Workshop GESEL - UFRJ: O presente e o futuro da energia ...

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

Reactors Gen III+

Introduction of AREVA

Reactors Gen III+

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 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


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.


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).

Reactors Gen III+


Reactors Gen III+

EPRTM Design

December 2009


Agenda

An evolutionary design

Technical overview

Best-in class safety

Operational excellence

Project certainty

1

2

3

4

5


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


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


Agenda


Technical overview



Project certainty

1

2

3

4

5


EPR Primary Circuit


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


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


Main Fluid Systems


Agenda


Technical overview



Project certainty

1

2

3

4

5


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


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


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


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


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



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


EPR™ Reactor Safety Systems: SIS / RHRS overview


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


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


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


Agenda


Technical overview



Project certainty

1

2

3

4

5


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


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


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


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


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


Agenda


Technical overview



Project certainty

1

2

3

4

5


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


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

http://annual-report.asn.fr/index.html

http://www.nrc.gov/index.html


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


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


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


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


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)


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


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

Reactors Gen III+


Reactors Gen III+

ATMEA-1™ Design

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


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 + 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 + 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


Agenda



Top level safety

High licensability


1

2

3

4

5


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


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


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”


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


Agenda



Top level safety

High licensability


1

2

3

4

5


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


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


Reactor

Building

Fuel Building


Div. A

Div. B Div. X

Div. C


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


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)


Safety Injection/Containment sprayResidual heat removal


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


Agenda



Top level safety

High licensability


1

2

3

4

5


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


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)


Agenda



Top level safety

High licensability


1

2

3

4

5


ATMEA-1™ – Concept and FeaturesSegregation between cold and hot area

Reactor

Building

Fuel Building


Div. A

Div. B Div. X

Div. C


Non-controlled area (cold)

Controlled area (hot)

Clear segregation between controlled and

non-controlled area to facilitate operation &

maintenance


operating floor is

accessible during power

operation

annular space is

accessible during power

operation

Containment accessibility during power operation

« Two room » concept


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


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)


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


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Workshop GESEL - UFRJ: O presente e o futuro da energia ...

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