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Sample records for areva group facilities

  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. 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

  3. 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.

  4. 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.)

  5. 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.)

  6. 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.)

  7. 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

  8. 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.)

  9. 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.)

  10. 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.)

  11. 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.)

  12. 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.)

  13. 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.)

  14. 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.)

  15. 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.)

  16. 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.)

  17. 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.)

  18. 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)

  19. 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.)

  20. 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

  1. 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)

  2. 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

  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 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

  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. 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.)

  7. 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

  8. 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.)

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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)

  15. 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)

  16. 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

  17. 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.

  18. 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

  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: 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

  1. 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

  2. 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.

  3. 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.

  4. 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

  5. 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

  6. 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

  7. Facilities removal working group

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This working group`s first objective is to identify major economic, technical, and regulatory constraints on operator practices and decisions relevant to offshore facilities removal. Then, the group will try to make recommendations as to regulatory and policy adjustments, additional research, or process improvements and/or technological advances, that may be needed to improve the efficiency and effectiveness of the removal process. The working group will focus primarily on issues dealing with Gulf of Mexico platform abandonments. In order to make the working group sessions as productive as possible, the Facilities Removal Working Group will focus on three topics that address a majority of the concerns and/or constraints relevant to facilities removal. The three areas are: (1) Explosive Severing and its Impact on Marine Life, (2) Pile and Conductor Severing, and (3) Deep Water Abandonments This paper will outline the current state of practice in the offshore industry, identifying current regulations and specific issues encountered when addressing each of the three main topics above. The intent of the paper is to highlight potential issues for panel discussion, not to provide a detailed review of all data relevant to the topic. Before each panel discussion, key speakers will review data and information to facilitate development and discussion of the main issues of each topic. Please refer to the attached agenda for the workshop format, key speakers, presentation topics, and panel participants. The goal of the panel discussions is to identify key issues for each of the three topics above. The working group will also make recommendations on how to proceed on these key issues.

  8. 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.)

  9. 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.)

  10. 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.)

  11. 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.)

  12. 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.)

  13. 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.)

  14. AREVA General Inspectorate 2010 Annual Report. Status of safety in nuclear facilities

    International Nuclear Information System (INIS)

    After messages by different managers, this report proposes a description of the context for nuclear safety: group's policy in matters of nuclear safety and radiation protection, regulatory changes (in France, with respect to information, changes in administrative organization, overhaul of general technical regulations, international context). It describes the organizational changes which occurred within the company. It reports actions regarding transparency, briefly describes actions and principles aimed at improving safety, indicates and comments noteworthy nuclear events, discusses their assessment from a HOF (human and organizational factors) perspective, comments lessons learned from inspections, comments data regarding radiation protection and actions aimed at improving radiation protection. It discusses environmental impact issues. It addresses the different processes and factors which transversely appear in nuclear safety: safety management, human and organizational factors, safety in design, project management, and emergency management. Several specific risks are discussed: criticality control, nuclear materials safeguards, fire, spill prevention, transportation, radioactive waste, shutdown and dismantling, service operations, mining, and environmental liabilities. Document in French and in English

  15. 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

  16. 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

  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. 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.)

  19. 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.)

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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.)

  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. 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

  7. 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.)

  8. 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

  9. 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.)

  10. 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

  11. 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

  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. 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)

  14. 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)

  15. 76 FR 34103 - In the Matter of Areva Enrichment Services, LLC (Eagle Rock Enrichment Facility); Notice of...

    Science.gov (United States)

    2011-06-10

    ... Facility), 74 FR 38,052, 38,054 (July 30, 2009) (CLI-09-15, 70 NRC 1, 7-8 (2009)). \\2\\ After conducting a... backpacks, and is reminded to allow sufficient time for security screening. C. Date, Time, and Location of... requested not to bring any unnecessary hand-carried items, such as packages, briefcases, backpacks, or...

  16. 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

  17. 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

  18. 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)

  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. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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.)

  6. 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)

  7. 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.)

  8. 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.)

  9. 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.)

  10. 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

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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)

  17. 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)

  18. 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.)

  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. 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)

  1. 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

  2. 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)

  3. 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

  4. 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.)

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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)

  14. 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

  15. 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.

  16. 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.

  17. 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

  18. 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

  19. AREVA in the Republic of South Africa

    International Nuclear Information System (INIS)

    field of nuclear energy, will play a vital role to be the anchor for the coordination of all nuclear energy R and D and innovation, to undertake and lead the development of uranium conversion capabilities, to develop nuclear fuel fabrication capabilities and obtain established fuel fabrication technologies, and to investigate the viability of building an indigenous reprocessing facility. Already, NECSA has managed a low and medium level waste storage site in Vaalputs since 1986. In 2005, the government issued the national radwaste management policy based on the recycling of used fuel and minimizing packaging and storage of waste volumes. On January, 2008, AREVA submitted its proposal for the construction of two EPRs within the scope of the 'Nuclear-1' program and possibly 10 other EPR within the scope of 'Fleet' program. The proposal is accompanied by the first elements of a global partnership aiming at the joint development of a South African nuclear industry and related skills development. AREVA achieved overall revenues of 94 million euros in South Africa in 2007, comprising 55 million euros in its Reactors and Services Division, 12 million euros in its Fuel Division and 27 million euros in its T and D Division in 2006. AREVA built the twin units of the Koeberg nuclear power plant. In 2006, the two reactors provided 10 TWh net of electricity, which represents 4.4% of the country's total electricity production. Today AREVA is present in Koeberg in the fields of utility services, technical assistance and fuel supply. Utility services mainly comprise inspection operations, maintenance, repair and component replacement as well as engineering and upgrading services. AREVA supplies fuel to the Koeberg nuclear power plant and provides NECSA with technical support for the conversion and fabrication of low enriched uranium for the SAFARI research reactor. Half of the installed transmission and distribution base in South Africa has been supplied by AREVA 's T and D Division

  20. 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

  1. 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

  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. 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

  4. 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

  5. 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

  6. 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.

  7. 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)

  8. 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.)

  9. 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

  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. '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

  12. 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.

  13. 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

  14. 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.

  15. 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

  16. 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

  17. Assisted Living Facilities, group homes, Published in 2006, Washoe County.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Assisted Living Facilities dataset, was produced all or in part from Published Reports/Deeds information as of 2006. It is described as 'group homes'. Data by...

  18. 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)

  19. 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)

  20. 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

  1. '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

  2. 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.)

  3. 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.)

  4. 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.)

  5. 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

  6. The Fifth Omega Laser Facility Users Group Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Petrasso, R. D.

    2015-10-01

    A capacity gathering of over 100 researchers from 25 universities and laboratories met at the Laboratory for Laser Energetics (LLE) for the Fifth Omega Laser Facility Users Group (OLUG) workshop. The purpose of the 2.5-day workshop was to facilitate communications and exchanges among individual Omega users and between users and the LLE management; to present ongoing and proposed research; to encourage research opportunities and collaborations that could be undertaken at the Omega Laser Facility and in a complementary fashion at other facilities [such as the National Ignition Facility (NIF) or the Laboratoire pour l’Utilisation des Lasers Intenses (LULI)]; to provide an opportunity for students, postdoctoral fellows, and young researchers to present their research in an informal setting; and to provide feedback to LLE management from the users about ways to improve the facility and future experimental campaigns.

  7. The Sixth Omega Laser Facility Users Group Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Petrasso, R. D.

    2014-10-01

    A capacity gathering of over 100 researchers from 25 universities and laboratories met at the Laboratory for Laser Energetics (LLE) for the Sixth Omega Laser Facility Users Group (OLUG) workshop. The purpose of the 2.5-day workshop was to facilitate communications and exchanges among individual OMEGA users, and between users and the LLE management; to present ongoing and proposed research; to encourage research opportunities and collaborations that could be undertaken at the Omega Laser Facility and in a complementary fashion at other facilities [such as the National Ignition Facility (NIF) or the Laboratoire pour l’Utilisation des Lasers Intenses (LULI)]; to provide an opportunity for students, postdoctoral fellows, and young researchers to present their research in an informal setting; and to provide feedback from the users to LLE management about ways to improve and keep the facility and future experimental campaigns at the cutting edge.

  8. Sorting facility for group 1 solid radioactive waste

    International Nuclear Information System (INIS)

    A facility for sorting group 1 solid radioactive waste (SRW) (its gamma radiation dose rate not in excess of 0.5x10-4 Sv/h at a distance of 0.1 m from the surface), which has been developed and manufactured by OJSC SverdNIIkhimmash, is described. The facility integrates boxes for sorting, packaging, loading and acceptance of SRW, an accumulating container, a guillotine and control system. The purpose and operation principle of each element of the facility, as well as operation of the facility as a unit, are considered, its technical characteristics being provided. The facility has been placed into operation at the Kursk NPP and demonstrated high reliability and efficiency during operation in service conditions

  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. 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

  11. 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.

  12. 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.)

  13. 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)

  14. Sorting facility for group 1,2 solid radioactive waste

    International Nuclear Information System (INIS)

    A facility for sorting group 1 and 2 solid radioactive waste (SRW) (its gamma radiation dose rate being not in excess of 5x10-4 and 0.5x10-2 Sv/h, respectively, at a distance of 0.1 m from the surface), which has been developed and manufactured by OJSC SverdNIIkhimmash is described. The facility integrates a bunker, a large guillotine, a box fitted out with manipulators, a discharge chamber, a small guillotine, a sorting chamber, a feeder and control system. The purpose and structure of each element of the facility are considered along with operation of the facility as a whole, its technical characteristics being provided

  15. 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

  16. 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.)

  17. 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.

  18. 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.

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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)

  4. 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)

  5. 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)

  6. Change-management. From commercial power operation to post power operation and decommissioning; Change-Management. Vom Leistungsbetrieb ueber den Nachbetrieb zum Rueckbau. T. 1. Stilllegung und Rueckbau von Reaktoren und Anlagen im Brennstoffkreislauf durch AREVA

    Energy Technology Data Exchange (ETDEWEB)

    Wasinger, Karl [AREVA GmbH, Offenbach am Main (Germany)

    2015-02-15

    Transition from power generation to decommissioning challenges utilities. Power generation is mainly characterized by a stable working environment and constant workload, decommissioning and dismantling, however, by transformation and change. Also, changing requirements for the workforce's skills challenge the organization and its senior management. Ensuring effective and efficient performance, while maintaining motivation of staff, requires adjustment of management processes as well as of operational organization and human resources management. AREVA has more than 20 years of experience in decommissioning of own nuclear fuel cycle plants in France, as well as of other large plants and power reactors in Germany, the United Kingdom and the US. Therefore, the group has developed and successfully implemented integrated change management processes. The implementation of well-established and proven methods, developed by the productive industry and adjusted to the nuclear regulatory requirements, significantly improves the performance and efficiency of means and methods in use. The AREVA Performance Improvement Process defines concrete approaches to identify and improve potential deficits of productivity in six main areas (decommissioning scenarios and stra-tegies, waste treatment and logistics, operations management, supply chain, regulatory monitoring and controls as well as dismantling operation). Nuclear plant and facility owners around the world benefit from AREVA experts well experienced in execution of large and complex decommissioning projects.

  7. 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.)

  8. 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.)

  9. 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...

  10. 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

  11. 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

  12. 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

  13. 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)

  14. 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

  15. 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

  16. 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

  17. 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.)

  18. 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.)

  19. 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)

  20. Facilities offered by the CEA group for training foreign specialists

    International Nuclear Information System (INIS)

    First set up in 1945, the CEA (French Atomic Energy Commission) opened its doors to foreign scientists and technicians as long ago as the 1950s, and particularly so since 1960. Among the 15 000 foreigners concerned, some have come in the capacity of co-workers, while others - approximately 10 000 - have taken courses for the purpose of receiving training. Since the CEA constitutes both a public scientific institution and an industrial group, especially by virtue of its branch organizations and specialized production units, it possesses incomparably varied facilities. This is why almost all the countries of the world, at some time or other, have had nationals at the Saclay, Fontenay-aux-Roses, Grenoble and Cadarache research centres, or the National Institute of Nuclear Science and Technology (INSTN) at Saclay, a specialized establishment set up in 1956, or else at the Razes Information and Further Training Centre (CIPRA), specializing in the uranium ore industry. Most of the trainees received over the last few years by the CEA Group stem from the developing countries, those coming to receive practical technological training being ever more numerous. Several of the training programmes devised have involved participation in industrial operations, either in conjunction with Technicatome, a branch organization specializing in nuclear engineering (Iran, Iraq) or in association with other CEA Group units (South Korea). The trainees usually receive fellowships through the intermediary of French diplomatic missions, in which case it is enough if they continue to receive the salary normally paid to them by the public organization employing them. On the other hand, technological training sometimes involves payment because of the expense involved (intensive supervision and expensive experimental work). Finally, courses in French are organized in France by specialized institutions, but English is acceptable for very brief training periods. (author)

  1. 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)

  2. 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.)

  3. 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

  4. 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.)

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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.)

  12. 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.)

  13. 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)

  14. 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)

  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. 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

  17. 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

  18. 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

  19. 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)

  20. 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

  1. 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

  2. How Groups Learn: The Role of Communication Patterns, Cue Recognition, Context Facility, and Cultural Intelligence

    Science.gov (United States)

    Silberstang, Joyce; London, Manuel

    2009-01-01

    This article explores the role of group learning by focusing on how intragroup communication patterns (implicit and explicit) influence learning readiness dimensions (cue recognition, context facility, and cultural intelligence), which in turn influences the group's ability to learn and the type of leaning that occurs. Groups with high levels of…

  3. 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)

  4. 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)

  5. 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)

  6. 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)

  7. 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

  8. 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.)

  9. 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.)

  10. 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

  11. Areva first half 2008 financial results

    International Nuclear Information System (INIS)

    Operating income: 539 million euros; net income attributable to equity holders of the parent: up 465 million euros to 760 million euros, i.e. 21.45 euros per share; net debt of 2.385 billion euros, i.e. 30.1% of equity (26.2% at 12/31/2007). For 2008 as a whole, the group confirms its outlook for a sharp increase in backlog and in revenue and rising operating income. The backlog rose to 38.123 billion euros at June 30, 2008, up 13.6% compared with the 33.553 billion euros recognized at June 30, 2007. In Nuclear, contributors to growth were the Reactors and Services division (+36%) and the Front End division (+11%). The Transmission and Distribution division posted growth of 41%. First half 2008 revenue rose to 6.168 billion euros, for 14.8% reported growth and 16.0% organic growth. In the nuclear businesses, organic growth was 18.6%, including 31.3% growth in Reactors and Services as new power plant construction projects moved forward and 12.0% growth in Transmission and Distribution business. The group's operating income rose to 539 million euros in the first half of 2008, for a margin rate of 8.7%, compared with 207 million euros in the first half of 2007 and a margin rate of 3.9%. This 332 million euro increase includes: - the strong volume increase in our commercial and industrial operations and the positive impact this had on profitability for all of our divisions; - a substantial operational gain in the Front End division, including a significant dilution gain related to acquisition by Suez of an equity interest in the GB II enrichment plant; - an additional provision on the OL3 contract, made necessary by: cost overruns generated by the use of additional resources needed to meet the schedule and offset the customer's operating practices; and the difficulties and risks on operations managed by some subcontractors. Operating income for the Back End division rose to 400 million euros, an increase of 177 million euros compared with the first half of 2007. The

  12. Factors associated with group bullying and psychopathology in elementary school students using child-welfare facilities

    Science.gov (United States)

    Kim, Jun Won; Lee, KounSeok; Lee, Young Sik; Han, Doug Hyun; Min, Kyung Joon; Song, Sung Hwan; Park, Ga Na; Lee, Ju Young; Kim, Jae Ock

    2015-01-01

    Purpose Low socioeconomic status is an important risk factor for child psychiatric problems. Low socioeconomic status is also associated with psychiatric problems later in life. We investigated the effects of group bullying on clinical characteristics and psychopathology in elementary school students using child-welfare facilities. Methods Three hundred and fifty-eight elementary school students using child-welfare facilities were recruited. The School Bullying Self Rating Questionnaire was used to assess group bullying. To evaluate related psychopathology, the Children’s Problem-Behavior Screening Questionnaire, the Children’s Depression Inventory, the Beck Anxiety Inventory, the Suicidal Ideation Questionnaire, Young’s Internet Addiction Scale, and Conners–Wells’ Adolescent Self-Report Scale were applied. Samples were classified according to school grade (lower or upper), and each group’s characteristics were compared as they related to bullying victims versus non-victims. Results The prevalence rate of group bullying was 22% in the lower-grade group and 12% in the higher-grade group. Bullying victims in lower grades reported high somatization, depressive symptoms, Internet addiction, and attention deficit hyperactivity disorder tendencies, whereas those in upper grades reported cognitive problems, symptoms of depression and anxiety, suicidal ideation, Internet addiction, and attention deficit hyperactivity disorder tendencies. Somatization and depressive symptoms were significant predictors of bullying in the lower-grade group, and anxiety was a significant predictor of bullying in the upper-grade group. Conclusion This study demonstrated that elementary school students using child-welfare facilities might have an increased risk of being bullied and that bullying victims may have different psychopathologies depending on their ages. PMID:25897236

  13. 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

  14. Social Relationships and Group Dynamics Inside a Community Correction Facility for Women.

    Science.gov (United States)

    Cantora, Andrea; Mellow, Jeff; Schlager, Melinda D

    2016-07-01

    This article presents research on women's perceptions and experiences residing in a female community correction facility. Qualitative interview data and field observations are used to examine resident relationships, perceptions of on-site group treatment, and benefits of receiving off-site treatment. Findings from this study indicate an overwhelming feeling of tension and lack of trust among residents, resulting in most women withdrawing from social interactions. Relationship dynamics also played a role in women's participation during on-site group treatment and desiring off-site treatment. This study supports the need to create, and sustain, therapeutic environments within community correction settings for women. PMID:26138351

  15. IAEA advisory group meeting on establishment of an accelerator facility. Final report

    International Nuclear Information System (INIS)

    The interests and needs of several IAEA and IAEA Co-ordinated Research Programmes have been discussed with the Advisory Group on 'Establishment of an Analytical Accelerator Facility'. Based on these discussions, it was concluded that the methods and techniques of Ion Beam Analysis would provide indispensable information in support of Agency programmes. Ion Beam Analysis is a well-developed field using accelerator-based methods of analysis. The range of techniques available are discussed and attached in the appendix. The recommendations and conclusions of the Advisory Group for implementing the Ion Beam Analysis capability are given

  16. 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

  17. Factors associated with group bullying and psychopathology in elementary school students using child-welfare facilities

    Directory of Open Access Journals (Sweden)

    Kim JW

    2015-04-01

    Full Text Available Jun Won Kim,1,2 KounSeok Lee,3 Young Sik Lee,4 Doug Hyun Han,4 Kyung Joon Min,4 Sung Hwan Song,5 Ga Na Park,6 Ju Young Lee,1 Jae Ock Kim5 1Division of Child and Adolescent Psychiatry, Department of Neuropsychiatry, College of Medicine, Seoul National University, Seoul, South Korea; 2Department of Psychiatry, Graduate School, Chung-Ang University, Seoul, South Korea; 3Department of Psychiatry, Samsung Medical Center, Seoul, South Korea; 4Department of Psychiatry, Chung-Ang University, College of Medicine, Seoul, South Korea; 5Department of Psychiatry, Gongju National Hospital, Gongju, South Korea; 6Department of Special Education, Graduate School, Dankook University, Jukjeon, South Korea Purpose: Low socioeconomic status is an important risk factor for child psychiatric problems. Low socioeconomic status is also associated with psychiatric problems later in life. We investigated the effects of group bullying on clinical characteristics and psychopathology in elementary school students using child-welfare facilities.Methods: Three hundred and fifty-eight elementary school students using child-welfare facilities were recruited. The School Bullying Self Rating Questionnaire was used to assess group bullying. To evaluate related psychopathology, the Children’s Problem-Behavior Screening Questionnaire, the Children’s Depression Inventory, the Beck Anxiety Inventory, the Suicidal Ideation Questionnaire, Young’s Internet Addiction Scale, and Conners–Wells’ Adolescent Self-Report Scale were applied. Samples were classified according to school grade (lower or upper, and each group’s characteristics were compared as they related to bullying victims versus non-victims.Results: The prevalence rate of group bullying was 22% in the lower-grade group and 12% in the higher-grade group. Bullying victims in lower grades reported high somatization, depressive symptoms, Internet addiction, and attention deficit hyperactivity disorder tendencies, whereas

  18. 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.

  19. 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

  20. 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.

  1. 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

  2. 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

  3. 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

    radiological release due to off-normal events are relatively low; (4) costs are relatively low; and (5) maintenance activities are relatively simple. The primary drawback associated with the wireline emplacement mode for DBD is the number of emplacement trips-in to the borehole, which results in a relatively higher probability for a drop event. Fortunately, the WPs can be engineered with impact limiters that will minimize the likelihood of a breach of the WP due to a drop. The WP designs presented in the M2 report appear to be focused on compatibility with the drill-string emplacement mode (e.g., the threaded connections). With the recommendation that the wireline emplacement mode be utilized for the DBFT, some changes may be warranted to these WPs. For example, the development of a WP release connection that is more reliable than the currently credited connection, which is considered to have a high failure probability, and the integration of an impact limiter into its design. The M2 report states the engineering demonstration of the DBFT will occur in the FTB over a 4-year period. AREVA recommends development and testing of the WP emplacement handling equipment occur separately (but concurrently, if not earlier) from the FTB at a mock-up facility. The separation of this activity would prevent schedule interference between the science and engineering thrusts of the project. Performing tests in a mock-up facility would allow additional control and observation compared to the FTB. The mock-up facility could also be utilized as a training facility for future operations. Terminal velocity and impact limiter testing would require the FTB for testing, since these areas would be difficult to reproduce in a limited depth mock-up. Although only at the end of the conceptual stage of design development, DBD appears to be a viable solution for some waste forms produced by the nuclear industry. However, regulatory requirements have yet to be established for pre- and post

  4. Decommissioning of TRIGA-reactors and other nuclear research facilities. Aims of the German working group for incorporation monitoring

    International Nuclear Information System (INIS)

    In 2001 the working group decommissioning was founded in the department incorporation of the German/Switzerland association for radiation protection. Members of the group are representatives of dismantling projects, dismantling companies, organizations of experts, authorities, institutions of measuring incorporations, research facilities and universities. Aims of the group are to guarantee a continuous information and experience exchange between the different decommissioning projects, to establish criteria for facility specific advanced training and further education, to propose requirements for in-vitro incorporation measuring facilities and to draw up a recommendation for incorporation protection of decommissioning projects. It is tried to harmonize the procedure in principle regarding the specific conditions of the different nuclear facilities. The bases for the recommendation are formed by the experiences of the previous dismantling projects in Germany. As an example in this contribution the procedure at the TRIGA reactor of MHH is presented and compared to a facility with alpha-emitters. (author)

  5. 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

  6. The Integral Test Facility Karlstein

    OpenAIRE

    Stephan Leyer; Michael Wich

    2012-01-01

    The Integral Test Facility Karlstein (INKA) test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant A...

  7. 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.

  8. 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

  9. Areva first half 2008 financial results; Areva - Resultats du 1. semestre 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Operating income: 539 million euros; net income attributable to equity holders of the parent: up 465 million euros to 760 million euros, i.e. 21.45 euros per share; net debt of 2.385 billion euros, i.e. 30.1% of equity (26.2% at 12/31/2007). For 2008 as a whole, the group confirms its outlook for a sharp increase in backlog and in revenue and rising operating income. The backlog rose to 38.123 billion euros at June 30, 2008, up 13.6% compared with the 33.553 billion euros recognized at June 30, 2007. In Nuclear, contributors to growth were the Reactors and Services division (+36%) and the Front End division (+11%). The Transmission and Distribution division posted growth of 41%. First half 2008 revenue rose to 6.168 billion euros, for 14.8% reported growth and 16.0% organic growth. In the nuclear businesses, organic growth was 18.6%, including 31.3% growth in Reactors and Services as new power plant construction projects moved forward and 12.0% growth in Transmission and Distribution business. The group's operating income rose to 539 million euros in the first half of 2008, for a margin rate of 8.7%, compared with 207 million euros in the first half of 2007 and a margin rate of 3.9%. This 332 million euro increase includes: - the strong volume increase in our commercial and industrial operations and the positive impact this had on profitability for all of our divisions; - a substantial operational gain in the Front End division, including a significant dilution gain related to acquisition by Suez of an equity interest in the GB II enrichment plant; - an additional provision on the OL3 contract, made necessary by: cost overruns generated by the use of additional resources needed to meet the schedule and offset the customer's operating practices; and the difficulties and risks on operations managed by some subcontractors. Operating income for the Back End division rose to 400 million euros, an increase of 177 million euros compared with the first half of

  10. A facile method to synthesize magnetic polymer nanospheres with multifunctional groups

    Energy Technology Data Exchange (ETDEWEB)

    Zhang Xiaojuan, E-mail: xixi@jit.edu.c [School of Material Engineering, Jinling Institute of Technology, Nanjing 211169 (China); Jiang Wei [National Special Superfine Powder Engineering Research Center, Nanjing University of Science and Technology, Nanjing 210094 (China); Ye Yuanfeng; Feng Zhiqiang [School of Material Engineering, Jinling Institute of Technology, Nanjing 211169 (China); Sun Zhendong; Li Fengsheng [National Special Superfine Powder Engineering Research Center, Nanjing University of Science and Technology, Nanjing 210094 (China); Hao Lingyun [School of Material Engineering, Jinling Institute of Technology, Nanjing 211169 (China); Chu Jianjun [Fourth Affiliated Hospital of Soochow University, Wuxi 214062 (China)

    2011-06-15

    Magnetic poly(styrene methyl methacrylate)/Fe{sub 3}O{sub 4} nanospheres with ester groups were prepared by a modified one-step mini-emulsion polymerization in the presence of Fe{sub 3}O{sub 4} ferrofluids. The effects of monomer dose, surfactant content, ferrofluid concentration and initiator content on the particle characteristics such as the size, morphology and magnetic properties were investigated by Fourier-transform infrared spectroscopy, transmission electron microscopy, thermogravimetric analysis and vibrating sample magnetometer. The results indicated that magnetic nanospheres were superparamagnetic with high saturation magnetization of 51.0 emu/g and corresponding magnetite content of 61.5 wt%. Subsequently, magnetic nanospheres with carboxyl and amino groups were also obtained by hydrolysis and ammonolysis reaction. These magnetic nanospheres with multifunctional groups have biomedical applications. - Research highlights: Facile way of synthesis of ester-functionalized superparamagnetic nanospheres. Wide scope of synthesis for other kinds of functional magnetic polymer nanospheres. The modification bilayer is the key factor controlling the encapsulation of products. Potential application of biomedical field.

  11. Facile synthesis and characterization of novel biodegradable amphiphilic block copolymers bearing pendant hydroxyl groups

    International Nuclear Information System (INIS)

    Novel amphiphilic block copolymers bearing pendant hydroxyl groups polylactide-b–poly(3,3-bis(Hydroxymethyl–triazolylmethyl) oxetane)-b–polylactide (PLA-b–PHMTYO-b–PLA) were synthesized via a facile and efficient method. First, the block copolymer intermediates polylactide-b–poly(3,3-Diazidomethyloxetane)-b–polylactide (PLA-b–PBAMO-b–PLA) were synthesized through ring-opening polymerization of lactide using PBAMO as a macroinitiator. Following “Click” reaction of PLA-b–PBAMO-b–PLA with propargyl alcohol provided the targeted amphiphilic block copolymers PLA-b–PHMTYO-b–PLA with pendant hydroxyl groups. The composition and structure of prepared copolymers were characterized by 1H nuclear magnetic resonance (1H NMR) spectroscopy, Fourier transform infrared (FT-IR) and gel permeation chromatography (GPC). The self-assembly behavior of the copolymers in water was investigated by transmission electron microscope (TEM), dynamic light scattering (DLS) and static light scattering (SLS). The results showed that the novel copolymers PLA-b–PHMTYO-b–PLA self-assembled into spherical micelles with diameters ranging from 100 nm to 200 nm in aqueous solution. These copolymers also exhibited low critical micellar concentrations (CMC: 6.9 × 10−4 mg/mL and 3.9 × 10−5 mg/mL, respectively). In addition, the in vitro cytotoxicity of these copolymers was determined in the presence of L929 cells. The results showed that the block copolymers PLA-b–PHMTYO-b–PLA exhibited better biocompatibility. Therefore, these well-defined copolymers are expected to find some applications in drug delivery or tissue engineering. - Highlights: • The method to synthesize PLA-b–PHMTYO-b–PLA is relatively facile and efficient. • PLA-b–PHMTYO-b–PLA self-assembles into spherical micelles with low CMC in water. • PLA-b–PHMTYO-b–PLA exhibits better biocompatibility and biodegradability

  12. Facile synthesis and characterization of novel biodegradable amphiphilic block copolymers bearing pendant hydroxyl groups

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Gaicen; Fan, Xiaoshan; Xu, Bingcan; Zhang, Delong; Hu, Zhiguo, E-mail: zghu@htu.cn

    2014-10-01

    Novel amphiphilic block copolymers bearing pendant hydroxyl groups polylactide-b–poly(3,3-bis(Hydroxymethyl–triazolylmethyl) oxetane)-b–polylactide (PLA-b–PHMTYO-b–PLA) were synthesized via a facile and efficient method. First, the block copolymer intermediates polylactide-b–poly(3,3-Diazidomethyloxetane)-b–polylactide (PLA-b–PBAMO-b–PLA) were synthesized through ring-opening polymerization of lactide using PBAMO as a macroinitiator. Following “Click” reaction of PLA-b–PBAMO-b–PLA with propargyl alcohol provided the targeted amphiphilic block copolymers PLA-b–PHMTYO-b–PLA with pendant hydroxyl groups. The composition and structure of prepared copolymers were characterized by {sup 1}H nuclear magnetic resonance ({sup 1}H NMR) spectroscopy, Fourier transform infrared (FT-IR) and gel permeation chromatography (GPC). The self-assembly behavior of the copolymers in water was investigated by transmission electron microscope (TEM), dynamic light scattering (DLS) and static light scattering (SLS). The results showed that the novel copolymers PLA-b–PHMTYO-b–PLA self-assembled into spherical micelles with diameters ranging from 100 nm to 200 nm in aqueous solution. These copolymers also exhibited low critical micellar concentrations (CMC: 6.9 × 10{sup −4} mg/mL and 3.9 × 10{sup −5} mg/mL, respectively). In addition, the in vitro cytotoxicity of these copolymers was determined in the presence of L929 cells. The results showed that the block copolymers PLA-b–PHMTYO-b–PLA exhibited better biocompatibility. Therefore, these well-defined copolymers are expected to find some applications in drug delivery or tissue engineering. - Highlights: • The method to synthesize PLA-b–PHMTYO-b–PLA is relatively facile and efficient. • PLA-b–PHMTYO-b–PLA self-assembles into spherical micelles with low CMC in water. • PLA-b–PHMTYO-b–PLA exhibits better biocompatibility and biodegradability.

  13. 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

  14. 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)

  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. AGS SUPER NEUTRINO BEAM FACILITY ACCELERATOR AND TARGET SYSTEM DESIGN (NEUTRINO WORKING GROUP REPORT-II).

    Energy Technology Data Exchange (ETDEWEB)

    DIWAN,M.; MARCIANO,W.; WENG,W.; RAPARIA,D.

    2003-04-21

    This document describes the design of the accelerator and target systems for the AGS Super Neutrino Beam Facility. Under the direction of the Associate Laboratory Director Tom Kirk, BNL has established a Neutrino Working Group to explore the scientific case and facility requirements for a very long baseline neutrino experiment. Results of a study of the physics merit and detector performance was published in BNL-69395 in October 2002, where it was shown that a wide-band neutrino beam generated by a 1 MW proton beam from the AGS, coupled with a half megaton water Cerenkov detector located deep underground in the former Homestake mine in South Dakota would be able to measure the complete set of neutrino oscillation parameters: (1) precise determination of the oscillation parameters {Delta}m{sub 32}{sup 2} and sin{sup 2} 2{theta}{sub 32}; (2) detection of the oscillation of {nu}{sub {mu}}-{nu}{sub e} and measurement of sin{sup 2} 2{theta}{sub 13}; (3) measurement of {Delta}m{sub 21}{sup 2} sin 2{theta}{sub 12} in a {nu}{sub {mu}} {yields} {nu}{sub e} appearance mode, independent of the value of {theta}{sub 13}; (4) verification of matter enhancement and the sign of {Delta}m{sub 32}{sup 2}; and (5) determination of the CP-violation parameter {delta}{sub CP} in the neutrino sector. This report details the performance requirements and conceptual design of the accelerator and the target systems for the production of a neutrino beam by a 1.0 MW proton beam from the AGS. The major components of this facility include a new 1.2 GeV superconducting linac, ramping the AGS at 2.5 Hz, and the new target station for 1.0 MW beam. It also calls for moderate increase, about 30%, of the AGS intensity per pulse. Special care is taken to account for all sources of proton beam loss plus shielding and collimation of stray beam halo particles to ensure equipment reliability and personal safety. A preliminary cost estimate and schedule for the accelerator upgrade and target system are also

  18. Regulatory effectiveness from the operator's viewpoint. Fuel cycle facilities

    International Nuclear Information System (INIS)

    Sustainable development is a keystone of AREVA's industrial strategy for achieving growth that is profitable, socially responsible and environmentally respectful. As an operator AREVA is committed to establishing and maintaining 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 same is true when acting as vendors of nuclear facilities, whether nuclear power reactors or other facilities. Achieving a high safety record is also a necessary condition for ensuring the economic performance of these facilities and for strengthening the acceptance of nuclear energy by the local population as well as the decision makers. The existence of a solid international framework and strong and independent national authorities is an important element to support those goals. From an operator's point of view, regulatory effectiveness is resulting from clear and stable rules, designed and applied in a rigorous yet pragmatic way to cater to the specificities of each type of facilities. Clear rules avoid the uncertainty related to the potential for diverging interpretations. Stability of rules ensures that solutions developed to meet the regulations and the investments made are useful and derive real value for both safety objectives and the objectives of the industry. Regulatory effectiveness is also achieved when actual experience and the input of operators can be taken into account to achieve stringent safety objectives in a most efficient way. Finally, it must be recognized that the nuclear industry is now mature and international. To further support the expected development of nuclear energy in the world, it is important to move towards harmonization of the safety regime and increased cooperation between licensing authorities. (author)

  19. 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

  20. Facile synthesis and characterization of novel biodegradable amphiphilic block copolymers bearing pendant hydroxyl groups.

    Science.gov (United States)

    Hu, Gaicen; Fan, Xiaoshan; Xu, Bingcan; Zhang, Delong; Hu, Zhiguo

    2014-10-01

    Novel amphiphilic block copolymers bearing pendant hydroxyl groups polylactide-b-poly(3,3-bis(Hydroxymethyl-triazolylmethyl) oxetane)-b-polylactide (PLA-b-PHMTYO-b-PLA) were synthesized via a facile and efficient method. First, the block copolymer intermediates polylactide-b-poly(3,3-Diazidomethyloxetane)-b-polylactide (PLA-b-PBAMO-b-PLA) were synthesized through ring-opening polymerization of lactide using PBAMO as a macroinitiator. Following "Click" reaction of PLA-b-PBAMO-b-PLA with propargyl alcohol provided the targeted amphiphilic block copolymers PLA-b-PHMTYO-b-PLA with pendant hydroxyl groups. The composition and structure of prepared copolymers were characterized by (1)H nuclear magnetic resonance ((1)H NMR) spectroscopy, Fourier transform infrared (FT-IR) and gel permeation chromatography (GPC). The self-assembly behavior of the copolymers in water was investigated by transmission electron microscope (TEM), dynamic light scattering (DLS) and static light scattering (SLS). The results showed that the novel copolymers PLA-b-PHMTYO-b-PLA self-assembled into spherical micelles with diameters ranging from 100 nm to 200 nm in aqueous solution. These copolymers also exhibited low critical micellar concentrations (CMC: 6.9 × 10(-4)mg/mL and 3.9 × 10(-5)mg/mL, respectively). In addition, the in vitro cytotoxicity of these copolymers was determined in the presence of L929 cells. The results showed that the block copolymers PLA-b-PHMTYO-b-PLA exhibited better biocompatibility. Therefore, these well-defined copolymers are expected to find some applications in drug delivery or tissue engineering. PMID:25175206

  1. HA demonstration in the Atalante facility of the Ganex 2. cycle for the grouped TRU extraction

    International Nuclear Information System (INIS)

    The GANEX process (Group Actinide Extraction), developed by the CEA for the reprocessing of Generation IV spent nuclear fuel, is composed of two extraction cycles following the dissolution of the spent fuel. Once the uranium is selectively extracted from the dissolution solution, the transuranium elements (Np, Pu, Am, and Cm) are separated from the fission products in a second cycle, prior to their co-conversion step and their homogeneous recycling. The DIAMEX-SANEX process, initially developed for the partitioning of trivalent minor actinides (Am and Cm), was adapted to handle neptunium and plutonium along with americium and curium and selected as the reference route for the GANEX 2. cycle process. In the first step, actinides, lanthanides and other extractable fission products are co-extracted at high acidity by a mixture of a malonamide (DMDOHEMA) and an organophosphorous acid (HDEHP) diluted in HTP. In a second step, molybdenum, ruthenium and technetium are stripped from the solvent, before the selective recovery of all actinides by a mixture of HEDTA and citric acid at pH 3. The last step consists in stripping the remaining cations using specific aqueous complexing agents. Distribution ratios of actinides and major fission products were acquired at each step of the process and showed the possibility to adapt the DIAMEX-SANEX process to the group actinide extraction after adjusting experimental conditions (selection of complexing agents, optimization of reagent concentrations). From these batch experiments and from cold and hot counter-current tests, previously performed when studying minor actinide partitioning, a model was developed to describe the behaviour of the target elements. This model was implemented into our liquid-liquid process simulation code in order to design a flowsheet, which was tested in 48 mixer-settlers (laboratory scale) in the CBP hot cell (Atalante facility) on the high active raffinate issued from the GANEX 1. cycle test. (authors)

  2. Energy systems group environmental monitoring and facility effluent. Annual report 1979

    International Nuclear Information System (INIS)

    Soil, vegetation, and surface water were routinely sampled for radioactivity to a distance of 10 miles from Energy Systems Group (ESG) sites. Continuous ambient air sampling and radiation monitoring by thermoluminescent dosimetry are performed on-site for measuring airborne radioactivity concentrations and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from ESG facilities is continuously sampled and monitored to ensure that levels released to unrestricted areas are within appropriate limits, and to identify processes which may require additional engineering safeguards to minimize radioactivity levels in such effluents. In addition, selected nonradioactive constituent concentrations in surface water discharged to unrestrictted areas are determined. Monitoring results for 1979 are summarized and discussed. The random variations observed in the environmental monitoring data indicate that no local source of unnatural radioactive material exists in the environs. Additionally, the similarity between on-site and off-site results further indicates that the contribution to general environmental radioactivity due to operations at the ESG is essentially nonexistent. The environmental radioactivity reported herein is attributed to natural sources and to fallout of radioactive material from foreign atmospheric testing of nuclear devices

  3. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    Energy Technology Data Exchange (ETDEWEB)

    Austad, S. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-05-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  4. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    Energy Technology Data Exchange (ETDEWEB)

    Austad, Stephanie Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  5. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    International Nuclear Information System (INIS)

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  6. 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

  7. 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.)

  8. 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.)

  9. 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

  10. The benefits of Outsourcing facility services when selecting right service provider for a hotel:Case Kämp Group Oy

    OpenAIRE

    Paudyal, Manoj; Acharya, Saroj

    2015-01-01

    This research paper examines about the outsourcing of facility services in the Kämp group of hotels. The scope of the study includes Facility Management, outsourcing facilities services, and the selection process of the service providers for a hotel. The research was carried at the hotels of Kämp group Oy in the Metropolitan Area of Helsinki. Facility management includes wide ranges of non-core functions such as Property management, real estates, design and technology. Activities such as secu...

  11. Effects o f Electronic Banking Facilities, Employment Sector and Age - Group on Customers’ Choice o f Banks in Nigeria

    Directory of Open Access Journals (Sweden)

    Ahmed Audu Maiyaki

    2010-04-01

    Full Text Available The paper aims at investigating the relationships between the effects of electronic banking facilities, customers’ employment sector and customers’ age - group on th eir choice of banks. Both descriptive and inferential statistics were use. Five hundred copies of questionnaire were distributed and eventually 81.4 percent response rate was achieved. A multi - stage sampling design was employed; delivery and collection str ategy of data collection was also used. Chi - square statistical test of independence was employed. The results show that there is no significant relationship between electronic banking facilities and customers’ choice of banks. It was however found that the re is significant relationship between customers’ employment sector and customers’ age - group on one hand and their choice of banks on the other hand. It was recommended that the management of Nigerian commercial banks should find the relevant factors that are considered important by customers of various age group to appropriately segmenting the target market

  12. Information report issued in application of the article 146 of the regulation by the Commission for Finances, General Economy, and Budgetary Control on the development perspectives of AREVA and the future of the nuclear sector. Nr 2952

    International Nuclear Information System (INIS)

    As AREVA displays an unprecedented loss, and is facing a durable and persistent stagnation of its nuclear activities after the Fukushima accident, and as these losses are the consequences of misguided strategic decisions and disputable mining acquisitions, as well as of a problematic management of the main big industrial projects, this report comes after an intervention of the French President on the future of this company. The objectives are a restoration of Areva's competitiveness, and the elaboration of a new partnership between EDF and AREVA with a new definition of their respective roles in the design, manufacturing and selling of nuclear reactors. Notably based on hearings, and on visits of the Flamanville EPR site and of the La Hague reprocessing plant this reports aims at informing the French parliament on the different faced challenges and opportunities. The authors thus give an overview of the group financial situation and describe the important reorganisation issues. They analyse how the group has been weakened by its economic performance and a development mode with uncertain results. They try to define a possible future within the frame of a reorganised nuclear sector based on a high performance group, a good governance of the nuclear sector, an industrially consistent solution, and a relevant position for the French nuclear sector

  13. 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

  14. 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)

  15. 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

  16. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU'S) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment from doses to humans and animals and associated cancer risks, exposure via food chains, and historical data. (CBS)

  17. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU'S) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment from doses to humans and animals and associated cancer risks, exposure via food chains, and historical data

  18. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU's) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment and baseline human health evaluation including a toxicity assessment, and a baseline environmental evaluation

  19. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU's) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment and baseline human health evaluation including a toxicity assessment, and a baseline environmental evaluation.

  20. 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

  1. Psychosocial needs of a group of older people in a residential facility / Anna Petronella Zaaiman

    OpenAIRE

    Zaaiman, Anna Petronella

    2015-01-01

    This study, which is part of a research project conducted to explore the experiences of quality of life of older people living in a residential facility, focuses specifically on the psychosocial needs of these residents. Psychosocial needs refer to the innate psychological nutriments that prompt older people to take purposeful, self-directed action in an attempt to satisfy these needs and ultimately foster well-being. These may include needs for mastery, acknowledgement, social interaction an...

  2. 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

  3. 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)

  4. 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)

  5. 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)

  6. 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

  7. Organizational performance improvement through the development of a team-based facilities group.

    Science.gov (United States)

    Wanta, S A

    1997-11-01

    The support services division at Pennsylvania Hospital in Philadelphia developed and implemented a service concept to improve organizational effectiveness and service. The design of the new concept has five major elements: implementation of a team-based organization, establishment of individual performance criteria or standards, development of performance goals and objectives for the teams, individual staff development and a recognition program. This document discusses the elements of team design and implementation, stages of growth and the role that the other four components (performance standards, goals, staff development and recognition) play in achieving improved organizational performances. This case study is intended to show general management techniques that can be adopted into a facility's management plan. PMID:10173780

  8. Complementary safety assessment assessment of nuclear facilities - FBFC Romans plant - AREVA

    International Nuclear Information System (INIS)

    This complementary safety assessment analyses the robustness of the FBFC Romans plant to extreme situations such as those that led to the Fukushima accident. This plant is dedicated to the fabrication of nuclear fuels for experimental reactors. 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 4 main measures to be taken to limit the risks linked to natural disasters: -) the implementation of a seismic detection and cutting system; -) the seismic reinforcement of the recycling workshop (R1 building); -) the suppression of the use of recycled water in the AP2 building; -) the determination of the critical water levels admitted in the buildings in case of strong rain periods. (A.C.)

  9. On (Group) Strategy-Proof Mechanisms without Payment for Facility Location Games

    DEFF Research Database (Denmark)

    Thang, Nguyen Kim

    2010-01-01

    allowable location that minimizes the utilitarian social cost — the sum of agents costs. A mechanism is strategyproof (SP) if no agent may misreport its locations and be better off; it is group-strategyproof (GSP) if no coalition of agents benefits by jointly misreporting their locations The requirement for...

  10. Inferring Groups of Objects, Preferred Routes, and Facility Locations from Trajectories

    DEFF Research Database (Denmark)

    Ceikute, Vaida

    In today’s society, GPS-enabled devices are used widely. A broad range of location-based services (LBS) allow users to receive and share information related to their positions. Thus, it is possible to accumulate GPS data, and it is expected that the amount of available GPS data will increase very...... substantially in the years to come. The availability of such GPS data holds huge potential to improve existing LBS or lead to the creation of new ones. This thesis investigates the use of GPS data in three different areas. Specifically, from GPS data we obtain trajectories of moving objects, from which we can......-independent approach that makes no assumptions about when object positions are sampled and that supports the use of approximate trajectories. The framework’s algorithms exploit density-based clustering to identify groups. Such identified groups are scored based on cardinality and duration. With the use of domination...

  11. Establishing a LEU MTR fuel manufacturing facility in South Africa

    International Nuclear Information System (INIS)

    The South African MTR Fuel Manufacturing Facility was established in the 1970's to supply SAFARI-1 with Fuel Elements and Control Rods. South African capability was developed in parallel with the uranium enrichment program to meet the needs of the Reactor. Further to the July 2005 decision by the South African Governmnent to convert both SAFARI-1 and the Fuel Plant to LEU, the SAFARI-1 phase has been successfully completed and Necsa has commenced with the conversion of the MTR Fuel Manufacturing Facility. In order to establish, validate and qualify the facility, Necsa has entered into a co-operation and technology transfer agreement with AREVA CERCA, the French manufacturer of Research Reactor fuel elements. Past experiences, conversion challenges and the status of the MTR Fuel Facility Project are discussed. On-going co-operation with AREVA CERCA to implement the local manufacture of LEU fuel is explained and elaborated on. (author)

  12. The GMF (Group of European Municipalities with Nuclear Facilities) conference at Cernavoda. Opening talk

    International Nuclear Information System (INIS)

    Cernavoda NPP by 2015. Romania supports the idea of organizing an European debate related to the future of the nuclear energy. Finally, he stressed the good relationship of the Cernavoda NPP and Mioveni nuclear facility with local communities, as important contributors to the local municipality budget and also, in case of Cernavoda NPP, as the cheapest heating supplier in Romania

  13. 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.

  14. 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.

  15. Site characterization summary report for the Old Hydrofracture Facility, Waste Area Grouping 5, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This site characterization summary report summarizes the operational history and other information on the Old Hydrofracture Facility located in the Waste Area Grouping 5 at the Oak Ridge National Laboratory. The Old Hydrofracture Facility was a waste disposal facility that operated from the 1960s until 1979. Intermediate-level radioactive waste was mixed with grout and injected deep underground for permanent disposal. Facilities at the site include various buildings, pipes, waste pits, and five underground storage tanks that contain liquid and sludge that have been characterized as low-level, hazardous, and mixed wastes.

  16. Site characterization summary report for the Old Hydrofracture Facility, Waste Area Grouping 5, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    This site characterization summary report summarizes the operational history and other information on the Old Hydrofracture Facility located in the Waste Area Grouping 5 at the Oak Ridge National Laboratory. The Old Hydrofracture Facility was a waste disposal facility that operated from the 1960s until 1979. Intermediate-level radioactive waste was mixed with grout and injected deep underground for permanent disposal. Facilities at the site include various buildings, pipes, waste pits, and five underground storage tanks that contain liquid and sludge that have been characterized as low-level, hazardous, and mixed wastes

  17. VENUS-7 plutonium recycling benchmark, results of AREVA NP

    International Nuclear Information System (INIS)

    Solutions for the NBA VENUS-7 plutonium recycling benchmark are presented in this paper. Various few-group 3D transport calculations were performed with pin cell homogenized cross sections, mostly generated by CASMO-4 ('L-Lib' based on ENDF/B data). In addition, also 2D solutions with a finer energy group structure are presented. In general the calculated reactivity effects agree well with the measured ones. A comparison with other VENUS configurations indicates that the reactivity of the MOX pins with Inconel 800 cladding seems to be slightly under-estimated. The calculated fission rates in the VENUS-7/1 configurations show good agreement with the measured fission rate traverses. This is also confirmed by a VENUS-9/0 analysis where preliminary measured fission rate data were available also at the water reflector, displaying the strong peaking at this reflector boundary. (authors)

  18. Areva At December 31, 2010: Revenue rises to euros 9.104 bn: + 6.7% Backlog rises to euros 44.2 bn: + 2.0%

    International Nuclear Information System (INIS)

    In 2010, AREVA's consolidated revenue rose 6.7% to 9.104 billion euros (+ 5.1% growth like-for-like) compared with 2009. The Mining-Front End Business Group and the Reactors and Services Business Group were the leading growth engines, with revenue growth of 6.7% and 8.9% respectively. Foreign exchange had a positive impact of 141 million euros and the scope of consolidation remained stable over the period. Fourth quarter 2010 revenue totaled 2.936 billion euros, an increase of 7.7% (+4.8% like-for-like) compared with the fourth quarter of 2009, due in particular to 18.1% growth in the Mining-Front End BG. Foreign exchange had an impact of 58 million euros over the period. The group's backlog came to 44.2 billion euros at December 31, 2010, up 2.0% in relation to December 31, 2009. The backlog grew in the Mining-Front End and Renewable Energies BGs. Installed Base Business operations held up well, replenishing the backlog for the Reactors and Services BG. The agreement with the Indian utility NPCIL concerning the construction of two EPRTM reactors and fuel cycle supply for 25 years was not recorded in the backlog at December 31, 2010. The change in the Back End BG's backlog reflects the implementation of contracts signed in previous years. Nearly one billion euros in letters of intent signed in 2010 with US utilities corresponding to pre-sold production from the future enrichment plant were not included in the Mining-Front End BG's backlog. The backlog of the Mining-Front End BG came to 28.902 billion euros at December 31, 2010, up 4% compared with the end of 2009. Contracts won in 2010 include: - the 10-year uranium supply contract with CGNPC for approximately 3.5 billion dollars; - several other multi-year contracts signed in the front end of the cycle with US and Asian utilities. For the full year of 2010, the Mining-Front End BG reported revenue of 3.704 billion euros, an increase of 6.7% on a reported basis and of 4.2% LFL. Foreign exchange had a positive

  19. 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

  20. 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.

  1. 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)

  2. 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)

  3. 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)

  4. 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

  5. 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)

  6. Application of Safety Assessment Methodology for Near Surface Waste Disposal Facilities (ASAM) - Regulatory Review Working Group Safety Case

    International Nuclear Information System (INIS)

    Vincent Nys (AVN, Belgium) presented the IAEA international projects ISAM/ASAM. ASAM (application of methodology developed under ISAM) began in 2002 as a follow-up of ISAM (project to develop methodology for near-surface disposals e.g. scenarios). One of the objectives of the working group of the ISAM project was to provide definitions, to look at the integration of the safety assessment and at the review procedure. The NEA international FEP's database was used and adapted to the near-surface context. The so-called 'design scenario' might be defined as the expected scenario according to functions. Building confidence in each stage is related to the confidence in the system, the scenarios process, and the assessment context. With regards to the on-going ASAM project, participants acknowledged that the safety case contains both a safety assessment and a confidence statement. Additionally, traceability and transparency are of importance. The management framework, e.g. clear regulatory framework and clear regulatory process (review procedure), is a key element for the success of a safety case. The use of what-if scenarios could be helpful for testing the robustness of the design. It was also noted that at each stage of a safety case, the implementers should always give alternatives and should argue the choice of the reference (reversibility of the process). IGSC members noted that the safety case of near-surface disposal facilities has much in common with the safety case for deep disposal facilities. Discussion suggested that the definition and achievement of 'optimization' are open issues in the post-closure safety context. Optimisation has a generally accepted meaning in the context of achieving safety in the operational phase

  7. Areva at September 30, 2013: Backlog of euro 42 bn Robust revenue growth to euro 6.847 bn: +4.7% vs. Sept. 2012 (+7.6% like for like) Strong organic growth (+9.9%) in the nuclear operations

    International Nuclear Information System (INIS)

    After a remarkable first half and as anticipated, Areva's third quarter revenue was stable in the nuclear operations compared with the third quarter of 2012. Globally, Areva's nuclear operations generated organic growth of 10% in the first nine months of 2013. This performance demonstrates the strength of Areva's commercial positions in the installed base market, where the company continues to innovate while improving its competitiveness. The success of Areva's integrated offers and of its Safety Alliance and Forward Alliance programs are perfect examples of this. Moreover, agreements signed for the EDF project at Hinkley Point strengthen Areva's position in the new builds market and bolster the credibility of Areva's EPRTM offers to other customers. In the Renewable Energies BG, revenue is below Areva's Action 2016 plan outlook, mainly due to the current indecisiveness in the renewable markets. Based on Areva's performance over the past nine months, the company confirms its revenue outlook for its business as a whole in 2013. AREVA generated consolidated revenue of 6.847 billion euros in the first nine months of 2013, representing growth of 4.7% (+7.6% like for like) compared with the same period in 2012. Revenue growth was fueled by a 7.7% increase in recurring business (+11.0% like for like). Revenue from nuclear operations was 6.453 billion euros in the first nine months of 2013, compared with 6.035 billion euros in the first nine months of 2012, a 6.9% increase (+9.9% like for like). Revenue was led by growth in all nuclear Business Groups (BG): the Mining BG (+31.8% like for like), the Front End BG (+9.8% like for like), the Reactors and Services BG (+1.5% like for like) and the Back End BG (+10.3% like for like). Revenue fell 24.6% like for like in the renewable operations. Foreign exchange had a negative impact of 71 million euros during the period. The change in consolidation scope had a negative impact of 106 million euros. In the third quarter of 2013

  8. Areva At September 30, 2010: Revenue growth to euro 6.168 bn: + 6.3%. Backlog growth to euro 42.7 bn: + 2.2%

    International Nuclear Information System (INIS)

    AREVA generated consolidated revenue of 6.168 billion euros over the first nine months of 2010 for growth of 6.3% (+5.2% like-for-like) compared with the same period in 2009. The main revenue growth engines were the Reactors and Services Business Group and the Back End Business Group, with growth of 11.5% and 7.1% respectively. Foreign exchange had a positive impact of 82 million euros over the period, while changes in consolidation scope had negligible impact. Third quarter 2010 revenue amounted to 2.011 billion euros for growth of 6.1% (+4.4% LFL) compared with the third quarter of 2009. The Reactors and Services Business Group and the Back End Business Group, posting increases of 11.2% and 9.0% respectively, continued to lead this growth. Foreign exchange had a positive impact of 39 million euros, while changes in consolidation scope had negligible impact. The group's backlog came to 42.7 billion euros at September 30, 2010, an increase of 2.2% compared with September 30, 2009 (41.8 billion euros). For the full year of 2010, the group confirms its outlook for significant revenue and backlog growth, increased operating performance excluding particular items, negative operating income, and strong growth in net income attributable to owners of the group with the contribution of the gain on the sale of the Transmission and Distribution business

  9. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Kannard, J. R.; Wilson, R. C.; Zondlo, T. F.

    1991-09-01

    This report describes the borehole geophysical logging performed at selected monitoring wells at waste area grouping (WAG) 6 of Oak Ridge National Laboratory in support of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI). It identifies the locations and describes the methods, equipment used in the effort, and the results of the activity. The actual logs for each well logged are presented in Attachment 1 through 4 of the TM. Attachment 5 provide logging contractor service literature and Attachment 6 is the Oak Ridge National Laboratory (ORNL) Procedure for Control of a Nuclear Source Utilized in Geophysical logging. The primary objectives of the borehole geophysical logging program were to (1) identify water-bearing fractured bedrock zones to determine the placement of the screen and sealed intervals for subsequent installation, and (2) further characterize local bedrock geology and hydrogeology and gain insight about the deeper component of the shallow bedrock aquifer flow system. A secondary objective was to provide stratigraphic and structural correlations with existing logs for Hydraulic Head Monitoring Station (HHMS) wells, which display evidence of faulting.

  10. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    This report provides a detailed summary of the activities carried out to sample groundwater at Waste Area Grouping (WAG) 6. The analytical results for samples collected during Phase 1, Activity 2 of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI) are also presented. In addition, analytical results for Phase 1, activity sampling events for which data were not previously reported are included in this TM. A summary of the groundwater sampling activities of WAG 6, to date, are given in the Introduction. The Methodology section describes the sampling procedures and analytical parameters. Six attachments are included. Attachments 1 and 2 provide analytical results for selected RFI groundwater samples and ORNL sampling event. Attachment 3 provides a summary of the contaminants detected in each well sampled for all sampling events conducted at WAG 6. Bechtel National Inc. (BNI)/IT Corporation Contract Laboratory (IT) RFI analytical methods and detection limits are given in Attachment 4. Attachment 5 provides the Oak Ridge National Laboratory (ORNL)/Analytical Chemistry Division (ACD) analytical methods and detection limits and Resource Conservation and Recovery Act (RCRA) quarterly compliance monitoring (1988--1989). Attachment 6 provides ORNL/ACD groundwater analytical methods and detection limits (for the 1990 RCRA semi-annual compliance monitoring)

  11. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    This report describes the borehole geophysical logging performed at selected monitoring wells at waste area grouping (WAG) 6 of Oak Ridge National Laboratory in support of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI). It identifies the locations and describes the methods, equipment used in the effort, and the results of the activity. The actual logs for each well logged are presented in Attachment 1 through 4 of the TM. Attachment 5 provide logging contractor service literature and Attachment 6 is the Oak Ridge National Laboratory (ORNL) Procedure for Control of a Nuclear Source Utilized in Geophysical logging. The primary objectives of the borehole geophysical logging program were to (1) identify water-bearing fractured bedrock zones to determine the placement of the screen and sealed intervals for subsequent installation, and (2) further characterize local bedrock geology and hydrogeology and gain insight about the deeper component of the shallow bedrock aquifer flow system. A secondary objective was to provide stratigraphic and structural correlations with existing logs for Hydraulic Head Monitoring Station (HHMS) wells, which display evidence of faulting

  12. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    This report provides a detailed summary of the activities carried out to sample groundwater at Waste Area Grouping (WAG) 6. The analytical results for samples collected during Phase 1, Activity 2 of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI) are also presented. In addition, analytical results for Phase 1, activity sampling events for which data were not previously reported are included in this TM. A summary of the groundwater sampling activities of WAG 6, to date, are given in the Introduction. The Methodology section describes the sampling procedures and analytical parameters. Six attachments are included. Attachments 1 and 2 provide analytical results for selected RFI groundwater samples and ORNL sampling event. Attachment 3 provides a summary of the contaminants detected in each well sampled for all sampling events conducted at WAG 6. Bechtel National Inc. (BNI)/IT Corporation Contract Laboratory (IT) RFI analytical methods and detection limits are given in Attachment 4. Attachment 5 provides the Oak Ridge National Laboratory (ORNL)/Analytical Chemistry Division (ACD) analytical methods and detection limits and Resource Conservation and Recovery Act (RCRA) quarterly compliance monitoring (1988--1989). Attachment 6 provides ORNL/ACD groundwater analytical methods and detection limits (for the 1990 RCRA semi-annual compliance monitoring).

  13. 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

  14. Areva At December 31, 2010: Revenue rises to euros 9.104 bn: + 6.7% Backlog rises to euros 44.2 bn: + 2.0%; Areva au 31 decembre 2010: Croissance du chiffre d'affaires a 9104 Meuros: + 6,7 % Croissance du carnet de commandes a 44,2 Mdseuros: + 2,0 %

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    In 2010, AREVA's consolidated revenue rose 6.7% to 9.104 billion euros (+ 5.1% growth like-for-like) compared with 2009. The Mining-Front End Business Group and the Reactors and Services Business Group were the leading growth engines, with revenue growth of 6.7% and 8.9% respectively. Foreign exchange had a positive impact of 141 million euros and the scope of consolidation remained stable over the period. Fourth quarter 2010 revenue totaled 2.936 billion euros, an increase of 7.7% (+4.8% like-for-like) compared with the fourth quarter of 2009, due in particular to 18.1% growth in the Mining-Front End BG. Foreign exchange had an impact of 58 million euros over the period. The group's backlog came to 44.2 billion euros at December 31, 2010, up 2.0% in relation to December 31, 2009. The backlog grew in the Mining-Front End and Renewable Energies BGs. Installed Base Business operations held up well, replenishing the backlog for the Reactors and Services BG. The agreement with the Indian utility NPCIL concerning the construction of two EPR{sup TM} reactors and fuel cycle supply for 25 years was not recorded in the backlog at December 31, 2010. The change in the Back End BG's backlog reflects the implementation of contracts signed in previous years. Nearly one billion euros in letters of intent signed in 2010 with US utilities corresponding to pre-sold production from the future enrichment plant were not included in the Mining-Front End BG's backlog. The backlog of the Mining-Front End BG came to 28.902 billion euros at December 31, 2010, up 4% compared with the end of 2009. Contracts won in 2010 include: - the 10-year uranium supply contract with CGNPC for approximately 3.5 billion dollars; - several other multi-year contracts signed in the front end of the cycle with US and Asian utilities. For the full year of 2010, the Mining-Front End BG reported revenue of 3.704 billion euros, an increase of 6.7% on a reported basis and of 4.2% LFL. Foreign

  15. 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

  16. 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)

  17. 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

  18. 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)

  19. 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

  20. 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

  1. 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.)

  2. 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.)

  3. 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

  4. Site characterization summary report for the Old Hydrofracture Facility, Waste Area Grouping 5, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    The Old Hydrofracture (OHF) Facility was an experimental waste disposal test site located at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. ORNL is a research facility owned by the U.S. Department of Energy (DOE) and managed by Lockheed Martin Energy Research Corp. Legacy environmental restoration sites, such as the OHF Facility, are managed for DOE by Lockheed Martin Energy Systems, Inc. This report summarizes the known conditions at the OHF Facility located in the southwest comer of Waste Area Grouping (WAG) 5 at ORNL. The facility covers about I acre within the approximate ORNL grid coordinates N17100-N17300 and E28500-E28700. The facility was used for the injection of liquid intermediate-level wastes (ILW) into a shale formation well below ground surface as a means of permanent disposal. Wastes remaining at the site after the last series of injections in 1980 can be found in buildings, waste pits, the retention pond, tanks, and piping. Based on a recent assessment of risk posed by these wastes, the contents of the tanks will be removed. Characterization data collected to date are provided in this report to facilitate waste removal activities.

  5. Site characterization summary report for the Old Hydrofracture Facility, Waste Area Grouping 5, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    The Old Hydrofracture (OHF) Facility was an experimental waste disposal test site located at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. ORNL is a research facility owned by the U.S. Department of Energy (DOE) and managed by Lockheed Martin Energy Research Corp. Legacy environmental restoration sites, such as the OHF Facility, are managed for DOE by Lockheed Martin Energy Systems, Inc. This report summarizes the known conditions at the OHF Facility located in the southwest comer of Waste Area Grouping (WAG) 5 at ORNL. The facility covers about I acre within the approximate ORNL grid coordinates N17100-N17300 and E28500-E28700. The facility was used for the injection of liquid intermediate-level wastes (ILW) into a shale formation well below ground surface as a means of permanent disposal. Wastes remaining at the site after the last series of injections in 1980 can be found in buildings, waste pits, the retention pond, tanks, and piping. Based on a recent assessment of risk posed by these wastes, the contents of the tanks will be removed. Characterization data collected to date are provided in this report to facilitate waste removal activities

  6. 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)

  7. 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...

  8. 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)

  9. 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)

  10. Feasibility and effectiveness of a combined individual and psychoeducational group intervention in psychiatric residential facilities: A controlled, non-randomized study.

    Science.gov (United States)

    Magliano, Lorenza; Puviani, Marta; Rega, Sonia; Marchesini, Nadia; Rossetti, Marisa; Starace, Fabrizio

    2016-01-30

    This controlled, non-randomized study explored the feasibility of introducing a Combined Individual and Group Intervention (CIGI) for users with mental disorders in residential facilities, and tested whether users who received the CIGI had better functioning than users who received the Treatment-As-Usual (TAU), at two-year follow up. In the CIGI, a structured cognitivebehavioral approach called VADO (in English, Skills Assessment and Definition of Goals) was used to set specific goals with each user, while Falloon's psychoeducational treatment was applied with the users as a group. Thirty-one professionals attended a training course in CIGI, open to users' voluntary participation, and applied it for two years with all users living in 8 residential facilities of the Mental Health Department of Modena, Italy. In the same department, 5 other residential facilities providing TAU were used as controls. ANOVA for repeated measures showed a significant interaction effect between users' functioning at baseline and follow up assessments, and the intervention. In particular, change in global functioning was higher in the 55 CIGI users than in the 44 TAU users. These results suggest that CIGI can be successfully introduced in residential facilities and may be useful to improve functioning in users with severe mental disorders. PMID:26723137

  11. 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

  12. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3, Appendixes 1 through 8: Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU`S) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment from doses to humans and animals and associated cancer risks, exposure via food chains, and historical data. (CBS)

  13. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 2, Sections 4 through 9: Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU`s) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment and baseline human health evaluation including a toxicity assessment, and a baseline environmental evaluation.

  14. 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

  15. 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

  16. 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)

  17. Energy infrastructure of the United States and projected siting needs: Scoping ideas, identifying issues and options. Draft report of the Department of Energy Working Group on Energy Facility Siting to the Secretary

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    A Department of Energy (DOE) Working Group on Energy Facility Siting, chaired by the Policy Office with membership from the major program and staff offices of the Department, reviewed data regarding energy service needs, infrastructure requirements, and constraints to siting. The Working Group found that the expeditious siting of energy facilities has important economic, energy, and environmental implications for key Administration priorities.

  18. 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

  19. Areva - 2013 revenue of euro 9.3 bn thanks to sustained level of activity. Organic growth in the nuclear operations: + 7%, above our financial outlook. Backlog of euro 41.6 bn

    International Nuclear Information System (INIS)

    Two years after Fukushima, AREVA's level of activity was especially strong in 2013. The group outperformed its revenue outlook for nuclear operations with an organic growth of 7.1%. With more than 9 billion euros, the group's revenue benefited from the robustness of the recurring activities and from temporary elements, such as exceptionally high uranium sales. This growth demonstrates the resilience of Areva's end market, despite unfavourable current conditions, and the efficient match between its commercial offers and customers' expectations. Capitalizing on this dynamic, the group will continue its recovery in order to sustainably self-finance its capital expenditures. After the announcement on January 20, 2014 of exclusive negotiations with Gamesa for the creation of a joint company in the offshore wind field (50% AREVA, 50% Gamesa), and in accordance with IFRS 5 accounting standard, revenue generated by the Wind Energy business is not included in group revenue for 2012 and 2013 and the result of this business will be presented on a separate line, 'net income from discontinued operations' in the 2013 financial statements. In 2013, AREVA had consolidated revenue of 9.303 billion euros, an increase of 3.8% (+6.3% like for like) compared with 2012 benefiting from strong organic growth in the nuclear operations: - Revenue in the nuclear operations was 9.042 billion euros in 2013, compared with 8.633 billion euros in 2012, a 7.1% increase (+4.7% on a reported basis). Revenue was led by the Mining BG (+40.6% like for like) and the Front End BG (+7.5% like for like), offsetting the expected business downturn in the Reactors and Services BG (-1.5% like for like). Revenue was stable in the Back End BG (-0.6% like for like). - The Renewable Energies BG had 132 million euros in revenue, down from 2012 (-24.7% like for like). - Foreign exchange had a negative impact of 101 million euros, while the change in consolidation scope and accounting methods had a negative impact of

  20. The Integral Test Facility Karlstein

    Directory of Open Access Journals (Sweden)

    Stephan Leyer

    2012-01-01

    Full Text Available The Integral Test Facility Karlstein (INKA test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant Accident scenarios at the test facility. The INKA test facility represents the KERENA Containment with a volume scaling of 1 : 24. Component heights and levels are in full scale. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein—a vessel with a design pressure of 11 MPa and a storage capacity of 125 m3. The vessel is fed by a benson boiler with a maximum power supply of 22 MW. The INKA multi compartment pressure suppression Containment meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios, including a full train of passive systems, starting with the initiating event—for example pipe rupture.

  1. The Integral Test Facility Karlstein

    International Nuclear Information System (INIS)

    The Integral Test Facility Karlstein (INKA) test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant Accident scenarios at the test facility. The INKA test facility represents the KERENA Containment with a volume scaling of 1?:?24. Component heights and levels are in full scale. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein vessel with a design pressure of 11?MPa and a storage capacity of 125?m3. The vessel is fed by a benson boiler with a maximum power supply of 22?MW. The INKA multi compartment pressure suppression Containment meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios, including a full train of passive systems, starting with the initiating event for example pipe rupture.

  2. 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

  3. 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

  4. 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.)

  5. 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)

  6. 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.)

  7. 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)

  8. 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.

  9. Facility with the English language and problem-based learning group interaction: findings from an Arabic setting.

    Science.gov (United States)

    Mpofu, D J; Lanphear, J; Stewart, T; Das, M; Ridding, P; Dunn, E

    1998-09-01

    The Faculty of Medicine and Health Sciences (FMHS), United Arab Emirates (UAE) University is in a unique position to explore issues related to English language proficiency and medical student performance. All students entering the FMHS have English as a second language. This study focused on the issues of students' proficiency in English as measured by the TOEFL test, student background factors and interaction in problem-based learning (PBL) groups. Using a modification of Bales Interaction Process Analysis, four problem-based learning groups were observed over four thematic units, to measure the degree of student interaction within PBL groups and to compare this to individual TOEFL scores and key background variables. The students' contributions correlated highly with TOEFL test results in the giving of information (range r = 0.67-0.74). The female students adhered to interacting in English during group sessions, whereas the male students were more likely to revert to using Arabic in elaborating unclear phenomena (p TOEFL scores for the male students, but not for female students. Multivariate analysis was undertaken to analyse the relative contribution of the TOEFL, parental education and years of studying in English. The best predictor of students' contributions in PBL groups was identified as TOEFL scores. The study demonstrates the importance of facilitating a locally acceptable level of English proficiency prior to admission to the FMHS. However, it also highlights the importance of not focusing only on English proficiency but paying attention to additional factors in facilitating medical students in maximizing benefits from interactions in PBL settings. PMID:10211288

  10. 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

  11. 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)

  12. 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)

  13. Areva at March 31, 2014: Downturn in revenue as anticipated, to euro 1.781 bn (-17.3% like for like), Backlog of euro 40.2 bn

    International Nuclear Information System (INIS)

    Following the marked growth of the nuclear operations in 2013, thanks in particular to the strength of recurring activities and the contribution of exceptional items such as significant uranium sales volumes and non-recurring foreign contracts, revenue in the first quarter of the year fell sharply, as Areva had anticipated. A strong seasonal effect will materialize in 2014, with greater activity to be expected in the second half of the year. As indicated when releasing 2013 annual results, the current economic environment is still unfavorable, with market prices deteriorating in the front end of the cycle and lackluster demand from customers for installed base services. AREVA's operations generated consolidated revenue of 1.781 billion euros in the first quarter of 2014, a decrease of 18.1% (-17.3 % like for like) compared with the same period in 2013. The Front End Business Group (BG) reported strong growth of +59.0% (+59.8% like for like). Revenue was down in the Mining, Reactors and Services, Back End and Renewable Energies BGs, at -63.0% (-62.3% like for like), -14.1% (-12.5% like for like), -41.7% (-41.6% like for like) and -38.2% (-34.6% like for like) respectively. Foreign exchange had a negative impact of 18 million euros over the period, while the change in consolidation scope had a negative impact of 3 million euros. The group's backlog reached 40.2 billion euros at March 31, 2014, a decrease of 2.9% compared with December 31, 2013 and of 8.8% year on year

  14. Proceedings of 1991-workshops of the working group on 'Development and application of facilities for low temperature irradiation as well as controlled irradiation'

    International Nuclear Information System (INIS)

    This is the proceedings of 1991-workshops of the working group on 'Development and Application of Facilities for Low Temperature Irradiation as well as Controlled Irradiation' held at the Research Reactor Institute of Kyoto University on July 25, 1991 and on February 28, 1992. In the present proceedings, it is emphasized that the study of radiation damages in various materials must be performed under carefully controlled irradiation conditions (irradiation temperature, neutron spectrum and so forth) during reactor irradiations. Especially, it is pointed out that a middle scale reactor such as KUR is suitable for the precise control of neutron spectra. Several remarkable results, which are made through experiments using the Low Temperature Irradiation Facility in KUR (KUR-LTL), are reported. Also, possible advanced research programs are discussed including the worldwide topics on the radiation damages in metals, semi-conductors and also insulators. Further, the present status of KUR-LTL is reported and the advanced plan of the facility is proposed. (author)

  15. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    WAG 6 comprises a shallow land burial facility used for disposal of low-level radioactive wastes (LLW) and, until recently, chemical wastes. As such, the site is subject to regulation under RCRA and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). To comply with these regulations, DOE, in conjunction with the Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC), developed a strategy for closure and remediation of WAG 6 by 1997. A key component of this strategy was to complete an RFI by September 1991. The primary objectives of the RFI were to evaluate the site's potential human health and environmental impacts and to develop a preliminary list of alternatives to mitigate these impacts. The WAG 6 one of three solid waste management units evaluated Oak Ridge National Laboratory (ORNL) existing waste disposal records and sampling data and performed the additional sampling and analysis necessary to: describe the nature and extent of contamination; characterize key contaminant transport pathways; and assess potential risks to human health and the environment by developing and evaluating hypothetical receptor scenarios. Estimated excess lifetime cancer risks as a result for exposure to radionuclides and chemicals were quantified for each hypothetical human receptor. For environmental receptors, potential impacts were qualitatively assessed. Taking into account regulatory requirements and base line risk assessment results, preliminary site closure and remediation objectives were identified, and a preliminary list of alternatives for site closure and remediation was developed.

  16. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    WAG 6 comprises a shallow land burial facility used for disposal of low-level radioactive wastes (LLW) and, until recently, chemical wastes. As such, the site is subject to regulation under RCRA and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). To comply with these regulations, DOE, in conjunction with the Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC), developed a strategy for closure and remediation of WAG 6 by 1997. A key component of this strategy was to complete an RFI by September 1991. The primary objectives of the RFI were to evaluate the site's potential human health and environmental impacts and to develop a preliminary list of alternatives to mitigate these impacts. The WAG 6 one of three solid waste management units evaluated Oak Ridge National Laboratory (ORNL) existing waste disposal records and sampling data and performed the additional sampling and analysis necessary to: describe the nature and extent of contamination; characterize key contaminant transport pathways; and assess potential risks to human health and the environment by developing and evaluating hypothetical receptor scenarios. Estimated excess lifetime cancer risks as a result for exposure to radionuclides and chemicals were quantified for each hypothetical human receptor. For environmental receptors, potential impacts were qualitatively assessed. Taking into account regulatory requirements and base line risk assessment results, preliminary site closure and remediation objectives were identified, and a preliminary list of alternatives for site closure and remediation was developed

  17. Predictors of attendance to group exercise: a cohort study of older adults in long-term care facilities

    OpenAIRE

    Finnegan, Susanne; Bruce, Julie; Lamb, Sarah E; Griffiths, Frances

    2015-01-01

    Background The benefits of regular exercise and physical activity are well known. Those living in long-term care are often frail, but have the potential to benefit from physical activity; yet are less likely to be offered exercise. Promoting exercise within residential and nursing homes may reduce health risks associated with inactivity in this population. The aim of this cohort study is to identify predictors of attendance at physiotherapy led exercise groups offered to older adults residing...

  18. 75 FR 62895 - Notice of Availability of Safety Evaluation Report; AREVA Enrichment Services LLC, Eagle Rock...

    Science.gov (United States)

    2010-10-13

    ... Project Manager, Advanced Fuel Cycle, Enrichment, and Uranium Conversion, Division of Fuel Cycle Safety... material in a gas centrifuge uranium enrichment facility. The applicant proposes that the facility, known..., decommissioning, management measures, physical protection, and materials control and accountability. III....

  19. 76 FR 9054 - Notice of Availability of Final Environmental Impact Statement for the AREVA Enrichment Services...

    Science.gov (United States)

    2011-02-16

    ..., operation, and decommissioning of a gas centrifuge-based uranium enrichment facility on a presently... Facility), 74 FR. 38052 (July 30, 2009). NRC's Public Document Room (PDR): The public may examine and have... the proposed uranium enrichment facility. The application included an Environmental Report...

  20. 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.)

  1. A 39 neutron group self-shielded cross section library for the Lotus fusion-fission test facility

    International Nuclear Information System (INIS)

    A 39 neutron group cross section library for fusion fission blanket calculations and especially for the analysis of the LOTUS experiment has been processed using the NJOY system. The library has been generated mostly using the ENDF/B-IV basic files at 296 K. All cross sections were self-shielded using the Bondarenko method. 5 background cross sections, namely 1010, 104, 102, 10 and 1 barns respectively were considered. The tabulated dilution dependent cross sections have been interpolated with the code TRANSX-CTR which is adequate for fusion applications. The fission spectrum of the fissionable material thorium has been collapsed from the fission matrices using the Bondarenko weighting scheme. The correct geometry of the LOTUS blanket and the cell specifications were correctly considered in the interpolation scheme. Some reaction cross sections for dosimetry applications have been included into the library. These base on the more recent ENDF/B-V evaluation. Transport and response edit cross sections have been coupled in the usual way to form P0 - P3 card image tables. Furthermore they have been converted into a binary file suitable to our RSYST computational system. Moreover the cross section card image tables have been reformatted and fitted into a BXSLIB binary library for the LANL-ONEDANT transport module. (Auth.)

  2. Inter-CLI work-group: safety after Fukushima

    International Nuclear Information System (INIS)

    This document contains a whole set of questions asked about nuclear safety and security by a work-group made of members of associations belonging to local information commissions. These questions are asked either to the French State, or to EDF, or to AREVA. They bear on general issues common to La Hague and Flamanville nuclear installations, notably public information, emergency plans, post-accident management, subcontracting, loss of electricity supply, public health, governance, computer hacking, extreme meteorological events. A set of questions concerns the AREVA processing plant in La Hague (warehousing, pools for irradiated fuels, plutonium oxide storage and warehousing, and so on), and another set concerns the Flamanville nuclear power plant (different aspects of the management of a crisis situation). The last set of questions concerns the Manche nuclear waste storage centre

  3. 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

  4. Permanent group of experts for nuclear pressure equipment (GPESPN) - Session of the 14 September 2011: Repair operations of the vessel cover for the Flamanville 3 PWR reactor

    International Nuclear Information System (INIS)

    This report discusses elements stated by AREVA to justify the management of the process which has been defined to repair the vessel cover of the Flamanville PWR, and whether controls and measures aimed at the detection and correction of possible shifts of this process are adapted. The different steps of this process are discussed: buttering and welding, thermal treatment operations, design of the repaired cover. Recommendations are given by the expert group. Some related documents sent by the ASN to AREVA are present in appendix

  5. 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

  6. 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

  7. 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

  8. INRA Integrated Fuel Recycling Facility Solid Waste Management

    International Nuclear Information System (INIS)

    This paper presents an overview of the Integrated Fuel Recycling Facility solid waste management process for the Pre-Conceptual Design of the facility proposed by the International Nuclear Recycling Alliance (INRA) Team. Wastes estimates and expected activity level are provided. The low volume of expected produced waste benefits from years of experience and feedback from La Hague operations, where a determined waste management strategy has been implemented. All waste management information presented in this paper is based on existing industrial experience in AREVA facilities in France. Specific US and site specific local requirements that are not fully assessed yet may impact waste forms and quantities. Some process optimizations are still possible that would decrease the number of residues (most notably for low level waste), dependent on potential disposal paths in the U.S. and the associated waste acceptance criteria of the receiving facilities. (authors)

  9. The MELOX MOX fabrication facility: history of an industrial success and future prospects

    International Nuclear Information System (INIS)

    Along with the La Hague reprocessing plant, MELOX is part of the two industrial facilities that ensure the closure of the nuclear fuel cycle in France. Since started up in 1995, MELOX has specialized into recycling separated plutonium recovered from reprocessing operations performed at La Hague on spent UO2 fuel. Capitalizing on the unique know-how acquired through thirty years of plutonium-based fuel fabrication at the Cadarache plant, this subsidiary of AREVA group has quickly become a worldwide expert in the industrial process of fabricating MOX: a fuel blend comprised of both uranium and plutonium oxides that allows at safely exploiting the energetic potential of plutonium. In order to address the various factors responsible for this industrial breakthrough, we will first present an overview of MELOX's history in regards of the emergence of a global MOX market. The added-value provided through treatment and recycling operations on spent fuel will be further described in terms of waste volume and radiotoxicity reduction. The emphasis will then be put on the total quality management policy that is at the core of MELOX's corporate strategy. Because MELOX has succeeded in meeting both productivity requirements and stringent quality constraints, it has won confidence from its European and Japanese clients. With increased production capacity of diversified MOX designs, MELOX is demonstrating the industrial efficiency of a new concept of MOX plants that is inspiring large construction projects in Japan, the US, and Russia. (authors)

  10. 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)

  11. Adapting Dismantling and Decommissioning Strategies to a Variety of Nuclear Fuel Cycle Facilities - 12237

    International Nuclear Information System (INIS)

    AREVA has accumulated over 20 years of experience in managing and operating fuel cycle facilities Decontamination and Decommissioning (D and D) projects of many different types and a variety of scales, both as facility owner (at La Hague for example) and as prime contractor to external customers such as the French Atomic Energy Commission (at Marcoule). A specific Business Unit was created in 2008 to capitalize on this experience and to concentrate - in one division - the specific skills required to be successful and cost effective in decommissioning projects. Indeed one of the key lessons learned in the past decades is that decommissioning is a significantly different business as compared to normal operations of a nuclear facility. Almost all the functions of a project need to be viewed from a different angle, challenged and adapted consequently in order to optimize costs and schedule. Three examples follow to illustrate the point: Safety management needs to take into account the ever changing configuration of a plant under D and D (a quite new situation for the authorities). Production of waste is significantly different in term of volume, activities, conditioning and disposal path. Technology is important but technical issues are often less critical than good management and planning. Further examples and lessons learned are developed through reviewing the projects experience basis. AREVA has a long and vast experience in the cleanup and dismantling of a number of very large and complex nuclear facilities. This effort focused initially on AREVA's own plants and is expanding now to other customers. The setup of a specific Business Unit in 2008 to takeover this business allowed concentration of the skills and the lessons learned in a dedicated division so as to provide the best means to optimize safety, performance, costs and schedules. Indeed transitioning from operations to D and D of a nuclear facility is a quantum leap. The assistance from specialized teams can

  12. 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

  13. Tailings Management Best Practice: A Case Study of the McClean Lake Jeb Tailings Management Facility

    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. McClean Lake Operation commenced production in 1999, and its tailings management facility represents the state of the art for tailings management in the uranium industry in Canada. Tailings disposal has the potential to cause effects in the surrounding receiving environment primarily through migration of soluble contaminants from the facility to surface water receptors. In-pit disposal of mill tailings has become the standard in the uranium mining industry in Northern Saskatchewan. This method of tailings management demonstrates advances in terms of worker radiation protection and containment of soluble contaminants both during operations and into the long term. Sub-aqueous deposition of tailings protects personnel from exposure to radiation and airborne emissions and prevents freezing of tailings, which can hinder consolidation. The continuous inflow of groundwater to the facility is achieved during operations through control of water levels within the facility. This ensures hydrodynamic containment, which prevents migration of soluble radionuclides and heavy metals into the surrounding aquifer during operations. The environmental performance of the decommissioned facility depends upon the rate of release of contaminants to the receiving environment. The rate of contaminant loading to the receiving environment will ultimately be governed by the concentrations of soluble contaminants within the tailings mass, the mechanisms for contaminant release from the tailings to the surrounding groundwater system and transport of contaminants within the groundwater pathway to the receiving environment. The tailings preparation process was designed to convert arsenic into a stable form to reduce soluble concentrations within the tailings mass

  14. The French UMo group contribution to new LEU fuel development

    International Nuclear Information System (INIS)

    The French UMo Group was based on a close collaboration between CEA and AREVA's companies strongly involved in the MTR field. The aim of this program was to deliver industrially a high performance LEU UMo fuel able to be reprocessed, and suitable for a wide range of Research Reactor, covering the expected needs for MTR next generation. Since 1999, the program has been focused on industrial aspects with the intention to deal with the whole fuel cycle: manufacturing, irradiation behaviour, fuel characterisation, code development and reprocessing validation. It has been based on the fabrication of full-sized U-7%Mo fuel plates with a density up to 8 gU/cm3. The dedicated and advanced R and D means provided by the CEA have been used intensively with the contribution of HFR and BR2 facilities in Europe. This paper presents a synthesis of the program and the corresponding significant results obtained. These results have played a major role as regards the UMo dispersion fuel qualification route by issuing, for the first time, evidence of severe performance limitations. Consequently, the global international effort to develop and qualify a high density LEU UMo fuel has been definitively re-routed and forced to overcome these discrepancies by exploring new technical solutions. A French extended program sustained by a CEA and CERCA collaboration has been launched in 2004 in order to develop a suitable UMo fuel solution. UMo dispersion and monolithic fuel are both investigated through three new full-sized plate irradiations planned in OSIRIS. (author)

  15. 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)

  16. Presentation of 2004 earnings

    International Nuclear Information System (INIS)

    This presentation offers financial information on the AREVA Group earnings for the year 2004. 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. (A.L.B.)

  17. Presentation of 2004 earnings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-01

    This presentation offers financial information on the AREVA Group earnings for the year 2004. 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. (A.L.B.)

  18. Measurement of two-phase flow parameters with multi-channel gamma densitometry and local void probes at the INKA test facility

    International Nuclear Information System (INIS)

    At AREVA's integral test facility INKA, different passive safety systems of the generation III+ boiling water reactor KERENA™ are being tested. For the detailed analysis of condensation phenomena, an improved understanding and quantitative assessment of the occurring two-phase flow phenomena is essential. In this paper, we describe the special instrumentation of the INKA test facility with high-temperature high-pressure thermo needle probes and a special multichannel gamma densitometer. The paper gives a short overview of the passive safety concept of the KERENA™ system, the fundamentals of the special instrumentation and discusses some experimental results from the INKA test facility in Karlstein. (author)

  19. Effects of marketing group on the variability of fresh loin, belly, and fresh and processed ham quality from pigs sourced from a commercial processing facility

    Science.gov (United States)

    The objective was to quantify the effect of marketing group (MG) on the variability of primal quality. Pigs (N=7,684) were slaughtered in 3 MGs from 8 barns. Pigs were from genetic selection programs focused on lean growth (L; group 1 n=1,131; group 2 n=1,466; group 3 n=1,030) or superior meat qua...

  20. 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

  1. The decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries

  2. Theme day: corrosion and surface treatments in nuclear facilities. Proceedings

    International Nuclear Information System (INIS)

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

  3. 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.)

  4. 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)

  5. 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.)

  6. Project management plan for Waste Area Grouping 5 Old Hydrofracture Facility tanks contents removal at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    On January 1, 1992, the US Department of Energy (DOE), the US Environmental Protection Agency (EPA) Region IV, and the Tennessee Department of Environment and Conservation (TDEC) signed a Federal Facility Agreement (FFA) concerning the Oak Ridge Reservation. The FFA requires that inactive liquid low-level (radioactive) waste (LLLW) tanks at Oak Ridge National Laboratory (ORNL) be remediated in accordance with requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This revision is to update the schedule and designation of responsibilities for the Old Hydrofracture Facility (OHF) tanks contents removal project. The scope of this project is to transfer inventory from the five inactive LLLW tanks at the OHF into the active LLLW system

  7. Preliminary engineering report waste area grouping 5, Old Hydrofracture Facility Tanks content removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facilities Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the U.S. Department of Energy (DOE) Oak Ridge Operations Office, the U.S. Environmental Protection Agency (EPA) Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA is January 1, 1992. One objective of the FFA is to ensure that liquid low-level waste (LLLW) tanks that are removed from service are evaluated and remediated through the CERCLA process. Five inactive LLLW tanks, designated T-1, T-2, T-3, T-4, and T-9, located at the Old Hydrofracture (OHF) Facility in the Melton Valley area of Oak Ridge National Laboratory (ORNL) have been evaluated and are now entering the remediation phase. As a precursor to final remediation, this project will remove the current liquid and sludge contents of each of the five tanks (System Requirements Document, Appendix A). It was concluded in the Engineering Evaluation/Cost Analysis [EE/CA] for the Old Hydrofracture Facility Tanks (DOE 1996) that sluicing and pumping the contaminated liquid and sludge from the five OHF tanks was the preferred removal action. Evaluation indicated that this alternative meets the removal action objective and can be effective, implementable, and cost-effective. Sluicing and removing the tank contents was selected because this action uses (1) applicable experience, (2) the latest information about technologies and techniques for removing the wastes from the tanks, and (3) activities that are currently acceptable for storage of transuranic (TRU) mixed waste

  8. 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

  9. 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.)

  10. 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)

  11. The integral test facility Karlstein - INKA

    International Nuclear Information System (INIS)

    The INKA (INtegral Test Facility KArlstein) test facility was designed and erected to test and demonstrate performance of the passive safety systems of KERENA™, the new AREVA Boiling Water Reactor (BWR) design. The experimental program within the KERENA™ development program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests will be performed to simulate transients and LOCA (Loss of Coolant Accident) scenarios at the INKA test facility. These tests will test and demonstrate the interaction between the passive components/systems and demonstrate their ability to perform their design function. For the integral tests, the Passive Pressure Pulse Transmitter will be included. The INKA test facility represents the KERENA™ Containment with a volume scaling of 1:24. Component heights and levels are full scale in order to match the driving forces for natural circulation. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein - a vessel with a design pressure of 11 MPa and a storage capacity of 125 m3. The vessel is fed by a benson boiler with a maximum power supply of 22 MW. The drywell of the INKA containment is divided into two compartments and connected to the wetwell (Pressure Suppression System) via a full scale vent pipe. Therefore, the INKA pressure suppression system meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios starting with the initiating event - for example pipe rupture. At INKA a full train of passive safety systems is available. INKA is also able to simulate the functions of active safety system such as containment heat removal. Therefore accident scenarios relevant to modern Gen III as well as for operating Gen II design can be simulated in order to validate system and

  12. 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

  13. Areva at March 31, 2012: 2.4% revenue growth to 2026 million euros (+1.3% on a comparable basis); Backlog growth of 12 months to 45.1 billion euros (+3.7%), down slightly over 3 months (-1.0%)

    International Nuclear Information System (INIS)

    AREVA generated consolidated revenue of 2.026 billion euros in the first quarter of 2012, up 2.4% (+1.3% like for like) compared with the same period in 2011. The increase in revenue in the Mining Business Group (+11.9% reported, +6.5% like for like), the Reactors and Services Business Group (+5.8% reported, +6.0% like for like) and the Renewable Energies Business Group (+198.2% reported, +199.8% like for like) offsets the expected decrease in revenue in the Front End Business Group (-17.2% reported, -18.3% like for like). Foreign exchange had a positive impact of 29 million euros over the period, while changes in consolidation scope had a negative impact of 8 million euros. The Group had 45.1 billion euros in backlog at March 31, 2012, up 3.7% in relation to March 31, 2011 and down slightly (-1.0%) from December 31, 2011. Backlog growth in the Front End, Reactors and Services and Back End Business Groups offsets the decrease in backlog in the Mining and Renewable Energies Business Groups. Order cancellations as a result of the Fukushima accident totaled 612 million euros at March 31, 2012, compared with 464 million euros at December 31, 2011

  14. [Social rehabilitation in day care facilities for psychiatrically ill and handicapped patients--results of a concomitant study of a model program by the Rhine-Land District Group].

    Science.gov (United States)

    Regus, M; Gürtler, A

    1997-05-01

    Within the extension of new services for mentally ill and disabled peoples outside of inpatient settings, the Landschaftsverband Rheinland (LVR) decided in 1990 to finance day care facilities especially for those patients who could previously not be integrated in the existing community psychiatry service structure due to the severity of their illness or handicap. A cost reducing effect in the clinical and residential service area was also intended. The first ten of these facilities were included in a 2-year research project. This report includes findings in various sectors: characteristics of the user group, functions and focal points of care, association with other community psychiatry services, cost effectiveness, and user opinions. Most visitors experienced a stabilisation of their personal situation and improvement of their quality of life. The average length of hospital stays was reduced from 102 to 25 days per year. The hopes accompanied with the programme were only partially fulfilled; possible consequences are discussed. PMID:9289222

  15. Inter-CLI work-group: safety after Fukushima; GT inter-CLI 'surete post Fukushima'

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-03

    This document contains a whole set of questions asked about nuclear safety and security by a work-group made of members of associations belonging to local information commissions. These questions are asked either to the French State, or to EDF, or to AREVA. They bear on general issues common to La Hague and Flamanville nuclear installations, notably public information, emergency plans, post-accident management, subcontracting, loss of electricity supply, public health, governance, computer hacking, extreme meteorological events. A set of questions concerns the AREVA processing plant in La Hague (warehousing, pools for irradiated fuels, plutonium oxide storage and warehousing, and so on), and another set concerns the Flamanville nuclear power plant (different aspects of the management of a crisis situation). The last set of questions concerns the Manche nuclear waste storage centre

  16. Facilities & Leadership

    Data.gov (United States)

    Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

  17. Biochemistry Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Biochemistry Facility provides expert services and consultation in biochemical enzyme assays and protein purification. The facility currently features 1) Liquid...

  18. Exploring the Development of Competence in Lean Management through Action Learning Groups: A Study of the Introduction of Lean to a Facilities Management Function

    Science.gov (United States)

    Wyton, Paul; Payne, Robin

    2014-01-01

    The introduction of a Lean approach to management requires the development of understanding and capability. This in turn requires a structured training intervention and other supporting activities. This paper explores, through a case study, the way in which action learning groups (ALGs) supported the development of Lean capabilities in the…

  19. Areva excellent business volume: backlog as of december 31, 2008: + 21.1% to 48.2 billion euros. 2008 revenue: + 10.4% to 13.2 billion euros

    International Nuclear Information System (INIS)

    AREVA's backlog stood at 48.2 billion euros as of December 31, 2008, for 21.1% growth year-on-year, including 21.8% growth in Nuclear and 16.5% growth in Transmission and Distribution. The Nuclear backlog came to 42.5 billion euros at December 31, 2008. The Transmission and Distribution backlog came to 5.7 billion euros at year-end. The group recognized revenue of 13.2 billion euros in 2008, for year-on-year growth of 10.4% (+9.8% like-for-like). Revenue outside France was up 10.5% to 9.5 billion euros, representing 72% of total revenue. Revenue was up 6.5% in the Nuclear businesses (up 6.3% LFL), with strong performance in the Reactors and Services division (+10.9% LFL) and the Front End division (+7.2% LFL). The Transmission and Distribution division recorded growth of 17% (+15.8% LFL). Revenue for the fourth quarter of 2008 rose to 4.1 billion euros, up 5.2% (+1.6% LFL) from that of the fourth quarter of 2007. Revenue for the Front End division rose to 3.363 billion euros in 2008, up 7.1% over 2007 (+7.2% LFL). Foreign exchange (currency translations) had a negative impact of 53 million euros. Revenue for the Reactors and Services division rose to 3.037 billion euros, up 11.8% over 2007 (+10.9% LFL). Foreign exchange (currency translations) had a negative impact of 47 million euros. Revenue for the Back End division came to 1.692 billion euros, a drop of 2.7% (-2.5% LFL). Foreign exchange (currency translations) had a negative impact of 3.5 million euros. Revenue for the Transmission and Distribution division rose to 5.065 billion euros in 2008, up 17.0% (+15.8% LFL)

  20. Site characterization summary report for Waste Area Grouping 10 Wells at the Old Hydrofracture Facility, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the Department of Energy (DOE) by Martin Marietta Energy Systems (Energy Systems). As part of its DOE mission, ORNL has pioneered waste disposal technologies throughout the years of site operations since World War II. In the late 1950s, efforts were made to develop a permanent disposal alternative to the surface impoundments at ORNL at the request of the National Academy of Sciences. One such technology, the hydrofracture process, involved forming fractures in an underlying geologic host formation (a low-permeability shale) at depths of up to 1000 ft and subsequently injecting a grout slurry containing low-level liquid waste, cement, and other additives at an injection pressure of about 2000 psi. The objective of the effort was to develop a grout slurry that could be injected as a liquid but would solidify after injection, thereby immobilizing the radioisotopes contained in the low-level liquid waste. The scope of this site characterization was the access, sampling, logging, and evaluation of observation wells near the Old Hydrofracture Facility (OHF) in preparation for plugging, recompletion, or other final disposition of the wells

  1. Site characterization summary report for Waste Area Grouping 10 Wells at the Old Hydrofracture Facility, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the Department of Energy (DOE) by Martin Marietta Energy Systems (Energy Systems). As part of its DOE mission, ORNL has pioneered waste disposal technologies throughout the years of site operations since World War II. In the late 1950s, efforts were made to develop a permanent disposal alternative to the surface impoundments at ORNL at the request of the National Academy of Sciences. One such technology, the hydrofracture process, involved forming fractures in an underlying geologic host formation (a low-permeability shale) at depths of up to 1000 ft and subsequently injecting a grout slurry containing low-level liquid waste, cement, and other additives at an injection pressure of about 2000 psi. The objective of the effort was to develop a grout slurry that could be injected as a liquid but would solidify after injection, thereby immobilizing the radioisotopes contained in the low-level liquid waste. The scope of this site characterization was the access, sampling, logging, and evaluation of observation wells near the Old Hydrofracture Facility (OHF) in preparation for plugging, recompletion, or other final disposition of the wells.

  2. Project management plan for Waste Area Grouping 5 Old Hydrofracture Facility tanks contents removal at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    This revision (Rev. 1) updates the schedule and designation of responsibilities for the Old Hydrofracture Facility (OHF) tanks contents removal project. Ongoing and planned future activities include: cold testing of the sluicing and pumping system; readiness assessment; equipment relocation and assembly; isotopic dilution of fissile radionuclides; sluicing and transfer of the tanks contents; and preparation of the Removal Action Completion Report. The most significant change is that the sluicing and pumping system has been configured by and will be operated by CDM Federal Programs Corporation. In addition, a new technical lead and a new project analyst have been designated within Lockheed Martin Energy Systems, Inc. and Lockheed Martin Energy Research Corp. The schedule for tanks contents removal has been accelerated, with transfer of the final batch of tank slurry now scheduled for March 31, 1998 (instead of November 10, 1998). The OHF sluicing and pumping project is proceeding as a non-time-critical removal action under the Comprehensive Environmental Response, Compensation, and Liability Act. The purpose of the project is to remove the contents from five inactive underground storage tanks, designated T-1, T-2, T-3, T-4, and T-9. The tanks contain an estimated 52,700 gal of liquid and sludge, together comprising a radioactive inventory of approximately 30,000 Ci

  3. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1, Sections 1 through 3: Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    WAG 6 comprises a shallow land burial facility used for disposal of low-level radioactive wastes (LLW) and, until recently, chemical wastes. As such, the site is subject to regulation under RCRA and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). To comply with these regulations, DOE, in conjunction with the Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC), developed a strategy for closure and remediation of WAG 6 by 1997. A key component of this strategy was to complete an RFI by September 1991. The primary objectives of the RFI were to evaluate the site`s potential human health and environmental impacts and to develop a preliminary list of alternatives to mitigate these impacts. The WAG 6 one of three solid waste management units evaluated Oak Ridge National Laboratory (ORNL) existing waste disposal records and sampling data and performed the additional sampling and analysis necessary to: describe the nature and extent of contamination; characterize key contaminant transport pathways; and assess potential risks to human health and the environment by developing and evaluating hypothetical receptor scenarios. Estimated excess lifetime cancer risks as a result for exposure to radionuclides and chemicals were quantified for each hypothetical human receptor. For environmental receptors, potential impacts were qualitatively assessed. Taking into account regulatory requirements and base line risk assessment results, preliminary site closure and remediation objectives were identified, and a preliminary list of alternatives for site closure and remediation was developed.

  4. Is patient-grouping on basis of condition on admission indicative for discharge destination in geriatric stroke patients after rehabilitation in skilled nursing facilities? The results of a cluster analysis

    Directory of Open Access Journals (Sweden)

    Buijck Bianca I

    2012-12-01

    Full Text Available Abstract Background Geriatric stroke patients are generally frail, have an advanced age and co-morbidity. It is yet unclear whether specific groups of patients might benefit differently from structured multidisciplinary rehabilitation programs. Therefore, the aims of our study are 1 to determine relevant patient characteristics to distinguish groups of patients based on their admission scores in skilled nursing facilities (SNFs, and (2 to study the course of these particular patient-groups in relation to their discharge destination. Methods This is a longitudinal, multicenter, observational study. We collected data on patient characteristics, balance, walking ability, arm function, co-morbidity, activities of daily living (ADL, neuropsychiatric symptoms, and depressive complaints of 127 geriatric stroke patients admitted to skilled nursing facilities with specific units for geriatric rehabilitation after stroke. Results Cluster analyses revealed two groups: cluster 1 included patients in poor condition upon admission (n = 52, and cluster 2 included patients in fair/good condition upon admission (n = 75. Patients in both groups improved in balance, walking abilities, and arm function. Patients in cluster 1 also improved in ADL. Depressive complaints decreased significantly in patients in cluster 1 who were discharged to an independent- or assisted-living situation. Compared to 80% of the patients in cluster 2, a lower proportion (46% of the patients in cluster 1 were discharged to an independent- or assisted-living situation. Conclusion Stroke patients referred for rehabilitation to SNFs could be clustered on the basis of their condition upon admission. Although patients in poor condition on admission were more likely to be referred to a facility for long-term care, this was certainly not the case in all patients. Almost half of them could be discharged to an independent or assisted living situation, which implied that also in patients in

  5. Summary of the annual report 2003; Synthese du rapport annuel 2003

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    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. These businesses engage AREVA 70000 employees in the 21 century greatest challenges: making energy and communication resources available to all, protecting the planet, and acting responsibly towards future generations. This annual report of the Areva group activities contents : Key data, milestones of the group, AREVA global operations in 2003, Corporate governance, organization of the group, share information, the financial responsibility, the environmental responsibility, the social responsibility, the business overview, the global challenges in AREVA energy business, the research and development programs, the front end division reactors and services division, the back end division, the transmission and distribution division. (A.L.B.)

  6. Summary of the annual report 2003

    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. These businesses engage AREVA 70000 employees in the 21 century greatest challenges: making energy and communication resources available to all, protecting the planet, and acting responsibly towards future generations. This annual report of the Areva group activities contents : Key data, milestones of the group, AREVA global operations in 2003, Corporate governance, organization of the group, share information, the financial responsibility, the environmental responsibility, the social responsibility, the business overview, the global challenges in AREVA energy business, the research and development programs, the front end division reactors and services division, the back end division, the transmission and distribution division. (A.L.B.)

  7. 6th July 2010 - United Kingdom Science and Technology Facilities Council W. Whitehorn signing the guest book with Head of International relations F. Pauss, visiting the Computing Centre with Information Technology Department Head Deputy D. Foster, the LHC superconducting magnet test hall with Technology Department P. Strubin,the Centre Control Centre with Operation Group Leader M. Lamont and the CLIC/CTF3 facility with Project Leader J.-P. Delahaye.

    CERN Multimedia

    Teams : M. Brice, JC Gadmer

    2010-01-01

    6th July 2010 - United Kingdom Science and Technology Facilities Council W. Whitehorn signing the guest book with Head of International relations F. Pauss, visiting the Computing Centre with Information Technology Department Head Deputy D. Foster, the LHC superconducting magnet test hall with Technology Department P. Strubin,the Centre Control Centre with Operation Group Leader M. Lamont and the CLIC/CTF3 facility with Project Leader J.-P. Delahaye.

  8. COGEMA in Niger. Inquiry report on the situation of workers of SOMAiR and COMINAK, Niger's subsidies of the AREVA-COGEMA group

    International Nuclear Information System (INIS)

    After having briefly recalled the activities of COGEMA's subsidies in Niger, presented the context of the inquiry, and made some remarks about COGEMA's attitude with respect to this inquiry, this report gives an extremely critical analysis of security measures and working conditions: non existent information about risks related to radioactivity, non existent or insufficient security equipment, exposure of workers to ionizing radiation by water, ignored security orders, random dosimetry controls. The second part recalls the radiological risks present in uranium mines, gives a critical analysis of the worker medical follow-up quality, considers as inexplicable the absence of professional diseases, and discusses the issue of work accidents. It finally outlines that control structures (Mine Direction, Work Inspection) are inadequate

  9. Experimental facilities

    International Nuclear Information System (INIS)

    We have completed an engineering feasibility study of a major modification of the HFIR facility and are now beginning a similar study of an entirely new facility. The design of the reactor itself is common to both options. In this paper, a general description of the modified HFIR is presented with some indications of the additional facilities that might be available in an entirely new facility

  10. Integral Test Facility PKL: Experimental PWR Accident Investigation

    Directory of Open Access Journals (Sweden)

    Klaus Umminger

    2012-01-01

    Full Text Available Investigations of the thermal-hydraulic behavior of pressurized water reactors under accident conditions have been carried out in the PKL test facility at AREVA NP in Erlangen, Germany for many years. The PKL facility models the entire primary side and significant parts of the secondary side of a pressurized water reactor (PWR at a height scale of 1 : 1. Volumes, power ratings and mass flows are scaled with a ratio of 1 : 145. The experimental facility consists of 4 primary loops with circulation pumps and steam generators (SGs arranged symmetrically around the reactor pressure vessel (RPV. The investigations carried out encompass a very broad spectrum from accident scenario simulations with large, medium, and small breaks, over the investigation of shutdown procedures after a wide variety of accidents, to the systematic investigation of complex thermal-hydraulic phenomena. This paper presents a survey of test objectives and programs carried out to date. It also describes the test facility in its present state. Some important results obtained over the years with focus on investigations carried out since the beginning of the international cooperation are exemplarily discussed.

  11. Safe and durable storage of waste from reprocessing in E-EV-SE and ECC facilities

    International Nuclear Information System (INIS)

    The main industrial facilities involved in closing the back-end of the nuclear fuel cycle in France are La Hague reprocessing plant, in which fission products and minor actinides are vitrified and recyclable materials (U, Pu) are recovered and purified, and the MELOX plant where the recovered plutonium is used to fabricate MOX fuel. These facilities are operated by the COGEMA/AREVA Group. With a reprocessing capacity of 1,700 tHM/year, the La Hague site accounts for some two-thirds of the commercial capacity offered worldwide (LWR fuel), while MELOX plant produces 145 tHM of MOX per year. COGEMA commitment to sustainable development is at the core of its industrial strategy, through permanent care about minimizing releases to environment while reducing the amount of unavoidably generated waste to be disposed of. The final disposal of waste, and in particular regarding waste not compatible with surface repository, has become one of the key issues of the nuclear industry from both technological and economical aspects, not to mention the public acceptance aspects. Final disposal being under investigation, wastes not compatible with surface disposal are today temporary stored in interim storage facilities. Reprocessing coupled with interim storage, and if required long term interim storage thus provide duration flexibility to set up final disposal. The paper presents: a description of COGEMA interim storage facilities; an investigation regarding the possible lifetime extension of interim storage facilities; an assessment of the ability of the storage to cope with secular operation. In conclusion, through its nuclear fuel cycle activities, particularly in the fields of reprocessing and recycling, COGEMA has been accumulating knowledge and know-how to design and build safe and durable interim storage facilities. A significant optimization has been conducted from both technical and economical aspects, to customize the storage to the characteristics of the waste to be

  12. Validation of a new 39 neutron group self-shielded library based on the nucleonics analysis of the Lotus fusion-fission hybrid test facility performed with the Monte Carlo code

    International Nuclear Information System (INIS)

    The Swiss LOTUS fusion-fission hybrid test facility was used to investigate the influence of the self-shielding of resonance cross sections on the tritium breeding and on the thorium ratios. Nucleonic analyses were performed using the discrete-ordinates transport codes ANISN and ONEDANT, the surface-flux code SURCU, and the version 3 of the MCNP code for the Li2CO3 and the Li2O blanket designs with lead, thorium and beryllium multipliers. Except for the MCNP calculation which bases on the ENDF/B-V files, all nuclear data are generated from the ENDF/B-IV basic library. For the deterministic methods three NJOY group libraries were considered. The first, a 39 neutron group self-shielded library, was generated at EIR. The second bases on the same group structure as the first does and consists of infinitely diluted cross sections. Finally the third library was processed at LANL and consists of coupled 30+12 neutron and gamma groups; these cross sections are not self-shielded. The Monte Carlo analysis bases on a continuous and on a discrete 262 group library from the ENDF/B-V evaluation. It is shown that the results agree well within 3% between the unshielded libraries and between the different transport codes and theories. The self-shielding of resonance cross sections results in a decrease of the thorium capture rate and in an increase of the tritium breeding of about 6%. The remaining computed ratios are not affected by the self-shielding of cross sections. (Auth.)

  13. Information report sent in according to the Rule's article 146 by the finance, general economy and budget control Commission related to EDF's and Areva's financial situation and perspectives - Nr 4463

    International Nuclear Information System (INIS)

    This report presents a synthesis of the most recent information on the both public companies, EDF and AREVA, within the context of their industrial sector. While discussing hypotheses and assessments of future expenses, the report outlines that future expenses related to the electronuclear activity are well provisioned in the accounts of both companies, but that their value is probably under-estimated. As far as EDF is concerned, the authors outline that the international development strategy impacted investment and partnership choices, and that the company should review this posture within a new context. As far as Areva is concerned, they think that the company possesses the required assets to be revived, but this requires rigorous financial and industrial choices

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

    International Nuclear Information System (INIS)

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

  15. Animal facilities

    International Nuclear Information System (INIS)

    The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

  16. AREVA - First quarter 2011 revenue: 2.7% growth like for like to 1.979 billion euros

    International Nuclear Information System (INIS)

    The group reported consolidated revenue of 1.979 billion euros in the 1. quarter of 2011, for 2.2% growth compared with the 1. quarter of 2010 (+ 2.7% like for like). The increase was driven by the Mining / Front End Business Group (+ 20.8% LFL). Revenue from outside France rose 12.0% to 1.22 billion euros and represented 62% of total revenue. The impacts of foreign exchange and changes in consolidation scope were negligible during the period. The March 11 events in Japan had no significant impact on the group's performance in the 1. quarter of 2011. The group's backlog of 43.5 billion euros at March 31, 2011 was stable in relation to March 31, 2010. The growth in the backlog of the Mining / Front End and Renewable Energies Business Groups offset the partial depletion of the backlog in the Reactors and Services and Back End Business Groups as contracts were completed

  17. Calculation of the operation mode of the emergency condenser (EC) of the INKA test facility with ATHLET

    International Nuclear Information System (INIS)

    On 4th of April 2008 AREVA and E.ON signed a cooperation agreement. An essential part of this is the Final Basic Design Contract SWR 1000. On 28th of November 2008 AREVA and E.ON have signed a Memorandum of Understanding to develop a commercially viable product and to focus on the successful deployment of the SWR 1000 in a collaborative manner. Meanwhile a rebranding was conducted: the new name of this evolutionary boiling water reactor of the Generation III+ is KERENATM trademark. It is the common intention of AREVA and E.ON to complete the basic design until the end of 2010 so as to reach a design ready for bid and ready for licensing for a construction primarily in a European country. The KERENA trademark is not a completely new plant concept, it is a proven further developed design, based on Gundremmingen NPP and the whole accumulated German BWR operating experience. The design shall fulfill the following major safety items: - further reduction of core damage frequency, - control of postulated core melt accident by in-vessel melt retention without emergency response actions, - introduction of passive safety systems (principle of diversity and redundancy), and - long grace periods for manual intervention (> 3 days). Especially for the newly introduced passive safety systems, which are described in detail, not only an experimental testing and validation is needed, but also thermal-hydraulic system codes have to be qualified, to be able to consider the mostly gravity driven 3D-flow phenomena correctly. Since in some countries the code ATHLET is well established, it is useful to prove its capabilities or to enhance the capabilities, if necessary. Therefore the FZD (Forschungszentrum Dresden-Rossendorf) is performing a model development and calculations for code validation of the test results from INKA (INtegral test facility in KArlstein, Germany). This paves the way for licensing procedures later on. (orig.)

  18. Calculation of the operation mode of the emergency condenser (EC) of the INKA test facility with ATHLET

    Energy Technology Data Exchange (ETDEWEB)

    Wilschuetz, H.G. [E.ON Kernkraft GmbH, Hannover (Germany); Leyer, S. [AREVA NP GmbH, Offenbach (Germany); Kruessenberg, A.K.; Schaefer, F. [FZD Forschungszentrum Dresden-Rossendorf e.V. (Germany)

    2010-05-15

    On 4{sup th} of April 2008 AREVA and E.ON signed a cooperation agreement. An essential part of this is the Final Basic Design Contract SWR 1000. On 28{sup th} of November 2008 AREVA and E.ON have signed a Memorandum of Understanding to develop a commercially viable product and to focus on the successful deployment of the SWR 1000 in a collaborative manner. Meanwhile a rebranding was conducted: the new name of this evolutionary boiling water reactor of the Generation III+ is KERENATM trademark. It is the common intention of AREVA and E.ON to complete the basic design until the end of 2010 so as to reach a design ready for bid and ready for licensing for a construction primarily in a European country. The KERENA trademark is not a completely new plant concept, it is a proven further developed design, based on Gundremmingen NPP and the whole accumulated German BWR operating experience. The design shall fulfill the following major safety items: - further reduction of core damage frequency, - control of postulated core melt accident by in-vessel melt retention without emergency response actions, - introduction of passive safety systems (principle of diversity and redundancy), and - long grace periods for manual intervention (> 3 days). Especially for the newly introduced passive safety systems, which are described in detail, not only an experimental testing and validation is needed, but also thermal-hydraulic system codes have to be qualified, to be able to consider the mostly gravity driven 3D-flow phenomena correctly. Since in some countries the code ATHLET is well established, it is useful to prove its capabilities or to enhance the capabilities, if necessary. Therefore the FZD (Forschungszentrum Dresden-Rossendorf) is performing a model development and calculations for code validation of the test results from INKA (INtegral test facility in KArlstein, Germany). This paves the way for licensing procedures later on. (orig.)

  19. Areva at September 30, 2012: Backlog at a record level of euros 47 bn (+10.1% year on year). Revenue up sharply to euros 6.542 bn (+10.0% compared with September 2011, +8.5% like for like)

    International Nuclear Information System (INIS)

    AREVA generated consolidated revenue of 6.542 billion euros over the first nine months of 2012, representing growth of 10.0% (+8.5% growth like for like) compared with the same period in 2011. Revenue growth was fueled by a 7.0% increase in recurring business (+5.6% like for like) and ramp-up of the renewable business. Revenue from nuclear operations was 6.035 billion euros over the first nine months of 2012, compared with 5.731 billion euros for the first nine months of 2011, representing a 5.3% increase (+3.9% like for like). Like for like, revenue was led by the Mining BG (+28.0%), the Reactors and Services BG (+2.1%) and the Back End BG (+11.8%), offsetting the downturn in business in the Front End BG (-12.1%). Revenue was up 272% like for like in renewable energies. Foreign exchange had a positive impact of 130 million euros over the period. The change in consolidation scope had a negative impact of 52 million euros. Revenue growth was balanced between France and internationally, reflecting AREVA's ability to capture market opportunities while capitalizing on long-standing relations with its customers. Sales revenue for the third quarter of 2012 was 2.214 billion euros, an increase of 13.4% (+12.4% like for like) compared with the third quarter of 2011. Foreign exchange had a positive impact of 52 million euros over the period, while the change in consolidation scope had a negative impact of 34 million euros. At September 30, 2012, the consolidated backlog for the nuclear and renewable energy businesses was the highest since the Group was established, at a total of 47 billion euros. This represents an increase of 10.1% in relation to September 30, 2011 (42.7 billion euros) and an increase of 4.1% in relation to June 30, 2012 (45.2 billion euros). The increase is attributable mainly to the Mining, Front End and Reactors and Services BGs. Order intakes over the first nine months of the year were up 87% compared with first nine months of 2011. Order cancellations

  20. DeBeNe Test Facilities for Fast Breeder Development

    International Nuclear Information System (INIS)

    This report gives an overview and a short description of the test facilities constructed and operated within the collaboration for fast breeder development in Germany, Belgium and the Netherlands. The facilities are grouped into Sodium Loops (Large Facilities and Laboratory Loops), Special Equipment including Hot Cells and Reprocessing, Test Facilities without Sodium, Zero Power Facilities and In-pile Loops including Irradiation Facilities

  1. 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

  2. Overview of remote handling technologies developed for inspection and maintenance of spent fuel management facilities in France

    International Nuclear Information System (INIS)

    In the facilities of the end of the nuclear fuel cycle, like spent fuel storage pools, reprocessing plants, Plutonium-based fuel manufacturing plants or waste temporary storage units, materials handling must be carried out remotely, taking into account the nuclear radiating environment. In addition to the automation requirement, robotics equipment in the nuclear industry must be substituted to human operators in order to respect the ALARA principle. More over, remote handling technologies aim to improve the working conditions, as well as the quality of the work achieved by the operators. Ten years ago, COGEMA (AREVA Group) and CEA (French Atomic Energy Agency) started an ambitious R and D program in robotics and remote handling technologies applied to COGEMA spent fuel management facilities in France, with the aim to cover the requirements of the different plant life cycle steps. The paper gives an overview of the important developments that have been carried out by CEA and then transferred to the COGEMA industrial group. The range includes the next generation of servo-manipulators, long range inspection tools and carriers, nuclear versions of industrial robots, radiation hardened electronic systems, interactive environment modeling tools, as well as force-feedback master-slave generic control software for tele-operation systems. Some applications of this development are presented in the paper: - rad-hard electronic modules for robotic equipment which are used by COGEMA in high radiating environment; - long reach articulated carrier for inspection of spent full management blind cells; - new electrical force feedback master/slave system to improve the tele-operation of standard tele-manipulators; - generic control software for tele-manipulators. The results of the robotic program carried out by COGEMA and CEA have been very valuable for the introduction of new technologies inside nuclear industry. Innovative products and sub-systems can be integrated now in a large

  3. Direct C-C Coupling of CO2 and the Methyl Group from CH4 Activation through Facile Insertion of CO2 into Zn-CH3 σ-Bond.

    Science.gov (United States)

    Zhao, Yuntao; Cui, Chaonan; Han, Jinyu; Wang, Hua; Zhu, Xinli; Ge, Qingfeng

    2016-08-17

    Conversion of CO2 and CH4 to value-added products will contribute to alleviating the green-house gas effect but is a challenge both scientifically and practically. Stabilization of the methyl group through CH4 activation and facile CO2 insertion ensure the realization of C-C coupling. In the present study, we demonstrate the ready C-C coupling reaction on a Zn-doped ceria catalyst. The detailed mechanism of this direct C-C coupling reaction was examined based on the results from density functional theory calculations. The results show that the Zn dopant stabilizes the methyl group by forming a Zn-C bond, thus hindering subsequent dehydrogenation of CH4. CO2 can be inserted into the Zn-C bond in an activated bent configuration, with the transition state in the form of a three-centered Zn-C-C moiety and an activation barrier of 0.51 eV. The C-C coupling reaction resulted in the acetate species, which could desorb as acetic acid by combining with a surface proton. The formation of acetic acid from CO2 and CH4 is a reaction with 100% atom economy, and the implementation of the reaction on a heterogeneous catalyst is of great importance to the utilization of the greenhouse gases. We tested other possible dopants including Al, Ga, Cd, In, and Ni and found a positive correlation between the activation barrier of C-C coupling and the electronegativity of the dopant, although C-H bond activation is likely the dominant reaction on the Ni-doped ceria catalyst. PMID:27452233

  4. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 6, Technical memorandums 06-13, 06-14, and 06-15: Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    This report describes the borehole geophysical logging performed at selected monitoring wells at waste area grouping (WAG) 6 of Oak Ridge National Laboratory in support of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI). It identifies the locations and describes the methods, equipment used in the effort, and the results of the activity. The actual logs for each well logged are presented in Attachment 1 through 4 of the TM. Attachment 5 provide logging contractor service literature and Attachment 6 is the Oak Ridge National Laboratory (ORNL) Procedure for Control of a Nuclear Source Utilized in Geophysical logging. The primary objectives of the borehole geophysical logging program were to (1) identify water-bearing fractured bedrock zones to determine the placement of the screen and sealed intervals for subsequent installation, and (2) further characterize local bedrock geology and hydrogeology and gain insight about the deeper component of the shallow bedrock aquifer flow system. A secondary objective was to provide stratigraphic and structural correlations with existing logs for Hydraulic Head Monitoring Station (HHMS) wells, which display evidence of faulting.

  5. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 5, Technical Memorandums 06-09A, 06-10A, and 06-12A: Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    This report provides a detailed summary of the activities carried out to sample groundwater at Waste Area Grouping (WAG) 6. The analytical results for samples collected during Phase 1, Activity 2 of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI) are also presented. In addition, analytical results for Phase 1, activity sampling events for which data were not previously reported are included in this TM. A summary of the groundwater sampling activities of WAG 6, to date, are given in the Introduction. The Methodology section describes the sampling procedures and analytical parameters. Six attachments are included. Attachments 1 and 2 provide analytical results for selected RFI groundwater samples and ORNL sampling event. Attachment 3 provides a summary of the contaminants detected in each well sampled for all sampling events conducted at WAG 6. Bechtel National Inc. (BNI)/IT Corporation Contract Laboratory (IT) RFI analytical methods and detection limits are given in Attachment 4. Attachment 5 provides the Oak Ridge National Laboratory (ORNL)/Analytical Chemistry Division (ACD) analytical methods and detection limits and Resource Conservation and Recovery Act (RCRA) quarterly compliance monitoring (1988--1989). Attachment 6 provides ORNL/ACD groundwater analytical methods and detection limits (for the 1990 RCRA semi-annual compliance monitoring).

  6. Lab 6 winding facility

    International Nuclear Information System (INIS)

    This note describes the winding machine installed by the facility support group at lab 6 in the Fermilab village. It is available for use by outside users and groups within the lab. The machine can wind wire planes whose longest dimension is less than 10 feet. The Wire spacing range has an upper practical limit of about 5mm. Spacing beyond this requires a very long index time and therefore slows down the winding speed prohibitively

  7. COMMUNICATIONS GROUP

    CERN Multimedia

    L. Taylor

    2011-01-01

    The CMS Communications Group has been busy in all three areas of its responsibility: (1) Communications Infrastructure, (2) Information Systems, and (3) Outreach and Education. Communications Infrastructure The 55 CMS Centres worldwide are well used by physicists working on remote CMS shifts, Computing operations, data quality monitoring, data analysis and outreach. The CMS Centre@CERN in Meyrin, is the centre of the CMS Offline and Computing operations, and a number of subdetector shifts can now take place there, rather than in the main Control Room at P5. A new CMS meeting room has been equipped for videoconferencing in building 42, next to building 40. Our building 28 meeting room and the facilities at P5 will be refurbished soon and plans are underway to steadily upgrade the ageing equipment in all 15 CMS meeting rooms at CERN. The CMS evaluation of the Vidyo tool indicates that it is not yet ready to be considered as a potential replacement for EVO. The Communications Group provides the CMS-TV (web) cha...

  8. Advanced reactor experimental facilities

    International Nuclear Information System (INIS)

    For many years, the NEA has been examining advanced reactor issues and disseminating information of use to regulators, designers and researchers on safety issues and research needed. Following the recommendation of participants at an NEA workshop, a Task Group on Advanced Reactor Experimental Facilities (TAREF) was initiated with the aim of providing an overview of facilities suitable for carrying out the safety research considered necessary for gas-cooled reactors (GCRs) and sodium fast reactors (SFRs), with other reactor systems possibly being considered in a subsequent phase. The TAREF was thus created in 2008 with the following participating countries: Canada, the Czech Republic, Finland, France, Germany, Hungary, Italy, Japan, Korea and the United States. In a second stage, India provided valuable information on its experimental facilities related to SFR safety research. The study method adopted entailed first identifying high-priority safety issues that require research and then categorizing the available facilities in terms of their ability to address the safety issues. For each of the technical areas, the task members agreed on a set of safety issues requiring research and established a ranking with regard to safety relevance (high, medium, low) and the status of knowledge based on the following scale relative to full knowledge: high (100%-75%), medium (75 - 25%) and low (25-0%). Only the issues identified as being of high safety relevance and for which the state of knowledge is low or medium were included in the discussion, as these issues would likely warrant further study. For each of the safety issues, the TAREF members identified appropriate facilities, providing relevant information such as operating conditions (in- or out-of reactor), operating range, description of the test section, type of testing, instrumentation, current status and availability, and uniqueness. Based on the information collected, the task members assessed prospects and priorities

  9. Mammography Facilities

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Mammography Facility Database is updated periodically based on information received from the four FDA-approved accreditation bodies: the American College of...

  10. Health Facilities

    Science.gov (United States)

    Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, such as birthing centers and psychiatric care centers. When you ...

  11. Canyon Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — B Plant, T Plant, U Plant, PUREX, and REDOX (see their links) are the five facilities at Hanford where the original objective was plutonium removal from the uranium...

  12. Hazard Baseline Downgrade Effluent Treatment Facility

    International Nuclear Information System (INIS)

    This Hazard Baseline Downgrade reviews the Effluent Treatment Facility, in accordance with Department of Energy Order 5480.23, WSRC11Q Facility Safety Document Manual, DOE-STD-1027-92, and DOE-EM-STD-5502-94. It provides a baseline grouping based on the chemical and radiological hazards associated with the facility. The Determination of the baseline grouping for ETF will aid in establishing the appropriate set of standards for the facility

  13. The CUTLASS database facilities

    International Nuclear Information System (INIS)

    The enhancement of the CUTLASS database management system to provide improved facilities for data handling is seen as a prerequisite to its effective use for future power station data processing and control applications. This particularly applies to the larger projects such as AGR data processing system refurbishments, and the data processing systems required for the new Coal Fired Reference Design stations. In anticipation of the need for improved data handling facilities in CUTLASS, the CEGB established a User Sub-Group in the early 1980's to define the database facilities required by users. Following the endorsement of the resulting specification and a detailed design study, the database facilities have been implemented as an integral part of the CUTLASS system. This paper provides an introduction to the range of CUTLASS Database facilities, and emphasises the role of Database as the central facility around which future Kit 1 and (particularly) Kit 6 CUTLASS based data processing and control systems will be designed and implemented. (author)

  14. Passive BWR integral LOCA testing at the Karlstein test facility INKA

    Energy Technology Data Exchange (ETDEWEB)

    Drescher, Robert [AREVA GmbH, Erlangen (Germany); Wagner, Thomas [AREVA GmbH, Karlstein am Main (Germany); Leyer, Stephan [TH Univ. of Applied Sciences, Deggendorf (Germany)

    2014-07-01

    KERENA is an innovative AREVA GmbH boiling water reactor (BWR) with passive safety systems (Generation III+). In order to verify the functionality of the reactor design an experimental validation programme was executed. Therefore the INKA (Integral Teststand Karlstein) test facility was designed and erected. It is a mockup of the BWR containment with integrated pressure suppression system. In March 2013 the first integral test - Main Steam Line Break (MSLB) - was executed. The main target was to demonstrate the ability of the passive systems to ensure core coverage, decay heat removal and to maintain the containment within defined limits. The results of the test showed that the passive safety systems are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. (orig.)

  15. Passive BWR integral LOCA testing at the Karlstein test facility INKA

    International Nuclear Information System (INIS)

    KERENA is an innovative AREVA GmbH boiling water reactor (BWR) with passive safety systems (Generation III+). In order to verify the functionality of the reactor design an experimental validation programme was executed. Therefore the INKA (Integral Teststand Karlstein) test facility was designed and erected. It is a mockup of the BWR containment with integrated pressure suppression system. In March 2013 the first integral test - Main Steam Line Break (MSLB) - was executed. The main target was to demonstrate the ability of the passive systems to ensure core coverage, decay heat removal and to maintain the containment within defined limits. The results of the test showed that the passive safety systems are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. (orig.)

  16. AREVA at December 31, 2012: Sales revenue growth to euro 9.342 bn (+5.3% vs. 2011), led by nuclear and renewables operations; Backlog replenished in 2012 to euro 45.4 bn thanks to the increase in order intake

    International Nuclear Information System (INIS)

    AREVA had 9.342 billion euros in consolidated sales revenue in 2012, an increase of 5.3% compared with 2011 (+4.4% like for like). This increase reflects growth in both nuclear and renewables operations: - the nuclear operations reported sales revenue of 8.633 billion euros in 2012, compared with 8.426 billion euros in 2011, a 2.4% increase. On a reported basis, growth was led by the Mining Business Group (+5.5%), the Reactors and Services BG (+7.1%) and the Back End BG (+9.5%), offsetting the expected decrease in business in the Front End BG (-10.2%); - the Renewable Energies BG reported 572 million euros in sales revenue, a sharp increase in relation to 2011 (+92.3%); - foreign exchange had a positive impact of 159 million euros over the period, while changes in consolidation scope had a negative impact of 83 million euros. Fourth quarter 2012 sales revenue totaled 2.799 billion euros. It was down 4.2% on a reported basis (-4.1% like for like), chiefly due to a lower level of activity in the Mining BG compared with a particularly high fourth quarter 2011 and following three consecutive quarters of strong growth for the BG. Foreign exchange had a positive impact of 29 million euros over the period. Changes in consolidation scope had a negative impact of 31 million euros for the quarter. The group's backlog of 45.4 billion euros at December 31, 2012 was stable in relation to December 31, 2011 (45.6 billion euros). The 10.4% increase in nuclear order intake (a total of 8% for the group) compensated for the activity level growth in 2012 and cancellations of orders in nuclear operations following the Fukushima accident (for a total amount of 936 million euros, compared with 464 million euros at December 31, 2011 and 742 million euros at September 30, 2012)

  17. FACILITIES MANAGEMENT AT CERN

    CERN Multimedia

    2002-01-01

    Recently we have been confronted with difficulties concerning services which are part of a new contract for facilities management. Please see below for some information about this contract. Following competitive tendering and the Finance Committee decision, the contract was awarded to the Swiss firm 'Facilities Management Network (FMN)'. The owners of FMN are two companies 'M+W Zander' and 'Avireal', both very experienced in this field of facilities management. The contract entered into force on 1st July 2002. CERN has grouped together around 20 different activities into this one contract, which was previously covered by separate contracts. The new contract includes the management and execution of many activities, in particular: Guards and access control; cleaning; operation and maintenance of heating plants, cooling and ventilation equipment for buildings not related to the tunnel or the LHC; plumbing; sanitation; lifts; green areas and roads; waste disposal; and includes a centralised helpdesk for these act...

  18. Marina Facilities

    OpenAIRE

    2014-01-01

    The CIRPAS main facility and headquarters are at Marina Municipal Airport (formerly Fritchie Field, Fort Ord) in Marina, California. CIRPAS has a 30,000 sq. ft. maintenance hanger there, which houses staff offices, an instrument and calibration laboratory, maintenance and payload integration shops, conference rooms, and flight planning and operations control center.

  19. ORNL calibrations facility

    International Nuclear Information System (INIS)

    The ORNL Calibrations Facility is operated by the Instrumentation Group of the Industrial Safety and Applied Health Physics Division. Its primary purpose is to maintain radiation calibration standards for calibration of ORNL health physics instruments and personnel dosimeters. This report includes a discussion of the radioactive sources and ancillary equipment in use and a step-by-step procedure for calibration of those survey instruments and personnel dosimeters in routine use at ORNL

  20. Main Facilities

    International Nuclear Information System (INIS)

    This chapter discuss on main nuclear facilities available in the Malaysian Institute for Nuclear Technology Research (MINT). As a national research institute whose core activities are nuclear science and technology, MINT are made up of main commercializable radiation irradiators, pilot plant and fully equipped laboratories. Well elaboration on its characteristics and functions explain for RTP (PUPSPATI TRIGA reactors), Cobalt-60 gamma irradiator, electron beam accelerators, and radioactive waste management center

  1. Nuclear facility

    International Nuclear Information System (INIS)

    In nuclear facilities with a fuel storage pool in a spent fuel pit building there is a filter to each pool through which the fuel pit water is pumped. According to the invention the filter is provided with an independently movable housing placed beneath the surface of the pool water and fixed to the lateral side of the pool by means of detachable fixtures. (orig./RW)

  2. Support facilities

    International Nuclear Information System (INIS)

    Computer support is centered on the Remote Access Data Station (RADS), which is equipped with a 1000 lpm printer, 1000 cpm reader, and a 300 cps paper tape reader with 500-foot spools. The RADS is located in a data preparation room with four 029 key punches (two of which interpret), a storage vault for archival magnetic tapes, card files, and a 30 cps interactive terminal principally used for job inquiry and routing. An adjacent room provides work space for users, with a documentation library and a consultant's office, plus file storage for programs and their documentations. The facility has approximately 2,600 square feet of working laboratory space, and includes two fully equipped photographic darkrooms, sectioning and autoradiographic facilities, six microscope cubicles, and five transmission electron microscopes and one Cambridge scanning electron microscope equipped with an x-ray energy dispersive analytical system. Ancillary specimen preparative equipment includes vacuum evaporators, freeze-drying and freeze-etching equipment, ultramicrotomes, and assorted photographic and light microscopic equipment. The extensive physical plant of the animal facilities includes provisions for holding all species of laboratory animals under controlled conditions of temperature, humidity, and lighting. More than forty rooms are available for studies of the smaller species. These have a potential capacity of more than 75,000 mice, or smaller numbers of larger species and those requiring special housing arrangements. There are also six dog kennels to accommodate approximately 750 dogs housed in runs that consist of heated indoor compartments and outdoor exercise areas

  3. Linac working group technical summary

    International Nuclear Information System (INIS)

    The working group looked at linac injectors for a Superconducting Super Collider (SSC) or Hadron Facility. Discussion includes rf power, a possible strawman linac, ion source/injector, radio-frequency quadrupole, and coupled-cavity linac

  4. Remedial site evaluation report for the waste area grouping 10 wells associated with the new hydrofracture facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1: Evaluation, interpretation, and data summary

    International Nuclear Information System (INIS)

    The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the U.S. Department of Energy (DOE) by Lockheed Martin Energy System (Energy Systems). ORNL has pioneered waste disposal technologies since World War II as part of its DOE mission. In the late 1950s, at the request of the National Academy of Sciences, efforts were made to develop a permanent disposal alternative to the surface and tanks at ORNL. One such technology, the hydrofracture process, involved inducing fractures in a geologic host formation (a low-permeability shale) at depths of up to 1100 ft and injecting a radioactive grout slurry containing low-level liquid or tank sludge waste, cement, and other additives at an injection pressure of 2000 to 8500 psi. The objective of the effort was to develop a grout dig could be injected as a slurry and would solidify after injection, thereby entombing the radioisotopes contained in the low-level liquid or tank sludge waste. Four sites at ORNL were used: two experimental (HF-1 and HF-2); one developmental, later converted to batch process [Old Hydrofracture Facility (BF-3)]; and one production facility [New Hydrofracture Facility (BF-4)]. This document provides the environmental, restoration program with information about the the results of an evaluation of WAG 10 wells associated with the New Hydrofracture Facility at ORNL

  5. Remedial site evaluation report for the waste area grouping 10 wells associated with the new hydrofracture facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1: Evaluation, interpretation, and data summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the U.S. Department of Energy (DOE) by Lockheed Martin Energy System (Energy Systems). ORNL has pioneered waste disposal technologies since World War II as part of its DOE mission. In the late 1950s, at the request of the National Academy of Sciences, efforts were made to develop a permanent disposal alternative to the surface and tanks at ORNL. One such technology, the hydrofracture process, involved inducing fractures in a geologic host formation (a low-permeability shale) at depths of up to 1100 ft and injecting a radioactive grout slurry containing low-level liquid or tank sludge waste, cement, and other additives at an injection pressure of 2000 to 8500 psi. The objective of the effort was to develop a grout dig could be injected as a slurry and would solidify after injection, thereby entombing the radioisotopes contained in the low-level liquid or tank sludge waste. Four sites at ORNL were used: two experimental (HF-1 and HF-2); one developmental, later converted to batch process [Old Hydrofracture Facility (BF-3)]; and one production facility [New Hydrofracture Facility (BF-4)]. This document provides the environmental, restoration program with information about the the results of an evaluation of WAG 10 wells associated with the New Hydrofracture Facility at ORNL.

  6. Group cubization

    OpenAIRE

    Osajda, Damian

    2016-01-01

    We present a procedure of group cubization: It results in a group whose some features resemble the ones of a given group, and which acts without fixed points on a CAT(0) cubical complex. As a main application we establish lack of Kazhdan's property (T) for Burnside groups. Other applications include new constructions of non-exact groups.

  7. Reactor safety research program at Thai test facility

    International Nuclear Information System (INIS)

    Thermal-hydraulics, Hydrogen, Aerosol and Iodine (Thai) aims at providing experimental database for the verification and validation of Lumped Parameter (Lp) and Computational Fluid Dynamics (CFD) codes with 3-dimensional capabilities. Since its construction in 2000, Thai facility has been engaged in the field of reactor safety in the frame of various national (Thai I: 2000-2003, Thai II: 2003-2006, Thai III: 2006-2009, Thai IV: 2009-2012) and international programs (OECD-Thai: 2007-2009). Additionally, experimental data has been provided for several international standard problems (ISP 41, 46, 47 and 49) code validation exercises. Experiments performed in Thai facility cover a wide spectrum or reactor safety relevant issues by investigating separate and coupled-phenomenon experiments under design basis accident and severe-accident-typical scenarios. Experiments are performed in close co-operation with AREVA Erlangen and Grs Koln. Experimental configuration and the operating conditions in Thai vessel typical of those for PWR, BWR and High Temperature Gas Cooled Reactor can be produced thanks to its modular structure, appropriate feeding/generation devices for gases (H2, He, Steam, N2, etc.), Aerosol (inert and hygroscopic), Iodine Radiotracer, and advanced instrumentation. Experiments also cover investigation of passive safety systems, e.g. commercial Par for H2 mitigation in phenomenon orientated experiments to enhance the confidence in the performance of passive mitigation systems during severe accident scenarios and also to establish a common database accessible by a large research community to support further development and validation of the Lp and CFD codes with 3-dimensional capabilities. This paper summarizes experimental investigations made in Thai test facility to investigate issues related to the thermal-hydraulics, fission product (aerosol, iodine) transport and their interaction with containment walls (deposition, resuspension) and passive safety

  8. Facility Management

    OpenAIRE

    Král, David

    2012-01-01

    Tématem bakalářské práce je nalezení cesty ke zvýšení dlouhodobé efektivnosti a prosperity společnosti, která v rámci své podnikatelské činnosti spravuje a udržuje vlastní nemovitosti v centru Brna. Práce vychází z aktuálního stavu facility managementu společnosti a definování jejich silných a slabých stránek. Základem pro návrh efektivního řízení facility managementu je zpracování finanční analýzy společnosti a sledování nákladů včetně jejich optimalizace. Hlavním přínosem mé bakalářské prác...

  9. LAMPF: a nuclear research facility

    International Nuclear Information System (INIS)

    A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

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

  11. High-Average Power Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Dowell, David H.; /SLAC; Power, John G.; /Argonne

    2012-09-05

    There has been significant progress in the development of high-power facilities in recent years yet major challenges remain. The task of WG4 was to identify which facilities were capable of addressing the outstanding R&D issues presently preventing high-power operation. To this end, information from each of the facilities represented at the workshop was tabulated and the results are presented herein. A brief description of the major challenges is given, but the detailed elaboration can be found in the other three working group summaries.

  12. Dismantling of the 904 Cell at the HAO/Sud Facility - 13466

    Energy Technology Data Exchange (ETDEWEB)

    Vaudey, C.E.; Crosnier, S. [AREVA Clean-Up BU, 1 route de la Noue 91196 - Gif-sur-Yvette (France); Renouf, M.; Gaspard, N. [AREVA Clean-Up BU, Site de La Hague - BV 35 - 50444 Beaumont Hague (France); Pinot, L. [AREVA D and D BU, Site de La Hague - 50444 Beaumont Hague (France)

    2013-07-01

    La Hague facility, in France, is the spent fuel recycling plant wherein a part of the fuel coming from some of the French, German, Belgian, Swiss, Dutch and Japanese nuclear reactors is reprocessed before being recycled in order to separate certain radioactive elements. The facility has been successively handled by the CEA (1962-1978), Cogema (1978-2006), and AREVA NC (since 2006). La Hague facility is composed of 3 production units: The UP2-400 production unit started to be operated in 1966 for the reprocessing of UNGG metal fuel. In 1976, following the dropout of the graphite-gas technology by EDF, an HAO workshop to reprocess the fuel from the light water reactors is affiliated and then stopped in 2003. - UP2-400 is partially stopped in 2002 and then definitely the 1 January 2004 and is being dismantled - UP2-800, with the same capacity than UP3, started to be operated in 1994 and is still in operation. And UP3 - UP3 was implemented in 1990 with an annual reprocessing capacity of 800 tons of fuel and is still in operation The combined licensed capacity of UP2-800 and UP3 is 1,700 tons of used fuel. (authors)

  13. Passive BWR integral LOCA testing at the Karlstein test facility INKA

    Energy Technology Data Exchange (ETDEWEB)

    Drescher, Robert [AREVA GmbH, Erlangen (Germany); Wagner, Thomas [AREVA GmbH, Karlstein am Main (Germany); Leyer, Stephan [TH University of Applied Sciences, Deggendorf (Germany)

    2014-05-15

    KERENA is an innovative AREVA GmbH boiling water reactor (BWR) with passive safety systems (Generation III+). In order to verify the functionality of the reactor design an experimental validation program was executed. Therefore the INKA (Integral Teststand Karlstein) test facility was designed and erected. It is a mockup of the BWR containment, with integrated pressure suppression system. While the scaling of the passive components and the levels match the original values, the volume scaling of the containment compartments is approximately 1:24. The storage capacity of the test facility pressure vessel corresponds to approximately 1/6 of the KERENA RPV and is supplied by a benson boiler with a thermal power of 22 MW. In March 2013 the first integral test - Main Steam Line Break (MSLB) - was executed. The test measured the combined response of the passive safety systems to the postulated initiating event. The main goal was to demonstrate the ability of the passive systems to ensure core coverage, decay heat removal and to maintain the containment within defined limits. The results of the test showed that the passive safety systems are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. Therefore the test verified the function of those components and the interplay between them. The test proved that INKA is an unique test facility, capable to perform integral tests of passive safety concepts under plant-like conditions. (orig.)

  14. Passive BWR integral LOCA testing at the Karlstein test facility INKA

    International Nuclear Information System (INIS)

    KERENA is an innovative AREVA GmbH boiling water reactor (BWR) with passive safety systems (Generation III+). In order to verify the functionality of the reactor design an experimental validation program was executed. Therefore the INKA (Integral Teststand Karlstein) test facility was designed and erected. It is a mockup of the BWR containment, with integrated pressure suppression system. While the scaling of the passive components and the levels match the original values, the volume scaling of the containment compartments is approximately 1:24. The storage capacity of the test facility pressure vessel corresponds to approximately 1/6 of the KERENA RPV and is supplied by a benson boiler with a thermal power of 22 MW. In March 2013 the first integral test - Main Steam Line Break (MSLB) - was executed. The test measured the combined response of the passive safety systems to the postulated initiating event. The main goal was to demonstrate the ability of the passive systems to ensure core coverage, decay heat removal and to maintain the containment within defined limits. The results of the test showed that the passive safety systems are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. Therefore the test verified the function of those components and the interplay between them. The test proved that INKA is an unique test facility, capable to perform integral tests of passive safety concepts under plant-like conditions. (orig.)

  15. Group X

    Energy Technology Data Exchange (ETDEWEB)

    Fields, Susannah

    2007-08-16

    This project is currently under contract for research through the Department of Homeland Security until 2011. The group I was responsible for studying has to remain confidential so as not to affect the current project. All dates, reference links and authors, and other distinguishing characteristics of the original group have been removed from this report. All references to the name of this group or the individual splinter groups has been changed to 'Group X'. I have been collecting texts from a variety of sources intended for the use of recruiting and radicalizing members for Group X splinter groups for the purpose of researching the motivation and intent of leaders of those groups and their influence over the likelihood of group radicalization. This work included visiting many Group X websites to find information on splinter group leaders and finding their statements to new and old members. This proved difficult because the splinter groups of Group X are united in beliefs, but differ in public opinion. They are eager to tear each other down, prove their superiority, and yet remain anonymous. After a few weeks of intense searching, a list of eight recruiting texts and eight radicalizing texts from a variety of Group X leaders were compiled.

  16. Group Flow and Group Genius

    Science.gov (United States)

    Sawyer, Keith

    2015-01-01

    Keith Sawyer views the spontaneous collaboration of group creativity and improvisation actions as "group flow," which organizations can use to function at optimum levels. Sawyer establishes ideal conditions for group flow: group goals, close listening, complete concentration, being in control, blending egos, equal participation, knowing…

  17. Evaluation of health risks related to the operation of the AREVA sites of the Tricastin platform: Georges Besse plants I and II, SOCATRI, COGEMA Pierrelatte and COMURHEX (first level approach) Assessment of health studies. Final report

    International Nuclear Information System (INIS)

    This document reports the study of health risks related to the chemical toxicity of species related to the operation of several AREVA installations in Tricastin. A qualitative and quantitative inventory of the species released in the atmosphere and in waters is based on data supplied by the operator. A selection of health tracers has lead to a global investigation of nitrogen oxides, sulphur dioxide, fluorine, uranium, arsenic, hexavalent chromium, mercury and nickel. The hazard associated with each of these species has been characterized. Different exposure ways have been considered: inhalation, soil ingestion, by vegetable, fruit and crop ingestion, ingestion of meat, milk and eggs produced by local breeding, fish ingestion, and ingestion of water sampled from the Tricastin aquifer. Atmospheric concentrations, soil deposits, surface soil layer concentrations, and other concentrations (in meat, milk, eggs, crops, vegetables, fruits, and drinking water) have been either modelled or measured. Different exposure scenarios have been defined, and the different risks (carcinogen or not) have been assessed

  18. 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.)

  19. Active use of urban park facilities

    DEFF Research Database (Denmark)

    Lindberg, Michael; Schipperijn, Jasper

    2015-01-01

    Abstract Urban green spaces (UGS), and more specific a higher number of facilities in UGS, have been positively associated with physical activity (PA). However, more detailed studies of which facilities generate high levels of PA, for which type of users, are relevant as existing knowledge is...... mentioned as a key factor when designing facilities. Our results provide important knowledge to architects, planners and policy makers when aiming at designing activity-promoting facilities in UGS. Future studies need to further investigate the use of facilities among specific target groups, particularly...

  20. Designing Facilities for Collaborative Operations

    Science.gov (United States)

    Norris, Jeffrey; Powell, Mark; Backes, Paul; Steinke, Robert; Tso, Kam; Wales, Roxana

    2003-01-01

    A methodology for designing operational facilities for collaboration by multiple experts has begun to take shape as an outgrowth of a project to design such facilities for scientific operations of the planned 2003 Mars Exploration Rover (MER) mission. The methodology could also be applicable to the design of military "situation rooms" and other facilities for terrestrial missions. It was recognized in this project that modern mission operations depend heavily upon the collaborative use of computers. It was further recognized that tests have shown that layout of a facility exerts a dramatic effect on the efficiency and endurance of the operations staff. The facility designs (for example, see figure) and the methodology developed during the project reflect this recognition. One element of the methodology is a metric, called effective capacity, that was created for use in evaluating proposed MER operational facilities and may also be useful for evaluating other collaboration spaces, including meeting rooms and military situation rooms. The effective capacity of a facility is defined as the number of people in the facility who can be meaningfully engaged in its operations. A person is considered to be meaningfully engaged if the person can (1) see, hear, and communicate with everyone else present; (2) see the material under discussion (typically data on a piece of paper, computer monitor, or projection screen); and (3) provide input to the product under development by the group. The effective capacity of a facility is less than the number of people that can physically fit in the facility. For example, a typical office that contains a desktop computer has an effective capacity of .4, while a small conference room that contains a projection screen has an effective capacity of around 10. Little or no benefit would be derived from allowing the number of persons in an operational facility to exceed its effective capacity: At best, the operations staff would be underutilized

  1. Group morphology

    NARCIS (Netherlands)

    Roerdink, Jos B.T.M.

    2000-01-01

    In its original form, mathematical morphology is a theory of binary image transformations which are invariant under the group of Euclidean translations. This paper surveys and extends constructions of morphological operators which are invariant under a more general group TT, such as the motion group

  2. Abelian Groups

    Energy Technology Data Exchange (ETDEWEB)

    Mishina, A.P.

    1995-10-15

    This fifth survey of reviews on abelian groups comprises papers reviewed in 1985-1992. Just as in the preceding surveys, the issues concerning finite abelian groups, topological groups, ordered groups, group algebras, modules (with rare exceptions), and topics on logic are not considered. The issues on the lattice of subgroups of an abelian group are included in Section 11. In contrast to the fourth survey, this one does not contain Sections 6 (N-high subgroups), 9 (rings with a given additive group), and 10 (valuated groups); since only a few papers treated these topics, the material discussed earlier in Sections 9, and 10 is now included in Section 11 and the material of the former Section 6 will be found in Sections 1, 7, 8, and 11 of this survey. On the other hand, the fifth survey has three new sections devoted to separable groups (a new Sect. 5), Butler groups (a new Sect. 6), and the endormorphism rings and automorphism groups of abelian groups (a new Sect. 9).

  3. Spent Fuel Working Group Report

    International Nuclear Information System (INIS)

    The Department of Energy is storing large amounts of spent nuclear fuel and other reactor irradiated nuclear materials (herein referred to as RINM). In the past, the Department reprocessed RINM to recover plutonium, tritium, and other isotopes. However, the Department has ceased or is phasing out reprocessing operations. As a consequence, Department facilities designed, constructed, and operated to store RINM for relatively short periods of time now store RINM, pending decisions on the disposition of these materials. The extended use of the facilities, combined with their known degradation and that of their stored materials, has led to uncertainties about safety. To ensure that extended storage is safe (i.e., that protection exists for workers, the public, and the environment), the conditions of these storage facilities had to be assessed. The compelling need for such an assessment led to the Secretary's initiative on spent fuel, which is the subject of this report. This report comprises three volumes: Volume I; Summary Results of the Spent Fuel Working Group Evaluation; Volume II, Working Group Assessment Team Reports and Protocol; Volume III; Operating Contractor Site Team Reports. This volume presents the overall results of the Working Group's Evaluation. The group assessed 66 facilities spread across 11 sites. It identified: (1) facilities that should be considered for priority attention. (2) programmatic issues to be considered in decision making about interim storage plans and (3) specific vulnerabilities for some of these facilities

  4. Permutation groups

    CERN Document Server

    Passman, Donald S

    2012-01-01

    This volume by a prominent authority on permutation groups consists of lecture notes that provide a self-contained account of distinct classification theorems. A ready source of frequently quoted but usually inaccessible theorems, it is ideally suited for professional group theorists as well as students with a solid background in modern algebra.The three-part treatment begins with an introductory chapter and advances to an economical development of the tools of basic group theory, including group extensions, transfer theorems, and group representations and characters. The final chapter feature

  5. Galaxy Groups

    Science.gov (United States)

    Tully, R. Brent

    2015-02-01

    Galaxy groups can be characterized by the radius of decoupling from cosmic expansion, the radius of the caustic of second turnaround, and the velocity dispersion of galaxies within this latter radius. These parameters can be a challenge to measure, especially for small groups with few members. In this study, results are gathered pertaining to particularly well-studied groups over four decades in group mass. Scaling relations anticipated from theory are demonstrated and coefficients of the relationships are specified. There is an update of the relationship between light and mass for groups, confirming that groups with mass of a few times {{10}12}{{M}⊙ } are the most lit up while groups with more and less mass are darker. It is demonstrated that there is an interesting one-to-one correlation between the number of dwarf satellites in a group and the group mass. There is the suggestion that small variations in the slope of the luminosity function in groups are caused by the degree of depletion of intermediate luminosity systems rather than variations in the number per unit mass of dwarfs. Finally, returning to the characteristic radii of groups, the ratio of first to second turnaround depends on the dark matter and dark energy content of the universe and a crude estimate can be made from the current observations of {{Ω}matter}˜ 0.15 in a flat topology, with a 68% probability of being less than 0.44.

  6. Galaxy groups

    Energy Technology Data Exchange (ETDEWEB)

    Brent Tully, R. [Institute for Astronomy, University of Hawaii, 2680 Woodlawn Drive, Honolulu, HI 96822 (United States)

    2015-02-01

    Galaxy groups can be characterized by the radius of decoupling from cosmic expansion, the radius of the caustic of second turnaround, and the velocity dispersion of galaxies within this latter radius. These parameters can be a challenge to measure, especially for small groups with few members. In this study, results are gathered pertaining to particularly well-studied groups over four decades in group mass. Scaling relations anticipated from theory are demonstrated and coefficients of the relationships are specified. There is an update of the relationship between light and mass for groups, confirming that groups with mass of a few times 10{sup 12}M{sub ⊙} are the most lit up while groups with more and less mass are darker. It is demonstrated that there is an interesting one-to-one correlation between the number of dwarf satellites in a group and the group mass. There is the suggestion that small variations in the slope of the luminosity function in groups are caused by the degree of depletion of intermediate luminosity systems rather than variations in the number per unit mass of dwarfs. Finally, returning to the characteristic radii of groups, the ratio of first to second turnaround depends on the dark matter and dark energy content of the universe and a crude estimate can be made from the current observations of Ω{sub matter}∼0.15 in a flat topology, with a 68% probability of being less than 0.44.

  7. Galaxy Groups

    CERN Document Server

    Tully, R Brent

    2014-01-01

    Galaxy groups can be characterized by the radius of decoupling from cosmic expansion, the radius of the caustic of second turnaround, and the velocity dispersion of galaxies within this latter radius. These parameters can be a challenge to measure, especially for small groups with few members. In this study, results are gathered pertaining to particularly well studied groups over four decades in group mass. Scaling relations anticipated from theory are demonstrated and coefficients of the relationships are specified. There is an update of the relationship between light and mass for groups, confirming that groups with mass of a few times 10^12 Msun are the most lit up while groups with more and less mass are darker. It is demonstrated that there is an interesting one-to-one correlation between the number of dwarf satellites in a group and the group mass. There is the suggestion that small variations in the slope of the luminosity function in groups are caused by the degree of depletion of intermediate luminosi...

  8. North Slope, Alaska ESI: FACILITY (Facility Points)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains data for oil field facilities for the North Slope of Alaska. Vector points in this data set represent oil field facility locations. This data...

  9. Radiation safety training for accelerator facilities

    International Nuclear Information System (INIS)

    In November 1992, a working group was formed within the U.S. Department of Energy's (DOE's) accelerator facilities to develop a generic safety training program to meet the basic requirements for individuals working in accelerator facilities. This training, by necessity, includes sections for inserting facility-specific information. The resulting course materials were issued by DOE as a handbook under its technical standards in 1996. Because experimenters may be at a facility for only a short time and often at odd times during the day, the working group felt that computer-based training would be useful. To that end, Lawrence Livermore National Laboratory (LLNL) and Argonne National Laboratory (ANL) together have developed a computer-based safety training program for accelerator facilities. This interactive course not only enables trainees to receive facility- specific information, but time the training to their schedule and tailor it to their level of expertise

  10. Metabolomics Research Group 2011 Study

    OpenAIRE

    Asara, J. M.; Tolstikov, V.V.; Aronov, P.; Kesler, B.; Shulaev, V.; Turck, C. W.; Wikoff, W R

    2011-01-01

    The ABRF Metabolomics Research Group (MRG) was formed in 2009 and aims to educate research scientists and resource facilities in the analytical approaches and management of data resulting from comprehensive metabolite studies and to promote the science and standardization of metabolomic analyses for a variety of applications. Last year the MRG conducted a ‘Survey Study’ on the current use of metabolomics technologies and procedures in core facilities. This year the MRG is organizing a ‘Resear...

  11. Air Quality Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research FacilityFacilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other...

  12. Basic Research Firing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Basic Research Firing Facility is an indoor ballistic test facility that has recently transitioned from a customer-based facility to a dedicated basic research...

  13. Hydra groups

    CERN Document Server

    Dison, Will

    2010-01-01

    We give examples of CAT(0), biautomatic, free-by-cyclic, one-relator groups which have finite-rank free subgroups of huge (Ackermannian) distortion. This leads to elementary examples of groups whose Dehn functions are similarly extravagant. This behaviour originates in manifestations of Hercules-versus-the-hydra battles in string-rewriting.

  14. Reflection groups

    International Nuclear Information System (INIS)

    In 2005, PISA organised proactive meetings of reflection groups on involvement in decision making, expert culture and ethical aspects of radiation protection.All reflection group meetings address particular targeted audiences while the output publication in book form is put forward

  15. Facility Registry Service (FRS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Facility Registry Service (FRS) provides an integrated source of comprehensive (air, water, and waste) environmental information about facilities across EPA,...

  16. Licensed Healthcare Facilities

    Data.gov (United States)

    California Department of Resources — The Licensed Healthcare Facilities point layer represents the locations of all healthcare facilities licensed by the State of California, Department of Health...

  17. High Throughput Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Argonne?s high throughput facility provides highly automated and parallel approaches to material and materials chemistry development. The facility allows scientists...

  18. Report of study group 3.1 ''technological and economical developments for cost reduction of LNG facilities''; Rapport du groupe d'etude 3.1 ''developpements economiques et technologiques pour la reduction des couts dans les installations de GNL''

    Energy Technology Data Exchange (ETDEWEB)

    Rapallini, R.

    2000-07-01

    The design, engineering and operation of LNG base load liquefaction and re-gasification facilities is now considered a mature technology. However, process efficiency at these plants is limited by fundamental thermodynamic principles and no radical technology breakthroughs are expected in the near future. Three important aspects affecting the cost of production are the molecular weight of the gas, the amount of nitrogen in the feed and the acid gas composition. Variations in composition will also affect the design of the facilities and production rate. Previous projects have optimised economies of scale, using processes based on large industrial gas turbines, to achieve the minimum unit cost for LNG production. LNG producers have continued to focus on larger train designs to further capitalize on economies of scale as well as continued expansion of existing facilities. The latest plant designs expect the optimum integration with existing facilities to be a major factor in optimising specific capital costs. Whilst design codes and standards have not been discussed in many papers on LNG cost reduction, it is generally accepted that project specifications can significantly impact the project cost. The cost of equipment can be significantly inflated by onerous specifications with non standard requirements that vendors have trouble meeting. The possibility of developing gas projects will mainly be determined by the requirements of power generation and/or the industrial sector. As far as power generation is concerned, expansion will rely greatly on combined cycle plants. The competitiveness of LNG as regards power generation can be further improved by adopting integrated solutions. As in all other industrial projects, one of the first concerns for the investor when he envisages building an LNG liquefaction or re-gasification terminal is the selection of the site where the terminal will be located. (author)

  19. Guide to research facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

  20. Algebraic Groups

    DEFF Research Database (Denmark)

    2007-01-01

    The workshop continued a series of Oberwolfach meetings on algebraic groups, started in 1971 by Tonny Springer and Jacques Tits who both attended the present conference. This time, the organizers were Michel Brion, Jens Carsten Jantzen, and Raphaël Rouquier. During the last years, the subject of...... algebraic groups (in a broad sense) has seen important developments in several directions, also related to representation theory and algebraic geometry. The workshop aimed at presenting some of these developments in order to make them accessible to a "general audience" of algebraic group-theorists, and to...

  1. Group Grammar

    Science.gov (United States)

    Adams, Karen

    2015-01-01

    In this article Karen Adams demonstrates how to incorporate group grammar techniques into a classroom activity. In the activity, students practice using the target grammar to do something they naturally enjoy: learning about each other.

  2. Abelian groups

    CERN Document Server

    Fuchs, László

    2015-01-01

    Written by one of the subject’s foremost experts, this book focuses on the central developments and modern methods of the advanced theory of abelian groups, while remaining accessible, as an introduction and reference, to the non-specialist. It provides a coherent source for results scattered throughout the research literature with lots of new proofs. The presentation highlights major trends that have radically changed the modern character of the subject, in particular, the use of homological methods in the structure theory of various classes of abelian groups, and the use of advanced set-theoretical methods in the study of undecidability problems. The treatment of the latter trend includes Shelah’s seminal work on the undecidability in ZFC of Whitehead’s Problem; while the treatment of the former trend includes an extensive (but non-exhaustive) study of p-groups, torsion-free groups, mixed groups, and important classes of groups arising from ring theory. To prepare the reader to tackle these topics, th...

  3. El Cabril Facilities

    International Nuclear Information System (INIS)

    The El Cabril facilities have been designed such that they may be used for the long-term disposal of low and intermediate level radioactive wastes. For this purpose, the design has been carried out in accordance with general criteria of: Ensuring the immediate and deferred protection for people and the environment. Allowing for the free use of the site following a period of at most 300 years, without radiological limitations. Furthermore, a basic objective sought in the design of El Cabril has been the possibility of recovering the wastes if circumstances were to make this advisable. The disposal system is based on the creation of barriers around the materials to be treated, for which the 220-liter drums containing the wastes are stored inside concrete containers, which are located in the disposal cells. The main core of the facilities consists of the disposal zone and the buildings area. Twenty-eight cells have been constructed in the first of these zones, grouped into two areas or platforms: the north platform, with 16 structures, and the south platform, with 12 (To date the ninth cell has been completed and closed and the tenth is now being filled). The buildings area contains the auxiliary installations for the treatment and conditioning of the wastes and for their control, along with the auxiliary services required for the operation and maintenance of the Facility. The installation is equipped with a verification laboratory supporting the waste acceptance and characterization activities and for technical verification of the waste packages. This laboratory is fitted with the equipment required for sampling, mechanical testing, the extraction of dry test pieces, etc. The laboratory is completed with a waste package radiological characterization system (non-destructive characterization by gamma spectrometry). a system for the leach testing of drums (decorticated) and test pieces, a radiochemistry laboratory and a counting room. (Author)

  4. Reliable Facility Location Problem with Facility Protection.

    Science.gov (United States)

    Tang, Luohao; Zhu, Cheng; Lin, Zaili; Shi, Jianmai; Zhang, Weiming

    2016-01-01

    This paper studies a reliable facility location problem with facility protection that aims to hedge against random facility disruptions by both strategically protecting some facilities and using backup facilities for the demands. An Integer Programming model is proposed for this problem, in which the failure probabilities of facilities are site-specific. A solution approach combining Lagrangian Relaxation and local search is proposed and is demonstrated to be both effective and efficient based on computational experiments on random numerical examples with 49, 88, 150 and 263 nodes in the network. A real case study for a 100-city network in Hunan province, China, is presented, based on which the properties of the model are discussed and some managerial insights are analyzed. PMID:27583542

  5. Group dynamics.

    Science.gov (United States)

    Scandiffio, A L

    1990-12-01

    Group dynamics play a significant role within any organization, culture, or unit. The important thing to remember with any of these structures is that they are made up of people--people with different ideas, motivations, background, and sometimes different agendas. Most groups, formal or informal, look for a leader in an effort to maintain cohesiveness of the unit. At times, that cultural bond must be developed; once developed, it must be nurtured. There are also times that one of the group no longer finds the culture comfortable and begins to act out behaviorally. It is these times that become trying for the leader as she or he attempts to remain objective when that which was once in the building phase of group cohesiveness starts to fall apart. At all times, the manager must continue to view the employee creating the disturbance as an integral part of the group. It is at this time that it is beneficial to perceive the employee exhibiting problem behaviors as a special employee, as one who needs the benefit of your experience and skills, as one who is still part of the group. It is also during this time that the manager should focus upon her or his own views in the area of power, communication, and the corporate culture of the unit that one has established before attempting to understand another's point of view. Once we understand our own motivation and accept ourselves, it is then that we may move on to offer assistance to another. Once we understand our insecurities recognizing staff dysfunction as a symptom of system dysfunction will not be so threatening to the concept of the manager that we perceive ourselves to be. It takes a secure person to admit that she or he favors staff before deciding to do something to change things. The important thing to know is that it can be done. The favored staff can find a new way of relating to others, the special employee can find new modes of behavior (and even find self-esteem in the process), the group can find new ways

  6. Wet spent fuel interim storage facility

    International Nuclear Information System (INIS)

    The article deals with the Spent Fuel Complementary Storage Unit, which was designed for the Almirante Alvaro Alberto Nuclear Power Station situated near Rio de Janeiro. The aim of the article is to present the technical solution of complementary storage. The design deals with different reactor technologies made by Areva and Westinghouse. The article also deals with the technically interesting solution of the storage tank heat removal and its dimensioning. (author)

  7. AOV Facility Tool/Facility Safety Specifications

    Data.gov (United States)

    Department of Transportation — Develop and maintain authorizing documents that are standards that facilities must follow. These standards are references of FAA regulations and are specific to the...

  8. Technology Development Facility (TDF)

    International Nuclear Information System (INIS)

    We have been studying small, driven, magnetic-mirror-based fusion reactors for the Technology Development Facility (TDF), that will test fusion reactor materials, components, and subsystems. Magnetic mirror systems are particularly interesting for this application because of their inherent steady-state operation, potentially high neutron wall loading, and relatively small size. Our design is a tandem mirror device first described by Fowler and Logan, based on the physics of the TMX experiments at Lawrence Livermore National Laboratory (LLNL). The device produces 20 MW of fusion power with a first-wall, uncollided 14-MeV neutron flux of 1.4 MW/m2 on an area of approximately 8 m2, while consuming approximately 250 MW of electrical power. The work was done by a combined industrial-laboratory-university group

  9. The Portuguese gamma irradiation facility

    International Nuclear Information System (INIS)

    A Gamma Radiation Facility was built up in the National Laboratory of Industrial Technology and Engineering (LNETI), Lisbon, Portugal. This plant (UTR GAMA-Pi) is a Cobalt-60 dry storage continuous facility with a nominal capacity of 1.5 x 1016 Bq. The initial activity is 1.1 x 1016 Bq and the throughput capacity 103 ton/year for product with a bulk density of 0.2 g/cm3 treated with a minimum absorbed dose of 25 kGy. Complementary control devices were installed: ventilation system, closed water refrigeration circuit, internal TV system, detection and extinction fire system and emergency power group. It must be emphasized that the best attention was given to the conception and efficiency of the interlock safety systems. This facility will be utilized mainly for radiosterilization of medical articles and decontamination of wine cork stoppers. (author)

  10. Monitored retrievable storage facility (MRS)

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) contracts with Management and Operations (M ampersand O) contractors to provide design and support for Monitored Retrievable Storage Facilities (MRS). This paper outlines the steps taken by the M ampersand O contractor in the design and siting process for MRS facilities. These steps include conceptual, preliminary and final MRS design, evaluation and selection of storage technologies, developing a safety analysis report (SAR) and completing the facility license application. After the preliminary work is done, a M ampersand O support group assures licensing, siting, and community outreach. The community outreach or public relations includes information about the MRS in layman's terms so that DOE will get feed back from the community

  11. Transfer of Tritium in the Environment after Accidental Releases from Nuclear Facilities. Report of Working Group 7 Tritium Accidents of EMRAS II Topical Heading Approaches for Assessing Emergency Situations. Environmental Modelling for Radiation Safety (Emras II) Programme

    International Nuclear Information System (INIS)

    Environmental assessment models are used for evaluating the radiological impact of actual and potential releases of radionuclides to the environment. They are essential tools for use in the regulatory control of routine discharges to the environment and also in planning measures to be taken in the event of accidental releases. They are also used for predicting the impact of releases which may occur far into the future, for example, from underground radioactive waste repositories. It is important to verify, to the extent possible, the reliability of the predictions of such models by a comparison with measured values in the environment or with predictions of other models. The IAEA has been organizing programmes of international model testing since the 1980s. These programmes have contributed to a general improvement in models, in the transfer of data and in the capabilities of modellers in Member States. IAEA publications on this subject over the past three decades demonstrate the comprehensive nature of the programmes and record the associated advances which have been made. From 2009 to 2011, the IAEA organized a programme entitled Environmental Modelling for RAdiation Safety (EMRAS II), which concentrated on the improvement of environmental transfer models and the development of reference approaches to estimate the radiological impacts on humans, as well as on flora and fauna, arising from radionuclides in the environment. Different aspects were addressed by nine working groups covering three themes: reference approaches for human dose assessment, reference approaches for biota dose assessment and approaches for assessing emergency situations. This publication describes the work of the Tritium Accidents Working Group

  12. Group representations

    CERN Document Server

    Karpilovsky, G

    1994-01-01

    This third volume can be roughly divided into two parts. The first part is devoted to the investigation of various properties of projective characters. Special attention is drawn to spin representations and their character tables and to various correspondences for projective characters. Among other topics, projective Schur index and projective representations of abelian groups are covered. The last topic is investigated by introducing a symplectic geometry on finite abelian groups. The second part is devoted to Clifford theory for graded algebras and its application to the corresponding theory

  13. Group Anonymity

    CERN Document Server

    Chertov, Oleg; 10.1007/978-3-642-14058-7_61

    2010-01-01

    In recent years the amount of digital data in the world has risen immensely. But, the more information exists, the greater is the possibility of its unwanted disclosure. Thus, the data privacy protection has become a pressing problem of the present time. The task of individual privacy-preserving is being thoroughly studied nowadays. At the same time, the problem of statistical disclosure control for collective (or group) data is still open. In this paper we propose an effective and relatively simple (wavelet-based) way to provide group anonymity in collective data. We also provide a real-life example to illustrate the method.

  14. Tectaria group

    NARCIS (Netherlands)

    Holttum, R.E.

    1991-01-01

    Polypodiaceae subfam. Dryopteridoideae section A, auct.: C. Chr. in Verdoorn, Man. Pteridol. (1938) 543, p.p. Aspidiaceae tribe Aspidieae auct.: Ching, Sunyatsenia 5 (1940) 250, excl. Lomariopsis and related genera. — Aspidiaceae, group of Ctenitis Copel., Gen. Fil. (1947) 153. Aspidiaceae auct.: Pi

  15. Group Learning.

    Science.gov (United States)

    Black, Susan

    1992-01-01

    Research suggests that cooperative learning works best when students are first taught group-processing skills, such as leadership, decision making, communication, trust building, and conflict management. Inadequate teacher training and boring assignments can torpedo cooperative learning efforts. Administrators should reassure teachers with…

  16. Development and verification of a high performance multi-group SP3 transport capability in the ARTEMIS core simulator

    International Nuclear Information System (INIS)

    For satisfaction of future global customer needs, dedicated efforts are being coordinated internationally and pursued continuously at AREVA NP. The currently ongoing CONVERGENCE project is committed to the development of the ARCADIAR next generation core simulation software package. ARCADIAR will be put to global use by all AREVA NP business regions, for the entire spectrum of core design processes, licensing computations and safety studies. As part of the currently ongoing trend towards more sophisticated neutronics methodologies, an SP3 nodal transport concept has been developed for ARTEMIS which is the steady-state and transient core simulation part of ARCADIAR. For enabling a high computational performance, the SPN calculations are accelerated by applying multi-level coarse mesh re-balancing. In the current implementation, SP3 is about 1.4 times as expensive computationally as SP1 (diffusion). The developed SP3 solution concept is foreseen as the future computational workhorse for many-group 3D pin-by-pin full core computations by ARCADIAR. With the entire numerical workload being highly parallelizable through domain decomposition techniques, associated CPU-time requirements that adhere to the efficiency needs in the nuclear industry can be expected to become feasible in the near future. The accuracy enhancement obtainable by using SP3 instead of SP1 has been verified by a detailed comparison of ARTEMIS 16-group pin-by-pin SPN results with KAERI's DeCart reference results for the 2D pin-by-pin Purdue UO2/MOX benchmark. This article presents the accuracy enhancement verification and quantifies the achieved ARTEMIS-SP3 computational performance for a number of 2D and 3D multi-group and multi-box (up to pin-by-pin) core computations. (authors)

  17. One-pot facile synthesis of highly photoluminescent graphene quantum dots with oxygen-rich groups%一步法合成富氧基团石墨烯量子点及光致发光特性

    Institute of Scientific and Technical Information of China (English)

    代云茜; 孙贻白; 龙欢; 柴蕴玲; 孙岳明

    2014-01-01

    To achieve a new type of carbon-based quantum dots with unique photoluminescence PL a simple approach for fabrication of graphene quantum dots GQDs with oxygen-rich groups was developed via the hydrothermal reaction by using graphene oxides GOs as a precursor. Transmission electron microscope TEM and atomic force microscope AFM characterizations confirmed that the sizes and heights of GQDs were 5.02 ±0.92 nm and 0.6 nm respectively.A strong PL emission exhibited unique excitation wavelength dependent features.Also the carbene-like free zigzag edge sites were proposed to be the origin of the strong PL emission.The GQDs were demonstrated to be a superior probe for Fe3+ detection in aqueous solution with a high sensitivity and feasibility due to the special coordinate interaction between Fe3+and the phenolic hydroxyl group at GQDs.%为获得独特的光致发光特性的碳基量子点,以氧化石墨烯( GOs )为前驱物,采用水热反应合成了一类富氧官能团修饰的石墨烯量子点(GQDs).TEM和AFM表征GQDs平均粒径为(5.02±0.92) nm,厚度为0.6 nm.GQDs呈现特有的光致发光峰位随激发波长移动的特性,其光致发光机理来源于量子点边缘的类卡宾zigzag活性位.由于Fe3+与GQDs表面羟基的配位作用使GQDs呈现出对Fe3+离子检测的高灵敏度和快速响应,有望成为高效检测Fe3+离子的新型荧光探针.

  18. Fifteenth LAMPF users group meeting

    International Nuclear Information System (INIS)

    The Fifteenth LAMPF Users Group Meeting was held November 2-3, 1981 at the Clinton P. Anderson Meson Physical Facility. The program of papers scheduled to be presented was amended to include a Report from Washington by Clarence R. Richardson, US Department of Energy. The general meeting ended with a round-table working group discussion concerning the Planning for a Kaon Factory. Individual items from the meeting were prepared separately for the data base

  19. Fifteenth LAMPF users group meeting

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, D.R.F. (comp.)

    1982-03-01

    The Fifteenth LAMPF Users Group Meeting was held November 2-3, 1981 at the Clinton P. Anderson Meson Physical Facility. The program of papers scheduled to be presented was amended to include a Report from Washington by Clarence R. Richardson, US Department of Energy. The general meeting ended with a round-table working group discussion concerning the Planning for a Kaon Factory. Individual items from the meeting were prepared separately for the data base.

  20. Group play

    DEFF Research Database (Denmark)

    Tychsen, Anders; Hitchens, Michael; Brolund, Thea;

    2008-01-01

    Role-playing games (RPGs) are a well-known game form, existing in a number of formats, including tabletop, live action, and various digital forms. Despite their popularity, empirical studies of these games are relatively rare. In particular there have been few examinations of the effects of the...... various formats used by RPGs on the gaming experience. This article presents the results of an empirical study, examining how multi-player tabletop RPGs are affected as they are ported to the digital medium. Issues examined include the use of disposition assessments to predict play experience, the effect...... of group dynamics, the influence of the fictional game characters and the comparative play experience between the two formats. The results indicate that group dynamics and the relationship between the players and their digital characters, are integral to the quality of the gaming experience in...

  1. Group therapy

    International Nuclear Information System (INIS)

    Full text: In his review 'Genesis of Unified Gauge Theories' at the symposium in Honour of Abdus Salam (June, page 23), Tom Kibble of Imperial College, London, looked back to the physics events around Salam from 1959-67. He described how, in the early 1960s, people were pushing to enlarge the symmetry of strong interactions beyond the SU(2) of isospin and incorporate the additional strangeness quantum number. Kibble wrote - 'Salam had students working on every conceivable symmetry group. One of these was Yuval Ne'eman, who had the good fortune and/or prescience to work on SU(3). From that work, and of course from the independent work of Murray Gell- Mann, stemmed the Eightfold Way, with its triumphant vindication in the discovery of the omega-minus in 1964.' Yuval Ne'eman writes - 'I was the Defence Attaché at the Israeli Embassy in London and was admitted by Salam as a part-time graduate student when I arrived in 1958. I started research after resigning from the Embassy in May 1960. Salam suggested a problem: provide vector mesons with mass - the problem which was eventually solved by Higgs, Guralnik, Kibble,.... (as described by Kibble in his article). I explained to Salam that I had become interested in symmetry. Nobody at Imperial College at the time, other than Salam himself, was doing anything in groups, and attention further afield was focused on the rotation - SO(N) - groups. Reacting to my own half-baked schemes, Salam told me to forget about the rotation groups he taught us, and study group theory in depth, directing me to Eugene Dynkin's classification of Lie subalgebras, about which he had heard from Morton Hamermesh. I found Dynkin incomprehensible without first learning about Lie algebras from Henri Cartan's thesis, which luckily had been reproduced by Dynkin in his 1946 thesis, using his diagram method. From a copy of a translation of Dynkin's thesis which I found in the British Museum Library, I

  2. COMMUNICATIONS GROUP

    CERN Multimedia

    L. Taylor

    2011-01-01

    The CMS Communications Group, established at the start of 2010, has been busy in all three areas of its responsibility: (1) Communications Infrastructure, (2) Information Systems, and (3) Outreach and Education. Communications Infrastructure There are now 55 CMS Centres worldwide that are well used by physicists working on remote CMS shifts, Computing operations, data quality monitoring, data analysis and outreach. The CMS Centre@CERN in Meyrin, is the centre of the CMS offline and computing operations, hosting dedicated analysis efforts such as during the CMS Heavy Ion lead-lead running. With a majority of CMS sub-detectors now operating in a “shifterless” mode, many monitoring operations are now routinely performed from there, rather than in the main Control Room at P5. The CMS Communications Group, CERN IT and the EVO team are providing excellent videoconferencing support for the rapidly-increasing number of CMS meetings. In parallel, CERN IT and ...

  3. Armament Technology Facility (ATF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Armament Technology Facility is a 52,000 square foot, secure and environmentally-safe, integrated small arms and cannon caliber design and evaluation facility....

  4. Financing Professional Sports Facilities

    OpenAIRE

    Baade, Robert A.; Victor A. Matheson

    2011-01-01

    This paper examines public financing of professional sports facilities with a focus on both early and recent developments in taxpayer subsidization of spectator sports. The paper explores both the magnitude and the sources of public funding for professional sports facilities.

  5. Explosive Components Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The 98,000 square foot Explosive Components Facility (ECF) is a state-of-the-art facility that provides a full-range of chemical, material, and performance analysis...

  6. The Educational Facilities Charrette

    Science.gov (United States)

    Chase, William W.

    1970-01-01

    The deputy director for the Division of Facilities Development of the U.S. Office of Education discusses a technique for studying and resolving educational facilities development problems within the context of total community planning needs." (Author/AA)

  7. Ouellette Thermal Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Thermal Test Facility is a joint Army/Navy state-of-the-art facility (8,100 ft2) that was designed to: Evaluate and characterize the effect of flame and thermal...

  8. Health Facility General Information

    Data.gov (United States)

    U.S. Department of Health & Human Services — This dataset contains the locations of Article 28, Article 36 and Article 40 health care facilities and programs from the Health Facilities Information System...

  9. Projectile Demilitarization Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — The Projectile Wash Out Facility is US Army Ammunition Peculiar Equipment (APE 1300). It is a pilot scale wash out facility that uses high pressure water and steam...

  10. Dialysis Facility Compare

    Data.gov (United States)

    U.S. Department of Health & Human Services — Dialysis Facility Compare helps you find detailed information about Medicare-certified dialysis facilities. You can compare the services and the quality of care...

  11. Facility Response Plan (FRP)

    Data.gov (United States)

    U.S. Environmental Protection Agency — A Facility Response Plan (FRP) demonstrates a facility's preparedness to respond to a worst case oil discharge. Under the Clean Water Act, as amended by the Oil...

  12. Energetics Conditioning Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Energetics Conditioning Facility is used for long term and short term aging studies of energetic materials. The facility has 10 conditioning chambers of which 2...

  13. Wastewater Treatment Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Individual permits for municipal, industrial, and semi-public wastewater treatment facilities in Iowa for the National Pollutant Discharge Elimination System...

  14. Lego Group

    DEFF Research Database (Denmark)

    Møller Larsen, Marcus; Pedersen, Torben; Slepniov, Dmitrij

    2010-01-01

    The last years’ rather adventurous journey from 2004 to 2009 had taught the fifth-largest toy-maker in the world - the LEGO Group - the importance of managing the global supply chain effectively. In order to survive the largest internal financial crisis in its roughly 70 years of existence, the...... phase out the entire sourcing collaboration with Flextronics. This sudden change in its sourcing strategy posed LEGO management with a number of caveats. Despite the bright forecasts, the collaboration did not fulfill the initial expectations, and the company needed to understand why this had happened...

  15. COMMUNICATIONS GROUP

    CERN Multimedia

    L. Taylor

    2010-01-01

    The CMS Communications Group, established at the start of 2010, has been strengthening the activities in all three areas of its responsibility: (1) Communications Infrastructure, (2) Information Systems, and (3) Outreach and Education. Communications Infrastructure The Communications Group has invested a lot of effort to support the operations needs of CMS. Hence, the CMS Centres where physicists work on remote CMS shifts, Data Quality Monitoring, and Data Analysis are running very smoothly. There are now 55 CMS Centres worldwide, up from just 16 at the start of CMS data-taking. The latest to join are Imperial College London, the University of Iowa, and the Università di Napoli. The CMS Centre@CERN in Meyrin, which is now full repaired after the major flooding at the beginning of the year, has been at the centre of CMS offline and computing operations, most recently hosting a large fraction of the CMS Heavy Ion community during the lead-lead run. A number of sub-detector shifts can now take pla...

  16. Eighteenth LAMPF users group meeting: proceedings

    International Nuclear Information System (INIS)

    The Eighteenth Annual LAMPF Users Group Meeting was held October 29-30, 1984, at the Clinton P. Anderson Meson Physics Facility. The program included a number of invited talks on various aspects of nuclear and particle physics as well as status reports on LAMPF and discussions of upgrade options. The LAMPF working groups met and discussed plans for the secondary beam lines, experimental programs, and computing facilities

  17. Eighteenth LAMPF users group meeting: proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Bradbury, J.N. (comp.)

    1985-03-01

    The Eighteenth Annual LAMPF Users Group Meeting was held October 29-30, 1984, at the Clinton P. Anderson Meson Physics Facility. The program included a number of invited talks on various aspects of nuclear and particle physics as well as status reports on LAMPF and discussions of upgrade options. The LAMPF working groups met and discussed plans for the secondary beam lines, experimental programs, and computing facilities.

  18. Areva revenue growth in the first quarter of 2010: 8.4% like-for-like, i.e. 1.936 billion euros

    International Nuclear Information System (INIS)

    The group's first quarter 2010 consolidated revenue rose 6.5% to 1.936 billion euros (+8.4% LFL) compared with the first quarter of 2009. Growth was driven by the Reactors and Services Business Group (+18.0% LFL). Revenue from exports was up 16.6% to 1.089 billion euros, representing 56.2% of total revenue. Foreign exchange had a negative impact of 26 million euros. Changes in consolidation scope were negligible during the period. The group's backlog of 43.6 billion euros at March 31, 2010 was stable in relation to December 31, 2009. Growth in the backlog of the Reactors and Services Business Group helped offset the drawdown of the backlog in the Back End Business Group as contracts were completed. For the full year of 2010, the group confirms its outlook for significant backlog and revenue growth, rising operating income, and a strong increase in net income attributable to owners of the parent. Mining/Front End Business Group: The Mining/Front End BG reported first quarter 2010 revenue of 674 million euros, which was stable on a reported basis and up 3.5% LFL1. Foreign exchange had a negative impact of 16 million euros. - In Mining, quarterly revenue was driven by volume growth due to a favorable delivery schedule. - In Enrichment and Fuel, volumes were down compared with the first quarter of 2009, particularly due to time-lag in customer deliveries. Reactors and Services Business Group: Revenue for the Reactors and Services BG was up 16.4% in the first quarter of 2010 (up 18.0% LFL1), to 775 million euros. Foreign exchange had a negative impact of 10 million euros. - The New Builds Business reported strong growth due to significant progress on major reactor construction projects, particularly Taishan in China. - Installed Base Business was also up due to buoyant engineering operations, particularly in Germany, and to the more favorable seasonality of unit outage campaigns than in the first quarter of 2009. Back End Business Group: First quarter 2010 revenue for

  19. Cardiovascular group

    Science.gov (United States)

    Blomqvist, Gunnar

    1989-01-01

    As a starting point, the group defined a primary goal of maintaining in flight a level of systemic oxygen transport capacity comparable to each individual's preflight upright baseline. The goal of maintaining capacity at preflight levels would seem to be a reasonable objective for several different reasons, including the maintenance of good health in general and the preservation of sufficient cardiovascular reserve capacity to meet operational demands. It is also important not to introduce confounding variables in whatever other physiological studies are being performed. A change in the level of fitness is likely to be a significant confounding variable in the study of many organ systems. The principal component of the in-flight cardiovascular exercise program should be large-muscle activity such as treadmill exercise. It is desirable that at least one session per week be monitored to assure maintenance of proper functional levels and to provide guidance for any adjustments of the exercise prescription. Appropriate measurements include evaluation of the heart-rate/workload or the heart-rate/oxygen-uptake relationship. Respiratory gas analysis is helpful by providing better opportunities to document relative workload levels from analysis of the interrelationships among VO2, VCO2, and ventilation. The committee felt that there is no clear evidence that any particular in-flight exercise regimen is protective against orthostatic hypotension during the early readaptation phase. Some group members suggested that maintenance of the lower body muscle mass and muscle tone may be helpful. There is also evidence that late in-flight interventions to reexpand blood volume to preflight levels are helpful in preventing or minimizing postflight orthostatic hypotension.

  20. Group evaporation

    Science.gov (United States)

    Shen, Hayley H.

    1991-01-01

    Liquid fuel combustion process is greatly affected by the rate of droplet evaporation. The heat and mass exchanges between gas and liquid couple the dynamics of both phases in all aspects: mass, momentum, and energy. Correct prediction of the evaporation rate is therefore a key issue in engineering design of liquid combustion devices. Current analytical tools for characterizing the behavior of these devices are based on results from a single isolated droplet. Numerous experimental studies have challenged the applicability of these results in a dense spray. To account for the droplets' interaction in a dense spray, a number of theories have been developed in the past decade. Herein, two tasks are examined. One was to study how to implement the existing theoretical results, and the other was to explore the possibility of experimental verifications. The current theoretical results of group evaporation are given for a monodispersed cluster subject to adiabatic conditions. The time evolution of the fluid mechanic and thermodynamic behavior in this cluster is derived. The results given are not in the form of a subscale model for CFD codes.