iaea’s support of water cooled reactors in the 21st ......iaea international atomic energy agency...
TRANSCRIPT
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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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IAEA 10/28/2009 2
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