Workshop GESEL - UFRJ: O presente e o futuro da energia nuclear no Brasil

Transcription

1 Workshop GESEL - UFRJ: O presente e o futuro da energia nuclear no Brasil Jürgen Czech Diretor Técnico AREVA NP Johannes Höbart Diretor Presidente AREVA Brasil Rio de Janeiro - Dezembro/2009

2 Introduction of AREVA Reactors Gen III+ Reactors Gen III+

3 AREVA provides solutions for CO 2 free electricity generation, transmission and distribution Nuclear 13,160M sales (2008) 75,400 people 100 countries Transmission & Distribution

4 Our renewable energies offers Wind power Bioenergies Hydrogen power Become a major player in offshore wind energy Design & deliver biomass fired power plants world wide Develop Hydrogen Technologies for market introduction AREVA Multibrid in Germany 5 MW off-shore specific design Selected for major wind parks covering nearly 270 turbines Rich and diversified experience: Brazil, Western Europe and India JV Adage with Duke Energy in the US One of the largest install base in the world: 2,900 MWe in 100 power plants Helion, France Strong R&D capability (PEM technology) Developing next generation Storage solutions

5 AREVA in Brazil ~2000 Employees Sites / Representations: São Paulo, Canoas, Itajubá, Rio de Janeiro, Angra dos Reis, Recife, Blumenau AREVA Koblitz AREVA Nuclear AREVA T&D

6 Nuclear Business in Brazil Several co-operation agreements in the nuclear field between France/Gerrmany and Brazil. Long lasting relationship with Brazilian Nuclear Industry (ETN, INB, NCP). ELETRONUCLEAR ANGRA 1 Supply of the new Steam Generators, fabrication in co-operation with NUCLEP. Supply March years service contract for reactorfloor services 4-years contract for inspections Additional services such as inspection and repair works with submarine-robotor SUSI Loose parts monitoring system, etc. 6

7 Nuclear Business in Brazil ANGRA 2 Construction of Angra 2 finished in 12/2000 Integrated maintenance services since 2001 Engineering services Engineering support operation Supply of spare and ware parts Supply of components to INB for fuel fabrication ANGRA 3 AREVA will provide the import portion (engineering, supply of components, I&C and commissioning).

8 Introduction of AREVA Reactors Gen III+ Reactors Gen III+

9 EPR TM Design December 2009

10 Agenda An evolutionary design Technical overview Best-in class safety Operational excellence Project certainty

11 Building on N4 and Konvoi Achievements N4 KONVOI High output (1475MWe) Large core (205 FA) High steam pressure (73,1 bar) Fuel building Computerized MCR Concrete cylindrical containment Military aircraft resistance 4 independent Safety trains No spray system Top mounted instrumentation Very High output: ~1600MWe Very large core: 241 FA Very High steam pressure: 77,2 bar Fuel building Computerized MCR Best-in-class APC 4x100% independent Safety trains DBA: No spray system Top mounted instrumentation The EPR design combines and improves on the best features of the French and German technologies

12 Evolutionary Improvement Based on Two Already Best-in-Class Technologies N4 and Konvoi topped the 2008 Nucleonics Week output ranking In TWh Chooz-B1 Isar-2 Brokdorf Civaux-2 Emsland Chooz-B2 Neckar-2 Philippsburg-2 N4 Konvoi N4 Konvoi N4 Konvoi 12,5 11,9 11,8 11,7 11,2 11,2 11,2 11,2 South Texas-1 Palo Verde-3 11,2 11,2 Other vendors

13 Agenda An evolutionary design Technical overview Best-in class safety Operational excellence Project certainty

14 EPR Primary Circuit

15 Core and Reactor Coolant System CORE Active height 420 cm Number of Fuel Assemblies 241 Fuel rod lattice 17 x Type of fuel assembly HTP X5 Average linear hear generation rate W/cm Number of Rod Control Cluster Assemblies 89 Core outlet temperature 330 C REACTOR COOLANT SYSTEM Operating pressure 15.5 MPa Design pressure 17.6 MPa Reactor Pressure Vessel inlet temperature C Reactor Pressure Vessel outlet temperature C Coolant flow per loop m³/h

16 Pressurizer and Steam Generators PRESSURIZER Total volume Number of safety valves Capacity of each safety valve Diverse depressurization valve (B&F, SA ) STEAM GENERATORS (SG) Number Heat transfer surface area per SG Tube outer diameter Water mass per SG on secondary side at full load Saturation pressure in the tube bundle Pressure at hot zero power 75 m t/h 900 t/h 4 ~ 7960 m mm ~ 80.9 t 7.8 MPa 9.0 MPa

17 Main Fluid Systems

18 Agenda An evolutionary design Technical overview Best-in class safety Operational excellence Project certainty

19 Key Safety Requirements are rising Worldwide trend of increasingly tight regulation aiming at lowering severe accident probability & mitigating the consequences of a severe accident as exemplified by: Issue in the US by NRC of new and more stringent regulations such as NUREG-0800 in 2007 about Uncontrolled release of any radioactive elements in case of accidents Publication in Europe by a group of European utilities of the EURs in 2001 Additionally, new external threats have emerged. As a result, Air Plane Crash (APC) protection is becoming a standard requirement worldwide: in the US - recent NRC ruling (July 09) on Full protection from Airplane Crash or any other external hazards, in Europe, where EUR have been applied, in a particularly stringent manner by STUK and HSE International requirements increase: The EPR is setting the standards for all future nuclear programs and is a future proof investment

20 EPR Reactor Safety Systems: Best-in-class APC resistance Reinforced Concrete Shield Building Annulus 1,8 m Prestressed Concrete Containment Building Steel Liner 1,8 m thick Outside Inside BASEMAT EPR Reactor, Fuel and two Safeguard Buildings are airplane crash resistant for both military and commercial aircraft: - No licensing delay - Bolstering public and political acceptance

21 P19 S1 EPR Reactor Safety Systems: Redundant and Diverse 4 100% capacity allows for preventive maintenance at power (n+2 concept) MHSI, LHSI/RHR, CCWS, ESW EFWS with passive headers Common cause failures safety system diversity: Every system has a diversified back-up External hazards through systematic physical separation of the safety systems Clear separation of redundancies with 4 Safeguard buildings ensures robustness against hazards (flooding, fire) and Airplane Crash Reactor building, Safeguard buildings and Fuel building on a single raft to cope with seismic and Airplane Crash loads Proven yet: evolutionary safety systems deliver high reliability levels Four Train concept and physical separation

22 EPR Reactor Safety Systems: General Organization General layout Division 2 Division 3 ESWS ESWS CCWS CCWS SIS/RHRS SIS/RHRS EFWS EFWS EFWS EFWS Control Control room room Division 1 Division 4 ESWS FW IRWST ESWS CCWS CCWS SIS/RHRS SIS/RHRS EFWS CHRS EFWS SPREADING CHRS SPREADING AREA AREA SL FW ESWS CCWS ESWS SIS/RHRS CCWS EFWS SIS/RHRS CHRS EFWS CHRS 4 train concept Four trains are provided to cope with safety analyses: 1 train is unavailable due to the Single Failure Criterion 1 train is unavailable due to the Preventive Maintenance 1 train is affected by the accident (e.g. LOCA) The 4th train is sufficient to cope with the accident EBS EBS FPCS Spent Fuel Storage Pool EBS FPCS FPCS Airplane crash protected buildings

23 EPR Reactor Safety Systems: SIS / RHRS overview

24 EPR Reactor Safety Systems: Backup by Diverse Functions Safety-grade system Diverse system functions MHSI Medium Head Safety Injection System LHSI Low Head Safety Injection System Fast Depressurization via Secondary Side + Pressurizer Relief Valve Medium Head Safety Injection System + Accumulator Injection System + + For small breaks: Secondary Side Heat Removal System Low Head Safety Injection System RHR Residual Heat Removal System FPC Fuel Pool Cooling System EFWS Emergency Feedwater System + Steam Relief Diesels TLOCC (Total Loss of Cooling Chain) RCS closed: Secondary Side Heat Removal System Fuel Pool Water Heatup with subsequent Steaming Primary side Bleed via the pressurizer safety valves SBO Diesels RPV closed: Secondary Side Heat Removal System RCS open: Medium Head Safety Injection System + Steaming into the Containment + Coolant make-up + Primary side Feed with MHSI RPV open: LHSI + Steaming Note: LHSI pumps cooling by chilled water

25 EPR Reactor Safety Systems: Diversified power source with back-ups Two independent grid connections to ensure power distribution diversity 4 independent safety divisions, 2 with additional SBO Diesel 400kV Main grid 110kV Stand-by grid Emergency power supply with interruption Uninterrupted Emergency power supply

26 EPR Reactor Safety Systems: Protection of the environment with Passive and Active Systems Passive System (Short-term) Active System (Long-term) IRWST Reactor pit & x x spray nozzles passive flooding device x CHRS (2x) spreading compartment in-containment refueling water storage tank Sacrificial concrete Spreading area melt flooding via cooling device and lateral gap x water level in case of water injection into spreading compartment FL flow limiter 1. Temporary retention in the reactor pit (gravity and metal gate) 2. Spreading in the large surface dedicated area (metal gate melting and gravity) 3. Flooding and cooling of the spreading area using IRWST (In-containment Refueling Water Storage Tank) 1. Removal of containment heat: Containment spray system Recirculation and coolant heat exchange Optimum severe accident mitigation prevent releases of hazardous material into the atmosphere and/or the soil

27 Agenda An evolutionary design Technical overview Best-in class safety Operational excellence Project certainty

28 EPR Reactor Operational excellence Accessible containment Short cool down time Safety trains online maintenance Optimization of outages: World class <11 days for refueling only outage <1 unplanned reactor trip/year 92%+ availability over 60 year design lifetime Large core & low power density Heavy neutron reflector Improved total plant net efficiency High output and availability Low fuel cost: Up to 15% less than other Gen3/3+ reactors Low O&M costs: Up to 20% less than other Gen3/3+ reactors Best-in-class OPEX The EPR reactor offers unparalleled operational performance with no compromise on safety

29 EPR Reactor Operational excellence: High availability Outage duration reduction: Preventive maintenance on safety trains (4x100% safety trains) Large set-down area to prepare outage work Fast cool-down of the core Short outages: Refuelling only outage <11 days High reliability: Normal refuelling outage Ten-years outage <16 days <40 days Proven evolutionary components based on hundreds of years of reactor operations and comprehensive R&D programs: improved reliability Capability to cope with various grid failure situations and loss of equipment without Reactor Trip (RT) <1 unplanned reactor trip/year EPR Reactor design target availability: 92%+

30 EPR Reactor Operational excellence: Best-in class OPEX Fuel costs Large core & low power density: 241 fuel assemblies, low linear heat rate (7,5% lower than N4) Heavy neutron reflector: reduced neutron leakage enabling 2-3% fuel savings (and reducing RPV irradiation) Improved total plant efficiency: best-in-class steam generators for high steam pressure Fuel costs up to 15% lower than other Gen3/3+ reactors O&M costs High output and availability of a single unit reduce O&M cost/mwh Proven evolutionary components based on hundreds of years of reactor operations: large data-set to optimize preventive maintenance O&M costs/mwh up to 20% lower than other Gen3/3+ reactors EPR Reactor operational performance maximizes asset value

31 EPR Reactor Operational excellence: Fuel management Flexibility Cycle length: the EPR reactor can accommodate fuel cycles from 12 to 24 months for optimal outage planning and overall generation fleet management Cycle stretch: the EPR reactor can stretch a fuel cycle by up to 70 days improving an owner utility ability to cope with unforeseen events (e.g. unplanned outage of a coal-fired plant) MOX-ability: the EPR design can load up to 50% of MOX, offering more options in the management of the entire nuclear fuel cycle. Switching to 100% MOX fuel management would require only minor adaptations Uprate potential: the EPR design significant margins allow future uprate potential for further increase of the generation asset value The flexibility of the EPR Reactor enables optimal generation fleet management for a utility

32 EPR Reactor Operational excellence: Very Low Collective Dose Design optimized for radiation protection, Personnel exposure target < 0.5manSv/year Components Low frequency and small effort for maintenance work Equipped with quickly removable and reusable thermal insulation Selection of Material Activated corrosion products are kept low Reduction of cobalt base alloys to a minimum Component Layout and Accessibility Easily testable regarding operability Easily replaceable, if necessary Maintenance and In-Service Inspection Tanks, vessels, and heat exchangers designed to avoid radioactive deposits or at least enable easy removal Adequate access and space provided for inspection and maintenance of components Remotely controlled in-service inspection for primary components Hot/cold separation of rooms and access ways Protects workers and contributes to achieving excellence in fleet operation

33 Agenda An evolutionary design Technical overview Best-in class safety Operational excellence Project certainty

34 Project Certainty Project schedule is driven by licensing, design and procurement before construction even begins: Licensing certainty Design certainty Procurement certainty: robust international supply chain International experience and knowledge & best practice transfer are key: International construction experience 4 EPRs built by 2014 (updates OL3, FA3 & Taishan) AREVA capacities and the EPR TM experience bring project certainty

35 EPR TM reactor Licensing Certainty 2009 国 家 核 安 全 局 NNSA In September 2004, the French Safety Authorities stated that the safety options of the EPR TM reactor meet the safety enhancement objectives established for new reactors Construction license granted by Finnish and French Safety Authorities (Feb 2005 & Apr 2007 respectively), expected mid-2009 in China US NRC design certification expected 3rd Q 2011, rulemaking in 2012; first COL (Calvert Cliffs) in 2011 First reactor subjected to the Multinational Design Evaluation Program (MDEP) applied by US NRC, ASN (France), STUK (Finland) and NNSA (PRC). This sets favorable framework for EPR licensing in other countries

36 Procurement Certainty: A unique fully integrated supply chain Overview of AREVA integrated supply chain Nuclear Island Engineering and Project Management Forging of raw pieces for reactor heavy components Manufacturing of reactor heavy and mobile components Installation and commissioning of reactor key components AREVA new-build design offices in France, Germany, and the US Local engineering and project management on project sites Fully-owned Le Creusot plant for heavy component forgings Long term forgings supply agreement with JSW (Japan) Châlon-St-Marcel and AREVA Newport News heavy component manufacturing plants Jeumont mobile component plant Internal execution of Installation & Commissioning of heavy reactor components, performed by AREVA Services Business Unit Unlike most competitors, AREVA has developed a fully integrated supply chain, internally mastering the engineering, project management, forging, manufacturing, installation and commissioning steps for key nuclear components of reactor new-builds Will enable maximum supply certainty, execution quality and cost control in the era of the nuclear renaissance, when nuclear engineering and manufacturing will become rare and costly

37 Procurement Certainty: Growing capacities and new partnerships AREVA Newport News* Heavy components manufacturing * Start of operation anticipated in 2012 AREVA Dongfang (JV with DFEM) Reactor coolant pump manufacturing Creusot Forge Heavy forgings and machining capacities ENSA: heavy components long-term partnership JSW: ultra heavy forgings long-term supply agreement MHI: heavy components long-term partnership Jeumont plant Mobile components manufacturing JV in India (under negociation): forgings new industrial capapcity Chalon plant Heavy components manufacturing Industrial capacities increase New industrial capacity Partnerships and long-term subcontracting

38 Project certainty: We never stopped designing and building Sample of our constructions since the 80's ANGRA 2 PWR 1,275 MWe CHOOZ B2 PWR 1,500 MWe CHOOZ B1 PWR 1,500 MWe FLAMANVILLE1 PWR 1,300 MWe CHINON B1 PWR 900 MWe 1980 NECKAR 2 KONVOI PWR 1,300 MWe EMSLAND KONVOI PWR 1,300 MWe ISAR 2 KONVOI PWR 1,300 MWe TRILLO 1 PWR 1,000 MWe CIVAUX 1 PWR 1,500 MWe CIVAUX 2 PWR 1,500 MWe LING-AO 2 PWR 1,000 MWe LING-AO 1 PWR 1,000 MWe TSN1 EPR 1,600+ MWe FA3 EPR 1,600+ MWe OL3 EPR 1,600+ MWe TSN2 EPR 1,600+ MWe Construction Connection to the grid

39 Project certainty: Olkiluoto 3 update Olkiluoto 3 project status: Reactor dome installed Stage of completion unmatched in the world for Generation III+ plant More than 90% of orders and procurement placed Engineering more than 80% complete Civil works mostly complete by Spring 2010 Main Components on site A unique advantage benefiting from experience of the most advanced Gen 3+ project

40 Project certainty: Flamanville 3 update On the AREVA perimeter Manufacturing of primary components on schedule for delivery in 2010 Engineering more than 65% complete Civil work progress (excluded from AREVA scope) EDF Concrete Reinforcing steel

41 Project certainty: Taishan update As planned start of engineering in China with our partner CGNPC Significant civil work progress by the customer Preparation of the first concrete milestone CGNPC / SHEN ZUOBIN CGNPC / SHEN ZUOBIN

42 Wrap-up The EPR reactor is an evolutionary design featuring: The highest Safety level Best-in-class operational performance AREVA brings unparalleled capacities and experience: A robust and vibrant supply chain: integrated for key components, growing and complemented by international partnerships International construction experience, including in Brazil Ongoing construction of 4 EPR reactors in three different countries, improving project delivery capabilities The EPR will deliver safe, reliable and competitive energy.

43 Introduction of AREVA Reactors Gen III+ Reactors Gen III+

44 ATMEA-1 Design December 2009

45 Agenda ATMEA: a MHI and AREVA company ATMEA-1 reactor overview Top level safety High licensability Operational performance

46 What is ATMEA? Joint Venture company of two world leading nuclear suppliers 50% 50% Company name: ATMEA S.A.S. Established: November 2007 Office Location: Paris La Défense Scope of activities: Development, Marketing & Sales, Construction & Commissioning of the Nuclear Island of ATMEA MWe Generation III+ PWR

47 AREVA + MHI: Unrivaled Experience and Resources Unrivaled human nuclear expertise with more than skilled professionals Well established & proven supply chain: In house state of the art manufacturing workshops and technologies: on schedule and high quality delivery Large Forgings suppliers: Japan Steel Works, Japan Casting & Forging Corp (Group company of Mitsubishi), Creusot Forge (Sfarsteel subsidiary of AREVA) Long lead material suppliers: Sumitomo Metal Inc., Valinox, Standvick, for Steam Generator tubings

48 AREVA + MHI: Unrivaled Experience and Resources Construction capabilities Full capability to arrange turn-key partnership based on extensive and outstanding experience of projects realization and construction Tomari 3 by MHI Olkiluoto 3 by AREVA

49 Agenda ATMEA: a MHI and AREVA company ATMEA-1 reactor overview Top level safety High licensability Operational performance

50 ATMEA-1 Main Features Reactor Type : 3-Loop PWR Electrical Output: 1,000 1,150 MWe (net) Core: 157 FAs 4200 mm long Steam Pressure: 73 MPa Safety Systems: 3-Trains, reliable active systems with advanced accumulators Pre-stressed Concrete Containment Vessel : it resists Airplane Crash Full Digital I&C 1 1. Reactor Building 2. Fuel Building Safeguard Building 4. Emergency Power Building 5. Nuclear Auxiliary Building 4 6. Turbine Building 5

51 Main Plant Characteristics Item Thermal Output Electrical Output (net) Operation cycle length MOX loading Load follow operation Outage duration Design plant life Primary system Safety system Severe accident mitigation Provisions for airplane crash Seismic condition Public concerns Regulation compliance Specifications MWth MWe (depending on the heat sink temperature) 12 to 24 months Available for 0-100% MOX loading 100%-30%, 5% per min, including frequency control, instantaneous return to full power capability and effluent reduction by variable temperature control Less than 16 days for normal refueling outage 60 years 3-loop configuration 3-trains, reliable active system with advanced accumulators Core catcher and hydrogen recombiners/igniters, keep long term integrity of containment Safety related buildings protected against commercial airplane crash through reinforcement and physical separation Available for high seismic area No long term emergency planning required Compatible worldwide including US, Europe, Japan

52 Proven Technology: a validated design ATMEA-1 is an evolutionary design taking advantage of AREVA NP and MHI feedback experience Proven technologies based on AREVA s experience of more than 100 plants, and MHI s experience of more than 23 plants Reference design established from the latest Generation-III+ design, EPR and APWR ATMEA-1 answers to the highest safety requirements Full compliance with US regulations, codes, standards, and ICRP requirements Conceptual design was successfully reviewed by IAEA Incorporate the latest regulatory trends on severe accidents, airplane crash protection... required in many countries French, Japanese and other regulations, as well as URD/EUR were considered All this results in High Reliability and High Licensing Certainty

53 Proven Technology: Main components Reference technology Selected from AREVA and MHI products Examples of operating main components SG with axial economizer similar to the N4 s RPV close to operating AREVA s and MHI s ones Reactor Coolant Pumps

54 Agenda ATMEA: a MHI and AREVA company ATMEA-1 reactor overview Top level safety High licensability Operational performance

55 Top level Generation III+ Safety Steel Liner Annulus sub atmospheric and filtered to reduce radioisotope releases Airplane Crash Protection Pre stressed Concrete Containment Vessel In Containment Refueling Water Storage Pool Spreadin g area Core catcher for Severe Accident Mitigation Top level safety = Valuable assets for public acceptance

56 ~ 95 m ATMEA-1 Concept and Features Plot Plan for Nuclear Island APC protection Common basemat (~6800 m2) EPS A EPS B Safeguard Auxiliary Building Div. A Div. B Div. X Div. C EPS C EPS X Div. B Div. X Reactor Building Access Control Building APC protectio n Div. A Fuel Building Div. C Nuclear Auxiliary Building Waste Building ~ 70 m

57 ATMEA-1 Concept and Features Divisional separation concept Safeguard Auxiliary Building Safety trains are installed into dedicated areas, called divisions Div. A Div. B Div. X Div. C Each division is physically separated from the others (by walls, floors..) Div. B Reactor Building Div. X No spreading of internal hazards from one division to another one Div. A Div. C Fuel Building

58 Systems Conceptual Design Basic concept of the safeguard systems architecture 3 x 100% trains Independent 3 trains for 3 loops Clear separation of the divisions Sufficient capacity (100%) for each train Each train with a 100% capacity If 1 train lost by break + 1 train in single failure mode 1 train with 100% capacity remains Additional train for specific systems Division X provided in addition to 3 divisions Emergency power source - For SBO (Station Black Out), OPM (On Power Maintenance), and SA (Severe Accident) Cooling chain - To provide diversity in cooling chain for LUHS (Loss of Ultimate Heat Sink) - OPM (On Power Maintenance), and SA (Severe Accident)

59 Safety Injection/Containment spray Residual heat removal

60 Injected flow Advanced Accumulator Flow damper inside the tank Shift injection flow from large to small With static mechanism (no dynamic device) Benefits Achieve required flow to be injected until taking over by the safety injection pump No more need for low pressure pumps Blow down & RV refill Core re-flooding Long term cooling Advanced accumulator Outlet Pipe Requirement for injection flow Safety injection pump Standpipe Vortex Chamber Flow Damper SI pump allowable start time Time

61 Agenda ATMEA: a MHI and AREVA company ATMEA-1 reactor overview Top level safety High licensability Operational performance

62 Licensing requirements Probabilistic Objectives Core damage frequency (CDF) of less than 10-5 per year including internal and external hazards Large release frequency (LRF) of less than 10-6 per year ATMEA1 Design Objective: one order of magnitude lower, i.e.: CDF of 10-6 per year LRF of 10-7 per year Shutdown states are included in these values

63 ATMEA1 Regulatory, Safety & Licensing Codes and Standards Designed with US NRC regulations, US industrial Codes and Standards and ICRP for radioprotection Compliant with IAEA Safety Standards - ATMEA-1 s conceptual design addresses the IAEA Fundamental Safety Principles as well as key design and safety assessment requirements (IAEA report June 2008) URD and EUR requirements are taken into account Incorporated the latest regulatory trends on severe accidents, airplane crash protection... required in many countries Complemented by the experience of Generation III+ AREVA s EPR and MHI s APWR French Safety Authority (ASN) Review ASN will review ATMEA-1 safety features in This review will be conducted under the same conditions as if the reactor were to be built in France (Inside NRC- May 11, 2009)

64 Agenda ATMEA: a MHI and AREVA company ATMEA-1 reactor overview Top level safety High licensability Operational performance

65 ATMEA-1 Concept and Features Segregation between cold and hot area Safeguard Auxiliary Building Div. A Div. B Div. X Div. C Non-controlled area (cold) Div. B Div. X Controlled area (hot) Reactor Building Div. A Fuel Building Div. C Clear segregation between controlled and non-controlled area to facilitate operation & maintenance

66 Containment accessibility during power operation «Two room» concept operating floor is accessible during power operation annular space is accessible during power operation

67 Main Control Room Improve human-machine interface Probability of human error was minimized considering human-machine interfaces, automation, advanced signal processing, etc. Safety Back-up Panel with Post Accident Monitoring System (class-1e) Existing plant control room ATMEA-1 control room

68 High operational economic performance Optimized fuel economy more than 10% better than existing nuclear power plants thanks to: High efficiency with axial steam generator with economizer Heavy neutron reflector High availability: 92%+ design target Short refueling outages: Online maintenance capability Accessible containment High reliability (evolutionary & proven design)

69 ATMEA-1 is an evolutionary design Conclusion ATMEA-1 features are typical of existing PWRs Most of the systems and components are similar to the Generation III+ EPR and APWR With features included to: High Safety level Increase redundancy & separation Reduce core damage frequency & large early release frequency Mitigate severe accident scenarios Protect safety systems from external events Large Commercial Airplane Crash External hazards High operational performance: Upgrade human machine interface Improve availability and ease of operation Improve fuel efficiency High licensability and public acceptance certainty High reliability

70 Any reproduction, alteration or transmission of this document or its content to any third party or its publication, in whole or in part, are specifically prohibited, unless AREVA NP has provided its prior written consent. This document and any information it contains shall not be used for any other purpose than the one for which they were provided. Legal action may be taken against any infringer and/or any person breaching the aforementioned obligations.