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Pyrochemical Separations : Workshop Proceedings -- Avignon, France -- 14-16 March 2000. PDF

336 Pages·2001·6.75 MB·English
by  OECD
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Nuclear Science P yrochemical Separations Workshop Proceedings Avignon, France 14-16 March 2000 N U C L E A R • E N E R G Y • A G E N C Y © OECD, 2001. © Software: 1987-1996, Acrobat is a trademark of ADOBE. All rights reserved. OECD grants you the right to use one copy of this Program for your personal use only. Unauthorised reproduction, lending, hiring, transmission or distribution of any data or software is prohibited. You must treat the Program and associated materials and any elements thereof like any other copyrighted material. All requests should be made to: Head of Publications Service, OECD Publications Service, 2, rue André-Pascal, 75775 Paris Cedex 16, France. OECD PROCEEDINGS Proceedings of the Workshop on P YROCHEMICAL S EPARATIONS Co-organised by the European Commission Hosted by Commissariat à l’Énergie Atomique Valrhô Avignon, France 14-16 March 2000 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force on 30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies designed: − to achieve the highest sustainable economic growth and employment and a rising standard of living in Member countries, while maintaining financial stability, and thus to contribute to the development of the world economy; − to contribute to sound economic expansion in Member as well as non-member countries in the process of economic development; and − to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance with international obligations. The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany, Greece, Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The following countries became Members subsequently through accession at the dates indicated hereafter: Japan (28th April 1964), Finland (28th January 1969), Australia (7th June 1971), New Zealand (29th May 1973), Mexico (18th May 1994), the Czech Republic (21st December 1995), Hungary (7th May 1996), Poland (22nd November 1996) and the Republic of Korea (12th December 1996). The Commission of the European Communities takes part in the work of the OECD (Article 13 of the OECD Convention). NUCLEAR ENERGY AGENCY The OECD Nuclear Energy Agency (NEA) was established on 1st February 1958 under the name of the OEEC European Nuclear Energy Agency. It received its present designation on 20th April 1972, when Japan became its first non-European full Member. NEA membership today consists of 27 OECD Member countries: Australia, Austria, Belgium, Canada, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Luxembourg, Mexico, the Netherlands, Norway, Portugal, Republic of Korea, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The Commission of the European Communities also takes part in the work of the Agency. The mission of the NEA is: − to assist its Member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes, as well as − to provide authoritative assessments and to forge common understandings on key issues, as input to government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as energy and sustainable development. Specific areas of competence of the NEA include safety and regulation of nuclear activities, radioactive waste management, radiological protection, nuclear science, economic and technical analyses of the nuclear fuel cycle, nuclear law and liability, and public information. The NEA Data Bank provides nuclear data and computer program services for participating countries. In these and related tasks, the NEA works in close collaboration with the International Atomic Energy Agency in Vienna, with which it has a Co-operation Agreement, as well as with other international organisations in the nuclear field. © OECD 2000 Permission to reproduce a portion of this work for non-commercial purposes or classroom use should be obtained through the Centre français d’exploitation du droit de copie (CCF), 20, rue des Grands-Augustins, 75006 Paris, France, Tel. (33-1) 44 07 47 70, Fax (33-1) 46 34 67 19, for every country except the United States. In the United States permission should be obtained through the Copyright Clearance Center, Customer Service, (508)750-8400, 222 Rosewood Drive, Danvers, MA 01923, USA, or CCC Online: http://www.copyright.com/. All other applications for permission to reproduce or translate all or part of this book should be made to OECD Publications, 2, rue André-Pascal, 75775 Paris Cedex 16, France. FOREWORD In the future, nuclear fuel will reach high burn-up, and recycling of spent fuel will possibly have to be performed after shorter cooling times to be economically and ecologically attractive. Dry reprocessing using pyrochemical methods has received the attention of some research institutes due to its potential advantages of compactness in the plant design, criticality safety considerations as well as stability against high radiation dose. Recently, partitioning and transmutation (P&T) of long-lived fission products and minor actinides has been considered as one of the future options of waste management. In order to achieve effective transmutation, multi-recycling of fuel with much higher burn-up and shorter cooling time will be required. Therefore, the role of pyrochemical reprocessing becomes more important for the implementation of the P&T option. The proposed processes are complex and necessitate the use of highly controlled atmospheres to avoid hydrolysis and precipitation reactions. Except for the pilot-scale demonstration of the pyro-electrolysis at Argonne National Laboratory (Idaho) and the Russian Institute of Atomic Reactors, all other studies are at the laboratory scale. Much R&D work is required in order to upgrade the pyrochemical separation process to the current level of industrial aqueous reprocessing. For this reason, the OECD/NEA Nuclear Science Committee decided to organise a workshop to exchange information about recent activities on pyrochemical separations and to make a recommendation about the future activities of the OECD/NEA in the field. The Workshop on Pyrochemical Separations, co-organised by the European Commission and hosted by CEA Valrho, was successfully held in Avignon, France, on 14-15 March 2000, with more than 70 participants from 14 countries and 3 international organisations. There were 21 oral presentations and 8 posters on the following topics: • National and international R&D programmes on pyrochemical separations. • Role and requirements of pyrochemical reprocessing in future fuel cycles. • Recent progress in research activities, including: − Basic data (thermodynamics, reaction mechanisms, reaction kinetics, molecular modelling). − Results and experiences from process experiments. − Process simulation and process design. It was recommended that an expert group be set up to prepare a state-of-the-art report on pyrochemical separations. The report, furnishing timely and coherent coverage of situations in each country and providing a common scientific base on pyrochemical separations, will be very useful for promoting efficient international collaboration. 3 TABLE OF CONTENTS FOREWORD.................................................................................................................................... 3 EXECUTIVE SUMMARY.............................................................................................................. 9 OPENING SESSION....................................................................................................................... 11 C. Madic Welcome Address..................................................................................................... 13 Ph. Savelli Opening Address...................................................................................................... 15 SESSION I National and International R&D Programmes on Pyrochemical Separations.............................................................................................................. 17 Chair: G. Choppin, B. Boullis M. Hugon Research Work on Radionuclide Partitioning from Nuclear Waste Co-Financed by the European Commission............................................................. 19 J.T. Laidler Pyrochemical Separations Technologies Envisioned for the US Accelerator Transmutation of Waste System........................................................... 25 A.V. Bychkov, O.V. Skiba, S.K. Vavilov, M.V. Kormilitzyn, A.G. Osipenco Overview of RIAR Activity on Pyroprocess Development and Application to Oxide Fuel and Plans in the Coming Decade....................................................... 37 R. Thied, D. Hebditch, P. Parkes, R. Taylor, B. Hanson, P. Wilson BNFL’s Molten Salts Programme: Industrialising Processes for Irradiated Fuel........................................................................................................... 47 B. Boullis, Ph. Brossard Assessment of Pyrochemical Processes for Separation/Transmutation Strategies: Proposed Areas of Research................................................................... 59 SESSION II Role and Requirements of Pyrochemical Separations in the Future Fuel Cycles............................................................................................................... 61 Chairs: P. Wilson, M. Hugon L. Koch Role of Pyrochemistry in Advanced Nuclear Energy Generating System............... 63 5 J. Uhlir Pyrochemical Reprocessing Technology and Molten Salt Transmutation Reactor Systems........................................................................................................ 73 T. Inoue Actinide Recycling by Pyroprocess for Future Nuclear Fuel Cycle System............ 79 S. Kitawaki, K. Kosugi, M. Fukushima, M. Myochin Evaluation of Pyrochemical Reprocessing Technologies for Practical Use............. 87 SESSION III Part A: Basic Data (Thermodynamics, Reaction Mechanisms Reaction Kinetics, Molecular Modelling, etc.)..................................................... 97 Chairs: L. Koch, T. Ogawa M. Gaune-Escard, A.K. Adya, L. Rycerz Molten Salt Data for Pyrochemistry: New Research Advances and Development of Information System................................................................. 99 D. Lambertin, J. Lacquement, S. Sanchez, G. Picard Electrochemical Properties of Plutonium in Molten CaCl -NaCl at 550°C............. 111 2 F. Lantelme, T. Cartailler, P. Turq Application of Electrochemical Techniques in Pyropartitioning Processes and Reaction Modelling............................................................................................ 123 H. Yamana, J. Sheng, H. Moriyama Thermodynamic Stabilities of Lanthanides and Actinides in Molten Chloride and Liquid Metal........................................................................................ 135 Part B: Results and Experiences from Process Experiments............................. 145 Chairs: M. Gaune-Escard, T. Inoue G.R. Choppin Results of Demonstration Programme of Electrometallurgical Processing of Breeder Reactor Fuel............................................................................................ 147 T. Ogawa, Y. Arai Nitride/Pyroprocess for MA Transmutation and Fundamental Database................. 157 T. Usami, M. Kurata, T. Inoue, J. Jenkins, H. Sims, S. Beetham, D. Brown Pyrometallurgical Reduction of Unirradiated TRU Oxides by Lithium in a Lithium Chloride Medium................................................................................. 165 T. Koyama, K. Kinoshita, T. Inoue, M. Ougier, J.-P. Glatz, L. Koch Small-Scale Demonstration of Pyrometallurgical Processing for Metal Fuel and HLLW........................................................................................................ 177 T. Subramanian, B. Prabhakara Reddy, P. Venkatesh, R. Kandan, T. Vandarkuzhali, K. Nagarajan, P.R. Vasudeva Rao Studies on the Head-End Steps for Pyrochemical Reprocessing of Oxide Fuels........................................................................................................... 187 6 Part C: Process Simulation and Process Design.................................................. 195 Chairs: J. Uhlir, H. Boussier P. Hosnedl, O. Matal Development of Structural Material and Equipment for Molten Salt Technology............................................................................................................... 197 H. Moriyama, H. Yamana, K. Moritani Kinetics of Pyrochemical Processing of Nuclear Materials Using Molten Salt and Liquid Metal............................................................................................... 205 G. Picard, S. Sanchez, D. Lambertin, J. Lacquement A Rational Approach to Pyrochemical Processes Via Thermodynamic Analysis.................................................................................................................... 213 SESSION IV Open Discussion and Recommendations.............................................................. 227 Chair: C. Madic POSTER SESSION.......................................................................................................................... 231 K. Guerman, T. Reich, C. Sergeant, R. Ortega, V. Tarasov, M. Simonoff Technetium Metal and Pyrometallurgically Formed Sediments: Study and Speciation by Tc NMR and EXAFS/XANES.................................................... 233 V.V. Ignatiev, R.Ya. Zakirov, K.F. Grebenkine Molten Salt Burner Fuel Behaviour and Treatment.................................................. 243 C. Jouault, M. Allibert, R. Boen, X. Deschanels Recovery of Noble Metals (Ru, Rh, Pd, Mo) and Tellurium from Fission Products........................................................................................................ 255 S. Kitawaki, N. Kameshiro, M. Fukushima, M. Myochin Study of Oxidising Uranium for Pyrochemical Reprocessing.................................. 265 C. Pernel, M. Ougier, J.-P. Glatz, L. Koch, T. Koyama Partitioning of Americium Metal from Rare Earth Fission Products by Electrorefining..................................................................................................... 275 W.A. Punjak, A.J. Vargas, Jr., G.D. Bird, E. Garcia Americium Extraction Via In Situ Chlorination of Plutonium Metal....................... 285 G. Bourgès, A. Godot, C. Valot, D. Devillard Pyro-Oxidation of Plutonium Spent Salts with Sodium Carbonate.......................... 287 S.A. Kuznetsov, M. Gaune-Escard Electrochemical Studies of EuCl and EuCl in an Equimolar 3 2 NaCl-KCl Melt......................................................................................................... 295 V. Lelek, T. Marek Generalised Perturbation Theory and Source of Information through Chemical Measurements........................................................................................... 307 7 Annex 1. LIST OF PARTICIPANTS.............................................................................................. 317 Annex 2. WORKSHOP ORGANISATION.................................................................................... 327 Annex 3. STATE-OF-THE-ART REPORT ON PYROCHEMICAL SEPARATIONS............ 329 8

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The industrial treatment of spent nuclear fuel is presently performed using different wet chemical processes. Alternative dry processes, using pyrochemical methods, have received some attention due to their potential advantages in terms of plant design and criticality safety, as well as radiation do
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