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Description of the Advanced Gas Cooled Type of Reactor (AGR)

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Description of the Advanced Gas Cooled Type of Reactor (AGR) Nordisk Nordisk Poh|oismaincn Nordic kerne- karn- ydin- nuclear sikkerheds- sakcrhets- turvallisuus- safely forskning forskning lutkimus research KAK-2 NKS/RAK2(96)TR-C2 DK9700041 Description of the Advanced Gas Cooled Type of Reactor (AGR) Erik Nonbel Riso National Laboratory Roskilde, Denmark November 1996 Abstract The present report comprises a technical description of the Advanced Gas cooled Reactor (AGR), a reactor type which has only been built in Great Britain 14 AGR reactors have been built, located at 6 different sites and each station is supplied with twin-reactors The Torness AGR plant on the Lothian coastline of Scotland, 60 km east of Edinburgh, has been chosen as the reference plant and is described in some detail Data on the other 6 stations, Dungeness B, Hinkley Point B, Hunterston B, Hartlepool, Heysham I and Heysham II, are given only in tables with a summary of design data Where specific data for Torness AGR has not been available, corresponding data from other AGR plants has been used, primarily from Heysham II, which belongs to the same generation of AGR reactors The information presented is based on the open literature The report is written as a part of the NKS/RAK-2 subproject 3 "Reactors in Nordic Surroundings", which comprises a description of nuclear power plants neighbouring the Nordic countries NKS/RAK-2(96)TR-C2 ISBN 87-550-2264-2 Graphic Service, Riso, 1996 Tlic report can be obtained from NKS Secretariat Phone +45 46 77 40 45 POBox49 Fax +45 46 35 92 73 DK-4000 Roskildc hUp/Auuv nsoc dk/nks Denmark e-mail anncttc.lemmensfr nsoe dk -3- Contents 1 INTRODUCTION 8 2 SUMMARY OF DESIGN DATA 10 3 SITE AND REGION 13 3.1 Selection of the site 13 4 SAFETY CRITERIA 14 5 TECHNICAL DESCRIPTION AND DESIGN EVALUATION 15 5.1 Plant arrangement 15 5.2 Buildings and structures 16 5.3 Reactor core and other reactor vessel internals 17 5.3.1 Mechanical design... , 18 5.3.2 Nuclear design 20 5.3 3 Thermal and hydraulic design 28 5.4 Reactivity control system 30 5.4.1 Secondary shutdown system 31 5.5 Reactor main coolant system 32 5.5.1 Reactor coolant piping 32 5.5.2 Reactor coolant pumps 32 5 5.3 Steam generators 35 5.6 Residual heat removal systems 38 5.7 Emergency core cooling systems 40 5.8 Containment systems 42 5.8.1 Overall system information 42 5.8.2 Containment structure 43 5.8.3 Containment penetrations 44 5.8.4 Containment liner 44 5 8.5 Pressure reducing systems 45 5.9 Steam and power conversion systems 46 5.9.1 Turbine-generator ,. ....46 5.9.2 Main steam supply system 47 -4- 5.10 Fuel and component handling and storage systems 48 5.11 Radioactive waste systems 50 5.11.1 Liquid waste system 50 5.11.2 Gaseous waste system 50 5.11.3 Solid waste system 51 5.12 Control and instrumentation systems 53 5.12.1 Protection system 53 5.12.2 Regulating system 54 5.13 Electrical power systems 56 6 FIRE PROTECTION, WIGNER ENERGY AND GRAPHITE OXIDATION 58 7 PLANT PERFORMANCE DURING NORMAL OPERATION 60 8 PLANNING AND ORGANISATION 63 9 REFERENCES 65 10 APPENDICES 66 APPENDIX A: DUNGENESS B AGR STATION 67 APPENDIXB : HINKLEY POINTB AGR STATION 71 APPENDIXC : HUNTERSTON B AGR STATION 75 APPENDIX D: HARTLEPOOL AGR STATION 77 APPENDIXE : HEYSHAM AGR STATION 83 -5- List of Figures Figure 1.1. AGR stations in Great Britain 9 Figure 3.1. Site of Torness Nuclear Power Station 13 Figure 5.1. Components of a typically AGR nuclear power station 15 Figure 5.2. Layout of building structures 16 Figure 5.3. Main components of reactor ,. 17 Figure 5.4. Gas baffle with gas flow paths 19 Figure 5 5. Interconnection of graphite bricks with keys,. 21 Figure 5 6. Core layout - nearly 1/4 core symmetry. 22 Figure 5.7. Dimensions of an AGR fuel element. 24 Figure 5.8 AGR fuel element 25 Figure 5.9 Detailed view of AGR fuel element 26 Figure 5 10 Refuelling machine 27 Figure 5.11. Gas flow distribution in the core and vessel 28 Figure5 12. AGR control rod 30 Figure 5.13. AGR gas circulator 34 Figure 5.14. The four boiler quadrants in the AGR 35 Figure 5.15. AGR boiler unit 36 Figure 5.16. Diverse boiler-feed systems 38 Figure 5.17. Decay heat and emergency boiler feed system .39 Figure 5.18. The stressing gallery for the tendons at the top of the vessel 43 Figure 5 19. Pressure vessel with penetrations 45 Figure 5.20. Location and size of fuel assembly/fuel element 48 Figure 5.21. Fuel route from loading of new fuel to unloading of irradiated fuel 49 Figure 5.22. Electrical system 56 Figure 6.1. Accumulation of stored energy in graphite, (Ref. 6) 58 Figure 8.1. AGR average load factors 63 Figure 8.2 Load factors for Torness AGR station 64 Figure 10.1. Location of Dungeness Nuclear Power Station 67 Figure 10.2. Load factors for Dungeness B AGR station 70 Figure 10.3 Location of Hinkley Point Nuclear Power Plant 71 Figure 10.4. Load factors for Hinkley Point B AGR station 74 -6- Figure 10.5. Location of Hunterston Nuclear Power Plant 75 Figure 10 6. Load factors for Hunterston B AGR station..,.., 76 Figure 10 7 Location of Hartlepool Nuclear Power Station 77 Figure 10.8. Dimensions of single- and multi-cavity pressure vessels 78 Figure 10 9 Pressure vessel layout for Hartlepool AGR 79 Figure 10.10. Load factors for Hartlepool AGR station 80 Figure 10.11. Location of Heysham AGR station 83 Figure 10.12. Load factors for Heysham I AGR station 84 Figure 10.13. Load factors for Heysham II AGR station 84 Figure 10.14. Comparison of layout of Heysham I and Heysham II AGR stations 85 -7- List of Tables Table 1.1. AGR stations in operation 9 Table 2.1. Summary of design data for Torness AGR nuclear power station 10 Table 5.1. Design data for pressure vessel 18 Table 5.2. Main design data for the core 20 Table 5.3. Main design data for fuel elements 23 Table 5.4. Heat balance for an AGR plant 29 Table 5.5. Design data for gas circulators 32 Table 5.6. Design data for boilers 36 Table 5.7. Design data for turbine plant 46 Table 7.1. AGR Construction times and year for start of operation 60 Table 10.1. Summary of design data for Dungeness AGR nuclear power station 68 Table 10.2. Summary of design data for Hinkley Point AGR nuclear power station 72 Table 10.3. Summary of design data for Hartlepool AGR nuclear power station 81 Table 10.4. Comparison of main data for all 7 sites of AGR's in UK 86 -8- 1 Introduction A new four-year nuclear research program within the framework of NKS, Nordic Committee for Nuclear Safety Research, was started in 1994 as a follow-on to several preceding Nordic programmes. Joint research in this field is of interest for the five Nordic countries who have similar needs for maintaining their nuclear competence in the field of reactor safety and waste management, and who are exposed to the same outside risks from reactors in neighbouring countries, from nuclear powered vessels, and from risks of contamination of terrestrial and aquatic areas. This report is written as a part of the NKS/RAK-2 subproject 3: "Reactors in Nordic Surroundings", which comprises a description of nuclear power plants neighbouring the Nordic countries. The main objective of the project has been to investigate, collect, arrange and evaluate data of reactors in the Nordic neighbourhood to be used by the Nordic nuclear preparedness and safety authorities. In the former NKS project, SIK-3, reactors within 150 km from the border of a Nordic country were treated, but it was decided to add a description of the British reactors, although the minimum distance to a Nordic border, the Norwegian, is about 500 km. The present report comprises a technical description of the Advanced Gas cooled Reactor (AGR), a reactor type which has only been built in Great Britain. 14 AGR reactors have been built, located at 6 different sites and seven stations, Figure 1.1. and Table 1.1. Each station is supplied with twin-reactors, the site of Heysham has two stations Heysham I and Heysham II. Dungeness B was the first commercial AGR plant to be ordered and it represents together with Hinkley Point B and Hunterston B the first generation of AGR's. All three stations are almost identically and are therefore called sister plants. Hartlepool and Heysham I represent a modified version of first generation AGR's with a so-called multi-cavity pressure vessel, while Torness and Heysham II constitute second generation of AGR type of reactor with improved safety features. The Torness AGR plant on the Lothian coastline of Scotland, 60 km east of Edinburgh, has been chosen as the reference plant and is described in some detail. Data on the other 6 stations are given only in tables with a summary of design data in appendix A-E. Where specific data for Torness AGR has been unavailable, corresponding data from other AGR plants has been used, primarily from Heysham II, which belongs to the same generation of AGR reactor. The information presented is based on the open literature and the content of the report follows the format agreed on in the SIK-3 project (Ref.
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