Advanced Fuel CANDU Reactor - Home | SNC- Advanced Fuel CANDU Reactor (AFCR ) is a Generation III advanced fuel-efficient 740 MWe-class Pressurized Heavy Water Reactor developed by Candu Energy, a member of the SNC-Lavalin Group and China National Nuclear ...

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<ul><li><p>Advanced Fuel CANDU ReactorTechnical Summary</p></li><li><p>CANDU BRAND IS RECOGNIZED AS ONE OF THE TOP 10 MAJOR ENGINEERING ACHIEVEMENTSOF THE PAST CENTURY IN CANADA</p><p>3187%</p><p>CANDU REACTORSIN THE WORLDOPERABLE OR BEING REFURBISHED </p><p>CANDU REACTORS CONSISTENTLY RANK AS TOP PERFORMERS AND HOLD THE WORLD RECORD FOR LONGEST CONTINUOUS OPERATION</p><p>EXCELLENTPERFORMANCEOF THE CANDU 6 FLEET WITHAN AVERAGE LIFETIMECAPACITY FACTOR OF OVER</p><p>CANDU REACTORS CAN BE EASILY ADAPTED FORFLEXIBLE FUEL CYCLE OPTIONS</p><p>SNC-Lavalins 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.</p><p>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 </p><p>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 Internationals 2013 Top Lifetime Performers List.</p><p>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 Canadas 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%.</p><p>Company Profile</p><p>Noteworthy facts about the CANDU reactor fleet</p></li><li><p>Advanced Fuel CANDU Reactor ............................................................. 4Safety in Depth.........................................................................................................4Proven..........................................................................................................................4Economically Enabling the Fuel Cycle ............................................................4CANDU: A Success Story ..........................................................................5Proven Delivery Track Record ............................................................................6Development of AFCR Technology ...................................................................6Technical Description of the AFCR .........................................................8High Level Design Specifications ......................................................................8Main Characteristics of the AFCR .....................................................................8AFCR Advantages for Advanced Fuel Cycles ....................................11Fuel .............................................................................................................................12Direct use of Recycled Uranium Fuel ............................................................12Low-Enriched Uranium (LEU) and Thorium (Th) Fuel ............................ 13Economic Value Using Advanced Fuel Cycles ........................................... 13Safety is at Our Core .............................................................................. 14AFCR Safety Design Philosophy ..................................................................... 14AFCR Safety Goals .............................................................................................. 15Defence-in-Depth ................................................................................................. 15Designed Based on Post-Fukushima Requirements ................................17AFCR Fundamental Safety Function Features ........................................ 18Reactivity Control ................................................................................................ 19Fuel Cooling ...........................................................................................................20Spent Fuel Cooling .............................................................................................. 22Containment .......................................................................................................... 23Reliable and Robust Design .................................................................. 24Fail Safe Design .................................................................................................... 24Single Failure Criterion ....................................................................................... 24Diversity ................................................................................................................... 24Reliability ................................................................................................................. 24Grouping and Separation ................................................................................... 25Seismic Qualification .......................................................................................... 25Environmental Qualification............................................................................. 25Ageing ....................................................................................................................... 25Radiation Protection ............................................................................................ 26Human Factors ...................................................................................................... 26Out-of-Core Criticality Safety .......................................................................... 26Provision for In-Service Testing, Maintenance, Repair, Inspection and Monitoring ................................................................................. 26Severe Accident Recovery and Heat Removal System (SARHRS) .... 27Complementary Design Features to Enhance Safety Provisions ... 27Passive Water Make-up to the Calandria Vessel ...................................... 28Passive Calandria Vault Water Make-up ...................................................... 28Passive Containment Heat Removal System (PCHRS).......................... 28Emergency Containment Filtered Venting System (ECFVS) ................ 29Safety and Safety Support Systems ................................................... 30Safety Systems .....................................................................................................30Shutdown Systems .............................................................................................30Emergency Core Cooling System ..................................................................30Containment System .......................................................................................... 31</p><p>Safety Support Systems ................................................................................... 31Emergency Water Supply System ................................................................. 31Raw Service Water and Recirculated Cooling Water Systems ........... 32Emergency Power Supply System................................................................. 32AFCR Plant Siting and Layout ............................................................... 33Reactor Building ................................................................................................... 35Service Building .................................................................................................... 36Turbine Building .................................................................................................... 36Nuclear Systems ...................................................................................... 37Heat Transport System...................................................................................... 38Steam Generators ................................................................................................ 39Heat Transport System Pumps ...................................................................... 39Heat Transport Pressure and Inventory Control System ......................40Moderator System ...............................................................................................40Reactor Assembly ................................................................................................ 41Reactor Power Control .......................................................................................42Fuel Channel Assembly .....................................................................................42Fuel Handling and Storage System ...............................................................43Turbine-Generator System ....................................................................44Turbine Generators ..............................................................................................44Main Steam System ............................................................................................44Condensing System.............................................................................................45Condensate and Feedwater System .............................................................45Instrumentation and Control .................................................................46AFCR Control Centres ........................................................................................47Reactor Regulating System ..............................................................................49Reactor Safety Instrumentation .....................................................................49Safety Monitoring .................................................................................................49Electrical Power System ........................................................................ 50</p><p>Conventional Plant Services ................................................................. 51Service Water Systems ...................................................................................... 51Heating, Ventilation and Cooling Systems .................................................. 51Fire Protection System....................................................................................... 51Radioactive Waste Management .......................................................... 52Modular Air-Cooled Storage (MACSTOR) ................................................... 52AFCR Project Delivery ............................................................................ 53Design Engineering .............................................................................................. 53Licensing ................................................................................................................. 53Configuration Management.............................................................................. 53Project Management .......................................................................................... 53Procurement ..........................................................................................................54Construction Programs ......................................................................................54Construction Strategy ........................................................................................54Operations and Maintenance ................................................................ 55Plant Performance .............................................................................................. 55Features to Enhance Operating Performance ........................................... 55Technology Transfer and Localization ......................................................... 56Program Details .................................................................................................... 56</p><p>Table of Contents</p><p>3AFCR Technical Summary</p></li><li><p>The Advanced Fuel CANDU Reactor (AFCR) is a Generation III advanced fuel-efficient 740 MWe-class Pressurized Heavy Water Reactor developed by Candu Energy, a member of the SNC-Lavalin Group and China National Nuclear Corporation.</p><p>Based on over 60 years of proven operational excellence of the CANDU reactor fleet and experience in design, construction, operation and maintenance, the AFCR incorporates the latest advanced features that enhance safety, economics and operation and maintenance ease of the plant.</p><p>Safety in Depth &gt; Active and passive systems &gt; Enhanced safety margins &gt; Robust safety system configuration &gt; Meets post-Fukushima and most recent </p><p>safety requirements </p><p>Proven &gt; Based on over 60 years of CANDU reactor design </p><p>and operational expertise worldwide &gt; Proven technology </p><p>Economically Enabling the Fuel Cycle</p><p> &gt; Advanced fuel flexibility; ability to efficiently use recycled uranium and thorium-based fuels</p><p> &gt; High capacity factors &gt; Designed for 60 year life</p><p>Advanced Fuel CANDU Reactor</p><p>4 AFCR Technical Summary</p></li><li><p>Canada is a nuclear technology development pioneer with over 60 years of expertise and continuous improvement in the advancement of peaceful uses of nuclear energy. Through its member company, Candu Energy Inc., SNC-Lavalin has the exclusive rights to deliver state-of-the-art CANDU reactors. </p><p>SNC-Lavalins Nuclear team provides leading nuclear technology products and full-service solutions to nuclear utilities around the globe. Our highly-skilled employees offer customized operations, maintenance and plant life management services, including waste management and decommissioning forcustomers worldwide. Our experts in nuclear steam plant (NSP) and balance of plant (BOP) engineering carry out life extension projects, and design and deliver CANDU reactors, which are capable of operating on many types of fuel including natural uranium, recycled uranium (RU), thorium and mixed oxide (MOX).</p><p>We develop products to deliver safe, reliable affordable and CO2-free energy with a vision to the future, while meeting the highest regulatory standards of the global nuclear industry.</p><p>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 Canadas nuclear power program and has been adopted in the nuclear power programs of several countries. </p><p>CANDU: A Success Story</p><p>CANDU Reactors Worldwide </p><p>Ontario, Canada</p><p>Argentina</p><p>Romania</p><p>South Korea </p><p>China</p><p>New Brunswick, Canada</p><p>5AFCR Technical Summary</p></li><li><p>Proven Delivery Track RecordCandu has achieved an...</p></li></ul>

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