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

(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

(2)

Reactors Gen III+

Introduction of AREVA

(3)

AREVA provides solutions for CO

2

free electricity generation,

transmission and distribution

Nuclear

Transmission

& Distribution



75,400 people



100 countries



€13,160M sales

(2008)

(4)

Our renewable energies offers

Wind power

Become a major player

in 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

(5)

AREVA in Brazil

~2000 Employees

Sites / Representations: São Paulo, Canoas, Itajubá,

Rio de Janeiro, Angra dos Reis,

Recife, Blumenau

AREVA Nuclear

AREVA Koblitz

(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 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

(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)

Reactors Gen III+

(9)

EPR

TM

Design

(10)

Agenda

An evolutionary design

Technical overview

Best-in class safety

Operational excellence

Project certainty

1

2

3

4

5

(11)

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

(12)

Evolutionary Improvement Based on Two

Already Best-in-Class Technologies

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

Konvoi

In TWh

Other vendors

(13)

Agenda

Technical overview

Best-in class safety

Project certainty

1

2

3

4

5

(14)

(15)

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

(16)

Pressurizer and Steam Generators

PRESSURIZER

Total volume

Number of safety valves

Capacity of each safety valve

Diverse depressurization valve (B&F, SA )

75 m

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 m

2

19.05 mm

~ 80.9 t

7.8 MPa

9.0 MPa

(17)

(18)

Agenda

Technical overview

Project certainty

1

2

3

4

5

(19)

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

(20)

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

Building

Reinforced

Concrete

Shield Building

Annulus

Steel Liner

1,8 m

Inside

Outside

(21)

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

P19 –S1

Four Train concept

and physical separation

1

2

(22)

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

ESWS

CCWS

SIS/RHRS

EFWS

ESWS

CCWS

SIS/RHRS

EFWS

ESWS

CCWS

SIS/RHRS

CHRS

EFWS

ESWS

CCWS

SIS/RHRS

CHRS

EFWS

EBS

FPCS

Airplane crash protected buildings

Division 1

Division 4

Division 3

Division 2

SPREADING

AREA

IRWST

FW

SL

FW

ESWS

CCWS

SIS/RHRS

EFWS

CHRS

EBS

FPCS

SPREADING

AREA

IRWST

ESWS

CCWS

SIS/RHRS

EFWS

ESWS

CCWS

SIS/RHRS

EFWS

ESWS

CCWS

SIS/RHRS

EFWS

CHRS

EBS

FPCS

Spent Fuel Storage Pool

Control room

ESWS

CCWS

SIS/RHRS

EFWS

ESWS

CCWS

SIS/RHRS

EFWS

ESWS

CCWS

SIS/RHRS

CHRS

EFWS

ESWS

CCWS

SIS/RHRS

CHRS

EFWS

EBS

FPCS

Airplane crash protected buildings

Division 1

Division 4

Division 3

Division 2

SPREADING

AREA

IRWST

FW

SL

FW

ESWS

CCWS

SIS/RHRS

EFWS

CHRS

EBS

FPCS

SPREADING

AREA

IRWST

ESWS

CCWS

SIS/RHRS

EFWS

ESWS

CCWS

SIS/RHRS

EFWS

ESWS

CCWS

SIS/RHRS

EFWS

CHRS

EBS

FPCS

Spent Fuel Storage Pool Spent Fuel Storage Pool

Control room

(23)

(24)

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

RPV closed:

Secondary Side Heat

RPV open:

LHSI + Steaming

(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

(26)

Passive System (Short-term)

Reactor pit

IRWST

Spreading

area

Sacrificial

concrete

spray nozzles x x x x FLflow limiter CHRS

water level in case of water injection into spreading compartment

(2x)

passive spreading

compartment

melt flooding via cooling device and lateral gap

in-containment refueling water 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 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

Protection of the environment with Passive and

Active Systems

(27)

Agenda

Technical overview

Project certainty

1

2

3

4

5

(28)

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

(29)

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)

(30)

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

(31)

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

(32)

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

(33)

Agenda

Technical overview

Project certainty

1

2

3

4

5

(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)

(35)

Licensing Certainty

EPR

TM

reactor



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

国家核安全局

NNSA

2005

2007

2011

2009

2011

(36)

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

(37)

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:

(38)

Project certainty:

We never stopped designing and building

OL3

EPR™ 1,600+ MWe

CHOOZ B1

PWR 1,500 MWe

CHOOZ B2

PWR 1,500 MWe

FA3

EPR™ 1,600+ MWe

CIVAUX 1

PWR 1,500 MWe

TSN1

EPR™ 1,600+ MWe

TSN2

EPR™ 1,600+ MWe

LING-AO 1

PWR 1,000 MWe

LING-AO 2

PWR 1,000 MWe

CIVAUX 2

PWR 1,500 MWe

FLAMANVILLE1

PWR 1,300 MWe

ANGRA 2

PWR 1,275 MWe

CHINON B1

PWR 900 MWe

Sample of our constructions since the 80's

Construction

Connection to the grid

NECKAR 2

KONVOI PWR 1,300 MWe

EMSLAND

ISAR 2

TRILLO 1

PWR 1,000 MWe

(39)

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:

(40)

Project certainty:

Flamanville 3 update

© EDF

On the AREVA perimeter



Manufacturing of primary components

on schedule for delivery in 2010



Engineering

more than 65% complete

(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

(42)

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

(43)

Reactors Gen III+

(44)

ATMEA-1™ Design

(45)

Agenda

ATMEA: a MHI and AREVA company

ATMEA-1 reactor overview

Top level safety

High licensability

Operational performance

1

2

3

4

5

(46)

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%

(47)

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

(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

(49)

Agenda

Top level safety

High licensability

1

2

3

4

5

(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. 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

(51)

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

(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

Top level safety

High licensability

1

2

3

4

5

(55)

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

Spreadin g area

Top level safety = Valuable assets for public acceptance

Top level Generation III+ Safety

(56)

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. X Div. C

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

(57)

Reactor

Building

Fuel Building

Div. A

Div. B

Div. X

Div. C

Div. A

Div. B

Div. X

Div. C

Safeguard Auxiliary Building

Divisional 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

(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)

Blow down

& RV refill

Core re-flooding

Long term cooling

SI pump allowable

Requirement for

injection flow

Advanced

accumulator

Safety

injection

pump

Inj

ecte

d fl

ow

Time

Blow down

& RV refill

Core re-flooding

Long term cooling

SI pump allowable

Requirement for

injection flow

Advanced

accumulator

Safety

injection

pump

Inj

ecte

d fl

ow

Time

Vortex Chamber

Standpipe

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

(61)

Agenda

Top level safety

High licensability

1

2

3

4

5

(62)

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

(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 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)

(64)

Agenda

Top level safety

High licensability

1

2

3

4

5

(65)

Segregation between cold and hot area

Reactor

Building

Fuel Building

Div. A

Div. B

Div. X

Div. C

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 &

(66)

operating

floor is

accessible

during power

operation

annular

space is

accessible

during power

operation

Containment accessibility during power

operation

« Two room » concept

(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)

(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

(69)

Conclusion

ATMEA-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

(70)

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