DOCSLIB.ORG

Edf Group Presentation

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Edf Group Presentation EDF GROUP PRESENTATION Decommissioning & Waste Treatment Lokala säkerhetsnämnden 9/12/2016 AGENDA 1. EDF GROUP, THE WORLD’S LEADING ELECTRICITY COMPANY 2. OUR AMBITION IN THE NUCLEAR DECOMMISSIONING & WASTE TREATMENT MARKet EDF 2016 I P.2 EDF GROUP, THE WORLD’S LEADING ELECTRICITY COMPANY All electricity-related activities 38.5 MILLION CUSTOMERS — Generation — Transmission & Distribution 158,200 EMPLOYEES — Trading and Sales & Marketing — Energy services €75.0 BILLION SALES EDF ranks: €17.6 BILLION EBITDA among the top 100 largest companies in the world (Fortune Global 500 2014) €12.7 BILLION NET INVESTMENTS EDF is a leader in low-carbon generation: ELECTRICITY GENERATION 102 g/kWh, of which 87% 623.5 TWH carbon-free generation — World’s No. 1 nuclear operator — European No. 1 in generation from renewables — European No. 3 in energy services EDF 2016 I P.3 EDF GROUP IS THE WORLD’S LEADING NUCLEAR FLEET OWNER AND OPERATOR WITH 73 OPERATING UNITS . 72.9 GW installed capacity, 54% of the Group’s net generation capacity . 477.7 TWh generated, 77% of the Group’s output . 58 reactors operated in France, 15 in the UK 5 NEW NUCLEAR PROJECTS . 3 EPR under construction: - 1 in Flamanville (France) - 2 in Taishan (China) . 2 EPR in project phase EDF has a long track record of safe reliable nuclear generation and has a bright future ahead EDF 2016 I P.4 AGENDA 1. EDF GROUP, THE WORLD’S LEADING ELECTRICITY COMPANY 2. OUR AMBITION IN THE NUCLEAR DECOMMISSIONING & WASTE TREATMENT MARKET EDF 2016 I P.5 DECOMMISSIONNING AND WASTE MANAGEMENT ARE KEY TO EDF STRATEGY IN THE NUCLEAR INDUSTRY EDF, the efficient and responsible electricity company, the champion in low-carbon growth Energy Rene- Generating low-carbon electricity from Thermal Nuclear Grid Trading & wables nuclear power and renewables is a Supply top priority of the CAP 2030 strategy 77% of the Group’s power output Operating Decommissioning and As a responsible nuclear operator, New Build NPPs Waste Management (DP2D) demonstrate our full control along the entire life cycle, by efficiently • 3 EPRs under • 58 reactors in 9 NPPs under managing decommissioning projects decommissioning construction in France, 15 in in France and waste generated by our power France and the UK plants in operating or dismantlement China • 73 GW installed Waste treatment : Socodei, Cyclife phase. • Others in capacity project phase • 478 TWh Development of generated solutions for HLW … | 6 FAVORABLE MARKET OUTLOOK IN THE NUCLEAR DECOMMISSIONING AND WASTE TREATMENT Europe USA Japan In the USA In Europe Japan Dismantling market size Dismantling market size Waste treatment market size Dismantling market size x 4 x 2 x 3 x 2 . In the UK : 14 AGRs to be stopped by 2030 . In Germany : 7 PWRs and 2 BWRs to be stopped by 2022 . In Sweden : 1 PWRs and 3 BWRs to be stopped by 2025 | 7 OUR AMBITION and COMMITMENTS The European leader in nuclear waste treatment & decommissioning Corporate Social Responsibility & Value Creation • In control of the whole • Develop a customer- lifecycle of nuclear power oriented mindset A responsible generation Customer nuclear firm satisfaction • Provide differentiating • Best-in-class for safety solutions and security standards • Develop sustainable and A responsible • Attract and develop skills Innovation to cost-effective solutions employer • People-centered stay ahead • Promote innovation within the organizations • Technical excellence A responsible • Transparent and reliable Quality & social partner for all stakeholders Efficiency • Sustainable and profitable business The acquisition of Studsvik Waste Treatment business division is a key | 8 milestone in The EDF Group’s strategic plan INTRODUCING , PART OF THE EDF GROUP A strong player with a European footprint… …with 900 dedicated and well trained staff to handle all of your decommissioning and waste treatment requirements… …and an ambition to grow into the blossoming decommissioning and waste treatment market Decommissioning Services Waste Treatment Decommissioning Scenario & Costing Melting : up to 8 500 t/year Scrap and metallic large components Waste management strategy Incineration : up to 5 600 t/year Waste Characterization Metal Recycling Facility : up to Transition Management 2 500 t/year Training Pyrolysis : 50 t/year | 9 CYCLIFE CYCLIFE is a portmanteau word built with « cycle » and « life ». Sounding The name is brief, impacting, modern, positive, almost militant. Background - cycle, circle, and associated symbols (round, generous, community) - sequence repeated, revolution - character related with the beginning, the original state -life, energy, movement, dynamic - recycling - resources, sustainability - continuity Welcome home - 08/2016 EDF 2016 I P.10 OUR REFERENCES ON THE NUCLEAR VALUE CHAIN + Waste management / Treatment / Recycling to support operations and decommissioning EDF 2016 I P.11 EDF HAS A LONG EXPERIENCE IN DECOMMISSIONING AND WASTE MANAGEMENT EDF plants under decommissioning : 2- Brennilis 1- Chooz Heavy Water Reactor Commission date: 1967 Commission date : 1967 Shut-down date: 1985 Shut-down date: 1991 Pressurized Water Reactor UNGG Reactor Fast-neutron Reactor More than 15 years experience : EDF has taken 9 units from operating 3- Saint Laurent A 5- Bugey 1 Commission dates : Commission to decommissioning : 1 Pressurised 1969 & 1971 date : 1972 Water Reactor, 1 Heavy Water Shut-down dates: Shut-down 1990 & 1992 date: 1994 EDF is a also in preparing AGR decommissioning that will begin by mid 2020s - all closed in early 2030s 4- Chinon A Commission dates: 1963, 1965 & 1966 Shut-down dates: 6- Creys-Malville 1973 , 1985 & 1990 Commission date : 1986 Shut-down date: 1998 Waste treatment operations More than 25 years in waste treatment through Socodei (our waste treatment subsidiary based in France created in 1990) Melting, incineration, onsite waste treatment operations Recently created a dedicated division to accelerate its development in the waste treatment and decommissioning market. EDF 2016 I P.12 OUR AMBITION IS TO DEVELOP AN INTERNATIONAL PLATFORM IN DECOMMISSIONING & WASTE TREATMENT Objectives for our clients : . Use The EDF Group’s skills and assets to offer competitive waste treatment and decommissioning services . In the long-term, improve overall industrial capacity to match growing market needs . Develop innovative cost effective solutions for waste treatment and decommissioning . Answer growing incitation to recycle nuclear waste in order to preserve storage capacities The acquisition of Studsvik Waste Treatment business division is a milestone in The EDF Group’s strategic plan. EDF 2016 I P.13 EDF’S DEDICATED DIVISION TO DECOMMISSIONING AND WASTE MANAGEMENT DP2D Division created in 2016 EDF CEO Directly linked to the executive committee of EDF Now 900 people working on Decommissioning & Waste Management EDF Group Executive Director for Nuclear In charge of EDF’s nuclear dismantlement & Thermal generation (DPNT) program worldwide In charge of : Decommissioning and — EDF’s nuclear dismantlement program worldwide Waste Management Division — Managing waste generated by EDF’s nuclear (DP2D) power plants — Managing and developing waste treatment assets Existing waste treatment assets in France, Sweden and UK EDF 2016 I P.14 EDF CONTACTS Mats Fridolfsson Managing Director, Cyclife Sweden [email protected] Mobile : +46 76 00 09 201 EDF 2016 I P.15 CYCLIFE SWEDEN AB Lokala säkerhetsnämnden 09/12/2016 MYNDIGHETSÄRENDEN . Tillsynsaktiviteter genomförda under perioden 1 juli – 8 december 2016 Verksamhetsbevakning från SSM inom Transport 25/10 Inspektion inom Safeguard 27/7 . Kommande tillsynsaktiviteter Inga datumsatta SSM-tillsyner . Remisser Ny föreskrift för fysiskt skydd Föreskrifter om konstruktion, analys och drift av kärnkraftsreaktorer Studsviksfondens avskaffande . Övriga ärenden Diverse övriga ärenden Lokala säkerhetsnämnen | 12/2016 | 17 HÄNDELSER 1 JULI – 8 DECEMBER 2016 . Mindre barriärbrott, askfat Denna händelse har ej medfört något utsläpp Lokala säkerhetsnämnen | 12/2016 | 18 PYROLYSANLÄGGNINGEN . Status, går enligt plan (31/5/2017) Fortsatt provdrift Optimering av anläggningen Lokala säkerhetsnämnen | 12/2016 | 19 DOSSTATISTIK JULI – NOVEMBER 2016 Ackumulerade Doser, mmanSv Individ max dos, mSv doser (jan-xxx) Juli 1,51 1,51 (29,04) 0,33 Augusti 4,12 5,63 (33,16) 1,10 September 13,07 18,7 (46,23) 1,42 Oktober 4,07 22,77 (50,30) 0,91 November 2,94 25,71 (53,24) 0,30 Lokala säkerhetsnämnen | 12/2016 | 20 ÖVRIGA PUNKTER . Avvikelse gällande ytkontaminerade göt . Aktivitet inför 2017 (om SSM beviljar) Vi har ansökt om medel för rivning av R0 komplexet (3 byggnader) Lokala säkerhetsnämnen | 12/2016 | 21 THANK YOU EDF 2016 I P.22.
Load more

Recommended publications
  • Study of Acoustic Cavitation Near Metal Surfaces Contaminated by Uranium Ran Ji
    Study of acoustic cavitation near metal surfaces contaminated by uranium Ran Ji To cite this version: Ran Ji. Study of acoustic cavitation near metal surfaces contaminated by uranium. Other. Université Montpellier, 2018. English. NNT : 2018MONTS131. tel-02282007 HAL Id: tel-02282007 https://tel.archives-ouvertes.fr/tel-02282007 Submitted on 9 Sep 2019 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. THÈ SE POUR OBTENIR LE GRADE DE DOCTEUR DE L’UNIVERSITÉ DE MONTPELLIER En Chimie Sé parative - Maté riaux et Procé dé s É cole doctorale Sciences Chimiques Balard (ED 459) Unité de recherche Institut de Chimie Sé parative de Marcoule (UMR 5257) Study of Acoustic Cavitation near Metal Surfaces Contaminated by Uranium Pré senté e par Ran JI Le 13 novembre 2018 Sous la direction de Sergueï NIKITENKO Rapport de gestion Devant le jury composé de [Jean-Franç ois DUFÊ CHE, Prof, Université Montpellier] [Pré sident] [Jean-Yves HIHN, Prof, Université de Franche-Comté ] [Rapporteur] 2015 [Laurie BARTHE, MCF, INP Toulouse] [Rapporteur] [Sergueï NIKITENKO, DR, CNRS Montpellier] [Directeur de Thè se] [Claire LE NAOUR, CR, Université Paris Saclay] [Examinateur] [Micheline DRAYE, Prof, Université Savoie Mont Blanc] [Examinateur] [Rachel PFLIEGER, CR, CEA Marcoule] [Encadrant] [Matthieu VIROT, CR, CEA Marcoule] [Encadrant] [Pascal PILUSO, CR, CEA Cadarache] [Invité ] “The unity of inner knowledge and action” [Wang Yangming] Acknowledgements Acknowledgements The doctoral study of the past three years has greatly enriched my experience in academic and personal life.
    [Show full text]
  • Learning from Fukushima: Nuclear Power in East Asia
    LEARNING FROM FUKUSHIMA NUCLEAR POWER IN EAST ASIA LEARNING FROM FUKUSHIMA NUCLEAR POWER IN EAST ASIA EDITED BY PETER VAN NESS AND MEL GURTOV WITH CONTRIBUTIONS FROM ANDREW BLAKERS, MELY CABALLERO-ANTHONY, GLORIA KUANG-JUNG HSU, AMY KING, DOUG KOPLOW, ANDERS P. MØLLER, TIMOTHY A. MOUSSEAU, M. V. RAMANA, LAUREN RICHARDSON, KALMAN A. ROBERTSON, TILMAN A. RUFF, CHRISTINA STUART, TATSUJIRO SUZUKI, AND JULIUS CESAR I. TRAJANO Published by ANU Press The Australian National University Acton ACT 2601, Australia Email: [email protected] This title is also available online at press.anu.edu.au National Library of Australia Cataloguing-in-Publication entry Title: Learning from Fukushima : nuclear power in East Asia / Peter Van Ness, Mel Gurtov, editors. ISBN: 9781760461393 (paperback) 9781760461409 (ebook) Subjects: Nuclear power plants--East Asia. Nuclear power plants--Risk assessment--East Asia. Nuclear power plants--Health aspects--East Asia. Nuclear power plants--East Asia--Evaluation. Other Creators/Contributors: Van Ness, Peter, editor. Gurtov, Melvin, editor. All rights reserved. No part of this publication may be reproduced, stored in a retrieval system or transmitted in any form or by any means, electronic, mechanical, photocopying or otherwise, without the prior permission of the publisher. Cover design and layout by ANU Press. Cover image: ‘Fukushima apple tree’ by Kristian Laemmle-Ruff. Near Fukushima City, 60 km from the Fukushima Daiichi Nuclear Power Plant, February 2014. The number in the artwork is the radioactivity level measured in the orchard—2.166 microsieverts per hour, around 20 times normal background radiation. This edition © 2017 ANU Press Contents Figures . vii Tables . ix Acronyms and abbreviations .
    [Show full text]
  • Gestior Mr FRO302015 Doc
    Gestior Mr FRO302015 Doc. Enreg. 1 F4 If N'TRN INSTITUT D'ECONOMIE ET DE POLITIQUE DE LENERGIE The performing interaction between institutions and technology in the French electronuclear industry Dorninique Finon Carine Staropoli Working Paper (for submission to Industry& Innovation) Grenoble, October 2000 Institut 66conomie et de politique de 16nergie Unit6 mixte de recherche du Centre National de la Recherche Scientifique et de Mniversit6 Pierre Mends France (UFR DGES) IEPE, BP 47, 38040 Grenoble Cedex 09, Tel 04 76 51 42 40 Fax: 04 76 51 45 27 e mail iepeupmf-grenoble.fr ; http:Hwww.upmf-grenob1e.fr/iepe 2 The performing interaction between institutions and technology in the French electronuclear industry. Dominique Finon Carine Staropoli* Among the various traditional "grands programmes" typical of the French public intervention in high-tech industries, the nuclear programme is often considered as one of the major successes. About 60 nuclear reactors have been built between 1970 and 1998. Altogether they generate 80% of the electricity produced by the state-owned monopoly at a competitive cost. Moreover, the French nuclear industry ranks first on the world market of nuclear equipment and services. Such performances are all the more contrasting with those in the other OECD countries, where costs have dramatically increased while many projects never went ahead: since the 1980s a number of electricity companies decided to stop their riskyinvestments in nuclear equipment in many countries. Such a performance is attributable to an appropriate institutional set-up, which has been able to enforce all the technological leaming needed to the implementation of this kind of radical complex and large-sized innovation.
    [Show full text]
  • Gas-Cooled Reactors and Their Applications
    IAEA-TECDOC-436 GAS-COOLED REACTORS AND THEIR APPLICATIONS PROCEEDINGS OF A TECHNICAL COMMITTEE MEETING GAS-COOLEN O D REACTOR THEID SAN R APPLICATIONS ORGANIZED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY AND HELD IN JÜLICH, 20-23 OCTOBER 1986 A TECHNICAL DOCUMENT ISSUED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1987 GAS-COOLED REACTOR THEID SAN R APPLICATIONS IAEA, VIENNA, 1987 IAEA-TECDOC-436 Printe IAEe th Austri An i y d b a October 1987 FOREWORD Technological development r gas-coolefo s d reactor present a e ar st bein C(>2-cooler gfo larga carrieK n U o e e t scaldth ou d Advancen i e d Gas-Cooled Reactors Higr (AGRsfo h d Temperatur)an e Gas-Cooled Reactors (HTGRs) in the Federal Republic of Germany, United States of America, Japan and USSR. l programmeAl directee sar d towards constructio plantsf o n e Th . mose th t r advancefa y b s i d programmK efforU e th t n witi e h several commercial Hagnox Reactor and Advanced Gas-Cooled Reactor units in operatio d furthean n re constructio th AGR n i s r commissionino n g phase. HTGRs are in operation in the USA and in the Federal Republic of Germany. Othe R specifirHT c wor beins ki g carrieAustrian i t ou d , China and Switzerland. At the IAEA the International Working Group on Gas-Cooled Reactors (IWGGCR bees )ha n establishe 197n i d 8 in order to promote an exchange of information on gas-cooled reactor developmen stimulato t d tan e international cooperation framewore th n I .
    [Show full text]
  • Carbon-14 Source Term CAST
    CArbon-14 Source Term CAST WP5 Review of Current Understanding of Inventory and Release of C14 from Irradiated Graphite (D5.5) Author(s): Nelly Toulhout, Ernestas Narkunas, Borys Zlobenko, Daniela Diaconu, Laurent Petit, Stephan Schumacher, Stephane Catherin, Mauro Capone, Werner von Lensa, Gabriel Piña, Steve Williams, Johannes Fachinger, Simon Norris Editor: Simon Norris Date of issue of this report: 15/07/2015 The project has received funding from the European Union’s European Atomic Energy Community’s (Euratom) Seventh Framework Programme FP7/2007-2013 under grant agreement no. 604779, the CAST project. Dissemination Level PU Public X RE Restricted to the partners of the CAST project CO Confidential, only for specific distribution list defined on this document CAST WP5 Review of Current Understanding of Inventory and Release of C14 from Irradiated Graphite (D5.5) CAST – Project Overview The CAST project (CArbon-14 Source Term) aims to develop understanding of the potential release mechanisms of carbon-14 from radioactive waste materials under conditions relevant to waste packaging and disposal to underground geological disposal facilities. The project focuses on the release of carbon-14 as dissolved and gaseous species from irradiated metals (steels, Zircaloys), irradiated graphite and from ion-exchange materials. The CAST consortium brings together 33 partners with a range of skills and competencies in the management of radioactive wastes containing carbon-14, geological disposal research, safety case development and experimental work on gas generation. The consortium consists of national waste management organisations, research institutes, universities and commercial organisations. The objectives of the CAST project are to gain new scientific understanding of the rate of release of carbon-14 from the corrosion of irradiated steels and Zircaloys and from the leaching of ion-exchange resins and irradiated graphites under geological disposal conditions, its speciation and how these relate to carbon-14 inventory and aqueous conditions.
    [Show full text]
  • NRC Regulatory History of Non-Light Water Reactors (1950-2019)
    BNL-211739-2019-INRE NRC Regulatory History of Non-Light Water Reactors (1950-2019) Manuscript Completed: June 10, 2019 Prepared by: Pranab Samanta, David Diamond, and William Horak Nuclear Science and Technology Department Brookhaven National Laboratory Upton, NY 11973-5000 Prepared for: Imtiaz Madni and George Tartal Office of New Reactors U.S. Nuclear Regulatory Commission ABSTRACT This report describes the U.S. Nuclear Regulatory Commission’s (NRC’s) history with the licensing of non-light water reactors (non-LWRs). The focus is on regulatory policy and licensing issues that have arisen in the past so that NRC staff will be in a better position to deal with these matters in the future. It is not an objective to discuss in any detail the technology of non-LWR designs. Documenting the historical policy issues and licensing approaches is particularly important to NRC staff unfamiliar with non- LWRs and is an important incentive for the report. Hence, the report is written as a tutorial rather than as an historical archive. The subject is approached chronologically going from the early days of the Atomic Energy Commission to the formation of the NRC, then into the era when the regulatory structure newly developed for LWRs provided guidance for other types of reactors, followed by the era when policy was made specifically for advanced reactors including non-LWRs. This background provides the transition to current planning for future non-LWR licensing and policy─also described herein. iii TABLE OF CONTENTS ACRONYMS ...................................................................................................................vi 1 INTRODUCTION ................................................................................................... 1-1 1.1 Background ............................................................................................... 1-1 1.2 Objective ..................................................................................................
    [Show full text]
  • CW Deliverable T-3.4.3
    CARBOWASTE Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste Grant Agreement Number: FP7-211333 Technical Report T-3.4.3 Modelling of isotope release mechanism based on fission product transport codes Author(s): Ernestas Narkunas, Povilas Poskas; LEI Greg Black, Abby Jones; UoM Constantin Iorgulis, Daniela Diaconu; INR Laurent Petit, Bernard Poncet; EDF Date of issue of this report: 15/02/2013 Project co-funded by the European Commission under the Seventh Framework Programme (2007 to 2011) of the European Atomic Energy Community (EURATOM) for nuclear research and training activities Dissemination Level PU Public RE Restricted to the partners of the CARBOWASTE project X CO Confidential, only for specific distribution list defined on this document Start date of project: 01/04/2008 Duration: 60 Months CARBOWASTE Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste Distribution list Person and organisation name Comments and/or group Werner von Lensa, FZJ Gabriel Pina, CIEMAT Abbie Jones, UoM Daniela Diaconu, INR Laurent Petit, EDF CW1302-Deliverable -T-3-4-3.doc Page 2/83 CARBOWASTE Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste CARBOWASTE Work package: 3 CARBOWASTE document no.: Document type: Task: 3.4 CARBOWASTE-1302-T-3.4.3 T=Technical Report (e.g. May 2008 as date of issue: 0805) Issued by: LEI (LT) Document status: Internal no.: CW1302-Deliverable-T-3-4-3-final Final Document title Modelling of isotope release mechanism based on fission product transport codes Executive summary The Work Package 3 (Characterisation and Modelling) Task 3.4 (Modelling the Behaviour of Impurities and Isotopes in Graphite) focuses on modelling of the changes in graphite radiological inventory (list of present radionuclides and their activity) during reactor operation and after its final shutdown.
    [Show full text]
  • National Assessment Board
    NATIONAL ASSESSMENT BOARD FOR RESEARCH AND THE STUDIES INTO THE MANAGEMENT OF RADIOACTIVE WASTE AND MATERIALS Instituted by the law n°2006-739 of June 28, 2006 NATIONAL ASSESSMENT BOARD ASSESSMENT REPORT NO 12 Président: Jean-Claude DUPLESSY Vice-Présidents: Maurice LEROY & Gilles PIJAUDIER-CABOT General Secretary & Scientific Advisor: Stanislas POMMERET Administrative secretary: Véronique ADA-FAUCHEUX & Florence LEDOUX www.cne2.fr JUNE 2018 244 boulevard Saint-Germain • 75007 Paris • Phone: +33 (0)1 44 49 80 93 & +33 (0)1 44 49 80 94 ISSN : 2257-5758 NATIONAL ASSESSMENT BOARD Members of National Assessment Board: Jean-Claude DUPLESSY Anna CRETI Frank DECONINCK Pierre DEMEULENAERE Robert GUILLAUMONT Vincent LAGNEAU Maurice LAURENT Emmanuel LEDOUX* Mickaële LE RAVALEC Maurice LEROY José-Luis MARTINEZ Gilles PIJAUDIER-CABOT Claes THEGERSTRÖM General Secretary & Scientific Advisor: Stanislas POMMERET Honorary President: Bernard TISSOT Administrative secretary: Véronique ADA-FAUCHEUX Florence LEDOUX * Invited Expert NATIONAL ASSESSMENT BOARD FOR RESEARCH AND STUDIES INTO THE MANAGEMENT OF RADIOACTIVE MATERIALS AND WASTE Established by law No. 2006-739 of 28 June 2006 ASSESSMENT REPORT No. 12 JUNE 2018 TABLE OF CONTENTS FOREWORD: SETTING A DIRECTION .......................................................................................................... 5 SUMMARY – CONCLUSION ........................................................................................................................ 7 INTRODUCTION ......................................................................................................................................
    [Show full text]
  • Iaea Tecdoc Series Tecdoc Iaea @
    IAEA-TECDOC-1790 IAEA-TECDOC-1790 IAEA TECDOC SERIES Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal Waste Acceptance Criteria for Processing of Irradiated Graphite to Meet IAEA-TECDOC-1790 Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal Results of a Coordinated Research Project @ PROCESSING OF IRRADIATED GRAPHITE TO MEET ACCEPTANCE CRITERIA FOR WASTE DISPOSAL The following States are Members of the International Atomic Energy Agency: AFGHANISTAN GEORGIA OMAN ALBANIA GERMANY PAKISTAN ALGERIA GHANA PALAU ANGOLA GREECE PANAMA ANTIGUA AND BARBUDA GUATEMALA PAPUA NEW GUINEA ARGENTINA GUYANA PARAGUAY ARMENIA HAITI PERU AUSTRALIA HOLY SEE PHILIPPINES AUSTRIA HONDURAS POLAND AZERBAIJAN HUNGARY PORTUGAL BAHAMAS ICELAND QATAR BAHRAIN INDIA REPUBLIC OF MOLDOVA BANGLADESH INDONESIA ROMANIA BARBADOS IRAN, ISLAMIC REPUBLIC OF RUSSIAN FEDERATION BELARUS IRAQ RWANDA BELGIUM IRELAND SAN MARINO BELIZE ISRAEL SAUDI ARABIA BENIN ITALY SENEGAL BOLIVIA, PLURINATIONAL JAMAICA SERBIA STATE OF JAPAN SEYCHELLES BOSNIA AND HERZEGOVINA JORDAN SIERRA LEONE BOTSWANA KAZAKHSTAN SINGAPORE BRAZIL KENYA SLOVAKIA BRUNEI DARUSSALAM KOREA, REPUBLIC OF SLOVENIA BULGARIA KUWAIT SOUTH AFRICA BURKINA FASO KYRGYZSTAN SPAIN BURUNDI LAO PEOPLE’S DEMOCRATIC SRI LANKA CAMBODIA REPUBLIC SUDAN CAMEROON LATVIA SWAZILAND CANADA LEBANON SWEDEN CENTRAL AFRICAN LESOTHO SWITZERLAND REPUBLIC LIBERIA SYRIAN ARAB REPUBLIC CHAD LIBYA TAJIKISTAN CHILE LIECHTENSTEIN THAILAND CHINA LITHUANIA THE FORMER YUGOSLAV COLOMBIA LUXEMBOURG
    [Show full text]
  • The Amster Concept (Actinides Molten Salt Transmuter)
    1 THE AMSTER CONCEPT (ACTINIDES MOLTEN SALT TRANSMUTER) J VERGNES P. BARBRAULT,D LECARPENTIER, Ph TETART EDF Pole Industrie Division Recherche et Développement Département Physique des Réacteurs 1 Avenue du Général de Gaule 92140 CLAMART France e mail: jean.vergnes@edfgdf;fr H MOUNEY EDF Pole Industrie Division Ingéniérie et Services CAP AMPERE 93282 SAINT DENIS CEDEX France e mail: henri.mouney@edfgdf;fr ABSTRACT In the frame of the French law related to the management of long lived radioactive wastes, a reactor concept aiming both to generate electricity and to minimize existing transuranics (TRU) and long lived fission product is proposed. This concept named AMSTER is a Molten Salt Reactor, the molten fuel being a mixing of Transuranics and enriched Uranium. The salt processing is integrated and allows both to supply U-235 and to separate fission products while minimizing transuranics losses. Two options have been analyzed : · a TRU self-burning option, releasing only a few grams/Twhe of TRU in the wastes for geological storage. It needs an equilibrium inventory of 1.6 metric tons/Twhe in the reactor and a consumption of 10 metric tons/Twhe of natural uranium (compared to 21 for PWR) ; · a TRU incineration option which would permit, for example to burn the TRU present in PWR spent fuels at a rate of 28 kg/TWhe, for an inventory at equilibrium of 4.7 metric tons/Twhe of TRU. The consumption would be then of 2.2 metric ton/TWhe of PWR spent fuel and 3.7 metric ton/TWhe of natural Uranium. 2 1.
    [Show full text]
  • Thermal Treatment of Oldbury Magnox Reactor Irradiated Graphite
    THERMAL TREATMENT OF OLDBURY MAGNOX REACTOR IRRADIATED GRAPHITE A thesis submitted to the University of Manchester for the degree of Doctor of Philosophy in the Faculty of Engineering and Physical Sciences 2015 Robert Numa Worth School of Mechanical, Aerospace and Civil Engineering The University of Manchester - 2 - Table of Contents Table of Contents ..................................................................................................................... 3 List of Figures ........................................................................................................................... 7 List of Tables .......................................................................................................................... 12 Abstract .................................................................................................................................. 13 Declaration ............................................................................................................................. 14 Copyright Statement .............................................................................................................. 15 Acknowledgments .................................................................................................................. 16 Thesis Structure ..................................................................................................................... 17 1. Introduction ......................................................................................................................
    [Show full text]
  • Supplementary Data to Global Risk of Radioactive Fallout After Nuclear
    Supplementary Data to Global risk of radioactive fallout after nuclear reactor accidents Jos Lelieveld1,2 , Daniel Kunkel1, and Mark G. Lawrence1 1 Max Planck Institute for Chemistry, 55020 Mainz, Germany 2 The Cyprus Institute, 1645 Nicosia, Cyprus E-mail: [email protected] Net capacity Gross capacity Start of End of operation Energy supply Name Block Reactor type Status in MW in MW operation (planned) in GWh South Afrika Koeberg 1 PWR operational 900 944 04.04.1984 (14.08.2024) 127.092 Koeberg 2 PWR operational 900 944 25.07.1985 (15.11.2025) 122.496 Asia Armenia Mezamor (Armenia) 1 WWER‐440/270 decommissioned 376 408 22.12.1976 25.02.1989 25.266 Mezamor (Armenia) 2 WWER‐440/270 operational 376 408 05.01.1980 (2016) 46.546 China Changjiang 1 CNP‐600 under construction since 2010 610 650 – – – Changjiang 2 CNP‐600 under construction since 2010 610 650 – – – Daya Bay (Guangdong) 1 PWR operational 944 984 31.08.1993 (06.05.2034) 93.096 Daya Bay (Guangdong) 2 PWR operational 944 984 07.02.1994 (31.01.2034) 91.559 Fangchenggang 1 CPR‐1000 under construction since 2010 1 1,087 – – – Fangjiashan 1 CPR‐1000 under construction since 2008 1 1,087 – – – Fangjiashan 2 CPR‐1000 under construction since 2009 1 1,087 – – – Fuqing 1 CPR‐1000 under construction since 2008 1 1,087 (2014/15) – – Fuqing 2 CPR‐1000 under construction since 2009 1 1,087 – – – Haiyang 1 AP‐1000 under construction since 2009 1 1,25 – – – Haiyang 2 AP‐1000 under construction since 2010 1 1,25 – – – Hongyanhe 1 CPR‐1000 under construction since 2007 1 1,08 (2013/14) – – Hongyanhe
    [Show full text]