IAEAInternational Atomic Energy Agency

27 October 2009

K. S. Kang, S. Bilbao y León,

O. Glockler

IAEA’s Support of Water Cooled Reactors in the 21st

Century and Beyond

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Turbine Building

Main Objectives of 2009 Conference

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Operating Reactor Excellence

Technology Development for WCRs

ContentsContents

IAEA’s Support of WCRs in the 21st Century and Beyond

• Global Trends• Performance Improvement• Nuclear Energy Series• Operational Excellence

• Global Trends• Support to Technology Development• Technology Training

Opportunities & Challenges

• TC Activities• Opportunities and Challenges

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Age distribution (327/436 over or equal to 20 years)

Long-term operation and power uprating- Long term operation through continuous monitoring, replacement and regulatory review

Part 1. Global Trends in Nuclear Power

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Key Successful Trends in Operating NPPs

1. Availability factor increase & reduction of unavailability

2. Power upratings : • US: 5,695MW(e), Europe :1,212

MW(e), ~1% per year

3. Licensed Life Extension : • US: 51 NPPs, 21 application in review • Argentina, Czech, France, Hungary,

Japan, Korea, Netherlands, RF, Spain, Ukraine

4. High burn-up fuel

5. Success in liberalized markets

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Installed Capacity Utilization• Continuous increase during last 20 years,

• Slowed down in recent years

• In 2007 the Energy Availability Factor (EAF) was 81% in average.• Half of nuclear reactors operated with EAF above 85%.

• In 1990s an average annual increment was 1% - equivalent to construction of 4 new units every year

Energy Availability FactorWorldwide Average

50

55

60

65

70

75

80

85

90

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

2004

2005

2006

2007

2008

%

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Unavailability Trends

Energy Unavailability

19.518.2 18.7

16.4 16.3 16.014.9

15.7

13.6 13.312.3

11.5 11.712.4

11.312.1 11.8 12.4

13.9

7.77.4 7.1

7.36.4

5.4 5.9 5.86.2

4.54.1

3.5 3.7

5.8

4.7 3.9 4.35.1

5.3

0

5

10

15

20

25

30

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

2004

2005

2006

2007

2008

%

Planned Unavailability Unplanned UnavailabilityMain Reasons- External Hazards- Heavy Components Replacement & System Refurbishment

- Long Term Maintenance

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Nuclear Energy Series

Publications supporting the diverse needs of MSs

Level 3, Reports

Level 1,Basic Principles Objectives

Level 2,Guides

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• Maintenance and I&C systems• ISI, Reliability Centered Maintenance• I&C modernization• Condition Based Maintenance

• Maintenance and I&C systems• ISI, Reliability Centered Maintenance• I&C modernization• Condition Based Maintenance

• Ageing Management• Programmatic Guidelines• Component specific Guidelines• Ageing management review guideline

• Ageing Management• Programmatic Guidelines• Component specific Guidelines• Ageing management review guideline

• Integrity of System, Structure & Components

• RPV, Safety related SSC

• Integrity of System, Structure & Components

• RPV, Safety related SSC

Basic Structure for Operational Excellence

Construction of

Knowledgebase

RPV Material DBCon. Containment DB

SG DBPiping DB

RPV Material DBCon. Containment DB

SG DBPiping DB

• Safety Guidelines• Periodic Safety Review• Ageing management

• Safety Guidelines• Periodic Safety Review• Ageing management

• Guidelines & Procedures for PLiM• Light Water Reactor • Heavy Water Reactor

• Guidelines & Procedures for PLiM• Light Water Reactor • Heavy Water Reactor

Computer model for Eco. Assessment of PLiM

Computer model for Eco. Assessment of PLiM

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RPV Integrity under Irradiation Damage

Irradiation damage challenge

Coreweld

Testing

Model

Matrix damage

Coordinated Research Projects

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After I&C Modernization (Oskarshamn 1 NPP)

1972- 2001

After 2003

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Management System for Nuclear Facilities

• Management of resources• Process implementation• Measurement, assessment &

improvement

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Part 2 : Technology Development for Water Cooled Reactors

http://www.iaea.org/NuclearPower/Technology/WRC/

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Projection of WCR Technology

Projection for Future Share of WCRsIn

stal

led

Nuc

lear

Cap

acity

[GW

e]

Installed Nuclear CapacityLWR Fleet Electric OutputFR Fleet Electric Output

Reference: MIT

Time [Year]

（ ）

0

1000

2000

3000

4000

5000

6000

7000

1960 1970 1980 1990 2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

設備

容量

[万ｋＷ

]

既設の軽水炉

（４０年間運転の場合）

新設の新設の軽水炉軽水炉

高速増殖炉

既設の軽水炉の長期運転

年度

（ ）

0

1000

2000

3000

4000

5000

6000

7000

1960 1970 1980 1990 2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

設備

容量

[万ｋＷ

]

既設の軽水炉

（４０年間運転の場合）

新設の新設の軽水炉軽水炉

高速増殖炉

既設の軽水炉の長期運転

年度

Next Generation

LWR

FBR

year

Inst

alle

d c a

p aci

ty (x

1 04 W

)

Operating LWR

(40 years operation)

Long life operating

（ ）

0

1000

2000

3000

4000

5000

6000

7000

1960 1970 1980 1990 2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

設備

容量

[万ｋＷ

]

既設の軽水炉

（４０年間運転の場合）

新設の新設の軽水炉軽水炉

高速増殖炉

既設の軽水炉の長期運転

年度

（ ）

0

1000

2000

3000

4000

5000

6000

7000

1960 1970 1980 1990 2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

設備

容量

[万ｋＷ

]

既設の軽水炉

（４０年間運転の場合）

新設の新設の軽水炉軽水炉

高速増殖炉

既設の軽水炉の長期運転

年度

Next Generation

LWR

FBR

year

Inst

alle

d c a

p aci

ty (x

1 04 W

)

Operating LWR

(40 years operation)

Long life operating

7000

6000

5000

4000

3000

2000

1000

0

1960 1970 1980 1990 2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Reference: Hitachi-GE

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• Cost Reduction• Improving construction methods to shorten schedule • Modularization and factory fabrication• Standardization and series construction• Economy of scale larger reactors• Design features for longer lifetime

• Performance Improvement• Establishment of user design requirements • Development of highly reliable components and systems, including “smart”

components• Improving the technology base for reducing over-design• Further development of PSA methods and databases to support• Development of passive safety systems• Improved corrosion resistant materials• Development of computer based techniques • Development of systems with higher thermal efficiency and expanded

applications

Global Trends in WCR Technology

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Technical Descriptions of WCRs• Development goals & safety

objectives• Evolutionary and innovative • Electricity or co-generation

• Descriptions – each design: • Systems

• Nuclear• Power conversion• I&C• Electrical• Safety

• Summary level technical data

• Design measures to enhance economy and reliability

Under Development web-based Status Reports including all reactor lines

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Support to Technology Development

• Design and validation of Passive Safety Systems

• Heat Transfer & Thermal Hydraulics for Supercritical Water Cooled Reactors

• Benchmarking experiments & modelling (CFD codes)

• Advanced reactor physics methods• Technology development for WCR

SMRs• High Conversion Rate WCRs• Use of Thorium in WCRs• Databases of Thermo-physical

properties

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Support to Near-Term Deployment

• Advanced Construction Technologies

• Modularization• Technology Assessment• Feasibility Studies• Efficient Use of Water Resources

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• Suite of PC-based simulators for WCRs• Workshops on the use of PC-based simulators• Course on Natural Circulation• Workshops on Technology Assessment• Workshop on Nuclear Desalination• Desalination Economic Evaluation Program (DEEP)• Hydrogen Economic Evaluation Program (HEEP)

Technology Training

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Technical Cooperation Activities in 2009~2011

RLA 0038RLA 4021ARG 4093MEX 4057MEX 4058BRA 4058

RER 4030BUL 4013HUN 4017UKR 4014

RAS 4031CPR 4029CPR 4030CPR 4032ROK 9047

• Enhancing Research Reactor Utilization and Safety (AFRA) • Sustainable Energy Development and Preparation for Nuclear Power• Introduction of Nuclear Power for Electricity Generation• Developing and Implementing PLiM and PLeX Programmes in NPPs• Establishing a Structural Integrity Assessment Procedure for NPP Components

RAF 4022ALG 0013EGY 4053GHA 0010LIB 4010MOR 4017NIR 4008NIR 4009SUD 0011TUN 4005

RAS 0053INS 4037JOR 4005JOR 4006MAL 400THA 4015VIE 4015

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Support to Newcomers in 2010 under Inter-regional TC Projects

• Promoting Technology Development and Application of Future Nuclear Energy Systems

• Long-range Nuclear Programme Planning and Strategy Development (June, Vienna)

• Project Management for New Nuclear Power Projects (May, Korea)

• INPRO Dialogue Forum on Nuclear Energy Innovations (October, Vienna)

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Main Achievements Publications on Best Practices & Lessons Learned

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• Maintaining efficient & safe operation of existing reactors and research facilities• Aged Nuclear Power Plans and Workforce• Decline of government support in some Member States

• Provide confidence on proliferation and security concerns• Avoid diversion or misuse of nuclear material• Technology development on evolutionary/innovative designs

• Harmonization of safety standards and regulatory requirements• Promote the deployment of internationally standardized reactor designs

• Facilitating continuous improvement of management system• Support of change management in deregulation and aging plant/personnel• Development of leadership and effective management skill

• Cost Uncertainty and Supply Chain

• Support the success of the nuclear renaissance and beyond• Advanced technologies and advanced materials

• Effective use of fissionable resources• Availability of uranium and minimization of spent fuel

New Opportunities & Challenges

Slide Number 1Slide Number 2Slide Number 3Slide Number 4Key Successful Trends in Operating NPPsInstalled Capacity UtilizationSlide Number 7Nuclear Energy Series Basic Structure for Operational ExcellenceRPV Integrity under Irradiation DamageAfter I&C Modernization (Oskarshamn 1 NPP) Slide Number 12Part 2 : Technology Development for �Water Cooled ReactorsProjection of WCR TechnologyGlobal Trends in WCR TechnologyTechnical Descriptions of WCRsSupport to Technology DevelopmentSupport to Near-Term DeploymentSlide Number 19Technical Cooperation Activities in 2009~2011 Support to Newcomers in 2010 under �Inter-regional TC Projects Slide Number 22Slide Number 23