National Inventory of Radioactive Materials and Waste: Synthesis Report
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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. -
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. -
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. -
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. -
Chapter 15 Safe Decommissioning Of
ACTIVITIES REGULATED BY ASN SAFE DECOMMISSIONING OF BASIC NUCLEAR INSTALLATIONS (BNIs) 1 TECHNICAL AND LEGAL REQUIREMENTS APPLICABLE TO DECOMMISSIONING 421 1 I 1 Decommissioning strategies 1 I 2 Legal requirements 1 I 3 The financing of decommissioning and radioactive waste management 1 I 3 I 1 Reminder of regulatory provisions 1 I 3 I 2 Review of the reports forwarded by the licensees 1 I 4 Decommissioning risks 1 I 5 Complete clean-out 2 SITUATION OF NUCLEAR INSTALLATIONS UNDERGOING DECOMMISSIONING IN 2011 426 2 I 1 EDF nuclear power plants (NPPs) 2 I 1 I 1 The Brennilis NPP 2 I 1 I 2 Natural Uranium Graphite Gas Reactors (UNGG) 2 I 1 I 3 CHOOZ A reactor (Ardennes NPP) 2 I 1 I 4 SUPERPHÉNIX reactor 2 I 2 CEA installations 2 I 2 I 1 Fontenay-aux-Roses centre 2 I 2 I 2 The Grenoble centre 2 I 2 I 3 The Cadarache centre installations undergoing decommissioning 2 I 2 I 4 The Saclay centre installations undergoing decommissioning 2 I 3 AREVA installations 2 I 3 I 1 UP2 400 spent fuel reprocessing plant and associated facilities 2 I 3 I 2 SICN plant in Veurey-Voroize 2 I 4 Others installations 2 I 4 I 1 The Strasbourg University reactor 2 I 4 I 2 The Electromagnetic radiation laboratory 3 OUTLOOK 437 APPENDIX 1 LIST OF BASIC NUCLEAR INSTALLATIONS DELICENSED AS AT 31.12.2011 437 APPENDIX 2 LIST OF BASIC NUCLEAR INSTALLATIONS UNDERGOING DECOMMISSIONING AS AT 31.12.2011 439 CHAPTER 15 419 CHAPTER 15 SAFE DECOMMISSIONING OF BASIC NUCLEAR INSTALLATIONS (BNIs) The term “decommissioning” generally covers all the technical and administrative activities performed after shutdown of a nuclear installation in order to achieve a predetermined final status. -
Rapport Transparence Et Sécurité Nucléaire Du CEA De Cadarache
Rapport Transparence et Sécurité Nucléaire 2020 du CEA de Cadarache SommaireSommaire 4 Présentation du Centre CEA de Cadarache > > 6 Dispositions prises en matière de sûreté > 26 Dispositions prises en matière de radioprotection Événements significatifs en matière de sûreté nucléaire, > 34 de radioprotection et de transport Résultats des mesures des rejets > 40 et leur impact sur l’environnement > 54 Déchets radioactifs entreposés dans les INB du Centre > 58 Conclusion générale > 60 Annexes > 76 Glossaire > 83 Recommandations du CSE du CEA Cadarache Le rapport public du centre CEA Cadarache pour l’année 2020 que vous êtes en train de consulter, est un bilan annuel portant sur la sûreté nucléaire, la radioprotection, les incidents ou accidents, la nature et la composition des rejets radioactifs et chimiques issus de nos activités de recherche et les déchets radioactifs qui sont temporairement entreposés sur notre site*. Pour une plus large diffusion vers le public, il est transmis à la Commission Locale d’Information et au Haut Comité pour la Transparence et l’Information sur la Sécurité Nucléaire. * Il a été rédigé au titre des articles L. 125-15 et L. 125-16 du Code de l’environnement. 2 | Centre CEA de Cadarache - Rapport transparence et sécurité nucléaire 2020 Éditorial Le Centre CEA de Cadarache se présente comme un très grand centre de recherche en Europe sur les énergies décarbonées. Ses activités se sont beaucoup diversifiées depuis sa construction en 1959. Entièrement dédié aux recherches sur l’électronucléaire à ses débuts, le site s’est spécialisé depuis dans de nombreuses autres activités, comme le nucléaire de fusion, les bioénergies et le solaire. -
Acronyms and Abbreviations
RA2011 Annexe B_bat 27/07/12 16:29 Page483 APPENDIX B ACRONYMS AND ABBREVIATIONS ACC hulls and end-pieces compaction facility AIEA IAEA International Atomic Energy Agency (AREVA NC – La Hague) ALARA As Low As Reasonably Achievable (radiation ACN Aarhus Convention and Nuclear (ANCCLI protection principle also called “optimisation initiative) principle”) ACO Orsay collider ring (LURE – CNRS – Orsay) ALLEGRO experimental low-power, non-electricity generating, gas-cooled fast reactor (GFR) ACR resins conditioning facility (AREVA NC – project La Hague) ALQA Lorraine Air Quality Association ACRO Association for the Control of Radioactivity in the West ALS Saclay linear accelerator (CEA) AD2 technological waste packaging facility AMDE French equivalent of FMEA (Failure Modes (AREVA NC – La Hague) and Effects Analysis) ADEME French Environment and Energy AMI irradiated material facility (EDF – Chinon) Management Agency ANCCLI National Association of Local Information ADF Assembly of départements of France Commissions and Committees (since 2009) ADN French acronym for DeoxyriboNucleic Acid ANCLI National Association of Local Information (DNA) Committees (until 2009) ADNR Agreement on the transport of dangerous ANDRA French National Agency for Radioactive substances on the Rhine Waste Management ADR European Agreement concerning the ANR French Reasearch Agency International Carriage of Dangerous Goods ANRE Agency for Natural Resources and Energy by Road (Japan) ADS Accelerator Driven System (nuclear reactor ANSES National Agency responsible for -
The Safety of the Nuclear Fuel Cycle
Cov-Safety Nuclear FuelCyc 3588 10/10/05 16:04 Page 1 Nuclear Safety The Safety of the Nuclear Fuel Cycle NUCLEAR•ENERGY•AGENCY Nuclear Safety The Safety of the Nuclear Fuel Cycle Third edition © OECD 2005 NEA No. 3588 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT The OECD is a unique forum where the governments of 30 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies. The OECD member countries are: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Korea, Luxembourg, Mexico, the Netherlands, New Zealand, Norway, Poland, Portugal, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The Commission of the European Communities takes part in the work of the OECD. OECD Publishing disseminates widely the results of the Organisation’s statistics gathering and research on economic, social and environmental issues, as well as the conventions, guidelines and standards agreed by its members. * * * This work is published on the responsibility of the Secretary-General of the OECD. The opinions expressed and arguments employed herein do not necessarily reflect the official views of the Organisation or of the governments of its member countries. -
3Rd French National Report on Implementation of the Obligations of The
3rd French national report on implementation of the obligations of the Convention on nuclear safety - Issued for the 2005 Peer review meeting - English version – Original report in French July 2004 Content Table of contents INTRODUCTION ......................................................................................................................................5 1. General introduction.............................................................................................................................5 2. Main changes with respect to the 2nd French report.............................................................................7 2.1 Changes in nuclear safety supervision in 2002 .............................................................................7 2.2 Changes in the content of the third report with respect to the second report.................................7 2.3 Topical safety issues in France in 2004.........................................................................................7 3. Nuclear national policy and practices.................................................................................................12 3.1 General policy..............................................................................................................................12 3.2 Nuclear power plants...................................................................................................................12 3.3 Nuclear research reactors ...........................................................................................................13 -
WNTI and NUTRANSTOR Workshop Collaboration
WNTI and NUTRANSTOR Workshop collaboration: International spent fuel shipment experience: Information sharing of lessons learned and best practices. Monday 19th July 2021 Virtual Meeting - WebEx Agenda Introduction Mitch Arvidson The Council of State Governments Midwestern Office Presentation - Some Aspects on The Swedish Back-End System Anna Wikmark, SKB (Sweden) Presentation – Nuclear Material Transportation Global Acceptance Anne Presta (France) & Mike Valenzano (USA) Orano NPS Q&A Session All Panelists Workshop Presenters and Hosts • W. Scott Edwards, WNTI, London, England • Catherine Shelton, NUTRANSTOR, St. Croix, USVI • Michael Snee, Ohio Dept. of Health, Columbus, Ohio • Mitch Arvidson, The Council of State Governments Midwestern Office • Anna Wikmark, SKB, Stockholm, Sweden • Mike Valenzano, TN Americas, Columbia, Maryland • Anne Presta, Orano NPS, Paris, France What is the World Nuclear Transport Institute? What is it for? • Founded in 1998 in London, England, by 3 Founder Members ORANO (ex AREVA), Nuclear Transport Solutions (ex INS), FEPC (Japan) • 49 Members from a wide range of industry sectors: radioisotopes producers, major utilities, fuel producers, transport companies, package designers, package producers, mining companies, insurers... Observer Status at Major International Organizations World Nuclear Transport Institute • The voice of the radioactive materials transport industry • Industry Representation at International Organisations • Factual information – Fact Sheets, website www.wnti.co.uk • Good Practice Guides -
Regional Overview of Nuclear Safety and Radiation Protection
ASN ACTIONS REGIONAL OVERVIEW OF NUCLEAR SAFETY AND RADIATION PROTECTION 1 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE AQUITAINE, POITOU-CHARENTES AND MIDI-PYRÉNÉES REGIONS REGULATED BY THE BORDEAUX DIVISION 209 2 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE BASSE AND HAUTE NORMANDIE REGIONS REGULATED BY THE CAEN DIVISION 211 3 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE PICARDIE AND CHAMPAGNE-ARDENNE REGIONS REGULATED BY THE CHÂLONS-EN-CHAMPAGNE DIVISION 217 4 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE BOURGOGNE AND FRANCHE-COMTÉ REGIONS REGULATED BY THE DIJON DIVISION 221 5 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE NORD-PAS-DE-CALAIS REGION REGULATED BY THE LILLE DIVISION 223 6 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE RHÔNE-ALPES AND AUVERGNE REGIONS REGULATED BY THE LYON DIVISION 227 7 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE PROVENCE-ALPES-CÔTE-D’AZUR, LANGUEDOC-ROUSSILLON AND CORSE REGIONS REGULATED BY THE MARSEILLE DIVISION 233 8 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE PAYS DE LOIRE AND BRETAGNE REGIONS REGULATED BY THE NANTES DIVISION 239 9 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE CENTRE, LIMOUSIN AND ILE-DE-FRANCE REGIONS REGULATED BY THE ORLÉANS DIVISION 243 10 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION ER IN THE ILE-DE-FRANCE REGION AND OVERSEAS FRANCE DÉPARTEMENTS CHAPT 8 AND TERRITORIAL COMMUNITIES REGULATED BY THE PARIS DIVISION 247 11 THE STATE OF NUCLEAR SAFETY AND RADIATION PROTECTION IN THE ALSACE AND LORRAINE REGIONS REGULATED BY THE STRASBOURG DIVISION 249 205 206 CHAPTER 8 REGIONAL OVERVIEW OF NUCLEAR SAFETY AND RADIATION PROTECTION ASN has 11 regional divisions through which it carries out its regulatory responsibilities nationwide and in the Overseas France and Territorial Communities. -
Radioactive Waste Management and Decommissioning in France
Andra – ASN – CEA - IRSN March 2013 RADIOACTIVE WASTE MANAGEMENT AND DECOMMISSIONING IN FRANCE 1. NATIONAL FRAMEWORK FOR MANAGEMENT AND REGULATION OF RADIOACTIVE WASTE AND DECOMMISSIONING 1.1 National framework 1.1.1 Overview of national policy The French nuclear activities produce solid, liquid or gaseous waste, some of which is radioactive. The national policy on radioactive waste is that reliable, transparent and stringent management of this waste must ensure the protection of individuals, preservation of the environment and limitation of undue burdens imposed on future generations. After their operating period, nuclear installations need to be decommissioned and dismantled in due time. Installations (NPPs, nuclear plants, research installations, etc.) have to remain at all times in a satisfactory safety condition, even when they have ceased to be operated, taking into account the specific nature of the dismantling operations. Dismantling operations produce radioactive waste which has to be managed with the same principle as the above-mentioned one. In this respect two important acts were promulgated in 2006: - the “Transparency and Security in the nuclear field” Act (June 13th 2006), sometimes called “TSN Act” and available in English at http://www.french- nuclear-safety.fr/index.php/English-version/Asn-s-publications - the Planning Act on the sustainable management of radioactive materials and waste (June 28th 2006). This Act is available in English at http://www.andra.fr/index.php?id=edition_1_5_2&recherche_thematique=all&gl obal_id_item=387.