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The Community's Research and Development Programme on Decommissioning of Nuclear Installations (1989-93) Annual Progress Report 1991

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The Community's Research and Development Programme on Decommissioning of Nuclear Installations (1989-93) Annual Progress Report 1991 "JtfS Commission of the European Communities nuclear science and technology The Community's research and development programme on decommissioning of nuclear installations (1989-93) Annual progress report 1991 EUR 14498 EN Commission of the European Communities nuclear science and technology The Community's research and development programme on decommissioning of nuclear installations (1989-93) Annual progress report 1991 Publication of this report has been supported by the Dissemination of Scientific and Technical Knowledge Unit, ' Directorate-General for Telecommunications, Information Industries and Innovation, Commission of the European Communities, Luxembourg Directorate-General Science, Research and Development IŢAKL EURUP. Biblioth. 1992 |N.C. EUR 14498 EN| cT Published by the COMMISSION OF THE EUROPEAN COMMUNITIES Directorate-General Telecommunications, Information Industries and Innovation L-2920 Luxembourg LEGAL NOTICE Neither the Commission of the European Communities nor any person acting on behalf of the Commission is responsible for the use which might be made of the following information Cataloguing data can be found at the end of this publication Luxembourg: Office for Official Publications of the European Communities, 1992 ISBN 92-826-4400-6 © ECSC-EEC-EAEC, Brussels • Luxembourg, 1992 Printed in Belgium FOREWORD The following second Annual Progress Report summarises the activities of the European Communities R&D Programme on Decommissioning of Nuclear Installations for the year 1991. (For the first report s. Ref. /I/). This programme was adopted by the EC Council in March 1989 /2/ to find "effective solutions which are capable of ensuring the safety and protection of both mankind and its environment against the potential hazards in decommissioning". As a large number of older nuclear facilities will be taken out of service in the next ten years, the public, the industry and national regulations are becoming increasingly concerned over the occupational doses, environmental hazards and the costs which could be incurred in the decommissioning of such plants. The European Community, well aware of these concerns, has since 1978 operated and financed research programmes in this field. The 1989-1993 programme concerns the following areas: A. Research and development projects concerning the following subjects: Area N° 1: Long-term integrity of building and systems; Area N° 2 Decontamination for decommissioning purposes; Area N° 3 Dismantling techniques; Area N° 4 Treatment of specific waste materials: steel, concrete and graphite; Area N° 5 Qualification and adaptation of remote-controlled semi-autonomous manipulator systems; Area N° 6: Estimation of the quantities of radioactive wastes arising from the decommissioning of nuclear installations in the Community. B. Identification of guiding principles relating to: the design and operation of nuclear installations with a view to simplifying their subsequent decommissioning, the decommissioning operations with a view to making occupational radiation exposure as low as reasonably achievable, the technical elements of a Community policy in this field. G Testing of new techniques in practice: pilot projects, alternative tests, staff secondment. The research is carried out by public organisations and private firms in the Community under cost- sharing contracts with the Commission of the European Communities. The Commission budget for this five-year programme amounts to 33.8 million ECU. This includes 2.3 million ECU voted by the European Parliament as additional funding for 1991, thus permitting a second call for research proposals /3/ for Area C (except pilot projects) of the programme. Of the 26 research proposals submitted to this call for proposals, 11 were selected; contract negotiations for these new projects were completed and most of them were signed before the end of 1991. As these and other contracts which become effective after July 1991 had not yet produced significant results, only the objectives, scope and work programme are reported in the following. Work on the first phase of the four pilot dismantling projects was successfully completed and the respective contracts were amended to accommodate the work programme for the second phase. Also during 1991, Part B "Identification of guiding principles" was launched and a major action to collect data relevant to cost, occupational doses, working time and waste arisings was commissioned. Both activities are introduced briefly in this report. I am most grateful to the contractors who have produced most of the substance of this report and who, this year, provided a particular effort to make its timely publication possible. For its compilation and editing I wish to thank my colleagues, Messrs R Bisci, B Huber, K Pflugrad, E Skupinski and R Wampach. /Co_-_ 4_>--vvn^rv R SIMON Head of the Programme References /l/ "The Community's research and development programme on decommissioning of nuclear installations (1989-1993)". Annual progress report 1990. EUR 14227. HI Council Decision of 14 March 1989 adopting a research and technological development programme for the European Atomic Energy Community in the field of the decommissioning of nuclear installations. OJ No. L 98, 11.04.1989, p. 33. /3/ Commission Communication concerning the research programme on the decommissioning of nuclear installations (19S9 to 1993). Call for research proposals. OJ No. C 24, 31.01.1991, p. 8. IV - CONTENTS SECTION A: RESEARCH AND DEVELOPMENT PROJECTS Page 1. AREA No. 1: LONG-TERM INTEGRITY OF BUILDINGS AND SYSTEMS 1 1.1. Examination and long-term assessment of nuclear power structures 2 2. AREA No. 2: DECONTAMINATION FOR DECOMMISSIONING PURPOSES 7 2.1. On-line decontamination of complex components for unrestricted release, using ultrasonic waves in a flowing aggressive chemical agent 8 2.2. Development and optimisation of an easy-to-process electrolyte for electrochemical decontamination of stainless steel 13 2.3. Microwave system to scarify concrete surfaces 19 2.4. Decontamination of large-volume nuclear components using foams 24 2.5. Decontamination of an evaporator of a pilot reprocessing plant (EUREX-Saluggia) using a chemical agent dispersed as fog -¿1 2.6. Decontamination technique using a dispersed chemical agent .... 32 3. AREA No. 3: DISMANTLING TECHNIQUES 37 3.1. Effectiveness and long-term behaviour of cleanable high efficiency aerosol filters 38 3.2. Abrasive water jet cutting technique from the stage of laboratory into real application 44 3.3. Steel cutting using linear-shaped charges 52 3.4. Evaluation of the segmentation by various cutting techniques (plasma torch, arc saw, circular disc, etc) 58 3.5. Underwater thermal cutting techniques and associated remote- controlled manipulator systems 64 3.6. Development of a plasma arc torch and control/monitoring technique for the internal cutting of small bore pipework 70 3.7. Development of a steel cable to cut highly reinforced concrete with minimised water consumption 7^ 3.8. Assessment of state-of-the-art CO laser technology as an improved dismantling tool 76 3.9. Cutting of C02 primary circuit pipes of G2/G3 reactors using explosive charges 85 3.10. Underwater laser cutting of metal structures 88 3.11. Optimisation of plasma torch electrode design for nuclear dismantling tasks 94 v - 4. AREA No. 4: TREATMENT OF SPECIFIC WASTE MATERIALS: STEEL, CONCRETE AND GRAPHITE 97 4.1. Industrial-scale melting of tritium-containing steel from nuclear installations 98 4.2. Development of a process for volume reduction of contaminated/activated concrete waste including pilot-scale testing with active waste 105 4.3. Treatment and conditioning of radioactive graphite from nuclear installations 4.4. Recycling of activated/contaminated reinforcement metal in concrete 110 116 4.5. Investigations on recycling of radioactive non-ferrous aluminium and copper by melting process 120 5. AREA No. 5: QUALIFICATION AND ADAPTATION OF REMOTE- CONTROLLED SEMI-AUTONOMOUS MANIPULATOR SYSTEMS 127 5.1. Robotic system for dismantling of the process cell of a reprocessing plant 128 5.2. Design, construction and testing of a manipulator for removing slag, measuring temperature and taking samples during melting of radioactive metal 133 5.3. Telerobotic monitoring, decontamination and size reduction system - TMDSRS 139 5.4. Adaptation and testing of a remotely-controlled underwater vehicle 145 5.5. Test of long-range teleoperated handling equipment with different tools for concrete dismantling and radiation protection monitoring 148 5.6. Underwater qualification of RD 500 manipulator 154 6. AREA No. 6: ESTIMATION OF THE QUANTITIES OF RADIOACTIVE WASTE ARISING FROM DECOMMISSIONING OF NUCLEAR INSTALLATIONS IN THE COMMUNITY 159 6.1. Methodology to evaluate the risks of decommissioning operations on nuclear plants 160 6.2. Doses due to the reuse of very slightly radioactive steel • • 166 6.3. Quick measuring methods of radionuclides in materials and wastes during decommissioning of nuclear installations 172 6.4. Radiological aspects of recycling concrete debris from dismantling of nuclear installations 176 6.5. Definition of reference levels for exemption of concrete coming from dismantling 18_ VI 6.6. The characterisation and determination of radioactive waste from decommissioning 185 6.7. Quantification of activity levels and optimisation of dose rate management to prepare stage 3 decommissioning of gas-cooled reactors 192 6.8. Decommissioning costs for nuclear installations 197 6.9. Development of a prototype apparatus
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