limit. Replacing the antiquark with a heavy antiquark {\\bar Q} q^{Nc+1}, the two towers become degenerate, split only by O(1/mQ) hyperfine interactions. We obtain predictions for the strong decay widths of heavy pentaquarks to ordinary baryons and heavy H(*)_{\\bar Q} mesons at leading order in 1/Nc and 1/mQ.

  20. Processing of the GALILEO fuel rod code model uncertainties within the AREVA LWR realistic thermal-mechanical analysis methodology

    International Nuclear Information System (INIS)

    The availability of reliable tools and associated methodology able to accurately predict the LWR fuel behavior in all conditions is of great importance for safe and economic fuel usage. For that purpose, AREVA has developed its new global fuel rod performance code GALILEO along with its associated realistic thermal-mechanical analysis methodology. This realistic methodology is based on a Monte Carlo type random sampling of all relevant input variables. After having outlined the AREVA realistic methodology, this paper will be focused on the GALILEO code benchmarking process, on its extended experimental database and on the GALILEO model uncertainties assessment. The propagation of these model uncertainties through the AREVA realistic methodology is also presented. This GALILEO model uncertainties processing is of the utmost importance for accurate fuel design margin evaluation as illustrated on some application examples. With the submittal of Topical Report GALILEO to the U.S. NRC in 2013, GALILEO and its methodology are on the way to be industrially used in a wide range of irradiation conditions. (authors)

  1. AREVA. Operating and financial results for the first half of 2011

    International Nuclear Information System (INIS)

    The first half of 2011 was marked by the accident at the Fukushima power plant following the unprecedented natural disasters that struck Japan. AREVA drew the first consequences from these events as early as June 2011 and recorded provisions and impairment in its half-year financial statements, related in particular to the expected short-term level of activity of some facilities. Close to 200 million euros in orders were canceled out of a total in backlog of more than 43 billion euros, which was down by a little more than 1 billion euros compared with the end of 2010. The longer term consequences of these events for AREVA are being assessed. They could concern all operations in the nuclear cycle and will be included in the strategic plan to be prepared by the end of the second half of the year. The fundamentals underpinning the development of the nuclear market are unchanged: strong growth in demand for electricity in the coming decades, diminished fossil resources, the search by many countries for energy independence, and the growing need to address climate issues. Through its efficient integrated business model, AREVA is present in every segment of the nuclear chain and is positioned in high-tech renewable energies with an offering that is perfectly suited to the requirements of the world's power companies. Decisions by governments on energy policy and by the safety authorities in different countries will influence market developments and the schedule for executing certain projects. Germany announced its decision to withdraw permanently from nuclear power and Switzerland intends to do the same, while Italy has opted not to restart its program. And yet the majority of countries have confirmed their decision to pursue nuclear power programs, present and future. In the first half, the group continued to draw down debt, achieving a net debt level of less than 3 billion euros at the end of June, thanks in particular to the conclusion of the proceedings with Siemens

  2. Evolutionary conservation and functional roles of ncRNA

    OpenAIRE

    Qu, Zhipeng; Adelson, David L.

    2012-01-01

    Non-coding RNAs (ncRNAs) are a class of transcribed RNA molecules without protein-coding potential. They were regarded as transcriptional noise, or the byproduct of genetic information flow from DNA to protein for a long time. However, in recent years, a number of studies have shown that ncRNAs are pervasively transcribed, and most of them show evidence of evolutionary conservation, although less conserved than protein-coding genes. More importantly, many ncRNAs have been confirmed as playing...

  3. Critical association of ncRNA with introns

    OpenAIRE

    Rearick, David; Prakash, Ashwin; McSweeny, Andrew; Shepard, Samuel S.; Fedorova, Larisa; Fedorov, Alexei

    2010-01-01

    It has been widely acknowledged that non-coding RNAs are master-regulators of genomic functions. However, the significance of the presence of ncRNA within introns has not received proper attention. ncRNA within introns are commonly produced through the post-splicing process and are specific signals of gene transcription events, impacting many other genes and modulating their expression. This study, along with the following discussion, details the association of thousands of ncRNAs—snoRNA, miR...

  4. Non-leptonic kaon decays at large $N_c$

    CERN Document Server

    Donini, A; Pena, C; Romero-López, F

    2016-01-01

    We study the scaling with the number of colours, $N_c$, of the weak amplitudes mediating kaon mixing and decay. We evaluate the amplitudes of the two relevant current-current operators on the lattice for $N_c=3-7$. We conclude that the subleading $1/N_c$ corrections in $\\hat{B}_K$ are small, but those in the $K \\rightarrow \\pi\\pi$ amplitudes are large and fully anti-correlated in the $I=0, 2$ isospin channels. We briefly comment on the implications for the $\\Delta I=1/2$ rule.

  5. On pseudorandom generators in NC0

    DEFF Research Database (Denmark)

    Cryan, Mary; Miltersen, Peter Bro

    In this paper we consider the question of whether NC 0 circuits can generate pseudorandom distributions. While we leave the general question unanswered, we show – • Generators computed by NC 0 circuits where each output bit depends on at most 3 input bits (i.e, DNC 3 0 circuits) and with stretch...... is an NC 4 0 generator with a super-linear stretch that passes the linear dependency test as well as k-wise independence tests, for any constant k....

  6. Lattice study of large $N_c$ QCD

    CERN Document Server

    DeGrand, Thomas

    2016-01-01

    We present a lattice simulation study of large $N_c$ regularities of meson and baryon spectroscopy in $SU(N_c)$ gauge theory with two flavors of dynamical fundamental representation fermions. Systems investigated include $N_c=2$, 3, 4, and 5, over a range of fermion masses parametrized by a squared pseudoscalar to vector meson mass ratio between about 0.2 to 0.7. Good agreement with large $N_c$ scaling is observed in the static potential, in meson masses and decay constants, and in baryon spectroscopy.

  7. Areva - Revenue up by 6% in the first half of 2009

    International Nuclear Information System (INIS)

    In Nuclear, the levels of activity among the various divisions and their contribution to revenues can vary significantly from one half of the year to the next, which affects relative group performance over the period in question. Like-for-like growth for the first half of 2008 had thus reached 18.6% compared to the first half of 2007, due to several positive events, in particular exceptional sales in Asia in the Front-End division, favourable seasonality in Services, and a very high concentration of production in Recycling (Back-End). These events, which resulted in achieving more than 80% of nuclear 2008 operating income in the first six months and about 48% of sales revenues, illustrate the non-representative nature of the half-year performance in terms of usual profitability profile of nuclear activities. As of June 30, 2009, AREVA had a backlog of 48.9 billion euro, up 28.2% compared to June 30, 2008 and a slight increase compared to end of year 2008. In Nuclear, the backlog of orders came to 42.9 billion euro at June 30, 2009, 32.7% ahead of figures for June 30, 2008. In Transmission and Distribution, the order backlog on June 30, 2009 came to 6.0 billion euro, an increase of 3.0% over one year. In the first half of 2009, AREVA recorded revenues of 6,522 million euro, representing a 5.7% rise (+2.8% like-for-like) compared to the first half of 2008. Revenues outside France were up 12% to 4,758 million euro or 73% of total revenues. In the first half, revenue from Nuclear businesses came to 3,906 million euro, remaining stable compared to the same period last year (-2.9% LFL). The Transmission and Distribution division recorded revenues of 2,614 million euro, up 14.5% (+12.5% LFL), illustrating a good flow in the order backlog for Products (+11.8% LFL) and Systems (+15.1% LFL). Sales revenue for the second quarter of 2009 rose to 3,519 million euro, for growth of 3.5% (+1.9% LFL) compared with the second quarter of 2008. The Nuclear division recorded sales

  8. Evaluation of a Novel Hybrid Spectroscopic System Developed at Canberra-AREVA

    International Nuclear Information System (INIS)

    Radiometric systems used to screen and prevent illicit trafficking of radiological materials are designed with the goal of being very sensitive and selective. While high sensitivity of such non proliferation technologies enhances the probability of detection, selectivity is also needed to accurately corroborate or refute manifests of legal shipments and to better avoid false alarms caused by innocuous sources. Selectivity is best achieved using high resolution spectroscopy detectors, but such detectors are limited in size and by cost. The efficiency of a spectroscopic measurement system can be improved by adding detectors to the system and combining all the signals. Historically, this has been done using detectors of the same type, all with the same peak response function. Summing measured spectra with matched energy calibrations allows analysis of the final summation spectrum using the common peak response function. The benefit is improved sensitivity at the cost of the additional detectors and additional calculations to match energy calibrations prior to spectral summing. This traditional approach does not support combining different types of detectors with very different peak response functions. Standard summing would require subsequent analysis of the summed spectrum using a complex multi-modal peak response function dependent on the relative efficiency ratio as a function of energy. A novel approach developed at CANBERRA-AREVA has been proposed for combining spectroscopy detectors of any type, producing a hybrid spectrum that can be analyzed with a simple peak response function, accommodating existing analysis methods. This hybrid detection system (Patent pending) would combine detectors of different types into a single spectroscopy system. A hybrid detection system might combine a higher efficiency, lower resolution detector with a lower efficiency, higher resolution detector, achieving both higher efficiency and better energy resolution in a single system. A

  9. Large Nc from Seiberg-Witten curve and localization

    Science.gov (United States)

    Russo, Jorge G.

    2015-09-01

    When N = 2 gauge theories are compactified on S4, the large Nc limit then selects a unique vacuum of the theory determined by saddle-point equations, which remains determined even in the flat-theory limit. We show that exactly the same equations can be reproduced purely from Seiberg-Witten theory, describing a vacuum where magnetically charged particles become massless, and corresponding to a specific degenerating limit of the Seiberg-Witten spectral curve where 2Nc - 2 branch points join pairwise giving aDn = 0, n = 1 , … ,Nc - 1. We consider the specific case of N = 2 SU (Nc) SQCD coupled with 2Nf massive fundamental flavors. We show that the theory exhibits a quantum phase transition where the critical point describes a particular Argyres-Douglas point of the Riemann surface.

  10. 78 FR 49317 - North Carolina Disaster # NC-00054

    Science.gov (United States)

    2013-08-13

    ... From the Federal Register Online via the Government Publishing Office SMALL BUSINESS ADMINISTRATION North Carolina Disaster NC-00054 AGENCY: U.S. Small Business Administration. ACTION: Notice.... Small Business Administration, Processing And Disbursement Center, 14925 Kingsport Road, Fort Worth,...

  11. Observations of NC stop nets for bottlenose dolphin takes

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — To observe the NC stop net fishery to document the entanglement of bottlenose dolphins and movement of dolphins around the nets.

  12. How large is "large $N_c$" for Nuclear matter?

    CERN Document Server

    Torrieri, Giorgio

    2011-01-01

    We argue that a so far neglected dimensionless scale, the number of neighbors in a closely packed system, is relevant for the convergence of the large $N_c$ expansion at high chemical potential. It is only when the number of colors is large w.r.t. this new scale ($\\sim \\order{10}$) that a convergent large $N_c$ limit is reached. This provides an explanation as to why the large $N_c$ expansion, qualitatively successful in in vacuum QCD, fails to describe high baryo-chemical potential systems, such as nuclear matter. It also means that phenomenological claims about high density matter based on large $N_c$ extrapolations should be treated with caution.

  13. Research on Visual Virtual Design Platform for NC Machine Tools

    Institute of Scientific and Technical Information of China (English)

    HU Rufu; CHEN Xiaoping; SUN Qinghong

    2006-01-01

    The fundamental ideas on building the collaborative design platform of virtual visualization for NC machine tools are introduced. The platform is based on the globally shared product model conforming to the STEP Standard, and used PDM system to integrate and encapsulate CAD/CAE and other application software for the product development. The platform also integrated the expert system of NC machine tools design, analysis and estimation. This expert system utilized fuzzy estimation principle to evaluate the design and simulation analysis results and make decisions. The platform provides the collaborative intelligent environment for the design of virtual NC machine tools prototype aiming at integrated product design team. It also supports the customized development of NC machine tools.

  14. Reliability Evaluation of NC Machine Tools considering Working Conditions

    OpenAIRE

    Li, Hongzhou; Yang, Zhaojun; Xu, Binbin; Chen, Chuanhai; Kan, Yingnan; Liu, Guofei

    2016-01-01

    Reliability evaluation is the basis for reliability design of NC machine tools. Since traditional reliability evaluation methods do not consider the working conditions’ effects on reliability, there is a great error of a result of a traditional method compared with an actual value. A new reliability evaluation model of NC machine tools is proposed based on the Cox proportional hazards model, which describes the mathematical relation between the working condition covariates and the reliability...

  15. precision deburring using NC and robot equipment. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, L.K.

    1980-05-01

    Deburring precision miniature components is often time consuming and inconsistent. Although robots are available for deburring parts, they are not precise enough for precision miniature parts. Numerical control (NC) machining can provide edge break consistencies to meet requirements such as 76.2-..mu..m maximum edge break (chamfer). Although NC machining has a number of technical limitations which prohibits its use on many geometries, it can be an effective approach to features that are particularly difficult to deburr.

  16. Vanishing chiral couplings in the large-Nc resonance theory

    OpenAIRE

    Portolés, Jorge; Rosell, Ignasi; Ruiz Femenía, Pedro

    2007-01-01

    The construction of a resonance theory involving hadrons requires implementing the information from higher scales into the couplings of the effective Lagrangian. We consider the large-Nc chiral resonance theory incorporating scalars and pseudoscalars, and we find that, by imposing LO short-distance constraints on form factors of QCD currents constructed within this theory, the chiral low-energy constants satisfy resonance saturation at NLO in the 1/Nc expansion.

  17. Codes and Methods Supporting AREVA Fuel Solutions for the Future - Development Strategy

    International Nuclear Information System (INIS)

    Energy suppliers are keenly interested in effective margin management in their nuclear operations. They also need to accurately predict the capabilities and behavior of their reactors. For example, the inability to accurately predict thermal limit margins during reactor start-ups or the onset of reactor coast-down at the end of cycle can significantly impact their ability to deliver on their power generation commitments and, ultimately, impacts the power generation revenues. Fuel suppliers are expected to increase (1) availability factors (flawless fuel operation, short time reloading..), (2) fuel performance (reliability, flexibility, burn-up, thermal hydraulic performance..), (3) safety margins. The present evolution of fuel assembly and core designs towards greater heterogeneity, higher enrichments and burnup, Gd-loading, MOX loading, low leakage, etc., challenge the codes and methods (C and M) development. Safety Authority requirements are evolving (e.g. new RIA criteria, request for enlarged qualification databases..); fuel suppliers have to anticipate these evolutions and to come up with methods that properly meet the new needs, such that penalties on products or on limits in operation are avoided. Anticipating customer's needs for the future, the Fuel Sector of AREVA NP took up the challenge to significantly advance the state-of-the-art in nuclear methods and started in 2002 a series of large R and D programs preparing the next generation of C and M for fuel assembly design, core design, safety analysis and core monitoring. An overview is given over the strategic R and D axis of the Fuel Sector of AREVA NP. The domains of neutronics, core thermal-hydraulics and fuel rod thermal-mechanics are covered. The main goals of the C and M development strategy are: a) Providing the targeted market with the state-of-the-art C and M that meet customer needs and give appropriate answers to safety authority requirements. b) Anticipate future market needs in order to keep

  18. Task Order 22 – Engineering and Technical Support, Deep Borehole Field Test. AREVA Summary Review Report

    Energy Technology Data Exchange (ETDEWEB)

    Denton, Mark A. [AREVA Federal Services, Charlotte, NC (United States)

    2016-01-19

    Under Task Order 22 of the industry Advisory and Assistance Services (A&AS) Contract to the Department of Energy (DOE) DE-NE0000291, AREVA has been tasked with providing assistance with engineering, analysis, cost estimating, and design support of a system for disposal of radioactive wastes in deep boreholes (without the use of radioactive waste). As part of this task order, AREVA was requested, through a letter of technical direction, to evaluate Sandia National Laboratory’s (SNL’s) waste package borehole emplacement system concept recommendation using input from DOE and SNL. This summary review report (SRR) documents this evaluation, with its focus on the primary input document titled: “Deep Borehole Field Test Specifications/M2FT-15SN0817091” Rev. 1 [1], hereafter referred to as the “M2 report.” The M2 report focuses on the conceptual design development for the Deep Borehole Field Test (DBFT), mainly the test waste packages (WPs) and the system for demonstrating emplacement and retrieval of those packages in the Field Test Borehole (FTB). This SRR follows the same outline as the M2 report, which allows for easy correlation between AREVA’s review comments, discussion, potential proposed alternatives, and path forward with information established in the M2 report. AREVA’s assessment focused on three primary elements of the M2 report: the conceptual design of the WPs proposed for deep borehole disposal (DBD), the mode of emplacement of the WP into DBD, and the conceptual design of the DBFT. AREVA concurs with the M2 report’s selection of the wireline emplacement mode specifically over the drill-string emplacement mode and generically over alternative emplacement modes. Table 5-1 of this SRR compares the pros and cons of each emplacement mode considered viable for DBD. The primary positive characteristics of the wireline emplacement mode include: (1) considered a mature technology; (2) operations are relatively simple; (3) probability of a

  19. AREVA NP's advanced Thermal Hydraulic Methods for Reactor Core and Fuel Assembly Design

    International Nuclear Information System (INIS)

    The main objective of the Thermal Hydraulic (TH) analysis of reactor core and fuel assembly design is the determination of pressure loss and critical heat flux (CHF). Especially the description of the latter effect requires the modeling of a large variety of physical phenomena starting with single phase quantities like turbulence or fluid-wall friction, two phase quantities like void distributions, heat transfer between fuel rod and fluid and ultimately the CHF mechanism itself. Additional complexity is added by the fact that the relevant geometric scales which have to be resolved, cover a wide range from the length of the fuel assembly (∼ 4000 mm), over the typical dimensions of sub-channel cross sections and the vanes on the spacer grids (∼ 10 mm) down to the microscopic scales set by bubble sizes and boundary layers (mm to sub mm). Due to the above described situation the necessary TH quantities are often determined by measurements. The main advantage of this technique is that measurements are widely accepted and trusted if the geometry and flow conditions are sufficiently close to real reactor conditions. The main disadvantage of experiments is that they are expensive both with respect to time and money; especially in high pressure tests they give only limited access to the test object. Consequently there is a strong interest to develop computer codes with the goal of minimizing the need of experiments, and hence, speeding up and reducing costs of fuel assembly and core design. Today most of the design work is based on sub-channel codes, originally developed in the 70's; they provide an effective description of the TH in fuel assemblies by regarding the fuel assembly as a system of communicating channels (the volume enclosed by four fuel rods = one sub-channel). Further development of these codes is one main focus of AREVA NP's Thermal Hydraulic method and code development strategy. To focus the know-how and resources existing in the different regions of

  20. Environmental and Quality Management System at AREVA/COGEMA Resources, Inc

    International Nuclear Information System (INIS)

    COGEMA Resources Inc. (part of the Areva Group) is a Canadian company with its head office in Saskatoon, Saskatchewan. It owns and operates mining and milling facilities in Northern Saskatchewan, where it produces uranium concentrate. The company is also active in uranium exploration, decommissioning and joint ventures with other organizations at various operating sites within Canada. The company has adopted an integrated approach to environmental and quality management of all its operational activities, which comprise a complete cycle from uranium exploration to development to mining and milling through to decommissioning. This commences with exploration projects mainly in the Athabasca Basin of Northern Saskatchewan, continues with the McClean Lake site - a uranium mining and milling facility that started production in 1999 and closes with the decommissioning of the Cluff Lake site - a uranium mine which ceased production in 2002. The system is designed to provide an integrated approach to ensure that: All activities are conducted in a safe and efficient manner, meeting all applicable regulatory and internal requirements; the requirements of the ISO 14001 standard are met; The principles of sustainable development are implemented throughout the organization. To this end, the McClean Lake site and exploration activities (both were the first for the uranium industry within Canada) are ISO 14001 certified, while the Cluff Lake site should follow very shortly. The development of the integrated management system and operational experience are discussed with examples drawn from the various operating activities. Challenges and further development opportunities will be mentioned. (author)

  1. CEA and AREVA HTR fuel particles manufacturing and characterization R and D Program

    International Nuclear Information System (INIS)

    Worldwide, renewal of interest for High Temperature Reactors (HTR) moderated by graphite, using helium gas as coolant is due to the possibility offered by HTR technology to build small competitive modular units (100-300 MWe) and to produce high temperature gas required for hydrogen production or heat production. In this context, Commissariat a l'Energie Atomique (CEA) supported by AREVA, conducts R and D projects on HTR, which one is the mastering of the UO2 TRISO fuel fabrication technology including innovating prospects. The first step of the work is to recover fabrication know-how and to improve fabrication processes (for preparing the erection of a fuel pilot manufacture line of HTR particles). The second step will be the manufacturing of HTR fuel elements in purpose of irradiation tests. This publication deals with the know-how recovery and improved processes of UO2 TRISO manufacture, i.e. kernel and coatings manufacturing, the development of innovative characterization methods, a modelling approach of CVD processes and the status of the future laboratory manufacture line. Alternative fuel designs are also investigated, for instance the way of manufacturing UCO and UCx kernels with higher refractory coating material such as ZrC. (authors)

  2. Phase 1A Final Report for the AREVA Team Enhanced Accident Tolerant Fuels Concepts

    Energy Technology Data Exchange (ETDEWEB)

    Morrell, Mike E. [AREVA Federal Services LLC, Charlotte, NC (United States)

    2015-03-19

    In response to the Department of Energy (DOE) funded initiative to develop and deploy lead fuel assemblies (LFAs) of Enhanced Accident Tolerant Fuel (EATF) into a US reactor within 10 years, AREVA put together a team to develop promising technologies for improved fuel performance during off normal operations. This team consisted of the University of Florida (UF) and the University of Wisconsin (UW), Savannah River National Laboratory (SRNL), Duke Energy and Tennessee Valley Authority (TVA). This team brought broad experience and expertise to bear on EATF development. AREVA has been designing; manufacturing and testing nuclear fuel for over 50 years and is one of the 3 large international companies supplying fuel to the nuclear industry. The university and National Laboratory team members brought expertise in nuclear fuel concepts and materials development. Duke and TVA brought practical utility operating experience. This report documents the results from the initial “discovery phase” where the team explored options for EATF concepts that provide enhanced accident tolerance for both Design Basis (DB) and Beyond Design Basis Events (BDB). The main driver for the concepts under development were that they could be implemented in a 10 year time frame and be economically viable and acceptable to the nuclear fuel marketplace. The economics of fuel design make this DOE funded project very important to the nuclear industry. Even incremental changes to an existing fuel design can cost in the range of $100M to implement through to LFAs. If this money is invested evenly over 10 years then it can take the fuel vendor several decades after the start of the project to recover their initial investment and reach a breakeven point on the initial investment. Step or radical changes to a fuel assembly design can cost upwards of $500M and will take even longer for the fuel vendor to recover their investment. With the projected lifetimes of the current generation of nuclear power

  3. Nc-Si Thin Film Deposited at Low Temperature and Nc-Si Heterojunction Solar Cell

    Institute of Scientific and Technical Information of China (English)

    赵占霞; 崔容强; 孟凡英; 于化丛; 周之斌

    2004-01-01

    This paper reported some results about intrinsic nanocrystalline silicon thin films deposited by high frequency (HF) sputtering on p-type c-Si substrates at low temperature. Samples were examined by atomic force microscopy (AFM), X-ray diffraction (XRD), infrared absorption, and ellipsometry. XRD measurements show that this film has a new microstructure, which is different from the films deposited by other methods. The ellipsometry result gives that the optical band gap of the film is about 2.63 eV. In addition, the n-type nc-Si ∶ H/p-type c-Si heterojunction solar cell, which has open circuit voltage (Uoc) of 558 mV and short circuit current intensity (Isc) of 29 mA/cm2, was obtained based on the nanocrystalline silicon thin film. Irradiated under AM1.5, 100 mW/cm2 light intensity, the Uoc, Isc, and FF can keep stable for 10 h.

  4. Zirconia (NC) zircon as a potential standard

    Science.gov (United States)

    Covey, A. K.; Braun, S. A.; Gualda, G. A.; Bream, B. R.; Fisher, C.; Wooden, J. L.; Schmitz, M. D.

    2012-12-01

    As microanalysis continues to advance and become more widespread there is a greater need for abundant and suitable age standards. Megacrystic zircons from the inactive Freeman Mine near Zirconia, NC were collected from weathered mine dump piles. Zirconia zircon crystals are large (> 1 mm) relative to typical zircons (up to 100s μm) and easily obtained; attributes that make them attractive as a potential standard. We present here preliminary data and assess the suitability of Zirconia zircons as a U-Pb geochronology, Hf-isotope and trace-element standard. Grains are variably fluorescent (Callahan et al, Southeastern Geol., 2007), and we used shortwave fluorescence to separate grains with high, medium, low/no fluorescence from one another. Images were taken of the grains before mounting and post-polishing to understand the fluorescence characterization of the surface to the core. After preparing the grains, we found that the fluorescence was not homogenous and did not provide a good means of separating out grains. In order to investigate the differences in fluorescence, we collected cathodoluminescence (CL) and backscatter electron (BSE) images and energy dispersive spectroscopy (EDS) maps using a Tescan Vega 3 LMU equipped with an Oxford X-max 50 mm2 solid-state EDS detector at Vanderbilt University. This allowed division of the grains into two types: (a) grains with finely oscillatory zoned rims, which are variably crosscut by dull-CL irregular zones, sometimes showing hourglass zoning; and (b) grains with cores showing more irregular, patchy zoning with and without thin oscillatory rims. EDS maps show no major element zoning in the zircon grains, but reveal a variety of inclusions, particularly of quartz and thorite. Preliminary U-Pb ages were obtained using a Perkin Elmer Elan DRCII ICP-MS coupled with a New Wave/Mechantek 213 nm Nd:YAG laser ablation system at Vanderbilt University. A total of ~150 individual ages on oscillatory-zoned (Type a) crystals yield a

  5. Call for tender - Areva-Alstom: watershed in wind energy - Technological duel on the open sea; Appel d'offres - Areva-Alstom: partage des eaux dans l'eolien - Duel technologique au grand large

    Energy Technology Data Exchange (ETDEWEB)

    Dupin, L.

    2012-02-16

    The author comments the answers to a call for tender made by the French government and concerning five offshore wind farm sites (Le Treport, Fecamp, Courseulles sur Mer, Saint-Brieuc and Saint-Nazaire). As they are present within the three consortiums, Areva and Alstom should provide the wind turbines. This would result in the construction by Alstom of two blade and mast factories and two turbine and pad factories. For both companies, this market of 500 to 600 turbines is an opportunity. Many jobs are at stake. They push themselves forward for their experience or their innovation capacity. But their wind turbines will be based on foreign (Spanish or German) technology

  6. AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle; AREVA Technical Days (ATD) session 2: les activites du pole Aval du cycle du combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

  7. DMT - Areva's steam generator maintenance cleaning process concept and experiences

    International Nuclear Information System (INIS)

    Steam generators (SGs) are one of the key components for plant performance and plant availability of nuclear power plants. Depending on numerous factors (e.g. material concept, water chemistry, operational procedures) a certain amount of metal oxides and impurities are transported into the SG's via the feed water. Accumulation of these deposits is intrinsic during the operation of steam generators in PWRs. In order to maintain the integrity or to maintain or regain the performance of the steam generators, chemical cleaning is an essential part of the asset management. Recently the industry moves from curative (removing all SG deposits with one chemical application) cleanings to preventive (i.e. maintenance - removal of a portion of the SG deposits with one chemical application) cleanings. The intention of such preventive cleanings is to maintain the deposit inventory on a low level or even better to reduce the deposit inventory by repeated applications. Preventive cleanings remove only a part of the sludge inventory during each application. Nevertheless such cleanings still need to be efficient and most of all it is mandatory that the corrosion is very low - not only to minimize steam generator base metal corrosion but also to increase the efficiency of the cleaning. The AREVA developed proprietary Deposit Minimization Treatment (DMT) technology uses a different chemistry than EDTA. The technical advantage provided by DMT's different chemistry, besides the innocuousness towards Ni-alloys and stainless steels, is its self-inhibiting property. The in situ formation of a protective layer on the carbon steel surfaces limits the average carbon steel corrosion during a typical chemical cleaning campaign to values far below 10 μm. Due to this very low carbon steel corrosion, less than 5 % of the dissolved iron originates from SG base metal corrosion, while this portion can be more than 30 % in a comparable uninhibited EDTA solution. The DMT process protective

  8. AREVA Fatigue Concept (AFC). Live demonstration of a modern fatigue monitoring system FAMOS i

    International Nuclear Information System (INIS)

    The prevention of fatigue damage is to be considered as a crucial issue in the view of changing boundary conditions: code modifications, long term operation, new plants with operating periods of 60 years. The AREVA Fatigue Concept (AFC) provides for a multiple step and multidisciplinary process (process engineering, fatigue monitoring, fatigue analyses etc.) against fatigue before and during the entire operation of nuclear power plants (NPPs). The ensuing fatigue analyses are based on the real operational loads measured continuously on site in the plant by means of an installed fatigue monitoring system. This way, realistic load data are available and qualified fatigue usage factors can be determined. Locations of potential fatigue failure are reliably identified and expensive cost for inspection can be essentially reduced. The direct processing of the measured temperatures can immediately be used for a Fast Fatigue Evaluation (FFE). FFE calculates the real stress history in form of a six stress tensor approach. The shape functions of fatigue relevant NPP parts are included. Based on the stress history the fatigue evaluation is the last step. Effects based on environmental fatigue influence can also be analyzed inside AFC. The fatigue calculation workflow will be processed on the FAMOS i (i stands for ''integrated'') demonstration wall (cf. Figure 1). Starting with the measurement of transient temperatures, the thermal loads will be shown with the FAMOS i-viewer software. Within the next step the inner wall temperature is calculated, which is based on the FAMOS i measurements. In a third step the computation of the stress history is done, followed by the combination of the relevant stress ranges for the purpose of a particular fatigue usage calculation. In addition, a short overview will be given about the requirements and solutions of an effective modern measurement system, followed by showing the benefit of local monitoring for NPP owners. (orig.)

  9. Narrow gap mechanised arc welding in nuclear components manufactured by AREVA NP

    International Nuclear Information System (INIS)

    Nuclear components require welds of irreproachable and reproducible quality. Moreover, for a given welding process, productivity requirements lead to reduce the volume of deposited metal and thus to use narrow gap design. In the shop, narrow gap Submerged Arc Welding process (SAW) is currently used on rotating parts in flat position for thicknesses up to 300 mm. Welding is performed with one or two wires in two passes per layer. In Gas Tungsten Arc Welding process (GTAW), multiple applications can be found because this process presents the advantage of allowing welding in all positions. Welding is performed in one or two passes per layer. The process is used in factory and on the nuclear sites for assembling new components but also for replacing components and for repairs. Presently, an increase of productivity of the process is sought through the use of hot wire and/or two wires. Concerning Gas Metal Arc Welding process (GMAW), its use is growing for nuclear components, including narrow gap applications. This process, limited in its applications in the past on account of the defects it generated, draws benefit from the progress of the welding generators. Then it is possible to use this efficient process for high security components such as those of nuclear systems. It is to be noted that the process is applicable in the various welding positions as it is the case for GTAW, while being more efficient than the latter. This paper presents the state of the art in the use of narrow gap mechanised arc welding processes by AREVA NP units. (author)

  10. Areva's Actiflo trademark -Rad water treatment system for the Fukushima nuclear power plant

    International Nuclear Information System (INIS)

    In the wake of the March 11th 2011 earthquake and tsunami and the subsequent flooding of several of the Fukushima Daiichi reactor units, Japan and the Japanese utility Tepco faced a crisis situation with incredible challenges. Sea water and later desalted sea water used for open circuit post-accident reactor cooling accumulated in the basements of four reactor buildings as well as in the basements of the turbine buildings on the site. The water had been heavily contaminated due to the fact that it had been in contact with molten fuel assemblies in the reactor cores. The water from flooding and subsequent cooling needed to be collected, along with rainwater. Despite the use of additional water storage systems brought to the site, a shortage of water storage capacity was expected in a 3-month timeframe, especially in view of the coming rain season in Japan. The overall water inventory was estimated at around 110,000 tons with a contamination up to the order of 1 Ci/l (3.7 x 1010 Bq/l). To avoid an over-flow of highly contaminated water into the sea Tepco envisaged establishing a water treatment system. This article focuses on the Actiflo trademark -Rad water treatment project implemented by Areva as part of the Tepco general water treatment scheme. It presents a detailed look at the functional principle of the Actiflo trademark -Rad process, related on-the-fly research and development, an explanation of system implementation challenges and a brief summary of operation results. (orig.)

  11. NC Geometry and Discrete Torsion Fractional Branes I

    CERN Document Server

    Saidi, E H

    2002-01-01

    Considering the complex n-dimension Calabi-Yau homogeneous hyper-surfaces ${\\cal H}_{n}$ and using algebraic geometry methods, we develop the crossed product algebra method, introduced by Berenstein et Leigh in hep-th/0105229, and build the non commutative (NC) geometries for orbifolds ${\\cal O}={\\cal H}_{n}/{\\bf Z}_{n+2}^{n}$ with a discrete torsion matrix $t_{ab}=exp[{\\frac{i2\\pi}{n+2}}{(\\eta_{ab}-\\eta_{ba})}]$, $\\eta_{ab} \\in SL(n,{\\bf Z})$. We show that the NC manifolds ${\\cal O}^{(nc)}$ are given by the algebra of functions on the real $(2n+4)$ Fuzzy torus ${\\cal T}^{2(n+2)}_{\\beta_{ij}}$ with deformation parameters $\\beta_{ij}=exp{\\frac{i2\\pi}{n+2}}{[(\\eta^{-1}_{ab}-\\eta^{-1}_{ba})} q_{i}^{a} q_{j}^{b}]$, $q_{i}^{a}$'s being Calabi-Yau charges of ${\\bf Z}_{n+2}^{n}$. We develop graph rules to represent ${\\cal O}^{(nc)}$ by quiver diagrams which become completely reducible at singularities. Generic points in these NC geometries are be represented by polygons with $(n+2)$ vertices linked by $(n+2)$ edges ...

  12. AREVA announces US$ 7.75 Per share friendly cash offer for UraMin; Offre publique d'achat amicale d'AREVA sur UraMin sur la base d'un prix de 7,75US$ par action

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    AREVA and UraMin Inc. ('UraMin') entered on June 15, 2007 into an agreement in respect of AREVA's friendly cash offer for 100% of the share capital of UraMin. UraMin is listed in London (AIM) and Toronto (TSX). AREVA (Euronext Paris) already owns 5.5% of UraMin's share capital. This cash offer of AREVA will be made through its indirect wholly-owned subsidiary CFMM Development ('AREVA') based on a price of US$ 7.75 per UraMin share. The total offer consideration amounts to more than USD 2.5 billion for 100% of the fully diluted share capital of UraMin. This represents a premium of 21% over UraMin 20-day weighted average trading price ending on June 8, 2007. The UraMin Board of Directors, after consulting with its financial advisors, has determined that the offer is fair and in the best interest of the UraMin shareholders and it has resolved to recommend acceptance of the Offer. BMO Capital Markets has provided an opinion that the offer is fair, from a financial point of view, to the UraMin shareholders. In connection with the offer, all directors and certain other shareholders representing approximately 25% of the outstanding UraMin shares (calculated on a fully diluted basis) have entered into lock-up agreements with AREVA pursuant to which they have agreed to tender all their UraMin shares to AREVA's offer. The support agreement entered into between AREVA and UraMin provides for, among other things, in case a superior proposal is accepted by UraMin, a right to match in favour of AREVA. The support agreement also includes a break up fee in favour of AREVA of US$ 75 million under certain circumstances. Concurrently with the closing of the proposed offer, UraMin will declare a dividend payable in shares of the capital of Niger Uranium Limited held by UraMin (where permitted by law) or a cash equivalent of the value of such shares.

  13. AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

  14. AREVA's filtered containment venting system (FCVS). Basic design, performance and verification test of FCVS for BWRs

    International Nuclear Information System (INIS)

    After the great earthquake and a tsunami as consequence March 11, 2011, a severe accident happened at nuclear power plant Fukushima Daiichi. The severe accident lead to core damage and containment failure and finally to large release of radioactive substances to the environment. As part of the severe accident management and to reinforce the mitigation concepts against a containment failure, the Filtered Containment Venting System (FCVS) will be introduced at Japanese nuclear power plants, to have a possibility to depressurize safely and reliable the containment via a filtered process. This paper describes AREVA FCVS technology and its application for Japanese BWRs and also the background of the qualification and the licensing approach. (author)

  15. AREVA's Filtered Containment Venting System (FCVS). Basic design, performance and verification test of FCVS for BWRs

    International Nuclear Information System (INIS)

    After the great earthquake and a tsunami as consequence March 11, 2011, a severe accident happened at nuclear power plant Fukushima Daiichi. The severe accident lead to core damage and containment failure and finally to large release of radioactive substances to the environment. As part of the severe accident management and to reinforce the mitigation concepts against a containment failure, the Filtered Containment Venting System (FCVS) will be introduced at Japanese nuclear power plants, to have a possibility to depressurize safely and reliable the containment via a filtered process. This paper describes AREVA FCVS technology and its application for Japanese BWRs and also the background of the qualification and the licensing approach. (author)

  16. Non-global logarithms at finite Nc beyond leading order

    CERN Document Server

    Khelifa-Kerfa, Kamel

    2015-01-01

    We analytically compute non-global logarithms at finite Nc fully up to 4 loops and partially at 5 loops, for the hemisphere mass distribution in e+e- to di-jets to leading logarithmic accuracy. Our method of calculation relies solely on integrating the eikonal squared-amplitudes for the emission of soft energy-ordered real-virtual gluons over the appropriate phase space. We show that the series of non-global logarithms in the said distribution exhibits a pattern of exponentiation thus confirming - by means of brute force - previous findings. In the large-Nc limit, our results coincide with those recently reported in literature. A comparison of our proposed exponential form with all-orders numerical solutions is performed and the phenomenological impact of the finite-Nc corrections is discussed.

  17. Eikonal gluon radiation at finite-Nc beyond 2 loops

    CERN Document Server

    Khelifa-Kerfa, Kamel

    2015-01-01

    We present first calculations of QCD matrix-elements in perturbation theory at finite Nc beyond 2 loops in the eikonal approximation for e+ e- annihilation processes. For the emission of n soft energy-ordered gluons we solve both the colour and kinematic structures at a given order in perturbation theory by means of a Mathematica program that relies solely on a recently developed Mathematica code, ColorMath, that evaluates the trace of products of colour matrices. At large Nc, our squared amplitudes reduce to those already known in the literature.

  18. Shear viscosity from a large-Nc NJL model

    International Nuclear Information System (INIS)

    We investigate the shear viscosity to entropy ratio within the vicinity of the chiral phase transition/crossover using the NJL model in a large-Nc expansion. As heavy-ion collisions at RHIC and LHC in combination with hydrodynamic simulations suggest, this ratio is close to the AdS/CFT benchmark. This indicates a strongly correlated state of matter produced in such collisions. We study in detail the non-perturbative structure of the NJL model and the question if resummation techniques are required. In the large-Nc expansion next-to-leading-order contributions to the shear viscosity are derived.

  19. Resummation of non-global logarithms at finite Nc

    International Nuclear Information System (INIS)

    In the context of inter-jet energy flow, we present the first quantitative result of the resummation of non-global logarithms at finite Nc. This is achieved by refining Weigert's approach in which the problem is reduced to the simulation of associated Langevin dynamics in the space of Wilson lines. We find that, in e+e− annihilation, the exact result is rather close to the result previously obtained in the large-Nc mean field approximation. However, we observe enormous event-by-event fluctuations in the Langevin process which may have significant consequences in hadron collisions

  20. O(Nc) and USp(Nc) QCD from String Theory

    Science.gov (United States)

    Imoto, T.; Sakai, T.; Sugimoto, S.

    2009-12-01

    We propose a holographic dual of large N_c quantum chromodynamics (QCD) with the gauge groups O(N_c) and USp(N_c) and N_f flavors of massless quarks. This is constructed by adding O6-planes to an intersecting D4-D8 system in type IIA superstring theory. The holographic dual description is formulated in Witten's D4-brane background with D8-branes and O6-planes embedded in it as probes. The D4-brane background gives rise to a smooth interpolation of D8-overline{D8} pairs and an O6-overline{O6} pair. We show that the resultant brane configuration explains geometrically the flavor symmetry breaking patterns in O(N_c) and USp(N_c) QCD, which are caused by quark bilinear condensates. We next discuss that baryons can be realized as D4-overline{D4} pairs wrapped on S^4, which intersect with the O6-plane. By analyzing the tachyons on it, we reproduce the stability conditions of the baryons that are expected from the gauge theory viewpoint . The stable baryon configurations are classified systematically using K-theory. We also give a similar analysis of the flux tubes and again reproduce the results that are consistent with QCD.

  1. AREVA coating and adhesive technology. A method to mitigate and/or prevent leaks in pools with stainless steel liners

    Energy Technology Data Exchange (ETDEWEB)

    Kraemer, Georg [AREVA NP GmbH, Erlangen (Germany)

    2011-07-01

    Worldwide experience shows that stainless steel liners of concrete pools tend to leak primarily due to corrosion phenomena, although weld failure leakage can also occur. Extensive investigations by AREVA showed that mechanical defects are usually caused by mechanical impact and that the affected location is obvious. However, in the case of corrosion, which is the root cause in most of the cases, the defect in the liner begins from the concrete side and is only detected when a complete penetration occurs. Therefore, in the case of corrosion defects, it is not only vital to identify the location and repair the actual leak, but it is advantageous to apply a technology that works as a preventive measure. Repair methods based on conventional welding techniques are not promising as a preventive measure, mostly due to cost and time issues. With the AREVA coating and adhesive technology, a repair method is provided which is able to stop existing leaks. It also works as a prophylactic measure against future penetration from the concrete side of the pool. This technique covers the failure mechanisms from weld failures over corrosion to mechanical stresses. A further advantage of the coating and adhesive technology is the possibility to use remote-controlled underwater repair methods. These are particularly beneficial in the repair of leaks in spent fuel pools. Extensive laboratory testing and longstanding successful experience in nuclear power plants have proven the suitability of the coating and adhesive technology as an active and proactive method to minimize leakages in pools. (orig.)

  2. Areva return on experience from D and D programme management - what we have learned so far? - 59324

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: In November 1997, UP1, France first large scale reprocessing plant, ceased operations after 40 years of activities. A comprehensive D and D program was immediately initiated, scheduled to last for a period of approximately 30 years. In 2002, AREVA launched the decommissioning and dismantling of SICN sites, two GCR fuel fabrication located near Grenoble and Annecy. Shortly after, in 2003, the second reprocessing plant, UP2 400, commissioned in the sixties in La Hague (Normandy) followed. Less than a decade later, UP1 decommissioning program is well advanced, with the de-cladding facilities nearing completion, and the chemical plant showing a work progress of about 50%. The decommissioning of SICN sites is reaching its final stage, with concrete scrabbling operations launched in order to release the site for non nuclear industrial activities. A part of UP2 400 de-cladding facilities have been dismantled, and a vast D and D program is now on track for the bulk of the plant. AREVA is managing those operations, either as owner in La Hague and SICN, or as prime contractor for the French Atomic Energy commission in Marcoule. More than 10 years of continuous, large scale D and D operations have provided a unique feedback for such operations

  3. Magnetic properties of high-efficiency core materials NC-M3 and NC-M4

    Science.gov (United States)

    Kubota, T.; Nagai, T.

    1992-03-01

    High-efficiency core materials—New Core NC-M3 and NC-M4— with very low core loss and high permeability have been developed to improve the magnetic properties of conventional magnetic lamination steels. The magnetically favorable crystalline textures are enhanced through the addition of Mn and Sn to low-silicon steel. By adding Mn, particularly more than ~ 1.0 wt.%, to low- silicon steel, a decrease in (111) plane crystals and an increase in (110) and (100) plane crystals are achieved. Moreover, by adding Sn to low- silicon steel containing Mn, the decrease in (111) plane crystals and the increase in (110) plane crystals are more significant. The most suitable amount for the addition of Sn is ~ 0.1 wt.%, because excessive Sn content prevents normal grain growth in steels and makes magnetic properties, particularly core loss, inferior. Typical magnetic properties of NC- M3 (0.47- mm thickness) are 1.70 W/lb in W15/60 and 3000 Gauss/Oe in µ15/60, and those of NC- M4 (0.47- mm thickness) are 1.57 W/lb in W15/60 and 3000 Gauss/Oe in µ15/60. The lower core losses are attained mainly by reducing hysteresis loss. The superior magnetic properties of NC- M4 compared to NC- M3 are due to the fact that the steel is cleaner and has undergone sufficient hot band annealing during manufacturing.

  4. Highly conducting and preferred oriented boron doped nc-Si films for window layers in nc-Si solar cells

    Science.gov (United States)

    Mondal, Praloy; Das, Debajyoti

    2016-05-01

    Growth and optimization of the boron dopednanocrystalline silicon (nc-Si) films have been studied by varyingthe gaspressure applied to the hydrogendiluted silane plasma in RF (13.56 MHz) plasma-enhanced chemical vapor deposition (PECVD) system, using diborane (B2H6) as the dopant gas. High magnitudeof electrical conductivity (~102 S cm-1) andorientedcrystallographic lattice planes have been obtained with high crystalline volume fraction (~86 %) at an optimum pressure of 2.5 Torr. XRD and Raman studies reveal good crystallinity with preferred orientation, suitable for applications in stacked layer devices, particularly in nc-Si solar cells.

  5. AREVA General Inspectorate Annual Report 2013 - Status of safety in nuclear facilities

    International Nuclear Information System (INIS)

    This annual report by AREVA's General Inspectorate deals with the status of nuclear safety and radiation protection in the group's facilities and operations over the course of 2013. Based on the findings made during implementation of the annual inspection program, this annual report also includes the results of the analysis of significant events and the observations and assessments of specialists in the Safety Health Security Sustainable Development Department (SHSSDD), supplemented by regular interaction with the safety regulators, different government agencies, stakeholders and other nuclear operators. Additionally, this report presents the action plans put into motion and the directions taken for continuous improvement in risk prevention for operations conducted in France and internationally. In 2013, the level of safety in the group's nuclear facilities and operations remained satisfactory, although improvements are necessary in some domains. This report is based on established indicators, analyses of reported events, responses to commitments made to the regulators, and the results of different improvement actions reported on in the inspected and supported entities. In 2013, no level 2 event on the International Nuclear and Radiological Event Scale (INES) was reported, the bottom-up reporting of weak signals was confirmed, dose levels were low and there were no radiological impacts on the environment. The General Inspectorate conducted 45 inspections in 30 of the group's entities in 2013. Of these, 10 concerned sites outside France and 7 were conducted following events or particular situations. These inspections gave rise to 176 recommendations, which the inspected entities have translated into action plans. Verification of these different action plans according to planned procedures and announced schedules gave rise to 16 follow-up inspections. The major lessons learned from these inspections relate to project management, facility compliance and operational

  6. 75 FR 34365 - Safety Zone, Alligator River, NC

    Science.gov (United States)

    2010-06-17

    ... SECURITY Coast Guard 33 CFR Part 165 RIN 1625-AA00 Safety Zone, Alligator River, NC AGENCY: Coast Guard... the waters of the Alligator River at East Lake, North Carolina. The safety zone is intended to... on the Alligator River makes safety zone regulations necessary to provide for the safety...

  7. 75 FR 65389 - North Carolina Disaster #NC-00030

    Science.gov (United States)

    2010-10-22

    ... From the Federal Register Online via the Government Publishing Office SMALL BUSINESS ADMINISTRATION North Carolina Disaster NC-00030 AGENCY: U.S. Small Business Administration. ACTION: Notice... Carolina (FEMA-1942-DR), dated 10/14/ 2010. Incident: Severe storms, flooding, and straight-line...

  8. 78 FR 12806 - North Carolina Disaster #NC-00048

    Science.gov (United States)

    2013-02-25

    ... From the Federal Register Online via the Government Publishing Office SMALL BUSINESS ADMINISTRATION North Carolina Disaster NC-00048 AGENCY: U.S. Small Business Administration. ACTION: Notice... INFORMATION CONTACT: A. Escobar, Office of Disaster Assistance, U.S. Small Business Administration, 409...

  9. 77 FR 56250 - North Carolina Disaster #NC-00044

    Science.gov (United States)

    2012-09-12

    ... From the Federal Register Online via the Government Publishing Office SMALL BUSINESS ADMINISTRATION North Carolina Disaster NC-00044 AGENCY: U.S. Small Business Administration. ACTION: Notice... INFORMATION CONTACT: A. Escobar, Office of Disaster Assistance, U.S. Small Business Administration, 409...

  10. 77 FR 33997 - Television Broadcasting Services; Greenville, NC

    Science.gov (United States)

    2012-06-08

    ... COMMISSION 47 CFR Part 73 Television Broadcasting Services; Greenville, NC AGENCY: Federal Communications... Commission instituted a freeze on the acceptance of rulemaking petitions by full power television stations... petitions for rulemaking filed by full power television stations seeking to relocate from channel...

  11. ncRNA orthologies in the vertebrate lineage.

    Science.gov (United States)

    Pignatelli, Miguel; Vilella, Albert J; Muffato, Matthieu; Gordon, Leo; White, Simon; Flicek, Paul; Herrero, Javier

    2016-01-01

    Annotation of orthologous and paralogous genes is necessary for many aspects of evolutionary analysis. Methods to infer these homology relationships have traditionally focused on protein-coding genes and evolutionary models used by these methods normally assume the positions in the protein evolve independently. However, as our appreciation for the roles of non-coding RNA genes has increased, consistently annotated sets of orthologous and paralogous ncRNA genes are increasingly needed. At the same time, methods such as PHASE or RAxML have implemented substitution models that consider pairs of sites to enable proper modelling of the loops and other features of RNA secondary structure. Here, we present a comprehensive analysis pipeline for the automatic detection of orthologues and paralogues for ncRNA genes. We focus on gene families represented in Rfam and for which a specific covariance model is provided. For each family ncRNA genes found in all Ensembl species are aligned using Infernal, and several trees are built using different substitution models. In parallel, a genomic alignment that includes the ncRNA genes and their flanking sequence regions is built with PRANK. This alignment is used to create two additional phylogenetic trees using the neighbour-joining (NJ) and maximum-likelihood (ML) methods. The trees arising from both the ncRNA and genomic alignments are merged using TreeBeST, which reconciles them with the species tree in order to identify speciation and duplication events. The final tree is used to infer the orthologues and paralogues following Fitch's definition. We also determine gene gain and loss events for each family using CAFE. All data are accessible through the Ensembl Comparative Genomics ('Compara') API, on our FTP site and are fully integrated in the Ensembl genome browser, where they can be accessed in a user-friendly manner.Database URL: http://www.ensembl.org. PMID:26980512

  12. Feeding the nuclear fuel cycle with a long term view; AREVA's front-end business units, uranium mining, UF6 conversion and isotopic enrichment

    International Nuclear Information System (INIS)

    As a leading provider of technological solutions for nuclear power generation and electricity transmission, the AREVA group has the unique capability of offering a fully integrated fuel supply, when requested by its customers. At the core of the AREVA group, COGEMA Front End Division is an essential part of the overall fuel supply chain. Composed of three Business Units and gathering several subsidiaries and joint 'ventures, this division enjoys several leading positions as shown by its market shares and historical production records. Current Uranium market evolutions put the natural uranium supply under focus. The uranium conversion segment also recently revealed some concerning evolutions. And no doubt, the market pressure will soon be directed also at the enrichment segment. Looking towards the long term, AREVA strongly believes that a nuclear power renewal is needed, especially to help limiting green house effect gas release. Therefore, to address future supplies needed to fuel the existing fleet of nuclear power plants, but also new ones, the AREVA group is planning very significant investments to build new facilities in all the three front-end market segments. As far as uranium mining is concerned, these new mines will be based upon uranium reserves of outstanding quality. As for uranium conversion and enrichment, two large projects will be based on the most advanced technologies. This paper is aimed at recalling COGEMA Front End Division experience, the current status of its plants and operating entities and will provide a detailed overview of its major projects. (authors)

  13. Mechanism of Nucleic Acid Chaperone Function of Retroviral Nuceleocapsid (NC) Proteins

    Science.gov (United States)

    Rouzina, Ioulia; Vo, My-Nuong; Stewart, Kristen; Musier-Forsyth, Karin; Cruceanu, Margareta; Williams, Mark

    2006-03-01

    Recent studies have highlighted two main activities of HIV-1 NC protein contributing to its function as a universal nucleic acid chaperone. Firstly, it is the ability of NC to weakly destabilize all nucleic acid,(NA), secondary structures, thus resolving the kinetic traps for NA refolding, while leaving the annealed state stable. Secondly, it is the ability of NC to aggregate NA, facilitating the nucleation step of bi-molecular annealing by increasing the local NA concentration. In this work we use single molecule DNA stretching and gel-based annealing assays to characterize these two chaperone activities of NC by using various HIV-1 NC mutants and several other retroviral NC proteins. Our results suggest that two NC functions are associated with its zinc fingers and cationic residues, respectively. NC proteins from other retroviruses have similar activities, although expressed to a different degree. Thus, NA aggregating ability improves, and NA duplex destabilizing activity decreases in the sequence: MLV NC, HIV NC, RSV NC. In contrast, HTLV NC protein works very differently from other NC proteins, and similarly to typical single stranded NA binding proteins. These features of retroviral NCs co-evolved with the structure of their genomes.

  14. Control and maintenance of the Superphenix knowledge and its specific sodium skills through an innovative partnership between EDF and AREVA

    International Nuclear Information System (INIS)

    Superphenix is a 1200 MWe sodium cooled Fast Breeder Reactor (FBR) located in Creys-Malville (France). Its grid coupling occurred in 1986 and its final shutdown pronounced through a decree, 12 years later, in 1998. This Superphenix final shutdown decision marked a new stage in the life of the nuclear plant. Decommissioning activities were highly challenging due to the following: - Non recurrent and first-of-a-kind (FOAK) characteristics; - Environment constraints: radiation level, high temperatures, presence of argon, sodium, NaK, soda, hydrogen, etc.; - Complexity of the primary vessel internal structures; - Numerous interfaces to manage; - Numerous technical uncertainties due to the difficulty in anticipating the effective state of components (sodium and aerosols retentions, tritium concentration, NaK alteration, etc.). At the end of 1998, exchanges took place between EDF as 'Superphenix nuclear operator' and AREVA as 'Superphenix Nuclear Steam System Supply (NSSS) designer' in order to find the best way to meet the new challenge of decommissioning Superphenix. A key ingredient to achieving success was to ensure that existing local and specific sodium skills were controlled and maintained. AREVA was selected by EDF as its industrial partner for the sodium activities on this project being entrusted with the following missions: - Maintaining and adapting a strong EDF / AREVA partnership within the project duration; - Supplying support as the 'NSSS Designer'; - Rolling-out multidisciplinary skills from the design to the on-site operations; - Relying on its best technical experts to solve each technical challenge; - Developing and adapting durable specific skills of its technical team (sodium, mechanical, process, I and C, statutory, etc.) following each stage of the decommissioning. This EDF/AREVA partnership on the sodium activities has taken different forms according to the different stages of the project. From 1998 to 2005, AREVA was

  15. AREVA NP Inc next generation fresh UO2 fuel assembly shipping cask: SCALE - CRISTAL comparisons lead to safety criticality confidence

    International Nuclear Information System (INIS)

    AREVA NP as a worldwide PWR fuel provider has to have a fleet of fresh UO2 shipping casks being agreed within a lot of countries including USA (France), Germany, Belgium, Sweden, China, and South Africa... and to accommodate foreseen EPR Nuclear Power Plants fuel buildings. To reach this target the AREVA NP Fuel Sector decided to develop an up to date shipping cask gathering experience feedback of the today fleet and an improved safety allowing the design to comply with international regulations (NRC and IAEA) and local Safety Authorities. Based on pre design features a safety case was set up to highlight safety margins. Criticality hypothetical accidental assumptions were defined: -Preferential flooding - Fuel rod lattice pitch expansion for full length of fuel assemblies - Neutron absorber penalty -... Well known computer codes, American SCALE package and French CRISTAL package, were used to check configurations reactivity and to ensure that both codes lead to coherent results. Basic spectral calculations are based on similar algorithms with specific microscopic cross sections ENDF/BV for SCALE and JEF2.2 for CRISTAL. The main differences between the two packages is on one hand SCALE's three dimensional fuel assembly geometry is described by a pin by pin model while an homogenized fuel assembly description is used by CRISTAL and on the other hand SCALE is working with either 44 or 238 neutron energy groups while CRISTAL is with a 172 neutron energy groups. Those two computer packages rely on a wide validation process helping defining uncertainties as required by regulations in force. The shipping cask with two fuel assemblies is designed to maximize fuel isolation inside a cask and with neighboring ones even for large array configuration cases. Proven industrial products are used: - BoralTM as neutron absorber - High density polyethylene (HDPE) or Nylon as neutron moderator - Foam as thermal and mechanical protection The cask is designed to handle the complete

  16. AREVA NP next generation fresh UO2 fuel assembly shipping cask: SCALE - CRISTAL comparisons lead to safety criticality confidence

    International Nuclear Information System (INIS)

    AREVA NP as a worldwide PWR fuel provider has to have a fleet of fresh UO2 shipping casks being agreed within a lot of countries including USA, France, Germany, Belgium, Sweden, China, and South Africa - and to accommodate foreseen EPR Nuclear Power Plants fuel buildings. To reach this target the AREVA NP Fuel Sector decided to develop an up-to-date shipping cask (so called MAP project) gathering experience feedback of the today fleet and an improved safety allowing the design to comply with international regulations (NRC and IAEA) and local Safety Authorities. Based on pre design features a safety case was set up to highlight safety margins. Criticality hypothetical accidental assumptions were defined: - Preferential flooding; - Fuel rod lattice pitch expansion for full length of fuel assemblies; - Neutron absorber penalty; -... Well known computer codes, American SCALE package and French CRISTAL package, were used to check configurations reactivity and to ensure that both codes lead to coherent results. Basic spectral calculations are based on similar algorithms with specific microscopic cross sections ENDF/BV for SCALE and JEF2.2 for CRISTAL. The main differences between the two packages is on one hand SCALE's three dimensional fuel assembly geometry is described by a pin by pin model while an homogenized fuel assembly description is used by CRISTAL and on the other hand SCALE is working with either 44 or 238 neutron energy groups while CRISTAL is with a 172 neutron energy groups. Those two computer packages rely on a wide validation process helping defining uncertainties as required by regulations in force. The shipping cask with two fuel assemblies is designed to maximize fuel isolation inside a cask and with neighboring ones even for large array configuration cases. Proven industrial products are used: - BoralTM as neutron absorber; - High density polyethylene (HDPE) or Nylon as neutron moderator; - Foam as thermal and mechanical protection. The cask is

  17. Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2013. Figures and information about nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2013

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

  18. Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2014. Figures and information about nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2014

    International Nuclear Information System (INIS)

    Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for environment protection). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

  19. The AREVA integrated and sustainable concept of fatigue design, monitoring and re-assessment; AREVA FATIGUE CONCEPT - ein geschlossenes Konzept zur Verfolgung und Optimierung der auf Ermuedung basierenden Schaedigungseffekte von thermisch und mechanisch beanspruchten Kraftwerksbauteilen

    Energy Technology Data Exchange (ETDEWEB)

    Begholz, Steffen; Rudolph, Juergen [AREVA NP GmbH, Erlangen (Germany)

    2008-07-01

    Prevention of fatigue damage of components is an important topic with respect to safety and availability of a nuclear power plant. The issue of fatigue monitoring should be of primary interest throughout service life. Based on the changing general framework, i.e. planning of new plants with a projected lifetime of 60 years and the lifetime extension of existing plants AREVA is focussing R and D activities on improved detection methods. Primary objective is the realistic determination of the actual usage level of reactor components. The fatigue monitoring is supposed to enhance cost optimization and minimize inspection frequency. Fatigue monitoring should be implemented at the beginning of start-up period since the high loads during this phase introduce a significant contribution to the usage level. AREVA recommends the use of the FAMOS (fatigue monitoring system) for the assessment of the realistic transient loads and the data processing with respect to fatigue evaluation. Every 10 years the actual usage levels should be evaluated in detail according to the standards, based on measured load data. The fatigue evaluation is usually performed using finite element analyses taking into account the transient temperature loads at the component, dependent on the component demands based on elastic or elasto-plastic material behaviour. Potential problematic areas can be identified reliably. Direct measurement of fatigue damage, refined analysis concepts (short crack fracture mechanics, and ratcheting simulation) are supposed to support the concept. [German] Die Vermeidung von Ermuedungsschaeden an Komponenten der nuklearen Kraftwerkstechnik ist ein wichtiges Thema in Hinblick auf die Aufrechterhaltung der Anlagensicherheit sowie auf die Erhoehung der Verfuegbarkeit. Das Thema Ermuedungsueberwachung sollte somit waehrend der gesamten Laufzeit eines Kraftwerkes mit hoher Aufmerksamkeit verfolgt werden. Vor diesem Hintergrund und den sich aendernden Rahmenbedingungen, wie z

  20. Baryon Isovector Electric Properties and the Large N_c and Chiral Limits

    OpenAIRE

    Cohen, Thomas D.

    1995-01-01

    A model independent calculation is given for the nucleon isovector electric charge radius which is valid in the limit $N_c \\rightarrow \\infty$, $m_\\pi \\rightarrow 0$, $N_c m_\\pi$ fixed. This expression reduces to that of the Skyrme model in the limit $N_c m_{\\pi} \\rightarrow \\infty$.

  1. Parametric Modeling for Globoidal Cam Based and NC Machining

    Directory of Open Access Journals (Sweden)

    Haitao Liu

    2013-02-01

    Full Text Available The design and machining of globoidal cam is difficult, because the shape of working surface is complex,and the curved surface of its space is undevelopable. Based on the above reasons,we proposed the parametric Modeling method for globoidal cam based. Through the secondary development, we realized the parameterized modeling of globoidal cam. Base on using of globular indexing cam NC milling machine existing in the lab,research the programming technology,analyses the defects of conventional programming method,raise improvement measures,control the programming error,modify the feeding speed,develop the special purpose programming software, creat globular indexing cam NC machining program automaticly ,improve the machining precision and efficiency of globular indexing cam.  

  2. Permutation group SN and large Nc excited baryons

    International Nuclear Information System (INIS)

    We study the excited baryon states for an arbitrary number of colors Nc from the perspective of the permutation group SN of N objects. Classifying the transformation properties of states and quark-quark interaction operators under SN allows a general analysis of the spin-flavor structure of the mass operator of these states, in terms of a few unknown constants parametrizing the unknown spatial structure. We explain how to perform the matching calculation of a general two-body quark-quark interaction onto the operators of the 1/Nc expansion. The inclusion of core and excited quark operators is shown to be necessary. Considering the case of the negative parity L=1 states transforming in the MS of SN, we discuss the matching of the one-gluon and the Goldstone-boson exchange interactions.

  3. Series Design of Large-Scale NC Machine Tool

    Institute of Scientific and Technical Information of China (English)

    TANG Zhi

    2007-01-01

    Product system design is a mature concept in western developed countries. It has been applied in war industry during the last century. However, up until now, functional combination is still the main method for product system design in China. Therefore, in terms of a concept of product generation and product interaction we are in a weak position compared with the requirements of global markets. Today, the idea of serial product design has attracted much attention in the design field and the definition of product generation as well as its parameters has already become the standard in serial product designs. Although the design of a large-scale NC machine tool is complicated, it can be further optimized by the precise exercise of object design by placing the concept of platform establishment firmly into serial product design. The essence of a serial product design has been demonstrated by the design process of a large-scale NC machine tool.

  4. Large Nc from Seiberg–Witten curve and localization

    Directory of Open Access Journals (Sweden)

    Jorge G. Russo

    2015-09-01

    Full Text Available When N=2 gauge theories are compactified on S4, the large Nc limit then selects a unique vacuum of the theory determined by saddle-point equations, which remains determined even in the flat-theory limit. We show that exactly the same equations can be reproduced purely from Seiberg–Witten theory, describing a vacuum where magnetically charged particles become massless, and corresponding to a specific degenerating limit of the Seiberg–Witten spectral curve where 2Nc−2 branch points join pairwise giving aDn=0, n=1,…,Nc−1. We consider the specific case of N=2 SU(Nc SQCD coupled with 2Nf massive fundamental flavors. We show that the theory exhibits a quantum phase transition where the critical point describes a particular Argyres–Douglas point of the Riemann surface.

  5. Non-global jet evolution at finite N_c

    CERN Document Server

    Weigert, H

    2003-01-01

    Resummations of soft gluon emissions play an important role in many applications of QCD, among them jet observables and small x saturation effects. Banfi, Marchesini, and Smye have derived an evolution equation for non-global jet observables that exhibits a remarkable analogy with the BK equation used in the small x context. Here, this analogy is used to generalize the former beyond the leading N_c approximation. The result shows striking analogy with the JIMWLK equation describing the small x evolution of the color glass condensate. A Langevin description allows numerical implementation and provides clues for the formulation of closed forms for amplitudes at finite N_c. The proof of the new equation is based on these amplitudes with ordered soft emission. It is fully independent of the derivation of the JIMWLK equation and thus sheds new light also on this topic.

  6. Non-global jet evolution at finite Nc

    International Nuclear Information System (INIS)

    Resummations of soft gluon emissions play an important role in many applications of QCD, among them jet observables and small x saturation effects. For the case of non-global observables, Banfi, Marchesini, and Smye have cast the problem in terms of an evolution equation that exhibits a remarkable analogy with the BK equation used in the small x context. Here, this analogy is used to generalize the former beyond the leading Nc approximation. The result shows striking analogy with the JIMWLK equation describing the small x evolution of the color glass condensate. A Langevin description allows numerical implementation and provides clues for the formulation of closed forms for amplitudes at finite Nc. The proof of the new equation is based on amplitudes with ordered soft emission. It is fully independent of the derivation of the JIMWLK equation and thus sheds new light also on this topic

  7. Parametric Modeling for Globoidal Cam Based and NC Machining

    OpenAIRE

    Haitao Liu; Zhibin Chang; Lei Zhang; Wei Jiang; Guangguo Zhang

    2013-01-01

    The design and machining of globoidal cam is difficult, because the shape of working surface is complex,and the curved surface of its space is undevelopable. Based on the above reasons,we proposed the parametric Modeling method for globoidal cam based. Through the secondary development, we realized the parameterized modeling of globoidal cam. Base on using of globular indexing cam NC milling machine existing in the lab,research the programming technology,analyses the defects of conventional p...

  8. Steam turbine generators -from NC manufacturing to CAD/CAM

    Energy Technology Data Exchange (ETDEWEB)

    Searle, D.R.; King, F.E.; Kiniskern, J.M.

    1985-04-01

    A program has been designed to integrate engineering, manufacturing, and business systems using a common data base. There has been a significant increase in benefits obtained by extending the automation of the design/drafting function to include manufacturing operations. This extension would have been difficult without the existence of highly developed family-of-parts NC programs. The integration concept has also been applied to turbine buckets and is being extended to other turning-generator components.

  9. The Built Environment and Childhood Obesity in Durham, NC

    OpenAIRE

    Miranda, Marie Lynn; Edwards, Sharon E.; Anthopolos, Rebecca; DOLINSKY, DIANA H; Kemper, Alex R.

    2012-01-01

    The relationship between childhood obesity and aspects of the built environment characterizing neighborhood social context is understudied. We evaluate the association between seven built environment domains and childhood obesity in Durham, NC. Measures of housing damage, property disorder, vacancy, nuisances, and territoriality were constructed using data from a 2008 community assessment. Renter-occupied housing and crime measures were developed from public databases. We linked these measure...

  10. NC Lathe Training System Based on the Web

    Institute of Scientific and Technical Information of China (English)

    卢碧红; 黄文丽; 葛研军

    2004-01-01

    Based on an analysis of the requirement of network-oriented NC lathe training system, a general framework of web-based training system is established. The key techniques for establishing this system include a three-layer web structure in building the general framework, the technique of VRML to model a virtual operating environment, and the access to the database using the ASP technique.

  11. ncRNA orthologies in the vertebrate lineage

    OpenAIRE

    Pignatelli, M.; Vilella, A. J.; Muffato, M.; Gordon, L; White, S.; Flicek, P.; Herrero, J.

    2016-01-01

    Annotation of orthologous and paralogous genes is necessary for many aspects of evolutionary analysis. Methods to infer these homology relationships have traditionally focused on protein-coding genes and evolutionary models used by these methods normally assume the positions in the protein evolve independently. However, as our appreciation for the roles of non-coding RNA genes has increased, consistently annotated sets of orthologous and paralogous ncRNA genes are increasingly needed. At the ...

  12. Non-global jet evolution at finite N_c

    OpenAIRE

    Weigert, Heribert

    2003-01-01

    Resummations of soft gluon emissions play an important role in many applications of QCD, among them jet observables and small x saturation effects. Banfi, Marchesini, and Smye have derived an evolution equation for non-global jet observables that exhibits a remarkable analogy with the BK equation used in the small x context. Here, this analogy is used to generalize the former beyond the leading N_c approximation. The result shows striking analogy with the JIMWLK equation describing the small ...

  13. A hybrid approach to automatic generation of NC programs

    OpenAIRE

    G. Payeganeh; M. Tolouei-Rad

    2005-01-01

    Purpose: This paper describes AGNCP, an intelligent system for integrating commercial CAD and CAM systems for 2.5D milling operations at a low cost.Design/methodology/approach: It deals with different machining problems with the aid of two expert systems. It recognizes machining features, determines required machining process plans, cutting tools and parameters necessary for generation of NC programs.Findings: The system deals with different machining problems with the aid of two expert syste...

  14. Customer-operator partnership. A boiling water reactor developed jointly by AREVA NP and E.ON Kernkraft

    International Nuclear Information System (INIS)

    Many countries spread all over the world have publicly expressed their intention to pursue the construction of new nuclear power plants with improved safety, economy and more straight forwarded operation and maintenance. Reasons for the intention are: The world wide increasing demand for energy and hence the general necessity to build new power plants. The concerns for increased emissions of green house gases leading to a change in the climate have brought into question the primary reliance on plants utilizing fossil fuels. A new reactor type matching the previously stated issues is AREVA NP's further development of proven BWR design. Combining AREVA's and E.ON's expertise, a project was launched to customize the final basic design for this advanced nuclear power plant having a net power output of about 1,250 MW, a net efficiency of about 37% and a design service life of 60 years. Within this joint venture the overall plant design was simplified and additionally all active safety systems have passive safety related backup systems utilizing basic laws of physics, such as gravity, enabling them to function without electrical power supplies or activation by powered instrumentation and control systems. The development takes into account the technical and accumulated operating experience of the project partners. Based on the operating experience of the project partners a simplification of the overall system engineering was performed, flexible fuel cycle length (12 to 24 months) are possible as well as a reduction of process waste was achieved. These improvements regarding the operation and economics result on the one hand in lower investment cost and on the other hand in a high availability of the plant, hence in low maintenance costs. Generally, the electrical generation costs are accomplished, which are competitive to larger-capacity nuclear power plants and fossil-fired plants. (author)

  15. A theory of baryon resonances at large N_c

    CERN Document Server

    Diakonov, Dmitri; Vladimirov, Alexey A

    2013-01-01

    At large number of colors, N_c quarks in baryons are in a mean field of definite space and flavor symmetry. We write down the general Lorentz and flavor structure of the mean field, and derive the Dirac equation for quarks in that field. The resulting baryon resonances exhibit an hierarchy of scales: The crude mass is O(N_c), the intrinsic quark excitations are O(1), and each intrinsic quark state entails a finite band of collective excitations that are split as O(1/N_c). We build a (new) theory of those collective excitations, where full dynamics is represented by only a few constants. In a limiting (but unrealistic) case when the mean field is spherically-and flavor-symmetric, our classification of resonances reduces to the SU(6) classification of the old non-relativistic quark model. Although in the real world N_c is only three, we obtain a good accordance with the observed resonance spectrum up to 2 GeV.

  16. NC-Audit: Auditing for Network Coding Storage

    CERN Document Server

    Le, Anh

    2012-01-01

    Network coding-based storage has recently received a lot of attention thanks to its ability to efficiently repair failed nodes. Independently, another body of work has proposed integrity checking schemes for cloud storage, none of which, however, is customized for network coding storage or can efficiently support repair. In this work, we bridge the gap between these currently disconnected bodies of work, and we focus on the (novel) advantage of network coding for integrity checking. We propose NC-Audit - a remote data integrity checking scheme, designed specifically for network coding-based storage cloud. NC-Audit provides a unique combination of desired properties: (i) efficient checking of data integrity (ii) efficient support for repairing failed nodes (iii) full support for modification of outsourced data and (iv) protection against information leakage when checking is performed by a third party. The key ingredient of the design of NC-Audit is a novel combination of SpaceMac, a homomorphic MAC scheme for ...

  17. TRAC-PF1 post-test predictions for the Semiscale Natural-Circulation Tests S-NC-2 and S-NC-6

    International Nuclear Information System (INIS)

    The TRAC prediction are compared to the data for the Semiscale natural-circular Tests S-NC-2B and S-NC-6. S-NC-2B is a baseline test covering single- and two-phase natural circulation as well as reflux; here TRAC compares quite well with the experiment results for mass flow. For Test S-NC-6, which is a reflux test with various amounts of nitrogen injected into the system, the TRAC prediction of the reflux rate is close to the experiment value with no nitrogen in the system. Ultimately, the maximum reflux rate predicted by TRAC is about 20% higher than the data

  18. Model of automated computer aided NC machine tools programming

    Directory of Open Access Journals (Sweden)

    J. Balic

    2006-04-01

    Full Text Available Purpose: Modern companies tend towards the greatest possible automation in all areas. The new control concepts of manufacturing processes required development of adequate tools for the introduction of automated control in a certain area. The paper presents such system for automated programming of CNC machine tools.Design/methodology/approach: The system is based on the previously incorporated know-how and the rules of it implementation in tool – shop. The existing manufacturing knowledge of industry tool production was collected and analysing. On this bases flow chart of all activities were made. Theoretical contribution is made in systemization of technological knowledge, which is now accessible for all workers in NC preparation units.Findings: Utilization of technology knowledge. On the basis of the recognized properties it has worked out the algorithms with which the process of manufacture, the tool and the optimum parameters selected are indirectly determined, whereas the target function was working out of the NC programme. We can first out that with information approaching of the CAM and CAPP the barriers between them, strict so far, disappear.Research limitations/implications: Till now, the system is limited to milling, drilling and similar operation. It could be extended to other machining operations (turning, grinding, wire cutting, etc. with the same procedure. In advanced, some methods of artificial intelligence could be use.Practical implications: It is suitable for industry tools, dies and moulds production, while the system was proved in the real tool shop (production of tools for casting. The system reduces the preparation time of NC programs and could be used with any commercial available CAD/CAM/NC programming systems. Human errors are avoid or at lover level. It is important for engineers in CAD/CAM field and in tool – shops.Originality/value: The developed system is original and was not found in the literature or in the

  19. The NC (numerically controlled) assistant: Interfacing knowledge based manufacturing tools to CAD/CAM systems

    Energy Technology Data Exchange (ETDEWEB)

    Burd, W.C.

    1988-01-01

    A knowledge based computer program that assists programmers of numerically controlled (NC) machine tools is described. The program uses part features identified by the NC programmer and a set of expert system manufacturing rules to select cutting parameters and produce NC part programs. An expert system shell determines the NC sequence and the machining parameters. Several point-to-point NC functions are currently in production. A CAD/CAM system interface for milling and turning functions is also described. 2 refs., 24 figs.

  20. Software module for geometric product modeling and NC tool path generation

    International Nuclear Information System (INIS)

    The intelligent CAD/CAM system named VIRTUAL MANUFACTURE is created. It is consisted of four intelligent software modules: the module for virtual NC machine creation, the module for geometric product modeling and automatic NC path generation, the module for virtual NC machining and the module for virtual product evaluation. In this paper the second intelligent software module is presented. This module enables feature-based product modeling carried out via automatic saving of the designed product geometric features as knowledge data. The knowledge data are afterwards applied for automatic NC program generation for the designed product NC machining. (Author)

  1. smyRNA: A Novel Ab Initio ncRNA Gene Finder

    OpenAIRE

    Sahinalp, S. Cenk; Salari, Raheleh; Aksay, Cagri; HAJIRASOULIHA, Iman; Karakoc, Emre; Unrau, Peter J.

    2009-01-01

    Background Non-coding RNAs (ncRNAs) have important functional roles in the cell: for example, they regulate gene expression by means of establishing stable joint structures with target mRNAs via complementary sequence motifs. Sequence motifs are also important determinants of the structure of ncRNAs. Although ncRNAs are abundant, discovering novel ncRNAs on genome sequences has proven to be a hard task; in particular past attempts for ab initio ncRNA search mostly failed with the exception of...

  2. Classification of ncRNAs using position and size information in deep sequencing data

    Science.gov (United States)

    Erhard, Florian; Zimmer, Ralf

    2010-01-01

    Motivation: Small non-coding RNAs (ncRNAs) play important roles in various cellular functions in all clades of life. With next-generation sequencing techniques, it has become possible to study ncRNAs in a high-throughput manner and by using specialized algorithms ncRNA classes such as miRNAs can be detected in deep sequencing data. Typically, such methods are targeted to a certain class of ncRNA. Many methods rely on RNA secondary structure prediction, which is not always accurate and not all ncRNA classes are characterized by a common secondary structure. Unbiased classification methods for ncRNAs could be important to improve accuracy and to detect new ncRNA classes in sequencing data. Results: Here, we present a scoring system called ALPS (alignment of pattern matrices score) that only uses primary information from a deep sequencing experiment, i.e. the relative positions and lengths of reads, to classify ncRNAs. ALPS makes no further assumptions, e.g. about common structural properties in the ncRNA class and is nevertheless able to identify ncRNA classes with high accuracy. Since ALPS is not designed to recognize a certain class of ncRNA, it can be used to detect novel ncRNA classes, as long as these unknown ncRNAs have a characteristic pattern of deep sequencing read lengths and positions. We evaluate our scoring system on publicly available deep sequencing data and show that it is able to classify known ncRNAs with high sensitivity and specificity. Availability: Calculated pattern matrices of the datasets hESC and EB are available at the project web site http://www.bio.ifi.lmu.de/ALPS. An implementation of the described method is available upon request from the authors. Contact: florian.erhard@bio.ifi.lmu.de PMID:20823303

  3. Universell kopplingsbox mellan NC-maskin och industrirobot

    OpenAIRE

    Martín, Jose Antonio; Trujillo, Eduardo

    2010-01-01

    The aim of this thesis is the design and implementation of a standardized interface to communicate a NC machine with an industrial robot. This interface consists of an ‘electronic box’ which includes a powerful board that is perfect for automation projects composed of a microcontroller, serial ports, optocouplers, relays, etc… The main component of this PCB is the microcontroller. The Atmel AT90CAN128 microcontroller is a good choice for this purpose since it is perfectly suited for industria...

  4. CNC LATHE MACHINE PRODUCING NC CODE BY USING DIALOG METHOD

    Directory of Open Access Journals (Sweden)

    Yakup TURGUT

    2004-03-01

    Full Text Available In this study, an NC code generation program utilising Dialog Method was developed for turning centres. Initially, CNC lathes turning methods and tool path development techniques were reviewed briefly. By using geometric definition methods, tool path was generated and CNC part program was developed for FANUC control unit. The developed program made CNC part program generation process easy. The program was developed using BASIC 6.0 programming language while the material and cutting tool database were and supported with the help of ACCESS 7.0.

  5. Application of COBRA-NC to hydrogen transport

    International Nuclear Information System (INIS)

    COBRA-NC, a thermal-hydraulic computer code for the analysis of light water reactor (LWR) containment system transients is presented. A brief description of the code is provided. While the code is being developed for all phases of a containment transient, data comparisons with hydrogen distribution test data obtained in the Hanford Engineering Development Laboratory test facility and in the Battelle Memorial Institute's test facility are presented in this paper. The advantages this code features over other containment codes is also discussed

  6. Impact of uranium exploitation by Cogema-Areva subsidiaries in Niger. Assessment of analyses performed by the CRIIRAD laboratory in 2004 and at the beginning of 2005

    International Nuclear Information System (INIS)

    After a description of the uranium exploitation context (involved companies, production) in Arlit, Niger, by Cogema-Areva subsidiary companies, this report describes the context of controls performed by the CRIIRAD laboratory. Then, it reports and comments the contamination of underground so-called drinkable waters (contamination risks, Cogema statement, detection of a rather high concentration of alpha emitters, measurements performed in 2004 and 2005). The authors notice that water contamination is known by Cogema. Then, the report analyzes the issue of contaminated scrap metal dispersal, comments and criticizes the attitude of Cogema with respect to the associated risks. It comments the uranate transport accident which occurred in February 2004, the subsequent contamination, actions performed by Cogema, the associated health risks, and the statements made by Areva and Cogema. It also comments and analyzes the risks related to radioactive radon dusts inhalation around different sites and because of some technical practices, and Cogema statements about this issue. In conclusion, the authors outline the need of reinforced controls and of an epidemiological study, and outlines how Areva propagates wrong ideas

  7. AREVA - Results for the first half of 2012: performance materializes as 'Action 2016' plan is rolled out

    International Nuclear Information System (INIS)

    The results for the first half of 2012 demonstrate the effectiveness of Areva's 'Action 2016' plan, in particular with a sharp rise in EBITDA and a significant improvement in free operating cash flow after capex. Moreover, net debt remains stable even though the Group invested more than 900 million euros in strategic projects and in improvements to safety and to competitiveness of industrial assets. Several factors made this first phase towards restoring the Group's financial performance possible: - revenue growth in the nuclear businesses together with the ramp-up of operations in renewable energies, with the Group continuing to benefit from the strong visibility provided by its backlog, which has also grown over the past twelve months; - ongoing efforts begun in late 2011 to reduce operating costs, with savings measures at the end of June 2012 implemented for nearly 20% of the objective set for the Group through 2015, on an annual basis, another 45% of the objective being secured in addition. - execution ahead of schedule in Areva's asset disposal program, with 961 million euros mainly collected during the first half year and the objective of at least 1.2 billion euros for the 2012- 2013 period to be met this year with the recently announced disposal of La Mancha Resources for about 315 million Canadian dollars. After booking provisions, in accordance with the principle of prudent management, in two areas (construction of the Olkiluoto 3 EPR reactor and the Bakouma and Ryst Kuil mining sites), the Group reports positive operating income and positive net income for the first half of 2012. Results can be summarized as follows: Backlog rises 4.8% year on year to euro 45.2 bn; - Significant revenue growth to euro 4.329 bn, up 8.3% vs. H1 2011; - Strong increase in EBITDA to euro 725 m: +euro 508 m vs. H1 2011; - Marked improvement in FCF to -euro 591 m: +euro 328 m vs. H1 2011; - Net debt stable for the half year; - Positive operating income and net income to owners

  8. Can the nucleon axial charge be O(Nc^0)?

    CERN Document Server

    Kojo, Toru

    2012-01-01

    The nucleon self-energy and its relation to the nucleon axial charge gA are discussed at large Nc. The energy is compared for the hedgehog, conventional, and recently proposed dichotomous nucleon wavefunctions which give different values for gA. We consider their energies at both perturbative and non-perturbative levels. In perturbative estimates, we take into account the pion exchanges among quarks up to the third orders of axial charge vertices, including the many-body forces such as the Wess-Zumino terms. It turns out that the perturbative pion exchanges among valence quarks give the same leading Nc contributions for three wavefunctions, while their mass differences are O(Lamba_qcd). The signs of splittings flip for different orders of the axial charge vertices, so it is hard to conclude which one is the most energetically favored. For non-perturbative estimates involving the modification of quark bases, we use the chiral quark soliton model as an illustration. With the hedgehog quark wavefunctions with gA...

  9. The aeronautics face-gear NC hobbing machining technology

    Science.gov (United States)

    Wu, Canhui; Wang, Yanzhong

    2013-03-01

    Face-gear drives become the main direction of research for aeronautical drives because of their special advantages. Face-gear machining problems have became to baffle the embedded research for face-gear. The basal coordinate systems of face-gear hobbing were setted up according to the face-gear hobbing theory. The hobbing surface equation of facegear was established by using the equation of pinion tooth surface and matrix for coordinate transform based on the gear geometry and applied theory, then the hobbing tooth surface constrain conditions for dedendum undercutting were analyzed, at the same time, the hobbing nodal points were used to construct the three-dimensional basal worm model of face-gear hob by recurring to the three-dimensional software. Furthermore, the special hob for face-gear machining was designed and manufactured. The exact assembly and machining simulation were finished by using the program development software VC++6.0 and the UG customization function in the light of the face-gear hobbing theory. It validates the hob correctness and gets the gear hobbing program. According to the result of machining simulation, facegear numerical control(NC) hob machining was realized in the four-axis NC machine tool. It improves the cutting efficiency and establishs the base for face-gear grinding.

  10. ISO 14649 (STEP-NC: New Standards for CNC Machining

    Directory of Open Access Journals (Sweden)

    Yusri Yusof

    2010-06-01

    Full Text Available The changing economic climate has made global manufacturing a growing reality over the last decade, forcing companies from east and west and all over the world to collaborate beyond geographic boundaries in the design, manufacture and assemble of products. The ISO10303 and ISO14649 Standards (STEP and STEP-NC have been developed to introduce interoperability into manufacturing enterprises so as to meet the challenge of responding to production on demand. The paper focuses on the use of this new standard to address the process planning and machining of turn/mill discrete components. Due to the complexity of programming these machines there is a need to model their process capability to improve the interoperable manufacturing capability in places such as turning centres. Finally a proposed computational environment for a STEP-NC compliant system for turning operations (SCSTO is described. And supported by the specification of information models and constructed using a structured methodology and object-oriented methods. SCSTO was developed to generate a Part 21 file based on machining features to support the interactive generation of process plans utilizing feature extraction. A case study component has been developed to prove the concept for using the milling and turning parts of ISO14649 to provide a turn-mill CAD/CAPP/CAM environment.

  11. Microarray analysis of ncRNA expression patterns in Caenorhabditis elegans after RNAi against snoRNA associated proteins

    OpenAIRE

    Skogerbø Geir; He Housheng; Aftab Muhammad; Chen Runsheng

    2008-01-01

    Abstract Background Short non-coding RNAs (ncRNAs) perform their cellular functions in ribonucleoprotein (RNP) complexes, which are also essential for maintaining the stability of the ncRNAs. Depletion of individual protein components of non-coding ribonucleoprotein (ncRNP) particles by RNA interference (RNAi) may therefore affect expression levels of the corresponding ncRNA, and depletion of candidate associated proteins may constitute an alternative strategy when investigating ncRNA-protein...

  12. Construction of the Active Site of Metalloenzyme on Au NC Micelles

    Institute of Scientific and Technical Information of China (English)

    ZHANG, Zhiming; FU, Qiuan; HUANG, Xin; XU, Jiayun; LIU, Junqiu; SHEN, Jiacong

    2009-01-01

    For developing an efficient nanoenzyme system with self-assembly strategy, gold nanocrystal micelles (Au NC micelles) with inserted catalytic Zn(Ⅱ) centers were constructed by self-assembly of a catalytic ligand [N,N-bis(2-aminoethyl)-N'dodecylethylenediamine] Zn(Ⅱ) complexes (Zn(Ⅱ)L) on the surface of Au NC via hy- drophobic interaction. The functionalized Au NC micelles acted as an excellent nanoenzyme model for imitating ribonuclease. The catalytic capability of the Au NC micelles was evaluated by accelerating the cleavage of 2-hydroxypropyl p-nitrophenyl phosphate (HPNP). These functionalized Au NC micelles exhibited considerable ri- bonuclease-like activities by a factor of 4.9×104 (kcat/kuncat) for the cleavage of HPNP in comparison to the sponta- neous cleavage of HPNP at 37℃. The catalytic capability of the functionalized Au NC micelles can be considera- bly compared to other models reported previously as nanoenzymes under the comparable conditions.

  13. The Nc dependencies of baryon masses: Analysis with Lattice QCD and Effective Theory

    Energy Technology Data Exchange (ETDEWEB)

    Calle Cordon, Alvaro C. [JLAB; DeGrand, Thomas A. [University of Colorado; Goity, Jose L. [JLAB

    2014-07-01

    Baryon masses at varying values of Nc and light quark masses are studied with Lattice QCD and the results are analyzed in a low energy effective theory based on a combined framework of the 1/Nc and Heavy Baryon Chiral Perturbation Theory expansions. Lattice QCD results for Nc=3, 5 and 7 obtained in quenched calculations, as well as results for unquenched calculations for Nc=3, are used for the analysis. The results are consistent with a previous analysis of Nc=3 LQCD results, and in addition permit the determination of sub-leading in 1/Nc effects in the spin-flavor singlet component of the baryon masses as well as in the hyperfine splittings.

  14. CIM Diffusion: The Case of NC-Machines in the U.S. Metalworking Industry

    OpenAIRE

    Tchijov, I.

    1987-01-01

    Analysis and forecasting of NC-machine diffusion constitute one of the main activities of the IIASA Project "Computer Integrated Manufacturing" (CIM). Numerically controlled (NC) machines represent the first stage of flexible automation in the metalworking industry. NC-machines were developed in the early 1950s and became available commercially in 1955. Currently, they account for 5% of the total number of machine tools installed. Their share of production output is mare than 50% by value. ...

  15. Bioinformatics of Cancer ncRNA in High Throughput Sequencing: Present State and Challenges

    OpenAIRE

    Jorge, Natasha Andressa Nogueira; Ferreira, Carlos Gil; Passetti, Fabio

    2012-01-01

    The numerous genome sequencing projects produced unprecedented amount of data providing significant information to the discovery of novel non-coding RNA (ncRNA). Several ncRNAs have been described to control gene expression and display important role during cell differentiation and homeostasis. In the last decade, high throughput methods in conjunction with approaches in bioinformatics have been used to identify, classify, and evaluate the expression of hundreds of ncRNA in normal and patholo...

  16. De Novo Discovery of Structured ncRNA Motifs in Genomic Sequences

    OpenAIRE

    RUZZO, WALTER L.; Gorodkin, Jan

    2014-01-01

    De novo discovery of "motifs" capturing the commonalities among related noncoding ncRNA structured RNAs is among the most difficult problems in computational biology. This chapter outlines the challenges presented by this problem, together with some approaches towards solving them, with an emphasis on an approach based on the CMfinder CMfinder program as a case study. Applications to genomic screens for novel de novo structured ncRNA ncRNA s, including structured RNA elements in untranslated ...

  17. Role of the NC-Loop in Catalytic Activity and Stability in Lipase from Fervidobacterium changbaicum

    OpenAIRE

    Li, Binchun; Yang, Guangyu; Wu, Lie; Feng, Yan

    2012-01-01

    Flexible NC-loops between the catalytic domain and the cap domain of the α/β hydrolase fold enzymes show remarkable diversity in length, sequence, and configuration. Recent investigations have suggested that the NC-loop might be involved in catalysis and substrate recognition in many enzymes from the α/β hydrolase fold superfamily. To foster a deep understanding of its role in catalysis, stability, and divergent evolution, we here systemically investigated the function of the NC-loop (residue...

  18. Multi-agent System for Process Planning in Step-nc Based Manufacturing

    OpenAIRE

    Juan Du; Xianguo Yan

    2012-01-01

    In order to realize STEP-NC-oriented computer numerical control machining and achieve optimal performance in manufacturing, a multi-agent system for process planning in STEP-NC based manufacturing was designed. By analyzing the characteristic of STEP-NC data model, a manufacturing feature-oriented process planning method was proposed in this study and the distributed artificial intelligence methods, namely collaborative multi-agent was employed to accomplish process planning of part. The prop...

  19. Tritium management in the EPR™ and ATMEA1™ reactors: An AREVA computer tool AbsoluT-3

    International Nuclear Information System (INIS)

    Tritium, in NPP, is mainly produced by neutron activation reactions with lithium and boron isotopes dissolved in the primary coolant as well as with naturally-occurring deuterium in the primary coolant. The use of enriched boric acid, the increase in lithium concentration to control the pH and the new fuel management increase the tritium production in the primary coolant and thus the tritium releases in the environment. In this context AREVA developed a computational tool for management of the tritium activity: AbsoluT-3. AbsoluT-3 allows estimating the tritium activity in the primary coolant taking into account the mode of operation (with or without load follow), water movements and many other parameters. This activity can be estimated for many cycles in power operation and during shutdown. If the tritium releases are regulatory imposed, AbsoluT-3 allows determining maximum tritium concentration to be reached in the primary coolant and the total tritium releases to respect the discharge authorization. AbsoluT-3 allows anticipating tritium management issues according to the design as well as operational constraints. These constraints are mainly twofold: radiation protection during shutdown and releases into the environment. (author)

  20. Characterizing ncRNAs in human pathogenic protists using high-throughput sequencing technology

    Directory of Open Access Journals (Sweden)

    Lesley Joan Collins

    2011-12-01

    Full Text Available ncRNAs are key genes in many human diseases including cancer and viral infection, as well as providing critical functions in pathogenic organisms such as fungi, bacteria, viruses and protists. Until now the identification and characterization of ncRNAs associated with disease has been slow or inaccurate requiring many years of testing to understand complicated RNA and protein gene relationships. High-throughput sequencing now offers the opportunity to characterize miRNAs, siRNAs, snoRNAs and long ncRNAs on a genomic scale making it faster and easier to clarify how these ncRNAs contribute to the disease state. However, this technology is still relatively new, and ncRNA discovery is not an application of high priority for streamlined bioinformatics. Here we summarize background concepts and practical approaches for ncRNA analysis using high-throughput sequencing, and how it relates to understanding human disease. As a case study, we focus on the parasitic protists Giardia lamblia and Trichomonas vaginalis, where large evolutionary distance has meant difficulties in comparing ncRNAs with those from model eukaryotes. A combination of biological, computational and sequencing approaches has enabled easier classification of ncRNA classes such as snoRNAs, but has also aided the identification of novel classes. It is hoped that a higher level of understanding of ncRNA expression and interaction may aid in the development of less harsh treatment for protist-based diseases.

  1. Classification of ncRNAs using position and size information in deep sequencing data

    OpenAIRE

    Erhard, Florian; Zimmer, Ralf

    2010-01-01

    Motivation: Small non-coding RNAs (ncRNAs) play important roles in various cellular functions in all clades of life. With next-generation sequencing techniques, it has become possible to study ncRNAs in a high-throughput manner and by using specialized algorithms ncRNA classes such as miRNAs can be detected in deep sequencing data. Typically, such methods are targeted to a certain class of ncRNA. Many methods rely on RNA secondary structure prediction, which is not always accurate and not all...

  2. NC flame pipe cutting machine tool based on open architecture CNC system

    Institute of Scientific and Technical Information of China (English)

    Xiaogen NIE; Yanbing LIU

    2009-01-01

    Based on the analysis of the principle and flame movement of a pipe cutting machine tool, a retrofit NC flame pipe cutting machine tool (NFPCM) that can meet the demands of cutting various pipes is proposed. The paper deals with the design and implementation of an open architecture CNC system for the NFPCM, many of whose aspects are similar to milling machines; however, different from their machining processes and control strategies. The paper emphasizes on the NC system structure and the method for directly creating the NC file according to the cutting type and parameters. Further, the paper develops the program and sets up the open and module NC system.

  3. OPTIMIZATION AND APPROXIMATION OF NC POLYNOMIALS WITH SUMS OF SQUARES

    Directory of Open Access Journals (Sweden)

    Kristijan Cafuta

    2010-12-01

    Full Text Available In this paper we study eigenvalue optimization of non-commutative polynomials. That is, we compute the smallest or biggest eigenvalue a non-commutative polynomial can attain. Our algorithm is based on sums of hermittian squares. To test for exactness, the solutions of the dual SDP are investigated. When we consider the eigenvalue lower bounds we can show that attainability of the optimal value on the dual side implies that the eigenvalue bound is attained. We also show how to extract global eigenvalue optimizers with a procedure based on two ingredients: - the first is the solution to the truncated (tracial moment problem; - the second is the Gelfand-Naimark-Segal (GNS construction. The implementation of these procedures in our computer algebra system NC-SOStools is presented and several examples pertaining to matrix inequalities are given to illustrate the results.

  4. METHODS OF OBTAINING HIGH QUALITY OF METALWORKING NC MACHINES

    OpenAIRE

    Ota, Yoshimi

    2009-01-01

    Приведены сведения об опыте работы японской компании Mori Seiki в области создания перспективного металлообрабатывающего оборудования с ЧПУInformation about operational experience of Japanese company Mori Seiki in the field of making perspective metal-working NC machines is presented

  5. A study of Internet-based virtual NC turning system

    Science.gov (United States)

    Li, Yue; Li, Shujuan

    2004-03-01

    The virtual machining technique is a key issue of Virtual Manufacturing (VM) system, and the simulation of virtual machining process is a focus research field at the present time. This paper addresses the importance of integrating a virtual manufacturing system with the Internet and proposes a web-based, scalable and distributed architecture for developing a platform-independent virtual NC turning system. A Web-based virtual turning system has been developed using Virtual Reality Modeling Language and Java, and describes the structure of the system and the realization of its main functions. The user can easily setups machining conditions, operates the virtual turning machine in a web browser, and evaluates and optimizes the machining process on the Internet.

  6. Study of Machining Error Forecast in NC Lathe

    Institute of Scientific and Technical Information of China (English)

    LIU Jiwei; ZHANG Ying; YANG Zheqing

    2006-01-01

    This paper brings forward a kind of machining error forecast principle in NC lathe simulation system. It combines the method of math, dynamic, material and mechanism, etc, sums up the factors which can affect the machining error, coalescent knowledge of mechanism manufacture technique and interconvert characteristic, mapped the change of physics factor in cutting process into virtual manufacture system by mathematical model. On the platform of Windows 2000 and Visual C++, applying program is developed by use of C++. The lean warehouse of MATLAB is transferred in order to command MATLAB on the language platform of MATLAB, and then the curve of the results is drawn by the outcome of calculation, which is based on the mathematical model in order to manifest the simulation results in the pattern of data and curve.

  7. ncDNA and drift drive binding site accumulation

    Directory of Open Access Journals (Sweden)

    Ruths Troy

    2012-08-01

    Full Text Available Abstract Background The amount of transcription factor binding sites (TFBS in an organism’s genome positively correlates with the complexity of the regulatory network of the organism. However, the manner by which TFBS arise and accumulate in genomes and the effects of regulatory network complexity on the organism’s fitness are far from being known. The availability of TFBS data from many organisms provides an opportunity to explore these issues, particularly from an evolutionary perspective. Results We analyzed TFBS data from five model organisms – E. coli K12, S. cerevisiae, C. elegans, D. melanogaster, A. thaliana – and found a positive correlation between the amount of non-coding DNA (ncDNA in the organism’s genome and regulatory complexity. Based on this finding, we hypothesize that the amount of ncDNA, combined with the population size, can explain the patterns of regulatory complexity across organisms. To test this hypothesis, we devised a genome-based regulatory pathway model and subjected it to the forces of evolution through population genetic simulations. The results support our hypothesis, showing neutral evolutionary forces alone can explain TFBS patterns, and that selection on the regulatory network function does not alter this finding. Conclusions The cis-regulome is not a clean functional network crafted by adaptive forces alone, but instead a data source filled with the noise of non-adaptive forces. From a regulatory perspective, this evolutionary noise manifests as complexity on both the binding site and pathway level, which has significant implications on many directions in microbiology, genetics, and synthetic biology.

  8. Study on Interaction of ADN and (NC+NG) by Gasometric Method%量气法研究ADN与(NC+NG)的相互作用

    Institute of Scientific and Technical Information of China (English)

    何少蓉; 张林军; 衡淑云; 刘子如

    2008-01-01

    用 NBK型"拉瓦"量气测试系统研究了较高温度下二硝酰胺铵(ADN)与双基吸收药(NC+NG)体系的相互作用,从动力学角度阐述了二者的相互作用.结果表明: ADN与(NC+NG)混合物加热分解的最终放气量在标准状态下为626.8 mL·g-1,与ADN和(NC+NG)最大放气量之和相比并没有增加,但分解速度显著提高,活化能显著降低至82.58 kJ·mol-1,ADN与(NC+NG)之间存在强烈的相互作用.

  9. Land Use and Land Cover, NC Ecosystem Enhancement Program Targeted Local Watersheds, Published in 2007, 1:24000 (1in=2000ft) scale, NC DENR / Ecosystem Enhancement Program.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Land Use and Land Cover dataset, published at 1:24000 (1in=2000ft) scale, was produced all or in part from Other information as of 2007. It is described as 'NC...

  10. Land Use and Land Cover, NC Ecosystem Enhancement Program Local Watershed Plans, Published in 2007, 1:24000 (1in=2000ft) scale, NC DENR / Ecosystem Enhancement Program.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Land Use and Land Cover dataset, published at 1:24000 (1in=2000ft) scale, was produced all or in part from Other information as of 2007. It is described as 'NC...

  11. Study on Intelligent NC Programming for Complex Components of Marine Diesel Based on KBE and UG NX

    Institute of Scientific and Technical Information of China (English)

    ZHANG Liang; ZHANG Shengwen; FANG Xifeng

    2006-01-01

    The NC programming for complex components has lots drawbacks such as excessive repetitious labors, heavy workload and lack of optimization, which are especially serious in NC programming for complex components of marine diesel. Based on the key technologies of applying KBE(Knowledge Based Engineering)to NC programming--knowledge representation, generalized knowledge base, knowledge acquisition and knowledge reasoning, the system of intelligent NC programming for complex components of marine diesel has been built by means of the knowledge template and the UG/Open. The experiment results indicate that the NC program generated with high efficiency of NC programming by the system is accurate enough to meet the need of NC machining. Consequently, the automatization and intelligentization of NC programming has been presented, and the study is proved to be a successful attempt in the area of applying KBE to NC programming.

  12. Narrow gap mechanised arc welding in nuclear components manufactured by AREVA NP; Le soudage mecanise a l'arc en chanfrein etroit dans les constructions nucleaires realisees par AREVA NP

    Energy Technology Data Exchange (ETDEWEB)

    Peigney, A. [Departement Soudage AREVA Centre Technique - 71380 Saint-Marcel (France)

    2007-07-01

    Nuclear components require welds of irreproachable and reproducible quality. Moreover, for a given welding process, productivity requirements lead to reduce the volume of deposited metal and thus to use narrow gap design. In the shop, narrow gap Submerged Arc Welding process (SAW) is currently used on rotating parts in flat position for thicknesses up to 300 mm. Welding is performed with one or two wires in two passes per layer. In Gas Tungsten Arc Welding process (GTAW), multiple applications can be found because this process presents the advantage of allowing welding in all positions. Welding is performed in one or two passes per layer. The process is used in factory and on the nuclear sites for assembling new components but also for replacing components and for repairs. Presently, an increase of productivity of the process is sought through the use of hot wire and/or two wires. Concerning Gas Metal Arc Welding process (GMAW), its use is growing for nuclear components, including narrow gap applications. This process, limited in its applications in the past on account of the defects it generated, draws benefit from the progress of the welding generators. Then it is possible to use this efficient process for high security components such as those of nuclear systems. It is to be noted that the process is applicable in the various welding positions as it is the case for GTAW, while being more efficient than the latter. This paper presents the state of the art in the use of narrow gap mechanised arc welding processes by AREVA NP units. (author) [French] Les constructions nucleaires necessitent des soudures de qualite irreprochable et reproductible. Par ailleurs les imperatifs de productivite conduisent, pour un procede donne, a reduire le volume de metal a deposer et donc a utiliser des chanfreins etroits. En atelier, le soudage fil-flux en chanfrein etroit est couramment utilise sur des pieces tournantes en position a plat pour des epaisseurs atteignant 300 mm. On

  13. Experiment data report for Semiscale MOD-2A Natural-Circulation Test Series (tests S-NC-8B and S-NC-9)

    International Nuclear Information System (INIS)

    This report presents test data recorded for Tests S-NC-8B and S-NC-9 of the Semiscale Mod-2A Natural Circulation Test Series. These tests are part of a series of Semiscale tests that investigate the thermal-hydraulic phenomena resulting from operational transients involving loss of mechanical primary coolant circulation in a pressurized water reactor. Both tests also simulated a loss-of-coolant accident resulting from a 0.4% communicative cold-leg break. These tests provide experimental data to develop and assess the analytical capability of computer models used to predict the results of small-break loss-of-coolant accidents or operational transients involving the loss of primary pumping ability. The primary objective of Tests S-NC-8B and S-NC-9 was to experimentally characterize the thermal-hydraulic behavior of a system during single-phase, two-phase, and reflux natural circulation conditions experienced in the course of an integral small break with and without the presence of emergency core cooling water. Of special interest were the effects on single-phase natural circulation flow caused by changes in core power, primary pressure, and external heater power. This report presents the uninterpreted data from Tests S-NC-8B and S-NC-9 for future analysis. The data, presented as graphs in engineering units, have been analyzed only to the extent necessary to ensure that they are reasonable and consistent

  14. 33 CFR 165.T05-0091 - Safety Zone; Alligator River, NC.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety Zone; Alligator River, NC... Safety Zone; Alligator River, NC. (a) Definitions. For the purposes of this section, Captain of the Port... on the waters of the Alligator River centered at (35°54′3″ N/076°00′25″ W) a position directly...

  15. Anion-Dependent Aggregate Formation and Charge Behavior of Colloidal Fullerenes (n-C60)

    Science.gov (United States)

    The fate and transport of colloidal fullerenes (n-C60) in the environment is likely to be guided by electrokinetic and aggregation behavior. In natural water bodies inorganic ions exert significant effects in determining the size and charge of n-C60 nanoparticles. Although the ef...

  16. Nucleic Acid Chaperone Activity of HIV-1 NC Proteins Investigated by Single Molecule DNA Stretching

    Science.gov (United States)

    Williams, Mark C.; Gorelick, Robert J.; Musier-Forsyth, Karin; Bloomfield, Victor A.

    2002-03-01

    HIV-1 Nucleocapsid Protein (NC) is a nucleic acid chaperone protein that is responsible for facilitating numerous nucleic acid rearrangements throughout the reverse transcription cycle of HIV-1. To understand the mechanism of NC’s chaperone function, we carried out single molecule DNA stretching studies in the presence of NC and mutant forms of NC. Using an optical tweezers instrument, we stretch single DNA molecules from the double-stranded helical state to the single-stranded (coil) state. Based on the observed cooperativity of DNA force-induced melting, we find that the fraction of melted base pairs at room temperature is increased dramatically in the presence of NC. Thus, upon NC binding, increased thermal fluctuations cause continuous melting and reannealing of base pairs so that DNA strands are able to rapidly sample configurations in order to find the lowest energy state. While NC destabilizes the double-stranded form of DNA, a mutant form of NC that lacks the zinc finger structures does not. DNA stretching experiments carried out in the presence of NC variants containing more subtle changes in the zinc finger structures were conducted to elucidate the contribution of each individual finger to NC’s chaperone activity, and these results will be reported.

  17. 46 CFR 7.60 - Cape Fear, NC to Sullivans Island, SC.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false Cape Fear, NC to Sullivans Island, SC. 7.60 Section 7.60... Atlantic Coast § 7.60 Cape Fear, NC to Sullivans Island, SC. (a) A line drawn from the southernmost... Buoy “2CF”); thence to Oak Island Light. (b) A line drawn from the southernmost extremity of...

  18. 78 FR 42011 - Drawbridge Operation Regulation; The Straights, Harkers Island, NC

    Science.gov (United States)

    2013-07-15

    ... SECURITY Coast Guard 33 CFR Part 117 Drawbridge Operation Regulation; The Straights, Harkers Island, NC... 70/Harkers Island Bridge, across The Straights, mile 0.6, Harkers Island, NC. This deviation is necessary to facilitate coupling repair on the Route 70/ Harkers Island Bridge. This temporary...

  19. 77 FR 32394 - Drawbridge Operation Regulation; The Straights, Harkers Island, NC

    Science.gov (United States)

    2012-06-01

    ... SECURITY Coast Guard 33 CFR Part 117 Drawbridge Operation Regulation; The Straights, Harkers Island, NC... operation of the Route 70/Harkers Island Bridge across The Straights, at Harkers Island, NC. The deviation...) owns and operates the swing span of the Route 70/Harkers Island Bridge across The Straights, in...

  20. Renormalization of the baryon axial vector current in large-Nc chiral perturbation theory

    International Nuclear Information System (INIS)

    The baryon axial vector current is considered within the combined framework of large-Nc baryon chiral perturbation theory (where Nc is the number of colors) and the baryon axial vector couplings are extracted. Loop graphs with octet and decuplet intermediate states are systematically incorporated into the analysis

  1. Subleading-Nc corrections in non-linear small-x evolution

    International Nuclear Information System (INIS)

    We explore the subleading-Nc corrections to the large-Nc Balitsky-Kovchegov (BK) evolution equation by comparing its solution to that of the all-Nc Jalilian-Marian-Iancu-McLerran-Weigert-Leonidov-Kovner (JIMWLK) equation. In earlier simulations it was observed that the difference between the solutions of JIMWLK and BK is unusually small for a quark dipole scattering amplitude, of the order of 0.1%, which is two orders of magnitude smaller than the naively expected 1/Nc2∼11%. In this paper we argue that this smallness is not accidental. We provide analytical arguments showing that saturation effects and correlator coincidence limits fixed by group theory constraints conspire with the particular structure of the dipole kernel to suppress subleading-Nc corrections reducing the difference between the solutions of JIMWLK and BK to 0.1%. We solve the JIMWLK equation with improved numerical accuracy and verify that the remaining 1/Nc corrections, while small, still manage to slow down the rapidity-dependence of JIMWLK evolution compared to that of BK. We demonstrate that a truncation of JIMWLK evolution in the form of a minimal Gaussian generalization of the BK equation captures some of the remaining 1/Nc contributions leading to an even better agreement with JIMWLK evolution. As the 1/Nc corrections to BK include multi-reggeon exchanges one may conclude that the net effect of multi-reggeon exchanges on the dipole amplitude is rather small.

  2. NP is not AL and P is not NC is not NL is not L

    CERN Document Server

    Kobayashi, Koji

    2011-01-01

    This paper talk about that NP is not AL = P, P is not NC, NC is not NL, and NL is not L. The point about this paper is the dependent relation of the problem that need other problem's result to compute it. I show the structure of depend relation that could divide each coputation classes.

  3. Concept of automatic programming of NC machine for metal plate cutting by genetic algorithm method

    Directory of Open Access Journals (Sweden)

    B. Vaupotic

    2005-12-01

    Full Text Available Purpose: In this paper the concept of automatic programs of the NC machine for metal plate cutting by genetic algorithm method has been presented.Design/methodology/approach: The paper was limited to automatic creation of NC programs for two-dimensional cutting of material by means of adaptive heuristic search algorithms.Findings: Automatic creation of NC programs in laser cutting of materials combines the CAD concepts, the recognition of features and creation and optimization of NC programs. The proposed intelligent system is capable to recognize automatically the nesting of products in the layout, to determine the incisions and sequences of cuts forming the laid out products. Position of incisions is determined at the relevant places on the cut. The system is capable to find the shortest path between individual cuts and to record the NC program.Research limitations/implications: It would be appropriate to orient future researches towards conceiving an improved system for three-dimensional cutting with optional determination of positions of incisions, with the capability to sense collisions and with optimization of the speed and acceleration during cutting.Practical implications: The proposed system assures automatic preparation of NC program without NC programer.Originality/value: The proposed concept shows a high degree of universality, efficiency and reliability and it can be simply adapted to other NC-machines.

  4. DIWA trademark. AREVA's approach of intelligent computer-aided support of water chemistry monitoring in power plants

    International Nuclear Information System (INIS)

    The complexity of power plant operation makes stringent demands on the chemical quality of the coolant in process systems and loops. Optimal water chemistry ensures high corrosion resistance of these systems and is thus essential for safe and economic long term plant operation. The market offers a huge variety of commercial software packages for water chemistry control. Most of these computer programs have to be considered as data analysis or, respectively, data acquisition programs. Some of them require manual data input (Laboratory Information Management Systems), others are capable of performing a fully automated data acquisition. However, the plant operator typically is left alone with the actual interpretation of all collected and validated data, which would be the main characteristic feature of an analysis (or monitoring) system. The data validation is typical being performed by means of numerical methods in the broadest sense. This activity requires a long working experience and specific skills by the plant chemistry operator. True diagnostic systems need to be significantly more advanced. They contain the capability of data interpretation and derivation of specific diagnoses. This is combined with additional explanations on how the diagnoses were derived. Additionally, further recommendations are offered on how to proceed to reach the normal operational behavior as soon as possible. AREVA's DIWA trademark system features a fuzzy logic expert system that is based on expert knowledge. It is built on symptoms, which are combined in rules as part of the fuzzy tool set. These components can be edited without programming knowledge, which significantly reduces training efforts. It makes the system more robust, more compact and simpler compared to other so-called expert systems. DIWA trademark represents the knowledge in a natural way, in which other conventional expert system may have difficulties or need a larger set of rule algorithms. (orig.)

  5. Baryon wave function in large-Nc QCD: universality, nonlinear evolution equation and asymptotic limit

    CERN Document Server

    Pobylitsa, P V

    2004-01-01

    The 1/Nc expansion is formulated for the baryon wave function in terms of a specially constructed generating functional. The leading order of this 1/Nc expansion is universal for all low lying baryons [including the O(1/Nc)and O(1)excited resonances] and for baryon-meson scattering states. A nonlinear evolution equation of Hamilton-Jacobi type is derived for the generating functional describing the baryon distribution amplitude in the large-Nc limit. In the asymptotic regime this nonlinear equation is solved analytically. The anomalous dimensions of the leading twist baryon operators diagonalizing the evolution are computed analytically up to the next-to-leading order of the 1/Nc expansion.

  6. Benchmarking of AREVA BWR FDIC-PEZOG model against first BFE3 cycle 15 application of On-Line NobleChem results

    International Nuclear Information System (INIS)

    The combination of AREVA's BWR FDIC-PEZOG tools allows the calculation of the total liftoff as a measure of fuel performance and a risk indicator for fuel reliability. The AREVA BWR FDIC tool is a crud modeling tool. The PEZOG tool models the platinum-enhanced zirconium oxide growth of fuel cladding when exposed to platinum during operation. Continuous effort to improve these tools used for the total liftoff calculations is illustrated by the benchmarking of the tools after the application of On-Line NobleChemTM at TVA Browns Ferry Unit 3 during Cycle 15. A set of runs using the modified FDIC-PEZOG model and actual plant water chemistry for Cycle 15 and partial data for Cycle 16 were performed. The updated results' deposit thickness and deposit composition predictions for EOC15 were compared to the measured data from EOC15 and are presented in this paper. The updated predicted deposit thickness matched the actual, measured value exactly. Predicted deposit composition near the fuel rod boundary, nearer to the bulk reactor water, and as an averaged deposit, as presented in the paper, compared extremely well with the measured data at EOC15. The updated AREVA methodology resulted in lower fuel oxide thickness predictions over the life of the fuel as compared to the initial evaluations for BFE3 by incorporating more recent experimental data on the thermal conductivity of zirconia; unnecessary conservatism in the prediction of the fuel oxide thickness over the life of the fuel was removed in the improved model. (authors)

  7. Optimalizace NC programu pomocí CAD/CAM software

    OpenAIRE

    Paseka, Jan

    2014-01-01

    Cílem této diplomové práce je návrh úsporných opatření v procesu technologické přípravy výroby průmyslového podniku. V první části je zpracován obecný teoretický rozbor součástkové základny a stávajících NC programů. Na základě těchto poznatků a provedené analýzy byly stanoveny návrhy optimalizace popsané ve druhé části. Díky těmto návrhům dochází při jejich plné implementaci k úspoře časových nároků a finančních prostředků potřebných pro zavedení prototypového výrobku do sériové produkce....

  8. A hybrid approach to automatic generation of NC programs

    Directory of Open Access Journals (Sweden)

    G. Payeganeh

    2005-12-01

    Full Text Available Purpose: This paper describes AGNCP, an intelligent system for integrating commercial CAD and CAM systems for 2.5D milling operations at a low cost.Design/methodology/approach: It deals with different machining problems with the aid of two expert systems. It recognizes machining features, determines required machining process plans, cutting tools and parameters necessary for generation of NC programs.Findings: The system deals with different machining problems with the aid of two expert systems. The first communicates with CAD system for recognizing machining features. It is developed in LISP as machining features can be properly represented by LISP codes is ideal for manipulating lists and input data. The second expert system requires extensive communications with several databases for retrieving tooling and machining information and VP-Expert shell was found to be the most suitable package to perform this task.Research limitations/implications: 2.5D milling covers a wide range of operations. However, work is in progress cover 3D milling operations. The system can also be modified to be used for other activities such as turning, flame cutting, electro discharge machining (EDM, punching, etc.Practical implications: Use of AGNCP resulted in improved efficiency, noticeable time savings, and elimination of the need for expert process planners.Originality/value: The paper describes a method for eliminating the need for extensive user intervention for CAD/CAM integration.

  9. Subtractive hybridization identifies novel differentially expressed ncRNA species in EBV-infected human B cells

    OpenAIRE

    Mrázek, Jan; Kreutmayer, Simone B.; Grässer, Friedrich A; Polacek, Norbert; Hüttenhofer, Alexander

    2007-01-01

    Non-protein-coding RNAs (ncRNAs) fulfill a wide range of cellular functions from protein synthesis to regulation of gene expression. Identification of novel regulatory ncRNAs by experimental approaches commonly includes the generation of specialized cDNA libraries encoding small ncRNA species. However, such identification is severely hampered by the presence of constitutively expressed and highly abundant ‘house-keeping’ ncRNAs, such as ribosomal RNAs, small nuclear RNAs or transfer RNAs. We ...

  10. Small ncRNA transcriptome analysis from Aspergillus fumigatus suggests a novel mechanism for regulation of protein synthesis

    OpenAIRE

    Jöchl, Christoph; Rederstorff, Mathieu; Hertel, Jana; Stadler, Peter F.; Hofacker, Ivo L.; Schrettl, Markus; Haas, Hubertus; Hüttenhofer, Alexander

    2008-01-01

    Small non-protein-coding RNAs (ncRNAs) have systematically been studied in various model organisms from Escherichia coli to Homo sapiens. Here, we analyse the small ncRNA transcriptome from the pathogenic filamentous fungus Aspergillus fumigatus. To that aim, we experimentally screened for ncRNAs, expressed under various growth conditions or during specific developmental stages, by generating a specialized cDNA library from size-selected small RNA species. Our screen revealed 30 novel ncRNA c...

  11. Low friction and wear resistant nanocomposite nc-MeC/a-C and nc-MeC/a-C:H coatings

    Directory of Open Access Journals (Sweden)

    K. Włodarczyk

    2009-12-01

    Full Text Available Purpose: Elaboration of nanocomposite, low friction and wear resistant coatings in order to increase the life-time and reliability of friction couples especially in aviation industry, car industry and of cutting tools. These coatings consist of nanocrystallites of chromium or titanium carbides built into amorphous carbon matrix.Design/methodology/approach: Coatings type nc-MeC/a-C and nc-MeC/a-C:H (where Me means Cr or Ti transition metal are deposited by a PVD method based on magnetron sputtering of pure Ti or Cr and pure graphite targets in the atmosphere of Ar or Ar+H2, respectively. The coatings are deposited onto the surface of quenched and tempered HSS steel Vanadis23 and diffusion hardened titanium alloy Ti6Al4V.Findings: Depending on deposition parameters, like the power ratio of transition metal to carbon targets or the substrate bias, it is possible to obtain different morphological and tribological properties of coatings. These latter are very important for designing friction couples in mechanical applications.Originality/value: The coatings are characterized of very low friction coefficient (0.06 for nc-TiC/a-C and 0.08 for nc-TiC/a-C:H and nc-CrC/a-C:H coatings.

  12. A tale of two skyrmions: The nucleon's strange quark content in different large Nc limits

    International Nuclear Information System (INIS)

    The nucleon's strange quark content comes from closed quark loops, and hence should vanish at leading order in the traditional large Nc (TLNC) limit. Quark loops are not suppressed in the recently proposed orientifold large Nc (OLNC) limit, and thus the strange quark content should be non-vanishing at leading order. The Skyrme model is supposed to encode the large Nc behavior of baryons, and can be formulated for both of these large Nc limits. There is an apparent paradox associated with the large Nc behavior of strange quark matrix elements in the Skyrme model. The model only distinguishes between the two large Nc limits via the Nc scaling of the couplings and the Witten-Wess-Zumino term, so that a vanishing leading order strange matrix element in the TLNC limit implies that it also vanishes at leading order in the OLNC limit, contrary to the expectations based on the suppression/non-suppression of quark loops. The resolution of this paradox is that the Skyrme model does not include the most general type of meson-meson interaction and, in fact, contains no meson-meson interactions which vanish for the TLNC limit but not the OLNC. The inclusion of such terms in the model yields the expected scaling for strange quark matrix elements

  13. Directly Generating the NC Machining Program from AutoCAD Graph

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    One kind of auto-programming method directly gener at ing the NC machining program by AutoCAD graph is discussed in this article. Firs tly, the article discusses the open type graphic interface of AutoCAD. Then the graphic export among the AutoCAD, the adding of process information and the data storage, as well as technology of generating NC program has been introduced . Finally, a NC auto-programming system GAPS based on AutoCAD graph is develope d. The tendency of auto-programming is graphic auto-pro...

  14. Naming 'junk': Human non-protein coding RNA (ncRNA) gene nomenclature

    OpenAIRE

    Wright Mathew W; Bruford Elspeth A

    2011-01-01

    Abstract Previously, the majority of the human genome was thought to be 'junk' DNA with no functional purpose. Over the past decade, the field of RNA research has rapidly expanded, with a concomitant increase in the number of non-protein coding RNA (ncRNA) genes identified in this 'junk'. Many of the encoded ncRNAs have already been shown to be essential for a variety of vital functions, and this wealth of annotated human ncRNAs requires standardised naming in order to aid effective communica...

  15. ViRBase: a resource for virus–host ncRNA-associated interactions

    OpenAIRE

    Li, Yanhui; Wang, Changliang; Miao, Zhengqiang; Bi, Xiaoman; Wu, Deng; Jin, Nana; WANG, LIQIANG; Wu, Hao; Qian, Kun; Li, Chunhua; Zhang, Ting; Zhang, Chunrui; Yi, Ying; Lai, Hongyan; Hu, Yongfei

    2014-01-01

    Increasing evidence reveals that diverse non-coding RNAs (ncRNAs) play critically important roles in viral infection. Viruses can use diverse ncRNAs to manipulate both cellular and viral gene expression to establish a host environment conducive to the completion of the viral life cycle. Many host cellular ncRNAs can also directly or indirectly influence viral replication and even target virus genomes. ViRBase (http://www.rna-society.org/virbase) aims to provide the scientific community with a...

  16. A comparative genome-wide study of ncRNAs in trypanosomatids

    Directory of Open Access Journals (Sweden)

    Wachtel Chaim

    2010-11-01

    Full Text Available Abstract Background Recent studies have provided extensive evidence for multitudes of non-coding RNA (ncRNA transcripts in a wide range of eukaryotic genomes. ncRNAs are emerging as key players in multiple layers of cellular regulation. With the availability of many whole genome sequences, comparative analysis has become a powerful tool to identify ncRNA molecules. In this study, we performed a systematic genome-wide in silico screen to search for novel small ncRNAs in the genome of Trypanosoma brucei using techniques of comparative genomics. Results In this study, we identified by comparative genomics, and validated by experimental analysis several novel ncRNAs that are conserved across multiple trypanosomatid genomes. When tested on known ncRNAs, our procedure was capable of finding almost half of the known repertoire through homology over six genomes, and about two-thirds of the known sequences were found in at least four genomes. After filtering, 72 conserved unannotated sequences in at least four genomes were found, 29 of which, ranging in size from 30 to 392 nts, were conserved in all six genomes. Fifty of the 72 candidates in the final set were chosen for experimental validation. Eighteen of the 50 (36% were shown to be expressed, and for 11 of them a distinct expression product was detected, suggesting that they are short ncRNAs. Using functional experimental assays, five of the candidates were shown to be novel H/ACA and C/D snoRNAs; these included three sequences that appear as singletons in the genome, unlike previously identified snoRNA molecules that are found in clusters. The other candidates appear to be novel ncRNA molecules, and their function is, as yet, unknown. Conclusions Using comparative genomic techniques, we predicted 72 sequences as ncRNA candidates in T. brucei. The expression of 50 candidates was tested in laboratory experiments. This resulted in the discovery of 11 novel short ncRNAs in procyclic stage T. brucei

  17. AREVA Fatigue Concept (AFC) - an integrated and multi-disciplinary approach to the fatigue assessment of NPP components

    International Nuclear Information System (INIS)

    The AREVA fatigue concept (AFC) provides for a multi-step and multi-disciplinary process (process engineering, fatigue monitoring, fatigue analyses, etc.) against fatigue in the design and construction phase and also during the entire operation cycle of nuclear power plants (NPPs). The ensuing fatigue analyses are based on the real operational loads measured continuously on site in the plant. The entire process of fatigue design is based on an installed fatigue monitoring system, the FAMOS. This way, realistic load data are available. This system enables a reliable and realistic fatigue assessment of stressed components. FAMOS, as the central module of the AFC, contributes critically to the management of the component ageing problem and enables the identification of operating modes unfavorable to fatigue. Moreover, code conforming fatigue usage factors can be determined for the lifetime of the plant. The direct processing of the measured temperatures is immediately used for a fast fatigue evaluation (FFE). By means of FFE, the inverse thermal field at the inner surface of the pipe is calculated and transferred from measuring location to the component of concern for stress calculation. Then, a real time fatigue evaluation of the cumulative usage factor (CUF) can be performed after every operational cycle. This procedure is highly automated and gives a first fatigue status of the power plant. In the framework of the periodic safety inspection (PSI), a detailed fatigue calculation conforming to the code rules is carried out in order to determine the current state of the plant. This detailed fatigue check is based on the real loads (specification of thermal transient loads) and finite element analyses (FEA) in connection with the local strain approach to design against fatigue. These FEA always include transient thermal determination of the temperature field and subsequent determination of stresses and strains. The latter analyses may consist of simplified elastic or

  18. Sources of suspended sediment in the Lower Roanoke River, NC

    Science.gov (United States)

    Jalowska, A. M.; McKee, B. A.; Rodriguez, A. B.; Laceby, J. P.

    2015-12-01

    The Lower Roanoke River, NC, extends 220 km from the fall line to the bayhead delta front in the Albemarle Sound. The Lower Roanoke is almost completely disconnected from the upper reaches by a series of dams, with the furthest downstream dam located at the fall line. The dams effectively restrict the suspended sediment delivery from headwaters, making soils and sediments from the Lower Roanoke River basin, the sole source of suspended sediment. In flow-regulated rivers, bank erosion, especially mass wasting, is the major contributor to the suspended matter. Additional sources of the suspended sediment considered in this study are river channel, surface soils, floodplain surface sediments, and erosion of the delta front and prodelta. Here, we examine spatial and temporal variations in those sources. This study combined the use of flow and grain size data with a sediment fingerprinting method, to examine the contribution of surface and subsurface sediments to the observed suspended sediment load along the Lower Roanoke River. The fingerprinting method utilized radionuclide tracers 210Pb (natural atmospheric fallout), and 137Cs (produced by thermonuclear bomb testing). The contributions of surface and subsurface sources to the suspended sediment were calculated with 95% confidence intervals using a Monte-Carlo numerical mixing model. Our results show that with decreasing river slope and changing hydrography along the river, the contribution of surface sediments increases and becomes a main source of sediments in the Roanoke bayhead delta. At the river mouth, the surface sediment contribution decreases and is replaced by sediments eroded from the delta front and prodelta. The area of high surface sediment contribution is within the middle and upper parts of the delta, which are considered net depositional. Our study demonstrates that floodplains, often regarded to be a sediment sink, are also a sediment source, and they should be factored into sediment, carbon and

  19. The NC16A Domain of Collagen XVII Plays a Role in Triple Helix Assembly and Stability*

    OpenAIRE

    Van den Bergh, Françoise; Fu, Chang-Ling; Olague-Marchan, Monica; Giudice, George J.

    2006-01-01

    Collagen XVII/BP180 is a transmembrane constituent of the epidermal anchoring complex. To study the role of its non-collagenous linker domain, NC16A, in protein assembly and stability, we analyzed the following recombinant proteins: the collagen XVII extracellular domain with or without NC16A, and a pair of truncated proteins comprising the COL15-NC15 stretch expressed with or without NC16A. All four proteins were found to exist as stable collagen triple helices; however, the two missing NC16...

  20. NcRNA-microchip analysis: A novel approach to identify differential expression of non-coding RNAs

    OpenAIRE

    Hutzinger, Roland; Mrázek, Jan; Vorwerk, Sonja; Hüttenhofer, Alexander

    2010-01-01

    Epstein-Barr virus (EBV) infection of human B cells requires the presence of non-coding RNAs (ncRNAs), which regulate expression of viral and host genes. To identify differentially expressed regulatory ncRNAs involved in EBV infection, a specialized cDNA library, enriched for ncRNAs derived from EBV-infected cells, was subjected to deep-sequencing. From the deep-sequencing analysis, we generated a custom-designed ncRNA-microchip to investigate differential expression of ncRNA candidates. By t...

  1. Holographic realization of large-Nc orbifold equivalence with non-zero chemical potential

    CERN Document Server

    Hanada, Masanori; Karch, Andreas; Yaffe, Laurence G

    2012-01-01

    Recently, it has been suggested that large-Nc orbifold equivalences may be applicable to certain theories with chemical potentials, including QCD, in certain portions of their phase diagram. When valid, such an equivalence offers the possibility of relating large-Nc QCD at non-zero baryon chemical potential, a theory with a complex fermion determinant, to a related theory whose fermion determinant is real and positive. In this paper, we provide a test of this large Nc equivalence using a holographic realization of a supersymmetric theory with baryon chemical potential and a related theory with isospin chemical potential. We show that the two strongly-coupled, large-Nc theories are equivalent in a large region of the phase diagram.

  2. EnviroAtlas -Durham, NC- One Meter Resolution Urban Area Land Cover Map (2010)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EnviroAtlas Durham, NC land cover map was generated from USDA NAIP (National Agricultural Imagery Program) four band (red, green, blue and near infrared) aerial...

  3. Investigation on the foaming behaviors of NC-based gun propellants

    Directory of Open Access Journals (Sweden)

    Yu-xiang Li

    2014-09-01

    Full Text Available To prepare the porous NC-based (nitrocellulose-based gun propellants, the batch foaming process of using supercritical CO2 as the physical blowing agent is used. The solubilities of CO2 in the single-base propellants and TEGDN (trimethyleneglycol dinitrate propellants are measured by the gravimetric method, and SEM (scanning electron microscope is used to observe the morphology of foamed propellants. The result shows that a large amount of CO2 could be dissolved in NC-based propellants. The experimental results also reveal that the energetic plasticizer TEGDN exerts an important influence on the pore structure. The triaxial tensile failure mechanism for solid-state nucleation is used to explain the nucleation of NC-based propellants in the solid state. Since some specific foaming behaviors of NC-based propellants can not be explained by the failure mechanism, a solid-state nucleation mechanism which revises the triaxial tensile failure mechanism is proposed and discussed.

  4. Bidirectional expression of long ncRNA/protein-coding gene pairs in cancer.

    Science.gov (United States)

    Albrecht, Anne-Susann; Ørom, Ulf Andersson

    2016-05-01

    Bidirectional initiation of transcription by RNA polymerase II occurs prevalently at active promoters during protein-coding gene (PCG) expression. Upstream, antisense noncoding RNAs (ncRNAs) of differing lengths, stabilities and processings are being expressed from these promoters in concert with downstream, processive messenger RNA transcription. Although abundantly detected, the functional role and regulatory capacity of such transcripts have only been determined for individual cases. Long ncRNAs in general are reportedly able to regulate all steps of the gene expression process. Therefore, to get insight into the functionality of long ncRNAs transcribed bidirectionally from cancer-associated PCGs is of interest, as expression changes of tumor suppressor genes and oncogenes are prevalent in cancer.Here, we review the sources and characteristics of antisense transcription occurring at PCG loci in the human genome, and focus on the functional impact of bidirectional long ncRNA expression at cancer-associated PCGs. PMID:26578749

  5. Environmental effects on electron spin relaxation in N@C60

    CERN Document Server

    Morton, J J L; Ardavan, A; Porfyrakis, K; Lyon, S A; Briggs, G A D; Morton, John J. L.; Tyryshkin, Alexei M.; Ardavan, Arzhang; Porfyrakis, Kyriakos

    2006-01-01

    We examine environmental effects of surrounding nuclear spins on the electron spin relaxation of the N@C60 molecule (which consists of a nitrogen atom at the centre of a fullerene cage). Using dilute solutions of N@C60 in regular and deuterated toluene, we observe and model the effect of translational diffusion of nuclear spins of the solvent molecules on the N@C60 electron spin relaxation times. We also study spin relaxation in frozen solutions of N@C60 in CS2, to which small quantities of a glassing agent, S2Cl2 are added. At low temperatures, spin relaxation is caused by spectral diffusion of surrounding nuclear (35,37)Cl spins in the S2Cl2, but nevertheless, at 20 K, T2 times as long as 0.23 ms are observed

  6. EnviroAtlas -Durham, NC- One Meter Resolution Urban Area Land Cover Map (2010) Web Service

    Data.gov (United States)

    U.S. Environmental Protection Agency — This EnviroAtlas web service supports research and online mapping activities related to EnviroAtlas (https://www.epa.gov/enviroatlas ). The EnviroAtlas Durham, NC...

  7. De Novo Discovery of Structured ncRNA Motifs in Genomic Sequences

    DEFF Research Database (Denmark)

    Ruzzo, Walter L; Gorodkin, Jan

    2014-01-01

    De novo discovery of "motifs" capturing the commonalities among related noncoding ncRNA structured RNAs is among the most difficult problems in computational biology. This chapter outlines the challenges presented by this problem, together with some approaches towards solving them, with an emphas...... on an approach based on the CMfinder CMfinder program as a case study. Applications to genomic screens for novel de novo structured ncRNA ncRNA s, including structured RNA elements in untranslated portions of protein-coding genes, are presented.......De novo discovery of "motifs" capturing the commonalities among related noncoding ncRNA structured RNAs is among the most difficult problems in computational biology. This chapter outlines the challenges presented by this problem, together with some approaches towards solving them, with an emphasis...

  8. EnviroAtlas - Durham, NC - Tree Cover Configuration and Connectivity, Water Background Web Service

    Data.gov (United States)

    U.S. Environmental Protection Agency — This EnviroAtlas web service supports research and online mapping activities related to EnviroAtlas (https://www.epa.gov/enviroatlas ). The EnviroAtlas Durham, NC...

  9. SIMULATION SYSTEM FOR FIVE-AXIS NC MACHINING USING GENERAL CUTTING TOOL

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    A simulation system for five-axis NC machining using general cutting tools is presented. This system differs from other simulation system in that it not only focuses on the geometric simulation but also focuses on the collision detection which is usually not included in NC machining simulation. Besides all of these, estimating cutting forces is also discussed. In order to obtain high efficiency, all algorithms use swept volume modeling technique, so the simulation system is compact and can be performed efficiently.

  10. Anion-Dependent Aggregate Formation and Charge Behavior of Colloidal Fullerenes (n-C60)

    Science.gov (United States)

    Mukherjee, B.; Weaver, J. W.

    2009-12-01

    The fate and transport of colloidal fullerenes (n-C60) in the environment are likely to be guided by their electrokinetic and aggregation behavior. In natural water bodies inorganic ions exert significant effects in determining the size and charge of dispersed n-C60. Although the effects of cations on the behavior of n-C60 have been studied extensively; studies on the effect of anions are relatively few and thus were the focus of our investigation. The effects of anions (e.g., Cl- , SO42-) on average aggregate size (DH) and zeta potential (ZP) of n-C60 were found to be absent in presence of monovalent cations (e.g., Na+) over the tested range of pH (3-to-12) and ionic strength (0-to-20 mM). Similar observations were noted in the presence of multivalent cations (e.g., Mg2+) near acidic and neutral pH conditions. However, under alkaline conditions (pH~10) a strong anion-dependent reversal of surface charge was noted. The ZP of n-C60 changed from -65 mV, when dispersed in DI water, to +4 mV and +40 mV in the presence of SO42- and Cl-, respectively in a 10mM salt concentration (i.e., MgCl2 and MgSO4). The corresponding DH of the dispersed n-C60 changed simultaneously from 115 nm, in DI water, to 1450 nm and 225 nm for the MgSO4 and MgCl2 electrolytes. These findings provide a better understanding of interfacial interaction characteristics of n-C60 NPs, and may lead to remediation strategies for n-C60 NPs in the environment.

  11. Climate Analysis in IOWA Using XML and Spatiotemporal Dataset-NC94

    OpenAIRE

    Sugam Sharma; Shashi Gadia; Niranjan Kumar; Valliappan Narayanan; Xinyuan Zhao

    2010-01-01

    NC94 is a spatiotemporal (agricultural) dataset of North Central Region in USA and vastly used in variousresearch domains. In this research work we exploit XML on NC94 dataset to assess the impact of extremetemperatures in Iowa. The variation in climate is one of the factors that affect human life. The results of thisresearch help to identify the counties with suitable modest climate with least variations.

  12. Colorless quark-gluon gas in the limit of large Nc

    International Nuclear Information System (INIS)

    A quark-gluon gas in a finite volume with global internal symmetry group SU(Nc) on the states of which the condition of being colorless is imposed is studied in the limit Nc → ∞. It is shown that without allowance for the conservation law of the baryon charge this system undergoes a phase transition of the third kind. However, in the more realistic situation in which this conservation law is taken into account there is no phase transition

  13. NPInter v2.0: an updated database of ncRNA interactions

    OpenAIRE

    Yuan, Jiao; Wei WU; Xie, Chaoyong; Zhao, Guoguang; Zhao, Yi; Chen, Runsheng

    2013-01-01

    NPInter (http://www.bioinfo.org/NPInter) is a database that integrates experimentally verified functional interactions between noncoding RNAs (excluding tRNAs and rRNAs) and other biomolecules (proteins, RNAs and genomic DNAs). Extensive studies on ncRNA interactions have shown that ncRNAs could act as part of enzymatic or structural complexes, gene regulators or other functional elements. With the development of high-throughput biotechnology, such as cross-linking immunoprecipitation and hig...

  14. Design earthquakes for ITER in Europe at Cadarache. Comparison of the semi-empirical methods used according to the French regulation and the seismic probabilistic assessment of the site

    International Nuclear Information System (INIS)

    Input requirements and assumptions for ITER consider that an infrequent, severe earthquake (called SL-2) which, although unlikely to occur during the lifetime of the facility, is assessed to demonstrate adequate protection of the public. This earthquake is assumed to have a return period of 10,000 years. An investment protection level or inspection level (where all Structures, Systems and Components are safe) with a peak ground acceleration (pga) at 0.5 m/s2 is also considered. As a basis, orders of magnitude of consequences, if no countermeasures were taken, are given. The European site proposed for ITER is situated in the South of France, 40 km North-East of Aix-en-Provence, in a low to moderate seismic area according to the Global Seismic Hazard Map (GSHAP Group 1999). The-tokamak building would be implemented on good bedrock made of limestone with a shear wave velocity of over 1,300 m/s. Four aspects are discussed: regulation, implementation of this regulation for the proposed site (site geology, tectonic, seismo-tectonic), a probabilistic seismic hazard assessment of the site has been performed using a methodology which considers uncertainties (this work has been developed by the team which had contributed to large parts of the GSHAP map study), finally the fulfillment of the requirements and assumptions are discussed, according to IAEA guides for instance. As a conclusion of the studies the main characteristics of the Cadarache European site are discussed: as a reference the standardized 475 year mean return period hazard (i.e. 10 % of chance to occur in 50 years); 10,000 year return period in accordance with the ITER assumption. Preliminary studies have shown that the European site proposal will ensure a low level of project risk with respect to the seismic hazard. (authors)

  15. The baryon vector current in the combined chiral and 1/Nc expansions

    Energy Technology Data Exchange (ETDEWEB)

    Flores-Mendieta, Ruben; Goity, Jose L [JLAB

    2014-12-01

    The baryon vector current is computed at one-loop order in large-Nc baryon chiral perturbation theory, where Nc is the number of colors. Loop graphs with octet and decuplet intermediate states are systematically incorporated into the analysis and the effects of the decuplet-octet mass difference and SU(3) flavor symmetry breaking are accounted for. There are large-Nc cancellations between different one-loop graphs as a consequence of the large-Nc spin-flavor symmetry of QCD baryons. The results are compared against the available experimental data through several fits in order to extract information about the unknown parameters. The large-Nc baryon chiral perturbation theory predictions are in very good agreement both with the expectations from the 1/Nc expansion and with the experimental data. The effect of SU(3) flavor symmetry breaking for the |Delta S|=1 vector current form factors f1(0) results in a reduction by a few percent with respect to the corresponding SU(3) symmetric values.

  16. A novel denitrifying methanotroph of the NC10 phylum and its microcolony.

    Science.gov (United States)

    He, Zhanfei; Cai, Chaoyang; Wang, Jiaqi; Xu, Xinhua; Zheng, Ping; Jetten, Mike S M; Hu, Baolan

    2016-01-01

    The NC10 phylum is a candidate phylum of prokaryotes and is considered important in biogeochemical cycles and evolutionary history. NC10 members are as-yet-uncultured and are difficult to enrich, and our knowledge regarding this phylum is largely limited to the first species 'Candidatus Methylomirabilis oxyfera' (M. oxyfera). Here, we enriched NC10 members from paddy soil and obtained a novel species of the NC10 phylum that mediates the anaerobic oxidation of methane (AOM) coupled to nitrite reduction. By comparing the new 16S rRNA gene sequences with those already in the database, this new species was found to be widely distributed in various habitats in China. Therefore, we tentatively named it 'Candidatus Methylomirabilis sinica' (M. sinica). Cells of M. sinica are roughly coccus-shaped (0.7-1.2 μm), distinct from M. oxyfera (rod-shaped; 0.25-0.5 × 0.8-1.1 μm). Notably, microscopic inspections revealed that M. sinica grew in honeycomb-shaped microcolonies, which was the first discovery of microcolony of the NC10 phylum. This finding opens the possibility to isolate NC10 members using microcolony-dependent isolation strategies. PMID:27582299

  17. ncRNAclassifier: a tool for detection and classification of transposable element sequences in RNA hairpins

    Directory of Open Access Journals (Sweden)

    Tempel Sébastien

    2012-09-01

    Full Text Available Abstract Background Inverted repeat genes encode precursor RNAs characterized by hairpin structures. These RNA hairpins are then metabolized by biosynthetic pathways to produce functional small RNAs. In eukaryotic genomes, short non-autonomous transposable elements can have similar size and hairpin structures as non-coding precursor RNAs. This resemblance leads to problems annotating small RNAs. Results We mapped all microRNA precursors from miRBASE to several genomes and studied the repetition and dispersion of the corresponding loci. We then searched for repetitive elements overlapping these loci. We developed an automatic method called ncRNAclassifier to classify pre-ncRNAs according to their relationship with transposable elements (TEs. We showed that there is a correlation between the number of scattered occurrences of ncRNA precursor candidates and the presence of TEs. We applied ncRNAclassifier on six chordate genomes and report our findings. Among the 1,426 human and 721 mouse pre-miRNAs of miRBase, we identified 235 and 68 mis-annotated pre-miRNAs respectively corresponding completely to TEs. Conclusions We provide a tool enabling the identification of repetitive elements in precursor ncRNA sequences. ncRNAclassifier is available at http://EvryRNA.ibisc.univ-evry.fr.

  18. Silver Blaze Puzzle in 1/Nc Expansions of Cold and Dense QCD Matter

    CERN Document Server

    Armoni, Adi

    2014-01-01

    We consider quantum chromodynamics (QCD) with Nc colors and Nf quark flavors at finite quark chemical potential mu_q or isospin chemical potential mu_I. We specifically address the nature of the ``Silver Blaze'' behavior in the framework of 1/Nc expansion. Starting with the QCD partition function, we implement Veneziano's Nf/Nc expansion to identify the density onset. We find the baryon mass M_B and the pion mass m_pi appearing from different order of Veneziano's expansion. We argue that the confining properties are responsible for the Silver Blaze in the region of m_pi/2 < mu_q < M_B/Nc. We point out, however, that Veneziano's expansion brings about a puzzling subtlety along the same line as the baryon problem in finite-density quenched simulations. We emphasize that the large-Nc limit can allow for the physical ordering of M_B and m_pi thanks to the similarity to the quenched approximation, while the unphysical ghost quarks contaminate the baryon sector if Nc is finite. We also discuss the ``orientifo...

  19. The Dichotomous Nucleon: Some Radical Conjectures for the Large $\\Nc$ Limit

    CERN Document Server

    Hidaka, Yoshimasa; McLerran, Larry; Pisarski, Robert D

    2010-01-01

    We discuss some problems in the naive large Nc approximation for nucleons. As noted previously, a Skyrmion solution is susceptible to collapse. A natural scale for it to collapse to is r \\sim 1/fpi: since at large Nc, fpi \\sim Nc^1/2 Lambda_QCD, this is parametrically small in comparison to 1/Lambda_QCD. Quantum corrections to the pion sigma model become important at a scale \\sim 1/fpi. In a string vertex model of the baryon, this is also the typical scale over which the string vertex moves. The collapse of a Skyrmion to such a small size might solve some problems with the large Nc limit, especially the Goldberger-Treiman relation. We argue that most quarks bind into colored scalar diquarks, so that for odd Nc, the spin and isospin of the nucleon is carried by the lone, unpaired quark. The problems with the large Nc limit are resolved if the unpaired quark is in a spatial wavefunction orthogonal to the wavefunctions of the scalar diquarks. This could happen if the unpaired quark orbits at a size which is para...

  20. Naming 'junk': Human non-protein coding RNA (ncRNA gene nomenclature

    Directory of Open Access Journals (Sweden)

    Wright Mathew W

    2011-01-01

    Full Text Available Abstract Previously, the majority of the human genome was thought to be 'junk' DNA with no functional purpose. Over the past decade, the field of RNA research has rapidly expanded, with a concomitant increase in the number of non-protein coding RNA (ncRNA genes identified in this 'junk'. Many of the encoded ncRNAs have already been shown to be essential for a variety of vital functions, and this wealth of annotated human ncRNAs requires standardised naming in order to aid effective communication. The HUGO Gene Nomenclature Committee (HGNC is the only organisation authorised to assign standardised nomenclature to human genes. Of the 30,000 approved gene symbols currently listed in the HGNC database (http://www.genenames.org/search, the majority represent protein-coding genes; however, they also include pseudogenes, phenotypic loci and some genomic features. In recent years the list has also increased to include almost 3,000 named human ncRNA genes. HGNC is actively engaging with the RNA research community in order to provide unique symbols and names for each sequence that encodes an ncRNA. Most of the classical small ncRNA genes have now been provided with a unique nomenclature, and work on naming the long (> 200 nucleotides non-coding RNAs (lncRNAs is ongoing.

  1. Design and Investigation of SST/nc-Si:H/M (M = Ag, Au, Ni and M/nc-Si:H/M Multifunctional Devices

    Directory of Open Access Journals (Sweden)

    A. F. Qasrawi

    2013-01-01

    Full Text Available Hydrogenated nanocrystalline Silicon thin films prepared by the very high frequency chemical vapor deposition technique (VHF-CVD on stainless steel (SST substrates are used to design Schottky point contact barriers for the purpose of solar energy conversion and passive electronic component applications. In this process, the contact performance between SST and M (M = Ag, Au, and Ni and between Ag, Au, and Ni electrodes was characterized by means of current-voltage, capacitance-voltage, and light intensity dependence of short circuit ( current and open circuit voltage ( of the contacts. Particularly, the devices ideality factors, barrier heights were evaluated by the Schottky method and compared to the Cheung's. Best Schottky device performance with lowest ideality factor suitable for electronic applications was observed in the SST/nc-Si:H/Ag structure. This device reflects a of 229 mV with an of 1.6 mA/cm2 under an illumination intensity of ~40 klux. On the other hand, the highest being 9.0 mA/cm2 and the of 53.1 mV were observed for Ni/nc-Si:H/Au structure. As these voltages represent the maximum biasing voltage for some of the designed devices, the SST/nc-Si:H/M and M/nc-Si:H/M can be regarded as multifunctional self-energy that provided electronic devices suitable for active or passive applications.

  2. AREVA - 2012 Reference document

    International Nuclear Information System (INIS)

    After a presentation of the person responsible for this Reference Document, of statutory auditors, and of a summary of financial information, this report address the different risk factors: risk management and coverage, legal risk, industrial and environmental risk, operational risk, risk related to major projects, liquidity and market risk, and other risks (related to political and economic conditions, to Group's structure, and to human resources). The next parts propose information about the issuer, a business overview (markets for nuclear power and renewable energies, customers and suppliers, group's strategy, operations), a brief presentation of the organizational structure, a presentation of properties, plants and equipment (principal sites, environmental issues which may affect these items), analysis and comments on the group's financial position and performance, a presentation of capital resources, a presentation of research and development activities (programs, patents and licenses), a brief description of financial objectives and profit forecasts or estimates, a presentation of administration, management and supervision bodies, a description of the operation of corporate bodies, an overview of personnel, of principal shareholders, and of transactions with related parties, a more detailed presentation of financial information concerning assets, financial positions and financial performance. Addition information regarding share capital is given, as well as an indication of major contracts, third party information, available documents, and information on holdings

  3. Polarized photoluminescence of nc-Si–SiO{sub x} nanostructures

    Energy Technology Data Exchange (ETDEWEB)

    Michailovska, E. V.; Indutnyi, I. Z.; Shepeliavyi, P. E.; Sopinskii, N. V., E-mail: sopinsky@isp.kiev.ua, E-mail: sopinskyy@ua.fm [National Academy of Sciences of Ukraine, Lashkarev Institute of Semiconductor Physics (Ukraine)

    2016-01-15

    The effect of photoluminescence polarization memory in nc-Si–SiO{sub x} light-emitting structures containing Si nanoparticles (nc-Si) in an oxide matrix is for the first time studied. The polarization properties of continuous and porous nanostructures passivated in HF vapors (or solutions) are studied. It is established that the polarization memory effect is manifested only after treatment of the structures in HF. The effect is also accompanied by a shift of the photoluminescence peak to shorter wavelengths and by a substantial increase in the photoluminescence intensity. It is found that, in anisotropic nc-Si–SiO{sub x} samples produced by oblique deposition in vacuum, the degree of linear photoluminescence polarization in the sample plane exhibits a noticeable orientation dependence and correlates with the orientation of SiO{sub x} nanocolumns forming the structure of the porous layer. These effects are attributed to the transformation of symmetrically shaped Si nanoparticles into asymmetric elongated nc-Si particles upon etching in HF. In continuous layers, nc-Si particles are oriented randomly, whereas in porous structures, their preferential orientation coincides with the orientation of oxide nanocolumns.

  4. Link between the Potentially Hazardous Asteroid (86039) 1999 NC43 and the Chelyabinsk meteoroid tenuous

    CERN Document Server

    Reddy, Vishnu; Bottke, William F; Pravec, Petr; Sanchez, Juan A; Gary, Bruce L; Klima, Rachel; Cloutis, Edward A; Galád, Adrián; Guan, Tan Thiam; Hornoch, Kamil; Izawa, Matthew R M; Kušnirák, Peter; Corre, Lucille Le; Mann, Paul; Moskovitz, Nicholas; Skiff, Brian; Vraštil, Jan

    2015-01-01

    We explored the statistical and compositional link between Chelyabinsk meteoroid and potentially hazardous asteroid (86039) 1999 NC43 to investigate their proposed relation proposed by Borovi\\v{c}ka et al. (2013). Using detailed computation we confirm that the orbit of the Chelyabinsk impactor is anomalously close to 1999 NC43. We find about (1-3) x 10-4 likelihood of that to happen by chance. Taking the standpoint that the Chelyabinsk impactor indeed separated from 1999 NC43 by a cratering or rotational fission event, we run a forward probability calculation, which is an independent statistical test. However, we find this scenario is unlikely at the about (10-3 -10-2) level. We also verified compositional link between Chelyabinska and 1999NC43. Mineralogical analysis of Chelyabinsk (LL chondrite) and (8) Flora (the largest member of the presumed LL chondrite parent family) shows that their olivine and pyroxene chemistries are similar to LL chondrites. Similar analysis of 1999 NC43 shows that its olivine and ...

  5. nC60 deposition kinetics: the complex contribution of humic acid, ion concentration, and valence.

    Science.gov (United States)

    McNew, Coy P; LeBoeuf, Eugene J

    2016-07-01

    The demonstrated toxicity coupled with inevitable environmental release of nC60 raise serious concerns about its environmental fate and transport, therefore it is crucial to understand how nC60 will interact with subsurface materials including attached phase soil and sediment organic matter (AP-SOM). This study investigated the attachment of nC60 onto a Harpeth humic acid (HHA) coated silica surface under various solution conditions using a quartz crystal microbalance with dissipation monitoring. The HHA coating greatly enhanced nC60 attachment at low ion concentrations while hindering attachment at high ion concentrations in the presence of both mono and divalent cations. At low ion concentrations, the HHA greatly reduced the surface potential of the silica, enhancing nC60 deposition through reduction in the electrostatic repulsion. At high ion concentrations however, the reduced surface potential became less important due to the near zero energy barrier to deposition and therefore non-DLVO forces dominated, induced by compaction of the HHA layer, and leading to hindered attachment. In this manner, observed contributions from the HHA layer were more complex than previously reported and by monitoring surface charge and calculated DLVO interaction energy alongside attachment experiments, this study advances the mechanistic understanding of the variable attachment contributions from the humic acid layer. PMID:27061365

  6. Kinetic models of the interference of gene transcription to ncRNA and mRNA

    Science.gov (United States)

    Zhdanov, Vladimir P.

    2011-06-01

    The experiments indicate that the transcription of genes into ncRNA can positively or negatively interfere with transcription into mRNA. We propose two kinetic models describing this effect. The first model is focused on the ncRNA-induced chromatin modification facilitating the transcription of the downstream gene into mRNA. The second model includes the competition between the transcription into ncRNA and the binding of activator to a regulatory site of the downstream gene transcribed into mRNA. Our analysis based on the mean-field kinetic equations and Monte Carlo simulations shows the likely dependences of the transcription rate on RNA polymerase concentration in situations with different rate-limiting steps. Our models can also be used to scrutinize the dependence of the transcription rate on other kinetic parameters. Our kinetic Monte Carlo simulations show that the first model predicts stochastic bursts in the mRNA formation provided that the transcription into ncRNA is slow, while the second model predicts in addition anti-phase stochastic bursts in the mRNA and ncRNA formation provided that that the protein attachment to and detachment from a regulatory site is slow.

  7. Delta I=1/2 and ε'ε in Large-Nc QCD

    International Nuclear Information System (INIS)

    We present new results for the matrix elements of the Q6 and Q4 penguin operators, evaluated in a large-Nc approach which incorporates important O(Nc2/{nf}{Nc}) unfactorized contributions. Our approach shows analytic matching between short- and long-distance scale dependences within dimensional renormalization schemes, such as MS-bar. Numerically, we find that there is a large positive contribution to the Delta I =1/2 matrix element of Q6 and hence to the direct CP-violation parameter epsilon'/epsilon. We also present results for the Delta I = 1/2 rule in K→ππ amplitudes, which incorporate the related and important 'eye-diagram' contributions of O(Nc2/{1}/{Nc}) from the Q2 operator (i.e. the penguin-like contraction). The results lead to an enhancement of the Delta I = 1/2 effective coupling. The origin of the large unfactorized contributions which we find is discussed in terms of the relevant scales of the problem. (author)

  8. Polarization memory effect in the photoluminescence of nc-Si-SiOx light-emitting structures.

    Science.gov (United States)

    Michailovska, Katerina; Indutnyi, Ivan; Shepeliavyi, Petro; Sopinskyy, Mykola

    2016-12-01

    The polarization memory (PM) effect in the photoluminescence (PL) of the porous nc-Si-SiOx light-emitting structures, containing nanoparticles of silicon (nc-Si) in the oxide matrix and passivated in a solution of hydrofluoric acid (HF), has been investigated. The studied nc-Si-SiOx structures were produced by evaporation of Si monoxide (SiO) powder in vacuum and oblique deposition on Si wafer, and then the deposited silicon oxide (SiOx) films were annealed in the vacuum at 975 °C to grow nc-Si. It was found that the PM effect in the PL is observed only after passivation of nanostructures: during etching in HF solution, the initial symmetric nc-Si becomes asymmetric elongated. It was also found that in investigated nanostructures, there is a defined orientational dependence of the PL polarization degree (ρ) in the sample plane which correlates with the orientation of SiOx nanocolumns, forming the structure of the porous layer. The increase of the ρ values in the long-wavelength spectral range with time of HF treatment can be associated with increasing of the anisotropy of large Si nanoparticles. The PM effect for this spectral interval can be described by the dielectric model. In the short-wavelength spectral range, the dependence of the ρ values agrees qualitatively with the quantum confinement effect. PMID:27255897

  9. Nuclear Quadrupole Hyperfine Structure in HC14N/H14NC and DC15N/D15NC Isomerization: A Diagnostic Tool for Characterizing Vibrational Localization

    CERN Document Server

    Wong, Bryan M

    2010-01-01

    Large-amplitude molecular motions which occur during isomerization can cause significant changes in electronic structure. These variations in electronic properties can be used to identify vibrationally-excited eigenstates which are localized along the potential energy surface. This work demonstrates that nuclear quadrupole hyperfine interactions can be used as a diagnostic marker of progress along the isomerization path in both the HC14N/H14NC and DC15N/D15NC chemical systems. Ab initio calculations at the CCSD(T)/cc-pCVQZ level indicate that the hyperfine interaction is extremely sensitive to the chemical bonding of the quadrupolar 14N nucleus and can therefore be used to determine in which potential well the vibrational wavefunction is localized. A natural bonding orbital analysis along the isomerization path further demonstrates that hyperfine interactions arise from the asphericity of the electron density at the quadrupolar nucleus. Using the CCSD(T) potential surface, the quadrupole coupling constants of...

  10. Compositional, structural and mechanical characteristics of nc-TiC/a-C:H nanocomposite films

    International Nuclear Information System (INIS)

    Nanocomposite nc-TiC/a-C:H films, with an unusual combination of superhardness, high elastic modulus and high elastic recovery, are prepared by filtered cathodic vacuum arc technique using the C2H2 gas as the precursor. The effects of filter coil current on compositional, structural and mechanical properties of the nc-TiC/a-C:H films have been investigated by X-ray diffraction (XRD), X-ray photoelectron spectroscopy (XPS), energy disperse spectroscopy (EDS), microindentation and tribotester measurements. XPS and Raman analyses show that composition and nanostructure of the nc-TiC/a-C:H films can be changed by varying the filter coil current. By selecting the proper value of filter coil current, 2.5 A, one can remarkably enhance the mechanical properties of films such as superhardness (43.6 GPa). The superhardness can be ascribed to the phase variation and the nanostructure.

  11. NC INCREMENTAL SHEET METAL FORMING PROCESS AND VERTICAL WALL SQUARE BOX FORMING

    Institute of Scientific and Technical Information of China (English)

    Zhou Liuru; Mo Jianhua; Xiao Xiangzhi

    2004-01-01

    The forming principle and deformation analysis of NC incremental sheet metal forming process as well as the process planning, experiment and key process parameters of vertical wall square box forming are presented. Because the deformation of sheet metal only occurs around the tool head and the deformed region is subjected to stretch deformation, the deformed region of sheet metal thins, and surface area increases. Sheet metal forming stepwise is to lead to the whole sheet metal deformation. The forming half-apex angle θ and corner radius R are the main process parameters in NC incremental forming of vertical wall square box. According to sine law, a vertical wall square box can't be formed by NC incremental sheet metal forming process in a single process, rather, it must be formed in multi processes. Thus, the parallel line type tool path process method is presented to form the vertical wall square box, and the experiment and analysis are made to verify it.

  12. Comments on a Minimal Quasiparticle Approach for the QGP and Its Large-Nc Limits

    International Nuclear Information System (INIS)

    A minimal quasiparticle approach for describing QGP at temperatures much higher than the critical one is discussed. It involves an ideal-gas framework in which quark and gluon masses depend on temperature. This model is able to reproduce the recent equations of state computed in lattice QCD for temperatures typically higher than 2 Tc, in a range in which it is reasonable to neglect interactions between quasiparticles. In addition, the equations of state for a generic gauge theory with gauge groups SU(Nc) and quarks in an arbitrary representation are studied. The gauge independence in the pure glue sector and the large-N c equivalence between the gauge groups SU(Nc) and SO(2Nc) in a full plasma is finally shown for normalized thermodynamic quantities. (author)

  13. Multi-agent System for Process Planning in Step-nc Based Manufacturing

    Directory of Open Access Journals (Sweden)

    Juan Du

    2012-09-01

    Full Text Available In order to realize STEP-NC-oriented computer numerical control machining and achieve optimal performance in manufacturing, a multi-agent system for process planning in STEP-NC based manufacturing was designed. By analyzing the characteristic of STEP-NC data model, a manufacturing feature-oriented process planning method was proposed in this study and the distributed artificial intelligence methods, namely collaborative multi-agent was employed to accomplish process planning of part. The proposed multi-agent system consists of three types of autonomous agents, which are global manager agents, planning agents and manufacturing resource agents, respectively. Process planning can be automatically completed by multiple agents’ cooperation. Each agent is capable of communicating to each other through improved Knowledge Query and Manipulation Language (KQML. At last, one test part was designed and simulated to demonstrate the capabilities of this research in the study.

  14. Discovery of Novel ncRNA Sequences in Multiple Genome Alignments on the Basis of Conserved and Stable Secondary Structures

    OpenAIRE

    Fu, Yinghan; Xu, Zhenjiang Zech; Lu, Zhi J.; ZHAO, SHAN; Mathews, David H.

    2015-01-01

    Recently, non-coding RNAs (ncRNAs) have been discovered with novel functions, and it has been appreciated that there is pervasive transcription of genomes. Moreover, many novel ncRNAs are not conserved on the primary sequence level. Therefore, de novo computational ncRNA detection that is accurate and efficient is desirable. The purpose of this study is to develop a ncRNA detection method based on conservation of structure in more than two genomes. A new method called Multifind, using Multili...

  15. An overview of the role of context-sensitive HMMs in the prediction of ncRNA genes

    OpenAIRE

    Yoon, Byung-Jun; Vaidyanathan, P.P.

    2005-01-01

    Non-coding RNAs (ncRNA) are RNA molecules that function in the cells without being translated into proteins. In recent years, much evidence has been found that ncRNAs play a crucial role in various biological processes. As a result, there has been an increasing interest in the prediction of ncRNA genes. Due to the conserved secondary structure in ncRNAs, there exist pairwise dependencies between distant bases. These dependencies cannot be effectively modeled using traditional HMMs, and we nee...

  16. Role of the NC-loop in catalytic activity and stability in lipase from Fervidobacterium changbaicum.

    Directory of Open Access Journals (Sweden)

    Binchun Li

    Full Text Available Flexible NC-loops between the catalytic domain and the cap domain of the α/β hydrolase fold enzymes show remarkable diversity in length, sequence, and configuration. Recent investigations have suggested that the NC-loop might be involved in catalysis and substrate recognition in many enzymes from the α/β hydrolase fold superfamily. To foster a deep understanding of its role in catalysis, stability, and divergent evolution, we here systemically investigated the function of the NC-loop (residues 131-151 in a lipase (FClip1 from thermophilic bacterium Fervidobacterium changbaicum by loop deletion, alanine-scanning mutagenesis and site-directed mutagenesis. We found that the upper part of the NC-loop (residues 131-138 was of great importance to enzyme catalysis. Single substitutions in this region could fine-tune the activity of FClip1 as much as 41-fold, and any deletions from this region rendered the enzyme completely inactive. The lower part of the NC-loop (residues 139-151 was capable of enduring extensive deletions without loss of activity. The shortened mutants in this region were found to show both improved activity and increased stability simultaneously. We therefore speculated that the NC-loop, especially the lower part, would be a perfect target for enzyme engineering to optimize the enzymatic properties, and might present a hot zone for the divergent evolution of α/β hydrolases. Our findings may provide an opportunity for better understanding of the mechanism of divergent evolution in the α/β hydrolase fold superfamily, and may also guide the design of novel biocatalysts for industrial applications.

  17. Sublimation of the Endohedral Fullerene Er3N@C80

    OpenAIRE

    Stibor, Alexander; Schefzyk, Hannah; Fortágh, József

    2009-01-01

    The heat of sublimation of the endohedral metallofullerene Er3N@C80 was measured via Knudsen effusion mass spectrometry. The large molecule consists of a C80 fullerene cage which is stabilized by comprising a complex of three erbium atoms bounded to a nitrogen atom and has a mass of 1475 amu. The mass spectrum at a temperature of 1045 K and the relative intensities of the thermal fractions of Er3N@C80 are provided. We also discuss possible thermal decomposition processes for these particles. ...

  18. Covariant meson-baryon scattering with chiral and large Nc constraints

    International Nuclear Information System (INIS)

    We give a review of recent progress on the application of the relativistic chiral SU(3) Lagrangian to meson-baryon scattering. It is shown that a combined chiral and 1/Nc expansion of the Bethe-Salpeter interaction kernel leads to a good description of the kaon-nucleon, antikaon-nucleon and pion-nucleon scattering data typically up to laboratory momenta of plab ≅ 500 MeV. We solve the covariant coupled channel Bethe-Salpeter equation with the interaction kernel truncated to chiral order Q3 where we include only those terms which are leading in the large Nc limit of QCD. (orig.)

  19. A Search for Neutrino Induced Coherent NC($\\pi^{0}$) Production in the MINOS Near Detector

    Energy Technology Data Exchange (ETDEWEB)

    Cherdack, Daniel David [Tufts Univ., Medford, MA (United States)

    2011-02-01

    The production of single, highly forward π0 mesons by NC coherent neutrino-nucleus interactions (νμ + N → νμ + N + π0) is a process which probes fundamental aspects of the weak interaction. This reaction may also pose as a limiting background for long baseline searches for νμ → νe oscillations if the neutrino mixing angle θ13 is very small. The high-statistics sample of neutrino interactions recorded by the MINOS Near Detector provides an opportunity to measure the cross section of this coherent reaction on a relatively large-A nucleus at an average Ev = 4.9 GeV. A major challenge for this measurement is the isolation of forward-going electromagnetic (EM) showers produced by the relatively rare coherent NC0) process amidst an abundant rate of incoherently produced EM showers. The backgrounds arise from single π0 dominated NC events and also from quasi-elastic-like CC scattering of electron neutrinos. In this Thesis the theory of coherent interactions is summarized, and previous measurements of the coherent NC0) cross section are reviewed. Then, methods for selecting a sample of coherent NC0) like events, extracting the coherent NC0) event rate from that sample, estimating the analysis uncertainties, and calculating a cross section, are presented. A signal for neutrino-induced NC0) production is observed in the relevant kinematic regime as an excess of events of three standard deviations above background. The reaction cross sections, averaged over an energy window of 2.5 ≤ Ev ≤ 9.0 GeV is determined to be (31.6±10.5) x 10-40 cm2/nucleus. The result is the first evidence obtained for neutrino-nucleus coherent NC0) scattering on iron, and is the first measurement on an average nuclear target above A = 30. The cross section measurement

  20. RNAspace.org: An integrated environment for the prediction, annotation, and analysis of ncRNA

    OpenAIRE

    Cros, Marie-Josee; de Monte, Antoine; Mariette, Jérôme; Bardou, Philippe; Grenier-Boley, Benjamin; Gautheret, Daniel

    2011-01-01

    The annotation of noncoding RNA genes remains a major bottleneck in genome sequencing projects. Most genome sequences released today still come with sets of tRNAs and rRNAs as the only annotated RNA elements, ignoring hundreds of other RNA families. We have developed a web environment that is dedicated to noncoding RNA (ncRNA) prediction, annotation, and analysis and allows users to run a variety of tools in an integrated and flexible manner. This environment offers complementary ncRNA gene f...