International Atomic Energy Agency
Overview Nuclear Power Technology Development Section
Thomas Koshy, Head [email protected]
Division of Nuclear Power Presented to
NUCLEAR POWER ENGINEERING COMMITTEE
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International Atomic Energy Agency 2
Programme Areas
Nuclear Power Technology
Development
Water Cooled Reactors
Gas Cooled Reactors
Fast Reactors
Small and Medium Size Reactors
Non-Electric Applications
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Common Programme Activities
• Monitor worldwide activities on technology development
• Coordinate Research & Development with member states and international organizations for effectiveness and efficiency
• Facilitate exchange of information among IAEA Member States on technology development
• Support near term development and deployment for both emerging and existing countries in technology
• Provide technology training
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International Atomic Energy Agency
Water Cooled Reactors Group
Database • ARIS (Advanced Reactor Information System)
Training • Science and Technology of Super Critical
Water Reactors • Natural Circulation Phenomena and Passive
Safety Systems in Advanced Water Cooled Reactors
• Reactor Technology Assessment for Newcomers
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International Atomic Energy Agency
Cooperative Research Projects (CRPs)
• Heat Transfer Behaviour and Thermo-hydraulics Code Testing for Super-Critical Water-Cooled Reactors (SCWRs)
• Benchmarking Severe Accident Computer Codes for Heavy water Reactor Applications
• Application of Computational Fluid Dynamics (CFD) Codes for NPP Design
• Prediction of Axial and Radial Creep in Pressure Tubes • Investigation of Degradation Mechanisms of Candidate
Materials in an SCWR Environment (In Preparation)
International Collaborative Standard Projects (ICSPs)
• Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents
• Comparison of HWR Thermal-hydraulic Code Predictions with SBLOCA Experimental Data
• HWR Moderator Sub-cooling Requirements to Demonstrate Backup Heat Sink Capabilities of Moderator during Accidents
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• Held at the IAEA HQs, Vienna, Austria, 23 - 26 April 2012
• Attended by 8 external experts and 11 IAEA staff members
• The first step for Action12 “Effectively utilize R&D” in the IAEA Action Plan on Nuclear Safety
• To share information and discuss Lessons Learned • Suggestions for IAEA activities
“Applying Lessons Learned from the Fukushima Accident to WCR Technology Development”
International Atomic Energy Agency
Potential for Improving Thermal Efficiency of Nuclear Stations
Improves overall efficiency Recover some Waste Heat Off Peak Power Utilization
Net Electricity
Net Electricity
Potential heat
recovery
Losses
Losses
34% 72%
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International Atomic Energy Agency
Non – Electric Applications: Benefits • Higher efficiency by utilizing waste heat • Improvement of economics
(cogeneration + sharing of infrastructures)
• Benefits of coupling (eg. provide necessary industrial quality water to the NPP, make use of the off-peak power)
• Reduced temperature on water discharge • Process heat for paper mills, petroleum,
chemical and plastic industries
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International Atomic Energy Agency
IAEA-Tools available for NEA analysis
• Desalination Economic Evaluation Program (DEEP 5.0) Performance and cost evaluation of various power and water co-generation configurations
• Desalination Thermodynamic Optimization Program (DE-TOP 2.0b) Thermodynamic analysis and optimization of nuclear cogeneration systems
• Hydrogen Economic Evaluation Program (HEEP) Performance and cost evaluation of various power and hydrogen co-generation configurations
OBJECTIVE: Support for feasibility analysis, research and education
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Activities
• Completed CRP on New technologies for Sea water Desalination using NPPs
• New CRP planned for low temperature desalination
• Completed Efficient Water Management in Water Cooled Reactors (No. NP-T-2.6),
• CM and regional workshops on cogeneration and desalination continues
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International Atomic Energy Agency
Electricity
Hydrogen
District Heating
High Temperature Reactors
Greater suitability for non-electric
applications
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International Atomic Energy Agency
HTGR / LWR COMPARISON Item HTGR LWR Moderator Graphite Water Coolant Helium Water Avg coolant exit temp. 750° - 1000 °C 310°C Structural material Graphite Steel Fuel clad Graphite & silicon Zircaloy Fuel UCO/ UO2 UO2
Fuel damage temperature >2000°C 1260°C Power density, w/cc 6.5 58 - 105 Linear heat rate, kW/ft 1.6 19 Avg neutron energy, eV 0.22 0.17 Migration length, cms 57 6
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International Atomic Energy Agency
Inherent Safety Approach l Ceramic fuel retains radioactive materials
up to ~2000˚C
l Coated particles stable to beyond maximum accident temperatures
l Heat removed passively without primary coolant
l Fuel temperatures remain below design limits during loss-of-cooling events
Centre Reflector Pebble Bed Side Reflector Core Barrel RPV RCCS Citadel
RadiationConduction
Conduction
Conduction
Convection
Radiation
Convection
Conduction
Radiation
Convection
Conduction
Convection
Radiation
Convection
Conduction
Radiation
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International Atomic Energy Agency
CRP on the Creep Phenomenon
in Irradiated Graphite • 7 Member States are participating in the CRP
• Expected Output: A validated model for the irradiation creep of nuclear graphite based upon a mechanistic understanding of the controlling processes – important for the life extension of British AGRs and new HTGR graphite qualification
• The objective is to determine the uncertainty at all stages of coupled reactor physics/thermal hydraulics and depletion
calculations – • Eventually important for the licensing of design codes for
HTGRs • 8 Member States are participating in the CRP
On-going CRP on Uncertainty Analysis in HTGR Modelling
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Activities Planned for 2013
• Re-evaluation of maximum operating temperatures and accident conditions for HTR fuel and structural materials – TM 10 -12 June 2013, Vienna
• Development of ‘Deep-burn” concepts using coated HTGR coated particle fuel for incineration of nuclear waste, surplus fissile materials and plutonium without recourse to multiple reprocessing (August 14 – 16 2013)
• Continue with yearly courses for preserving knowledge
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International Atomic Energy Agency
Fast Reactors….
LWR Open Fuel Cycle
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International Atomic Energy Agency
Plutonium Recycling
Spent Fuel Direct
Disposal
Natural Uranium
Time (years)
Rel
ativ
e ra
diot
oxic
ity
Spent Fuel Transmutation
Duration Reduction
1.000x
Volume Reduction
100x
Why Fast Reactors : Waste Management
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Pu + MA + FP
MA +
FP FP
Radiotoxicity of ultimate waste
International Atomic Energy Agency
Why Fast Reactors: Great flexibility excess of neutrons and transmutation performances
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As first discovered by Enrico Fermi in 1944, the nuclear characteristics of transuranics (TRU) cross sections in a fast neutron spectrum allow a great FR flexibility:
Breed (i.e. Conversion Ratio CR> 1) Sustainability
Burn (TRU or MA), i.e. CR <1 Transmutation to facilitate waste management
Breed (e.g. Pu) and burn (MA)
CR~1: Self-sustaining cycles (isogenerator systems)
Extremely important for the sustainability is also the concept of Doubling Time (CDT) – associated with breeding - i.e. the time required for a breeder reactor to produce enough material to fuel a second reactor
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What is PRIS?
• A complete databank on nuclear power reactors • Reference data source used worldwide • 40 years of nuclear plant experience • Open system for development • Publications and analyses • Comprehensive reporting system • Modern on-line communication • Team of collaborators
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International Atomic Energy Agency
Most Popular Data Elements
• Reactor status overview • Reactor status changes • Historical development of nuclear power • NPP performance analyses using well defined
and internationally accepted indicators • Industrial standards – average, median, quartiles • Trend analyses • Process of reactor decommissioning
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International Atomic Energy Agency
Power Reactor Plant Types
BWR Boiling light water cooled and moderated reactor FBR Fast breeder reactor GCR Gas cooled graphite moderated reactor LWGR Light water cooled graphite moderated reactor PHWR Pressurized heavy water moderated and cooled reactor PWR Pressurized light water moderated and cooled reactor
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International Atomic Energy Agency
Nuclear Share of Electricity Production
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International Atomic Energy Agency
Total Power Reactor Plants by Nation
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International Atomic Energy Agency
Current Power Reactor Plant Status
435 reactors in operation (370 GWe) 5 reactors in long-term shutdown (3 GWe) 62 reactors under construction (59 GWe)
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International Atomic Energy Agency
Age of operating reactors
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International Atomic Energy Agency
Outages by type Grid disconnection break-down
World
63%12%
8%
15%2%
Planned w ithrefuelling
Planned w ithoutrefuelling
Unplanned outageextension
Unplanned duringoperation
Externally caused
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International Atomic Energy Agency
History of Power Reactor Construction
North America
2003 2004 2005 2006 2007 2008 2009 2010 2011 2012America - Latin 1 1 1 1 1 1 1 2 2 2America - Northern 0 0 0 0 1 1 1 1 1 1Asia - Far East 10 9 7 9 13 21 30 38 35 33Asia - Middle East and South 9 10 10 9 8 8 7 8 9 9Europe - Central and Eastern 10 7 7 8 10 12 16 17 16 16Europe - Western 0 0 1 1 2 2 2 2 2 2
0
10
20
30
40
50
60
70
Number of reactors under construction by region
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Refuelling outages for PWR and BWR
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Unavailability
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International Atomic Energy Agency
Net Nuclear Power Capacity by Region
North America
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International Atomic Energy Agency
2011- Status Changes in Power Reactors 7 new connections to the grid (5 in 2010):
• KAIGA 4 (202 MWe, PHWR, India), 19 January • CHASNUPP 2 (300 MWe, PWR, Pakistan), 14 March • LINGAO 4 (1000 MWe, PWR, China), 3 May • CEFR - China Experimental Fast Reactor (20 MWe, FBR, China), 21 July • BUSHEHR 1 (915 MWe, PWR-VVER, Iran), 3 September • KALININ-4 (950 MWe, PWR, RUSSIA) on 24 November • QINSHAN 2-4 (610 MWe, PWR, CHINA) on 25 November
13 final shutdowns (1 in 2010): • FUKUSHIMA-DAIICHI 1,2,3,4 (439/760/760/760 MWe, BWR, Japan), 20 May • OLDBURY A2 (217 MWe, GCR-Magnox, UK), 30 June • BIBLIS A and B (1167/1240 MWe, PWR, Germany), 6 August • BRUNSBUETTEL (771 MWe, BWR, Germany), 6 August • ISAR 1 (878 MWe, BWR, Germany), 6 August • KRUEMMEL (1346 MWe, BWR, Germany), 6 August • NECKARWESTHEIM 1 (785 MWe, PWR, Germany), 6 August • PHILIPPSBURG 1 (890 MWe, BWR, Germany), 6 August • UNTERWESER (1345 MWe, PWR, Germany), 6 August
4 construction initiations (16 in 2010): • CHASNUPP 3 (315 MWe, PWR, Pakistan), 28 May • RAJASTHAN 7 (630 MWe, PHWR, India), 18 July • RAJASTHAN-8 (630 MWe, PHWR, India) on 30 September • CHASNUPP 4 (315 MWe, PWR, PAKISTAN) on 18 December
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International Atomic Energy Agency
2012- Status Changes in Power Reactors 2 new connections to the grid:
• SHIN-WOLSONG-1 (960 MWe, PWR, KOREA) on 27 January • SHIN-KORI-2 (960 MWe, PWR, KOREA) on 28 January
1 final shutdowns: • OLDBURY-A1 (217 MWe, GCR, UK) on 29 February
2 construction starts :
• BALTIISK-1 (1082 MWe, PWR-VVER, Russia), 22 February • Barakah-1 (1340 MWe), PWR, UAE) on 18 July
2 cancelled constructions:
• BELENE 1 & 2 (953 MWe, PWR-VVER V-466, BULGARIA) on 28 March
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International Atomic Energy Agency
How to get information?
• Annual publications: • Nuclear Power Reactors in the World (since 1981) • Operating Experience with NPP (since 1970)
• Public website www.iaea.org/pris
• Web-based on-line system “PRIS-Statistics” for registered users
prisweb.iaea.org/statistics
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