DOCSLIB.ORG

Status of and Prospects for Gas-Cooled Reactors

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Status of and Prospects for Gas-Cooled Reactors 1 PROCESS STEAM \7 1 • • 1 1 I I II I I 11 11 •• •• 11 •• aa 1 — TECHNICAL REPORTS SERIES No. 235 Status of and Prospects for Gas-Cooled Reactors INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1984 STATUS OF AND PROSPECTS FOR GAS-COOLED REACTORS The following States are Members of the International Atomic Energy Agency: AFGHANISTAN HAITI PARAGUAY ALBANIA HOLY SEE PERU ALGERIA HUNGARY PHILIPPINES ARGENTINA ICELAND POLAND AUSTRALIA INDIA PORTUGAL AUSTRIA INDONESIA QATAR BANGLADESH IRAN, ISLAMIC REPUBLIC OF ROMANIA BELGIUM IRAQ SAUDI ARABIA BOLIVIA IRELAND SENEGAL BRAZIL ISRAEL SIERRA LEONE BULGARIA ITALY SINGAPORE BURMA IVORY COAST SOUTH AFRICA BYELORUSSIAN SOVIET JAMAICA SPAIN SOCIALIST REPUBLIC JAPAN SRI LANKA CAMEROON JORDAN SUDAN CANADA KENYA SWEDEN CHILE KOREA, REPUBLIC OF SWITZERLAND CHINA KUWAIT SYRIAN ARAB REPUBLIC COLOMBIA LEBANON THAILAND COSTA RICA LIBERIA TUNISIA CUBA LIBYAN ARAB JAMAHIRIYA TURKEY CYPRUS LIECHTENSTEIN UGANDA CZECHOSLOVAKIA LUXEMBOURG UKRAINIAN SOVIET SOCIALIST DEMOCRATIC KAMPUCHEA MADAGASCAR REPUBLIC DEMOCRATIC PEOPLE'S MALAYSIA UNION OF SOVIET SOCIALIST REPUBLIC OF KOREA MALI REPUBLICS DENMARK MAURITIUS UNITED ARAB EMIRATES DOMINICAN REPUBLIC MEXICO UNITED KINGDOM OF GREAT ECUADOR MONACO BRITAIN AND NORTHERN EGYPT MONGOLIA IRELAND EL SALVADOR MOROCCO UNITED REPUBLIC OF ETHIOPIA NAMIBIA TANZANIA FINLAND NETHERLANDS UNITED STATES OF AMERICA FRANCE NEW ZEALAND URUGUAY GABON NICARAGUA VENEZUELA GERMAN DEMOCRATIC REPUBLIC NIGER VIET NAM GERMANY, FEDERAL REPUBLIC OF NIGERIA YUGOSLAVIA GHANA NORWAY ZAIRE GREECE PAKISTAN ZAMBIA GUATEMALA PANAMA The Agency's Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is "to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world". © IAEA, 1984 Permission to reproduce or translate the information contained in this publication may be obtained by writing to the International Atomic Energy Agency, Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria. Printed by the IAEA in Austria April 1984 TECHNICAL REPORTS SERIES No. 235 STATUS OF AND PROSPECTS FOR GAS-COOLED REACTORS INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1984 STATUS OF AND PROSPECTS FOR GAS-COOLED REACTORS IAEA, VIENNA, 1984 STI/DOC/lO/235 ISBN 92-0-155084-7 FOREWORD The widespread interest in the development of gas-cooled reactors and their application for electricity generation and process heat production has highlighted the need to establish an international forum for the exchange of information in this area. In 1978 the IAEA established the International Working Group on Gas-Cooled Reactors (IWGCR) (see Annex I) in order to promote an exchange of information on national programmes and on new developments and experience and to stimulate international co-operation on gas-cooled reactor development. At its last meeting, the IWGCR recommended that the Agency prepare a report to disseminate up-to-date technical information to all Agency Member States on fast and thermal reactors cooled by C02, helium or N204. The present Technical Report, which is the result of that recommendation, is based mainly on submissions from Member States, and the Agency would like to thank all those individuals and institutions who have contributed to it. The Agency would also like to express its gratitude to the members of the Drafting Committee (see Annex II), who met several times to review the sub- missions and the status of the report, and who thus contributed materially to its successful completion. In particular, the work of Mr. F.J. Krings*, who prepared the first draft of this report, should be mentioned. * It is with great regret that the Agency has to announce that Mr. Krings died in October 1983. CONTENTS 1. INTRODUCTION 1 1.1. General information 2 1.2. Incentives for the application of gas-cooled reactors 4 1.2.1. General outline 4 1.2.2. National incentives for the cogeneration application and process heat application 6 1.2.2.1. National incentives in the USA 6 1.2.2.2. National incentives in the USSR 11 1.2.2.3. National incentives in the Federal Republic of Germany 13 1.2.2.4. National incentives in France 18 1.2.2.5. National incentives in Japan 19 2. HISTORICAL DEVELOPMENT OF GAS-COOLED REACTORS UP TO THE PRESENT 29 2.1. Introduction 29 2.2. Gas-cooled thermal reactors 33 2.2.1. Development of gas-cooled reactors in France 33 2.2.2. Development of gas-cooled reactors in the Federal Republic of Germany 35 2.2.2.1. AVR 35 2.2.2.2. Thorium high-temperature reactor (THTR-300) .... 38 2.2.2.3. Other GCR developments 41 2.2.3. Development of gas-cooled reactors in Japan 43 2.2.4. Development of gas-cooled reactors in Switzerland 44 2.2.5. Development of gas-cooled reactors in the United Kingdom... 47 2.2.5.1. Magnox reactor stations 47 2.2.5.2. Advanced gas-cooled reactors 48 2.2.5.3. High-temperature reactors 51 2.2.6. Development of gas-cooled reactors in the United States of America 51 2.2.6.1. Ultra High Temperature Reactor Experiment (UHTREX) 53 2.2.6.2. Peach Bottom Atomic Power Station - Unit 1 54 2.2.6.3. Fort St. Vrain Nuclear Generating Station 56 2.2.7. Development of gas-cooled reactors in the USSR 56 2.2.8. OECD project: The Dragon Reactor Experiment (DRE) 62 2.3. Gas-cooled fast breeder reactors (GCFR) 65 3. TECHNICAL STATUS OF THE APPLICATION OF GCRs 69 3.1. Electricity generation 69 3.1.1. Magnox stations 69 3.1.1.1. Status of the Calder Hall and Chapelcross Stations in the UK 69 3.1.1.2. Status of commercial Magnox stations 69 3.1.1.3. Modern Magnox reactor design 70 3.1.1.4. Costs of Magnox stations 72 3.1.1.5. Future application 72 3.1.1.6. Latina power station, Italy 73 3.1.1.7. Tokai Mura power station, Japan 75 3.1.1.8. Magnox reactors in France (UNGG reactors) 75 3.1.2. Advanced gas-cooled reactor (AGR) 78 3.1.2.1. Status of AGRs in the UK 78 3.1.2.2. AGRs in construction or operation in the UK 83 3.1.2.3. Windscale AGR 86 3.1.2.4. Costs of AGRs in the UK 87 3.1.3. High-temperature reactors 90 3.1.3.1. Introduction 90 3.1.3.2. Reactors under construction or in operation 92 3.1.3.2.1. Fort St. Vrain 92 3.1.3.2.2. AVR 97 3.1.3.2.3. Thorium high-temperature reactor (THTR-300) 98 3.1.3.3. Future reactor designs 102 3.1.3.3.1. HTGR steam-cycle design (USA) 102 3.1.3.3.2. Steam-cycle plant concepts in the Federal Republic of Germany 110 3.1.4. HTGR direct cycle (HTGR-GT) 127 3.1.4.1. Incentives for development 127 3.1.4.2. The HHT project (Federal Republic of Germany and Switzerland) 127 3.1.4.3. Overall gas-turbine plant features (USA) 129 3.1.5. Gas-cooled fast breeder reactor (GCFR) 133 3.1.5.1. Introduction 133 3.1.5.2. The GCFR programme in the USA 134 3.1.5.3. The OECD-NEA GCFR programme 137 3.1.5.4. GBRA design : 138 3.1.5.5. The GCFR programme in the USSR 143 3.1.5.6. The GCFR programme in Switzerland 146 3.1.5.7. GCFR design status and prospects 147 3.2. Process steam and process heat application 149 3.2.1. Introduction 149 3.2.2. Proposed reactor concepts 153 3.2.2.1. PNP-500 plant (Federal Republic of Germany) 153 3.2.2.2. Reference to modular reactor concepts and HTR-450 (Federal Republic of Germany) 159 3.2.2.3. HTGR steam cycle/cogeneration (USA) 161 3.2.2.4. 850°C indirect-cycle HTGR-PH plant (USA) 163 3.2.2.5. 950°C direct-cycle HTGR-PH plant (USA) 164 3.2.2.6. VGR-50 reactor (USSR) 165 3.2.2.7. VG-400 reactor (USSR) 167 3.2.2.8. Very high-temperature reactor (VHTR) (Japan) .... 168 3.2.3. Process steam applications 169 3.2.3.1. Application survey in the USA 169 3.2.3.2. Application for district heating 178 3.2.3.3. Processes in organic chemistry and petrochemistry.. 180 3.2.3.4. Extraction of heavy crude oil 180 3.2.3.5. SNG production by Lurgi coal gasification 181 3.2.4. Process heat applications 182 3.2.4.1. Synthesis gas 182 3.2.4.1.1. SNG production by hydrogasification of coal « 182 3.2.4.1.2. SNG production by steam gasification of hard coal 184 3.2.4.1.3. SNG production by steam-methane reforming and the thermochemical long-distance energy transport by gases 188 3.2.4.1.4. Demonstration plant EVA II/ADAM II for long-distance heat supply 190 3.2.4.1.5. SNG production by the Exxon catalytic coal gasification process .... 191 3.2.4.2. SNG as raw material in the chemical industry 195 3.2.4.3. Hydrogen production by thermochemical splitting of water and high-temperature electrolysis 196 4. SPECIAL FEATURES OF GAS-COOLED REACTORS 4.1. Technical performance 201 4.1.1. Magnox stations 201 4.1.1.1. Magnox stations in the United Kingdom 201 4.1.1.2. Magnox-type reactors (UNGG) in France 201 4.1.1.3.
Load more

Recommended publications
  • 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
    [Show full text]
  • 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]