Acronyms and Abbreviations
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Framatome in Latin America Strong History and Partnerships
SEN – Semana da Engenharia Nuclear UFRJ 17/10/2019 Framatome– 2019 1 © Framatome All right reserved Framatome– 2019 2 © Framatome All right reserved Framatome at a glance 60 years of experience, alongside our customers, in developing safe and competitive nuclear power worldwide Design Supply Manufacture Integrate Maintain Framatome– 2019 3 © Framatome All right reserved Framatome at a glance High-performing people and technologies for safe and competitive nuclear plants worldwide 92 14 000 250 3.3 NPPs PEOPLE REACTORS € BILLION As OEM Servicing … All over the world 2017 turnover Framatome– 2019 4 © Framatome All right reserved Our values More than principles, our values guide our actions and describe how we work each other, with our customers and business partners Safety Future Performance Integrity Passion Framatome– 2019 5 © Framatome All right reserved Framatome worldwide presence Germany 4 sites France 17 sites USA 7 sites China 8 sites 58 locations Argentina Japan Sweden 21 Belgium Republic of South Switzerland countries Others Brazil Africa The Netherlands locations Bulgaria Russia Ukraine Canada Slovakia United Arab Emirates Framatome– 2019 Czech Republic Slovenia United Kingdom 6 Finland South Korea © Framatome Hungary Spain All right reserved Our customers Asia CNNC Nawah CGN Tepco North & South America Doosan Hitachi Bruce Power Exelon OPG KHNP Dominion Corporation PSEG Africa MHI Duke Energy Luminant TVA Entergy NA-SA Eskom ETN NextEra Europe ANAV EDF Energy Skoda CNAT Engie TVO CEA EPZ Vattenfall CEZ Iberdrola DCNS KKG EnBW NEK Framatome– 2019 7 EDF RWE © Framatome All right reserved Framatome shareholder structure 19,5% 75,5% 5% • Stock-listed company • Majority shareholder: French state 100% Framatome Inc. -
Overview on RRSF Reprocessing, from Spent Fuel Transportation to Vitrified Residues Storage
TH RERTR 2015 – 36 INTERNATIONAL MEETING ON REDUCED ENRICHMENT FOR RESEARCH AND TEST REACTORS OCTOBER 11‐14, 2015 THE PLAZA HOTEL SEOUL, SOUTH KOREA Overview on RRSF reprocessing, from spent fuel transportation to vitrified residues storage J.F. VALERY, X. DOMINGO, P. LANDAU AREVA NC, 1 place Jean Millier, 92084 Paris La Défense Cedex – France M. LAUNEY, P. DESCHAMPS, C. PECHARD AREVA NC La Hague, 50440 Beaumont-Hague – France V. LALOY, M. KALIFA AREVA TN, 1 Rue des Hérons, 78180 Montigny-le-Bretonneux – France ABSTRACT AREVA has long experience in transportation and industrial-scale reprocessing of RR UAl spent fuel. Over 23 tons of RR UAl type fuels have been reprocessed at AREVA’s facilities in France, both in Marcoule and La Hague plants. Furthermore, More than 100 RR fuels transportations per year are carried out by AREVA (for fresh and spent fuels). Benefiting from its past experience, AREVA proposes to detail in pictures all the stages of a (Research Reactor Spent Fuel) RRSF reprocessing from its evacuation from reactor site to its corresponding post- reprocessing vitrified waste production and management. In order to comply with its customers growing needs in terms of RRSF management, AREVA is also developing new RRSF reprocessing capacities in the La Hague UP2-800 facility based on the same process principles. This new TCP facility is planned to reprocess several types of RRSF including both UAl and U3Si2 RRSF. 1. Introduction Reprocessing is one of the today-available options for managing back-end of Research Reactor fuel cycle. As described in figure 1 below, this solution offers to RR: - Non-proliferation: reducing 235U enrichment of RRSF from 20-93% to below 2%, - Final waste management optimization: standardizing final waste package and reducing volume and radio-toxicity, removing IAEA safeguards on final waste, - Sustainability of RRSF back-end management: long-lasting solution, re-use of valuable material for civilian purposes i.e. -
RIL AMT Workshop Summary
RIL 2021-03 NRC WORKSHOP ON ADVANCED MANUFACTURING TECHNOLOGIES FOR NUCLEAR APPLICATIONS Part I – Workshop Summary Date Published: Draft April 2021 Prepared by: A. Schneider M. Hiser M. Audrain A. Hull Research Information Letter Office of Nuclear Regulatory Research Disclaimer This report was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party’s use, or the results of such use, of any information, apparatus, product, or process disclosed in this publication, or represents that its use by such third party complies with applicable law. This report does not contain or imply legally binding requirements. Nor does this report establish or modify any regulatory guidance or positions of the U.S. Nuclear Regulatory Commission and is not binding on the Commission. EXECUTIVE SUMMARY Advanced manufacturing technologies (AMTs) are defined by the U.S. Nuclear Regulatory Commission (NRC) as those techniques and material processing methods that have not been traditionally used or formally standardized/codified by the nuclear industry. In June 2020, the NRC released Revision 1 to the Agency Action Plan for AMTs (AMT AP) (Agencywide Documents Access and Management System Accession No. ML19333B980 (package)). The AMT AP is a strategic plan that responds to the rapid pace of developments in respective AMTs and industry implementation plans. The NRC’s AMT activities are driven by industry interest in implementing specific AMTs and ensuring that the NRC staff are prepared to review potential AMT applications efficiently and effectively. -
ITER Project Garching for the Fusion Community an Historic Milestone Was Achieved at the Eighth ITER Negotiations Meeting on February 18-19, 2003 in St
newsletternewsletter Vol 2003 / 2 April 5, 2003 EUROPEAN FUSION DEVELOPEMENT AGREEMENT News Issued by the EFDA Close Support Unit China and the US as New Partners in the ITER Project Garching For the fusion community an historic milestone was achieved at the Eighth ITER Negotiations Meeting on February 18-19, 2003 in St. Petersburg (Russian Federation), when delega- tions from the People’s Republic of China and the United States of America joined those from Canada, the European Union, Japan and the Russian Federation in their efforts to reach agreement on the implementation of the ITER pro- ject. The Head of the Chinese Delegation indicated that Contents China, as the largest developing country in the world, has a great need to pursue alternative energy sources. China . Interview: believes that ITER can potentially lead to new forms of ener- Dr. Joseph V. Minervini gy and contribute to the peaceful and sustainable development page 2 of the world in the long-term. China expressed its strong wishes to be a valuable member of the ITER family, to make joint efforts with . Interview: other partners to the successful exploitation of fusion energy. Prof. Huo Yuping At their St. Petersburg meeting the ITER Negotiators approved the Report on the page 3 Joint Assessment of Specific Sites (JASS). The JASS Report provided as a main con- clusion and despite the differences between the candidate sites (Clarington in Canada, . ITER: Cadarache in France, Vandellos in Spain and Rokkasho-mura in Japan) that the JASS First Full Scale Primary assessment ascertained that all four sites are sound and fully capable to respond to all First Wall Panel ITER Site Requirements and Design Assumptions, as approved by the ITER Council in its January 2000 meeting. -
Olkiluoto 3: Framatome Teams All Set for Fuel Loading
PRESS RELEASE March 26, 2021 Olkiluoto 3: Framatome teams all set for fuel loading March 26, 2021 – The Olkiluoto 3 EPR reactor completes a decisive stage of its commissioning. The Finnish safety authority (STUK) has authorized the fuel load for the Olkiluoto 3 EPR reactor. Loading operations led by plant operator TVO, with the support from AREVA and Framatome, can begin. "Fuel loading is a major milestone for the project. Reaching this milestone illustrates the expertise and know-how of our teams," said Bernard Fontana, CEO of Framatome. "Framatome's teams are fully mobilized alongside AREVA and TVO to finalize and deliver the nuclear power plant while meeting the highest safety and security standards. I thank them for their engagement.” To carry out the loading operations, an integrated team made up of approximately 40 employees from TVO, AREVA and Framatome has been formed. It includes around 15 fuel handlers, employees specializing in the fuel handling operations, and four neutronics engineers in charge of monitoring the core during loading. A total of 241 fuel assemblies manufactured in Framatome's plants in Germany and in France will be loaded in the reactor vessel to constitute the first core. The Areva NP and Areva NP GmbH Olkiluoto 3 project teams, who will later join Framatome, are supported by over 110 Framatome employees permanently based on the site, and by Framatome engineering teams located in France and in Germany. Completion of the fuel loading will be followed by a new series of hot functional tests before the first criticality and commissioning for commercial operation. -
Nuclear France Abroad History, Status and Prospects of French Nuclear Activities in Foreign Countries
Mycle Schneider Consulting Independent Analysis on Energy and Nuclear Policy 45, allée des deux cèdres Tél: 01 69 83 23 79 91210 Draveil (Paris) Fax: 01 69 40 98 75 France e-mail: [email protected] Nuclear France Abroad History, Status and Prospects of French Nuclear Activities in Foreign Countries Mycle Schneider International Consultant on Energy and Nuclear Policy Paris, May 2009 This research was carried out with the support of The Centre for International Governance Innovation (CIGI) in Waterloo, Ontario, Canada (www.cigionline.org) V5 About the Author Mycle Schneider works as independent international energy nuclear policy consultant. Between 1983 and April 2003 Mycle Schneider was executive director of the energy information service WISE-Paris. Since 2000 he has been an advisor to the German Ministry for the Environment, Nature Conservation and Reactor Safety. Since 2004 he has also been in charge of the Environment and Energy Strategies Lecture of the International Master of Science for Project Management for Environmental and Energy Engineering at the French Ecole des Mines in Nantes, France. In 2007 he was appointed as a member of the International Panel on Fissile Materials (IPFM), based at Princeton University, USA (www.fissilematerials.org). In 2006-2007 Mycle Schneider was part of a consultants’ consortium that assessed nuclear decommissioning and waste management funding issues on behalf of the European Commission. In 2005 he was appointed as nuclear security specialist to advise the UK Committee on Radioactive Waste Management (CoRWM). Mycle Schneider has given evidence and held briefings at Parliaments in Australia, Belgium, France, Germany, Japan, South Korea, Switzerland, UK and at the European Parliament. -
Specials Steels and Superalloys for Nuclear Industry
Specials Steels and Superalloys for Nuclear Industry Enhancing your performance or almost 60 years Aubert & Duval has been a key partner for the development Aubert & Duval: Your partner F of forged and rolled products, especially those customized for the nuclear market. to energize your success With full vertical integration from melting, to remelting, hot converting and machining (rough machining through to near-net-shape parts), Aubert & Duval offers wide-ranging cutting edge capabilities for nuclear application. Equipment Process flow . MELTING Melting furnaces (EAF, AOD, LF) Melting up to 60 tons Vacuum Induction Melting (VIM) HPS NiSA up to 20 tons Remelting furnaces (ESR, VAR) up to 30 tons powder atomization (Gaz, VIM) . FORGING Open-die forging presses Remelting Powder atomization from 1,500 to 10,000 tons Closed-die forging presses from 4,500 to 65,000 tons . ROLLING MILL HPS 7-200 mm diameter bars High Performance Steels: Conversion . HEAT TREATMENT A range of alloyed steels with Solution and ageing furnaces tightly controlled characteristics HPS Ti NiSA AL PM Horizontal and vertical quenching offering optimum value for equipment customers. TESTING Forging Closed-die Hot Isostatic Immersion UT up to 13 tons and/or rolling Forging Forging Pressing (HIP) ©Valinox-Franck Dunouau (28,000 lbs) Automated contact UT up to 20 tons NiSA Aubert & Duval has also put in place over many decades dedicated skills to co-design re-engineered Nickel-base Superalloys: Nickel-based superalloys: materials metallurgical solutions with our clients. keeping high surface integrity while Sales of alloys and superalloys have progressively expanded across a broad spectrum of primary withstanding severe mechanical circuit contractors and their subcontractors. -
Press Kit Inauguration of the Conversion Orano Tricastin BP 16 26 701 Pierrelatte Plant 10 September 2018
Press kit Inauguration of the conversion Orano Tricastin BP 16 26 701 Pierrelatte plant 10 September 2018 Contacts Presse Nathalie Bonnefoy +33 (0)6 23 17 24 24 [email protected] Gilles Crest +33 (0)6 71 08 11 54 [email protected] www.orano.group Oranogroup EDITORIAL The plant we are opening today is a major industrial investment for Orano, for the French nuclear industry and for the industry of our country. ith the Georges Besse II enrichment plant on the same site, it is probably the largest industrial investment made in France in recent years. The Comurhex W II project was launched to give France an industrial facility offering cutting- edge safety, security, and environmental and industrial performance. A facility that gives us a global competitive advantage and guarantees an uninterrupted electricity supply for our markets. A tool integrating technological innovations in terms of safety, environment, and improvement of industrial performance: recycling of chemical reagents, reduction by 90% of water consumption, automated control-command system to improve the process control. It is an exceptional project that has required the best of our expertise from the teams of Orano Chemistry and Enrichment as well as Orano Projets, and throughout our group alongside our industrial partners. The project successfully completed at the same time as our group was reinventing itself to create a new flagship technology business to give nuclear materials all their value. While an important debate is taking place on France's multi-year energy program, the investment we have made in the Tricastin site and its plants shows the confidence we have in the future of nuclear energy. -
Industrialization of a Small Sludge Retrieval System
WM'05 Conference, February 27-March 3, 2005, Tucson, AZ WM - 5220 THE REPROCESSING PLANT OF THE FUTURE : A SINGLE EXTRACTION CYCLE P. Bretault, P. Houdin SGN, 1 rue des Hérons, Montigny-le-Bretonneux, 78 182 Saint Quentin-en-Yvelines, France JL. Emin COGEMA, 2 rue Paul Dautier, BP 4, 78141 Velizy-Villacoublay, Cedex, France P. Baron CEA Marcoule, BP 171, 30207 Bagnols-sur-Ceze, France ABSTRACT In France, COGEMA has been reprocessing spent nuclear fuel on an industrial scale for over 40 years, and has consistently worked to optimize facility design and operations. In COGEMA-La Hague’s UP3 reprocessing plant, to achieve the necessary decontamination needed to produce purified uranium and plutonium, five extraction cycles were implemented and used at start-up: first cycle for separation of fission products, uranium and plutonium, two uranium purification cycles and two plutonium purification cycle. By modifying processes at the design stage and making adjustments during operations, we saw that further decontamination of uranium could be achieved with only one cycle. Radiological specification of plutonium was also obtained at the end of the first plutonium purification cycle. These good performance levels were taken into account for the design of the UP2-800 plant where uranium is purified using a single cycle, and for the recent R4 facility which features only one plutonium purification cycle. Relevant information on extraction cycles in first-generation French reprocessing plants (UP1 and UP2-400) as well as design characteristics for the extraction cycles of reprocessing facilities currently operating at the COGEMA-La Hague plant is given. Experience shows that we can obtain adequate performance levels using only three cycles. -
The Jules Horowitz Reactor Core and Cooling System Design
The Jules Horowitz Reactor core and cooling system design M. Boyard*, JM. Cherel**, C. Pascal*, B. Guigon*** * AREVA-Technicatome, 1100 rue Jean René Guillibert Gautier de la Lauzière 13100 Aix en Provence, FRANCE ** AREVA-Framatome-ANP, 9-10 rue Juliette Récamier 69006 Lyon, FRANCE *** Commissariat à l’Energie Atomique, 13108 Saint-Paul-lez-Durance cedex, FRANCE ABSTRACT The CEA (Commissariat à l’Energie Atomique) is planning to build a new MTR called the Jules Horowitz Reactor (JHR). JHR at Cadarache will become by 2014 and for decades a major research infrastructure in Europe for supporting existing power plants operation and lifetime extension as well as future reactor developments [1]. AREVA (Technicatome and Framatome- ANP) and EDF are performing the design studies. The JHR will be a tank pool type reactor using light water as coolant and moderator. The reactor has been designed to provide a neutron flux strong enough to carry out irradiation relevant for generations 2, 3 and 4 power plants: flexibility and adaptability, high neutron flux, instrumented experiments, loops to reproduce environments representatives of the different power plant technologies . Updated safety requirements and LEU fuel elements have been taken into account in the design of this high flux reactor. This paper presents the guidelines for the design of the main items, the various options considered and the choices made at the end of the detailed studies phase regarding: − Core shape, − Fuel element and core pitch, − Reflector and core-reflector interface, − Normal and emergency cooling systems, − Reactivity control system. MAIN OBJECTIVES OF THE REACTOR The “Jules Horowitz Reactor” (JHR) will be a structuring infrastructure of the European research area. -
Operational and Decommissioning Experience with Fast Reactors
IAEA-TECDOC-1405 Operational and decommissioning experience with fast reactors Proceedings of a technical meeting held in Cadarache, France, 11–15 March 2002 August 2004 IAEA-TECDOC-1405 Operational and decommissioning experience with fast reactors Proceedings of a technical meeting held in Cadarache, France, 11–15 March 2002 August 2004 The originating Section of this publication in the IAEA was: Nuclear Power Technology Development Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria OPERATIONAL AND DECOMMISSIONING EXPERIENCE WITH FAST REACTORS IAEA, VIENNA, 2004 IAEA-TECDOC-1405 ISBN 92–0–107804–8 ISSN 1011–4289 © IAEA, 2004 Printed by the IAEA in Austria August 2004 FOREWORD The fast reactor, which can generate electricity and breed additional fissile material for future fuel stocks, is a resource that will be needed when economic uranium supplies for the advanced water cooled reactors or other thermal-spectrum options diminish. Further, the fast-fission fuel cycle in which material is recycled offers the flexibility needed to contribute decisively towards solving the problem of growing ‘spent’ fuel inventories by greatly reducing the volume of high level waste that must be disposed of in long term repositories. This is a waste management option that also should be retained for future generations. The fast reactor has been the subject of research and development programmes in a number of countries for more than 50 years. Now, despite early sharing and innovative worldwide research and development, ongoing work is confined to China, France, India, Japan, the Republic of Korea, and the Russian Federation. Information generated worldwide will be needed in the future. -
AVAILABLE REPROCESSING and RECYCLING SERVICES for RESEARCH REACTOR SPENT NUCLEAR FUEL the Following States Are Members of the International Atomic Energy Agency
IAEA Nuclear Energy Series IAEA Nuclear No. NW-T-1.11 No. IAEA Nuclear Energy Series Available Reprocessing and Recycling Services for Research Reactor Spent Nuclear Fuel Services for Research Reactor Spent Nuclear Reprocessing and Recycling Available No. NW-T-1.11 Basic Available Reprocessing Principles and Recycling Services for Research Reactor Objectives Spent Nuclear Fuel Guides Technical Reports @ IAEA NUCLEAR ENERGY SERIES PUBLICATIONS STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES Under the terms of Articles III.A and VIII.C of its Statute, the IAEA is authorized to foster the exchange of scientific and technical information on the peaceful uses of atomic energy. The publications in the IAEA Nuclear Energy Series provide information in the areas of nuclear power, nuclear fuel cycle, radioactive waste management and decommissioning, and on general issues that are relevant to all of the above mentioned areas. The structure of the IAEA Nuclear Energy Series comprises three levels: 1 — Basic Principles and Objectives; 2 — Guides; and 3 — Technical Reports. The Nuclear Energy Basic Principles publication describes the rationale and vision for the peaceful uses of nuclear energy. Nuclear Energy Series Objectives publications explain the expectations to be met in various areas at different stages of implementation. Nuclear Energy Series Guides provide high level guidance on how to achieve the objectives related to the various topics and areas involving the peaceful uses of nuclear energy. Nuclear Energy Series Technical Reports provide additional, more detailed information on activities related to the various areas dealt with in the IAEA Nuclear Energy Series. The IAEA Nuclear Energy Series publications are coded as follows: NG — general; NP — nuclear power; NF — nuclear fuel; NW — radioactive waste management and decommissioning.