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Annual Scientific Report 1974 ROYAUME DE BELGIQUE KONINKRIJK BELGIE MINISTERE DES AFFAIRES ECONOMIQUES MINISTERS VAN EKONOMISCHE ZAKEN ET DE L'ENERGIE EN ENERGIE BLG 506 ANNUAL SCIENTIFIC REPORT 1974 EDITED BY R. BILLIAU, K. BOBIN, G.MICHIELS, J. PROOST k 1 moF SS I P CENTRE D'ETUDE DE L'ENERGIE NUGLEAIRE STUDiECENTRUM VOOR KERNENERGIE Head Office S.C.K./C.E.N. E. Plaskylaan, 144, avenue E. Plasky B - 1040 Brussels (Belgium) Laboratories S.C.K./C.E.N. Boeretang 200 B-2400 Mol (Belgium) ANNUAL SCIENTIFIC REPORT 1974 BLG 506/75 Previous Annual Scientific Reports 1966: D/79/67 1967: D/55/68 1968: D/68/69 1969: D/69/70 1970: BLG 460 1971: BLG 467/72 1972: BLG 481/73 1973: BLG 495/74 BLG 506/75 ANNUAL SCIENTIFIC REPORT 1974 EDITED BY R. BILLIAU, K. BOBIN, G. MICHIELS, J. PROOST CONTENTS Chapter 1 — SODIUM COOLED FAST REACTORS INTRODUCTION 1-1 1.1. MIXED OXIDE FUEL 1-2 1.1.1. Mixed oxide fuel preparation techniques 1-3 1.1.2. Mixed oxide fuel irradiation programme 1-4 1.1.3. Fuel-clad compatibility 1-8 1.2. CARBIDE FUEL 1-9 1.2.1. Studies on uranium carbides 1-9 1.2.2. Mixed carbides 1-11 1.2.3. Reactor physics studies 1-14 1.3. FUEL ASSEMBLIES 1-15 1.3.1. Coolant mixing in fuel rod bundles 1-15 1.3.2. Fuel assembly testing in the Na3 loop 1-15 1.3.3. Post-endurance analyses on assembly components tested in Na3 1-16 1.4. DISPERSION-STRENGTHENED FERRITIC STEELS 1-17 1.4.1. Fabrication of dispersion-strengthened ferritic steels 1-17 1.4.2. Properties of dispersion-strengthened ferritic steels 1-19 1.4.3. Behaviour of ferritic steels 1-19 1.5. REPROCESSING 1-21 1.5.1. Fuel disaggregation by molten salts 1-22 1.5.2. Use of heat transfer salt (HTS) in the fast reactor fuel cycle 1-22 1.5.3. Purification of reprocessing off-gases 1-23 1.6. FAST REACTOR PHYSICS 1-28 1.6.1. Cross-section libraries 1-28 1.6.2. Reactor codes 1-28 1.6.3. Reactor materials dosimetry and cross-section valida- tion experiments 1-29 1.7. FAST REACTOR SAFETY AND INSTRUMENTATION 1-35 1.7.1. Fast reactor safety 1-36 1.7.2. Instrumentation 1-38 1.8. SODIUM COOLANT STUDIES 1-40 1.8.1. Operation of the sodium loops 1-40 1.8.2. Sodium chemistry and mass transfer studies 1-43 Chapter 2 — GAS COOLED REACTORS INTRODUCTION 2-1 2.1. GAS COOLED FAST REACTORS 2-1 2.1.1. Participation to the Gas Breeder Reactor Association 2-2 2.1.2. The "GSB" experiment 2-2 2.2. HIGH TEMPERATURE REACTORS 2-4 2.2.1. Fuel development for high temperature reactors 2-5 2.2.2. Helium loop "Hel" for participation and corrosion tests 2-6 2.2.3. Development of HTR irradiation devices 2-6 Chapter 3 — LIGHT WATER REACTORS INTRODUCTION 3-1 3.1. THE BR3 REACTOR 3-1 3.1.1. BR3/Cpre3 3-2 3.1.2. Plant operation 3-3 3.1.3. BR3/Core4 3-6 3.2. R & D WORK ON LIGHT WATER REACTOR FUELS 3-6 3.2.1. Gamma spectrometry development 3-7 3.2.2. Fuel densification 3-7 3.3.3. Burnable poisons v- 3-7 3.2.4. Irradiation tests in BR2 3-9 3.3. DEMONSTRATION PROGRAMME ON PLUTONIUM RECYCLING IN LWR'S 3-9 3.3.1. BR3 3-9 3.3.2. SENA 3-11 3.3.3. DODEWAARD 3-12 3.3.4. GARIGLIANO 3-13 3.4. HIGH PRESSURE WATER LOOP "ETL" FOR TEST- ING OF PWR AND BWR FUEL ASSEMBLIES 3-14 3.5. VIBRATION OF. REACTOR INTERNALS 3-14 3.6. DEVELOPMENT OF DEVICES FOR IRRADIATIONS OF LWR-FUELS IN BR2 3-15 Chapter 4 — APPLIED NUCLEAR RESEARCH 4.1. WASTE CONDITIONING AND DISPOSAL 4-1 4.2. SAFEGUARDS PROJECT 4-2 4.3. ACTINIUM-THORIUM 4-4 4.4. FUSION RESEARCH AND LITHIUM TECHNOLOGY 4-6 Chapter 5 — BASIC AND EXPLORATORY RESEARCH INTRODUCTION 5-1 5.1. SOLID STATE PHYSICS 5-3 5.1.1. Electrical properties of semiconductors 5-3 5.1.2. Magnetism and neutron scattering experiments 5-4 5.1.3. Electron microscopy 5-8 5.1.4. Relaxation effects 5-11 5.1.5. Resistometric study of structural defects in metals and alloys 5-14 5.1.6. Inert gases in metals and alloys 5-15 5.1.7. Quantum theory of solids 5-15 5.2. NUCLEAR PHYSICS 5-18 5.2.1. Experimental nuclear physics 5-18 5.2.1.1. Neutron spectrometry 5-18 5.2.1.2. Fission physics and chemistry 5-20 5.2.1.3. Nuclear spectroscopy 5-22 5.2.1.4. Instrumentation 5-24 5.2.2. Theoretical nuclear physics 5-25 5.3. RADIOBIOLOGY 5-26 5.3.1. Acute effects of radiation 5-26 5.3.2. Long-term effect of ionizing radiation 5-27 5.3.3. Genetic effects of radiations and chemicals in mam- mals 5-32 5.3.4. Study of integration, replication and biological ex- pression of foreign DNA administrated to different organisms 5-35 5.3.5. Radioactive contamination of the environment and the metalbolism of some radioelements 5-36 5.3.6. Non-radioactive contamination of the environment 5-38 5.4. EXPLORATORY RESEARCH PROGRAMMES 5-39 5.4.1. Exploratory research in chemistry 5-39 5.4.2. Exploratory research in metallurgy 5-40 5.4.3. Reactor physics and computational methods 5-40 5.4.4. Exploratory research in technology 5-42 Chapter 6 — NON-NUCLEAR RESEARCH AND DEVELOPMENT INTRODUCTION 6-1 6.1. AIR POLLUTION MEASUREMENT PROGRAMMES 6-2 6.2. MEDICAL AND BIOLOGICAL ASPECTS OF POLLU- TION 6-4 6.3. POLLUTION ABATEMENT AND WASTE HANDLING 6-5 6.4. FUEL CELLS AND APPLIED ELECTROCHEMISTRY 6-8 Chapter 7 — THE BR2 MATERIALS TESTING REACTOR AND ASSOCIATED FACILITIES INTRODUCTION 7-1 7.1. DEVELOPMENT, CONSTRUCTION AND OPERA- TION OF IRRADIATION DEVICES FOR THE BR2 REACTOR 7-2 7.2. BR2 TESTING AND COMMISSIONING SERVICE 7-10 7.3. OPERATION AND UTILIZATION OF THE REACTOR 7-11 7.4. HOT LABORATORIES 7-25 7.5. STUDIES IN SUPPORT OF THE IRRADIATION PRO- GRAMME AND OF REACTOR OPERATION 7-26 ~\ Chapter 8 — SUPPORTING. ACTIVITIES ;AND SERVICES 8.1. REACTORS AND APPLIED MATHEMATICS 8-1 8.2. MATERIALS RESEARCH 8-4 8.3. SUPPORTING CHEMISTRY SERVICES 8-5 8.4. MEDIUM ACTIVITY ^LABORATORIES (LMA) 8-7 8.5. PROTECTION 8-8 8.6. RADIOACTIVE WASTE PROCESSING 8-15 8.7. TECHNICAL SUPPORT 8-17 8.8. UNDERLYING TECHNOLOGY DEVELOPMENT 8-19 APPENDICES Appendix 1 — PUBLICATIONS 3 Appendix 2 — PAPERS PRESENTED AT COLLOQU1A, SEMINARS AND SYMPOSIA 14 Appendix 3 — THESES BY MEMBERS OF S.C.K./C.E.N. 24 Appendix 4 — PATENTS APPLIED FOR ANDiGRANTED IN BELGIUM AND IN OTHER COUNTRIES 25 Appendix 5 — SEMINARS HELD AT S.C.K./C.E.N. 28 Appendix 6 — EXTERNAL RELATIONS 31 Appendix 7 — PERSONNEL OFFICE 32 Appendix 8 — FINANCE 33 Appendix 9 — LIST OF ABBREVIATIONS 35 Chapter 1 SODIUM COOLED FAST REACTORS INTRODUCTION During 1974, S.C.K./C.E.N.'s programme on sodium cooled fast reactors was pursued as part of the Belgian contribution to the DEBENELUX fast breeder project. Within this project active collaboration is achieved between the utility companies, industry, government and research centres of the participating countries. Information on worldwide LMFBR development work is exchanged with the Atomic Energy Authority of the United Kingdom (UKAEA), the United States Energy Research and Development Administration (ERDA) and the Japanese Power Reactor and Nuclear Fuel Development Corporation (PNC). The construction of the SNR 300 fast reactor prototype plant at Kalkar, started in 1973, has been continued during 1974. Mainly as a result of additional safety studies and discussions, the initial target date (January 1980) for testing and commissioning of the plant, has been delayed for some months. This delay as well as price increases result in a cost increment which is estimated at present at 250 M DM. Associated R & D work mainly carried out by industry and co-ordinated within the "Bauzugehöriges Forschungs- und Entwicklungsprogramm", has allowed the elaboration of detailed specifications for most of the reactor components. Some of these are now being manufactured; for others, extensive test programmes are running on prototype equipment for detailed assessment of performance or optimizing of fabrication parameters. The DEBENELUX project also includes studies of a more general nature, which aim at long-term improvements in view of commercial development of fast breeder reactors. These are now progressively oriented towards the SNR 2 demonstration plant proposed to be constructed in the period 1980-1985 on behalf of ESK (Europäische Schnellbrüter-Kernkraftwerkgesellschaft), an international utility association of SBK (grouping RWE, SEP and SYNATOM), EdF, ENEL and CEGB. For the SNR 2 project, a conceptual design study has been completed by INTERATOM, which has also received a contract from ESK for a predesign study to be carried out during 1975. The tentative time schedule for SNR 2 might be altered as a result of continued negotiations with all partners involved both on the organizational and financial-economic aspects of the project, as well as on technical design features of the plant itself. As in the past, S.C.K./C.E.N. continued to focus its R & D work related to sodium cooled fast reactors on the fuel cycle and on some fields in which it has built up very valuable experience.
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