Advanced Fuel CANDU Reactor - SNC-Lavalin /media/Files/S/SNC-Lavalin/... The Advanced Fuel CANDU...

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Transcript of Advanced Fuel CANDU Reactor - SNC-Lavalin /media/Files/S/SNC-Lavalin/... The Advanced Fuel CANDU...

  • Advanced Fuel CANDU Reactor Technical Summary

  • CANDU BRAND IS RECOGNIZED AS ONE OF THE TOP 10 MAJOR ENGINEERING ACHIEVEMENTS OF THE PAST CENTURY IN CANADA

    31 87%

    CANDU REACTORS IN THE WORLD OPERABLE OR BEING REFURBISHED

    CANDU REACTORS CONSISTENTLY RANK AS TOP PERFORMERS AND HOLD THE WORLD RECORD FOR LONGEST CONTINUOUS OPERATION

    EXCELLENT PERFORMANCE OF THE CANDU 6 FLEET WITH AN AVERAGE LIFETIME CAPACITY FACTOR OF OVER

    CANDU REACTORS CAN BE EASILY ADAPTED FOR FLEXIBLE FUEL CYCLE OPTIONS

    SNC-Lavalin’s Nuclear team provides leading nuclear technology products and full-service solutions to nuclear utilities around the globe. Our team of 1,200 engineering, procurement, construction and project management experts offer customized operations, maintenance and plant life management services, including waste management and decommissioning. Our experts in nuclear steam plant and balance of plant engineering carry out life extension projects, and design and deliver state-of-the-art CANDU® reactors, which are capable of operating on many types of fuel including natural uranium, recycled uranium (RU), thorium and mixed oxide (MOX) fuel.

    We are the stewards of CANDU technology. The 47 heavy water reactors in operation or under life extension are based on our CANDU design and are an important component of clean air energy programs

    on four continents. CANDU technology provides safe, reliable, affordable and CO2-free energy to support the economic viability of businesses and quality of life for consumers in Canada, Romania, Korea, China and Argentina. CANDU reactors have an outstanding performance record, taking four of the top five places on Nuclear Engineering International’s 2013 Top Lifetime Performers List.

    Continuing a tradition of building nuclear reactors for over 50 years, we make significant contributions to the nuclear energy field. CANDU technology is the basis for Canada’s nuclear power program and has been adopted in the nuclear power programs of many countries. The 11 CANDU 6 units, in five countries, have consistently delivered an average lifetime capacity factor of over 87%.

    Company Profile

    Noteworthy facts about the CANDU reactor fleet

  • Advanced Fuel CANDU Reactor ............................................................. 4 Safety in Depth.........................................................................................................4 Proven..........................................................................................................................4 Economically Enabling the Fuel Cycle ............................................................4 CANDU: A Success Story ..........................................................................5 Proven Delivery Track Record ............................................................................6 Development of AFCR Technology ...................................................................6 Technical Description of the AFCR .........................................................8 High Level Design Specifications ......................................................................8 Main Characteristics of the AFCR .....................................................................8 AFCR Advantages for Advanced Fuel Cycles ....................................11 Fuel .............................................................................................................................12 Direct use of Recycled Uranium Fuel ............................................................12 Low-Enriched Uranium (LEU) and Thorium (Th) Fuel ............................ 13 Economic Value Using Advanced Fuel Cycles ........................................... 13 Safety is at Our Core .............................................................................. 14 AFCR Safety Design Philosophy ..................................................................... 14 AFCR Safety Goals .............................................................................................. 15 Defence-in-Depth ................................................................................................. 15 Designed Based on Post-Fukushima Requirements ................................17 AFCR Fundamental Safety Function Features ........................................ 18 Reactivity Control ................................................................................................ 19 Fuel Cooling ...........................................................................................................20 Spent Fuel Cooling .............................................................................................. 22 Containment .......................................................................................................... 23 Reliable and Robust Design .................................................................. 24 Fail Safe Design .................................................................................................... 24 Single Failure Criterion ....................................................................................... 24 Diversity ................................................................................................................... 24 Reliability ................................................................................................................. 24 Grouping and Separation ................................................................................... 25 Seismic Qualification .......................................................................................... 25 Environmental Qualification............................................................................. 25 Ageing ....................................................................................................................... 25 Radiation Protection ............................................................................................ 26 Human Factors ...................................................................................................... 26 Out-of-Core Criticality Safety .......................................................................... 26 Provision for In-Service Testing, Maintenance, Repair, Inspection and Monitoring ................................................................................. 26 Severe Accident Recovery and Heat Removal System (SARHRS) .... 27 Complementary Design Features to Enhance Safety Provisions ... 27 Passive Water Make-up to the Calandria Vessel ...................................... 28 Passive Calandria Vault Water Make-up ...................................................... 28 Passive Containment Heat Removal System (PCHRS).......................... 28 Emergency Containment Filtered Venting System (ECFVS) ................ 29 Safety and Safety Support Systems ................................................... 30 Safety Systems .....................................................................................................30 Shutdown Systems .............................................................................................30 Emergency Core Cooling System ..................................................................30 Containment System .......................................................................................... 31

    Safety Support Systems ................................................................................... 31 Emergency Water Supply System ................................................................. 31 Raw Service Water and Recirculated Cooling Water Systems ........... 32 Emergency Power Supply System................................................................. 32 AFCR Plant Siting and Layout ............................................................... 33 Reactor Building ................................................................................................... 35 Service Building .................................................................................................... 36 Turbine Building .................................................................................................... 36 Nuclear Systems ...................................................................................... 37 Heat Transport System...................................................................................... 38 Steam Generators ................................................................................................ 39 Heat Transport System Pumps ...................................................................... 39 Heat Transport Pressure and Inventory Control System ......................40 Moderator System ...............................................................................................40 Reactor Assembly ................................................................................................ 41 Reactor Power Control .......................................................................................42 Fuel Channel Assembly .....................................................................................42 Fuel Handling and Storage System ...............................................................43 Turbine-Generator System ....................................................................44 Turbine Generators ..............................................................................................44 Main Steam System ............................................................................................44 Condensing System.............................................................................................45 Condensate and Feedwater System ..........................................