Workshop GESEL - UFRJ:
O presente e o futuro da energia nuclear no Brasil
Jürgen CzechDiretor Técnico AREVA NP
Johannes HöbartDiretor Presidente AREVA Brasil
Rio de Janeiro - Dezembro/2009
AREVA provides solutions for CO2 free electricity generation, transmission and distribution
Nuclear
Transmission& Distribution
75,400 people
100 countries
€13,160M sales(2008)
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Our renewable energies offers
Wind power
Become a major playerin offshore wind energy
Helion, France
Strong R&D capability
(PEM technology)
Developing next generation
Storage solutions
Hydrogen power
Develop Hydrogen Technologies for market
introduction
Bioenergies
Design & deliver biomass fired power plants world
wide
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
AREVA in Brazil
~2000 Employees
Sites / Representations: São Paulo, Canoas, Itajubá,
Rio de Janeiro, Angra dos Reis,
Recife, Blumenau
AREVA Nuclear
AREVA Koblitz
AREVA T&D
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Nuclear Business in Brazil
6
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 2008.
4-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.
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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).
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
An evolutionary design
Technical overview
Best-in class safety
Operational excellence
Project certainty
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
N4
KONVOI
4x100% independent Safety trains
Top mounted instrumentation
DBA: No spray system
Very High output: ~1600MWe
Very large core: 241 FA
Best-in-class APC
Very High steam pressure: 77,2 bar
Computerized MCR
Fuel building
Military aircraft resistance
4 independent Safety trains
Top mounted instrumentation
No spray system
High output (1475MWe)
Large core (205 FA)
Concrete cylindrical containment
High steam pressure (73,1 bar)
Computerized MCR
Fuel building
The EPR™ design combines and improves on the best features
of the French and German technologies
Building on N4 and Konvoi Achievements
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Evolutionary Improvement Based on Two Already Best-in-Class Technologies
11,2
11,2
11,2
11,2
11,2
11,2
11,7
11,8
11,9
12,5
South Texas-1
Palo Verde-3
Philippsburg-2
Neckar-2
Chooz-B2
Emsland
Civaux-2
Brokdorf
Isar-2
Chooz-B1 N4
N4 and Konvoi topped
the 2008 Nucleonics Week output ranking
N4
N4
Konvoi
Konvoi
Konvoi
In TWh
Other vendors
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
An evolutionary design
Technical overview
Best-in class safety
Operational excellence
Project certainty
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR Primary Circuit
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Core and Reactor Coolant System
CORE
Active height 420 cm
Number of Fuel Assemblies 241
Fuel rod lattice 17 x 17 -24
Type of fuel assembly HTP X5
Average linear hear generation rate 156.1 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 295.9 C
Reactor Pressure Vessel outlet temperature 327.2 C
Coolant flow per loop 28330 m³/h
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Pressurizer and Steam Generators
PRESSURIZER
Total volume
Number of safety valves
Capacity of each safety valve
Diverse depressurization valve (B&F, SA )
75 m3
3
300 t/h
900 t/h
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
4
~ 7960 m2
19.05 mm
~ 80.9 t
7.8 MPa
9.0 MPa
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Main Fluid Systems
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
An evolutionary design
Technical overview
Best-in class safety
Operational excellence
Project certainty
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Key Safety Requirements are rising
International requirements increase:The EPR is setting the standards for all future nuclear programs and is a future proof investment
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Safety Systems: Best-in-class APC resistance
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
1,8 m thick
BASEMAT
Prestressed
Concrete
Containment
BuildingReinforced
Concrete
Shield Building
Annulus
Steel Liner
1,8 m
InsideOutside
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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 systemsdeliver high reliability levels
P19 –S1
Four Train conceptand physical separation
1
2
3 4
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Safety Systems: General Organization
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
Control room
ESWSCCWS SIS/RHRSEFWS
ESWSCCWSSIS/RHRSEFWS
ESWSCCWSSIS/RHRSCHRSEFWS
ESWSCCWSSIS/RHRSCHRSEFWS
EBS FPCS
Airplane crash protected buildings
Division 1 Division 4
Division 3Division 2
SPREADINGAREA
IRWSTFWSLFW
ESWS
CCWS
SIS/RHRS
EFWS
CHRS
EBS
FPCS
SPREADING
AREA
IRWSTIRWST
ESWS
CCWS
SIS/RHRS
EFWS
ESWS
CCWS
SIS/RHRS
EFWS
ESWS
CCWS
SIS/RHRS
EFWS
CHRS
EBS
FPCSSpent Fuel Storage Pool
Control roomControl room
ESWSCCWS SIS/RHRSEFWS
ESWSCCWSSIS/RHRSEFWS
ESWSCCWSSIS/RHRSCHRSEFWS
ESWSCCWSSIS/RHRSCHRSEFWS
EBS FPCS
Airplane crash protected buildings
Division 1 Division 4
Division 3Division 2
SPREADINGAREA
IRWSTFWSLFW
ESWS
CCWS
SIS/RHRS
EFWS
CHRS
EBS
FPCS
SPREADING
AREA
IRWSTIRWST
ESWS
CCWS
SIS/RHRS
EFWS
ESWS
CCWS
SIS/RHRS
EFWS
ESWS
CCWS
SIS/RHRS
EFWS
CHRS
EBS
FPCSSpent Fuel Storage PoolSpent Fuel Storage Pool
Control roomControl room
General layout 4 train concept
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Safety Systems: SIS / RHRS overview
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Safety Systems:Backup by Diverse Functions
Safety-grade system Diverse system functions
MHSI Medium Head Safety Injection System
Fast Depressurization via Secondary Side + Pressurizer Relief Valve
+
Accumulator Injection System
+
Low Head Safety Injection System
LHSI Low Head Safety Injection System
Medium Head Safety Injection System
+ For small breaks: Secondary Side Heat Removal System
RHR Residual Heat Removal System
RCS closed: Secondary Side Heat Removal System
RCS open: Medium Head Safety Injection System + Steaming into the Containment
FPC Fuel Pool Cooling System
Fuel Pool Water Heat-up with subsequent Steaming
+
Coolant make-up
EFWS Emergency Feedwater System + Steam Relief
Primary side Bleed via the pressurizer safety valves
+ Primary side Feed with MHSI
Diesels SBO Diesels
TLOCC (Total Loss
of Cooling Chain)
RPV closed: Secondary Side Heat Removal System
RPV open: LHSI + Steaming Note: LHSI pumps cooling by chilled water
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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 grid110kV
Stand-by grid
Emergency power supply with interruption
Uninterrupted Emergency power supply
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Passive System (Short-term)
Reactor pit
IRWST
Spreadingarea
Sacrificialconcrete
spray nozzles
xx
x
x
FL flow limiter
CHRS
water level in case of waterinjection into spreading compartment
(2x)
passive
spreading compartment
melt flooding via cooling deviceand lateral gap
in-containment refuelingwater storage tank
flooding device
Active System (Long-term)
1. Temporary retention in the reactor pit(gravity and metal gate)
2. Spreading in the large surface dedicatedarea (metal gate melting and gravity)
3. Flooding and cooling of the spreadingarea 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
EPR™ Reactor Safety Systems:Protection of the environment with Passive and
Active Systems
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
An evolutionary design
Technical overview
Best-in class safety
Operational excellence
Project certainty
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Operational excellence
Safety trains online
maintenance
Accessible containment
Large core & low power
density
Heavy neutron reflector
Improved total plant net
efficiency
High output and
availability
Optimization of outages:
World class <11 days
for refueling only outage
<1 unplanned reactor
trip/year
92%+ availability over
60 year design lifetime
Best-in-class OPEX
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
Short cool down time
The EPR reactor offers unparalleled operational performance
with no compromise on safety
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Operational excellence:High availability
EPR™ Reactor design target availability: 92%+
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
Normal refuelling outage <16 days
Ten-years outage <40 days
High reliability:
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Operational excellence:Best-in class OPEX
EPR™ Reactor operational performance maximizes asset value
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Operational excellence:Flexibility
The flexibility of the EPR™ Reactor enables optimal generation fleet management for a utility
Fuel management
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
EPR™ Reactor Operational excellence:Very Low Collective Dose
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
Design optimized for radiation protection, Personnel exposure target < 0.5manSv/year
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
An evolutionary design
Technical overview
Best-in class safety
Operational excellence
Project certainty
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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 EPRTM experience bring project certainty
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Licensing Certainty
EPRTM reactor
In September 2004, the French Safety Authorities stated that the safety
options of the EPRTM 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
国家核安全局NNSA
2005 2007
2011
2009
2011
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Procurement Certainty:A unique fully 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
Overview of AREVA integrated supply chain
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Heavy components manufacturing
* Start of operation anticipated in 2012
Mobile components manufacturing
Heavy forgings
and machining capacities
Heavy components manufacturing
Reactor coolant pump manufacturing
AREVA Newport News*
Creusot Forge
Jeumont plant
Chalon plant
AREVA Dongfang (JV with DFEM)
Industrial capacities increase
New industrial capacity
Partnerships and long-term subcontracting
JV in India (under negociation):
forgings new industrial capapcity
JSW: ultra heavy forgings long-term
supply agreement
MHI: heavy components long-term
partnership
ENSA: heavy components
long-term partnership
Procurement Certainty:Growing capacities and new partnerships
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Project certainty:We never stopped designing and building
OL3EPR™ 1,600+ MWe
CHOOZ B1 PWR 1,500 MWe
CHOOZ B2 PWR 1,500 MWe
FA3EPR™ 1,600+ MWe
CIVAUX 1 PWR 1,500 MWe
TSN1EPR™ 1,600+ MWe
TSN2EPR™ 1,600+ MWe
LING-AO 1PWR 1,000 MWe
LING-AO 2PWR 1,000 MWe
CIVAUX 2 PWR 1,500 MWe
FLAMANVILLE1PWR 1,300 MWe
ANGRA 2 PWR 1,275 MWe
1985 1990 1995 2000 2005 20101980
CHINON B1PWR 900 MWe
Sample of our constructions since the 80's
Construction
Connection to the grid
NECKAR 2KONVOI PWR 1,300 MWe
EMSLAND KONVOI PWR 1,300 MWe
ISAR 2KONVOI PWR 1,300 MWe
TRILLO 1PWR 1,000 MWe
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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
Olkiluoto 3 project status:
Reactor dome installed
A unique advantage benefiting from experience of the most
advanced Gen 3+ project
Project certainty:Olkiluoto 3 update
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Project certainty:Flamanville 3 update
Concrete Reinforcing steel
© EDF
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)
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Wrap-up
The EPR™ will deliver safe, reliable and competitive energy.
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
ATMEA: a MHI and AREVA company
ATMEA-1 reactor overview
Top level safety
High licensability
Operational performance
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
What is ATMEA™?
Joint Venture company of two world leading nuclear suppliers
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 ATMEA1 - 1100 MWe Generation III+ PWR
50%
50%
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
AREVA + MHI:Unrivaled Experience and Resources
Unrivaled human nuclear expertise
with more than 40.000 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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
ATMEA: a MHI and AREVA company
ATMEA-1 reactor overview
Top level safety
High licensability
Operational performance
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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. Reactor Building
2. Fuel Building
3. Safeguard Building
4. Emergency Power
Building
5. Nuclear Auxiliary
Building
6. Turbine Building
1
2 3
4
5
6
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Item Specifications
Thermal Output 2860-3150 MWth
Electrical Output (net) 1100+ MWe (depending on the heat sink temperature)
Operation cycle length 12 to 24 months
MOX loading Available for 0-100% MOX loading
Load follow operation 100%-30%, 5% per min, including frequency control,
instantaneous return to full power capability and
effluent reduction by variable temperature control
Outage duration Less than 16 days for normal refueling outage
Design plant life 60 years
Primary system 3-loop configuration
Safety system 3-trains, reliable active system with advanced accumulators
Severe accident mitigation Core catcher and hydrogen recombiners/igniters,
keep long term integrity of containment
Provisions for airplane
crash
Safety related buildings protected against commercial
airplane crash through reinforcement and physical
separation
Seismic condition Available for high seismic area
Public concerns No long term emergency planning required
Regulation compliance Compatible worldwide including US, Europe, Japan
Main Plant Characteristics
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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”
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
ATMEA: a MHI and AREVA company
ATMEA-1 reactor overview
Top level safety
High licensability
Operational performance
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Annulus sub–atmospheric
and filtered to reduce
radioisotope releases
In–Containment
Refueling Water
Storage Pool
Core catcher for Severe Accident
Mitigation
Pre–stressed Concrete
Containment Vessel
Airplane Crash Protection
Steel Liner
Spreading area
Top level safety = Valuable assets for public acceptance
Top level Generation III+ Safety
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
ATMEA-1™ – Concept and Features Plot Plan for Nuclear Island
APC protection Common basemat (~6800 m2)
Reactor
Building
Fuel Building
Div. A Div. B Div. CDiv. X
Div. A
Div. B Div. X
Div. C
EPS A
EPS B
EPS C
EPS X
Nuclear
Auxiliary
Building
Waste
Building
Access
Control
Building
Safeguard Auxiliary Building
APC protectio
n
~ 70 m
~ 9
5 m
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Reactor
Building
Fuel Building
Div. A Div. B Div. CDiv. X
Div. A
Div. B Div. X
Div. C
Safeguard Auxiliary Building
ATMEA-1™ – Concept and FeaturesDivisional separation concept
Safety trains are installed into
dedicated areas, called divisions
Each division is physically
separated from the others
(by walls, floors ..)
No spreading of internal
hazards from one division
to another one
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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)
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Safety Injection/Containment sprayResidual heat removal
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Blow down& RV refill
Core re-flooding Long term cooling
SI pump allowablestart time
Requirement for
injection flow
Advanced
accumulator
Safety injection pump
Inje
cte
d f
low
Time
Blow down& RV refill
Core re-flooding Long term cooling
SI pump allowablestart time
Requirement for
injection flow
Advanced
accumulator
Safety injection pump
Inje
cte
d f
low
TimeFlow Damper
Vortex ChamberStandpipe
Outlet Pipe
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
ATMEA: a MHI and AREVA company
ATMEA-1 reactor overview
Top level safety
High licensability
Operational performance
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Probabilistic Objectives
Licensing requirements
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
ATMEA1™ Regulatory, Safety & Licensing
Codes and Standards
Designed with US NRC regulations, US industrial Codes and Standardsand 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 2010 . - “This review will be conducted under the same conditions as if the reactor were to be built in
France” (Inside NRC- May 11, 2009)
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
Agenda
ATMEA: a MHI and AREVA company
ATMEA-1 reactor overview
Top level safety
High licensability
Operational performance
1
2
3
4
5
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
ATMEA-1™ – Concept and FeaturesSegregation between cold and hot area
Reactor
Building
Fuel Building
Div. A Div. B Div. CDiv. X
Div. A
Div. B Div. X
Div. C
Safeguard Auxiliary Building
Non-controlled area (cold)
Controlled area (hot)
Clear segregation between controlled and
non-controlled area to facilitate operation &
maintenance
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
operating floor is
accessible during power
operation
annular space is
accessible during power
operation
Containment accessibility during power operation
« Two room » concept
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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)
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
ConclusionATMEA-1™ is an evolutionary design
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
AREVA Jürgen Czech - Johannes Höbart Workshop Presente e o futuro da energia nuclear no Brasil December 2009
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