generation 3 nuclear reactors · 2010. 9. 13. · cea – delegation for central europe kočovce...
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CEA – Delegation for Central Europe 1Kočovce (Slovakia) – September 2010
G. CognetG. Cognet
CEA Delegate for Central EuropeCEA Delegate for Central EuropeNuclear Counsellor Nuclear Counsellor –– French EmbassyFrench Embassy
Generation 3 Nuclear ReactorsGeneration 3 Nuclear Reactors
FrenchFrench-- Slovak summer schoolSlovak summer school
The different generations of nuclear reactorsThe different generations of nuclear reactorsFrom GenerationFrom Generation--1 to Generation1 to Generation--44
CEA – Delegation for Central Europe 2Kočovce (Slovakia) – September 2010
UE-25
Suisse
CandidatsUkraine
EUROPE
177 reactors ASIA + RUSSIA
131 reactorsNORTH AMERICA
120 reactors
SOUTH AMERICA
4 reactors Afrique du Sud2 réacteursBrésilArgentine
États-unis
Canada
Mexique
Japon
Russie
Corée
Inde
TaiwanChine
Arménie
Nuclear energy in the world Nuclear energy in the world
CEA – Delegation for Central Europe 3Kočovce (Slovakia) – September 2010
Nuclear : a very concentrated energy Nuclear : a very concentrated energy
1 kg of natural uranium yields 100 000 kWh in a thermal fission reactor while 1 kg of coal generates 8 kWh, i.e.12500 times less
The first nuclear reactor was a natural one (Oklo, 2 billion years ago).
CEA – Delegation for Central Europe 4Kočovce (Slovakia) – September 2010
The tree of nuclear reactorsThe tree of nuclear reactors
• WPu: Military plutonigenousreactor.• SGHWR: Heavy water reactors supplying industrial heat(Steam Generating Heavy Water Reactor).• AGR: Graphite-gas reactors (Advanced Gas-cooled Reactor).• (V)HTR: (Very) High Temperature Reactor.• SCWR: Super Critical Water Reactor.• ADS: Hybrid spallation-fission system (Accelerator-Driven System).• FR: Fast Reactor.• MSR: (Molten Salt Reactor).
CEA – Delegation for Central Europe 5Kočovce (Slovakia) – September 2010
Two main types of water reactor coexist: pressurized water reactors (PWR) and boiling water reactors (BWR)
Types of GenTypes of Gen--2 reactors2 reactors
PWRPWR
CEA – Delegation for Central Europe 6Kočovce (Slovakia) – September 2010
CEA – Delegation for Central Europe 7Kočovce (Slovakia) – September 2010
Control of the chain reaction
Evacuation at any moment of the residual power (energy produced in the core at the level of a few % after stopping the chain reaction)
Containment of radioactivity, the main part of this relating to the fission products formed in the fuel
Three barriers and 3 safety functions
Safety principle of PWRsSafety principle of PWRs
CEA – Delegation for Central Europe 8Kočovce (Slovakia) – September 2010
Competitiveness improvement : 10% less of kWh production costIncrease of the availability factor and of core managementIncrease of life-time from 30 or 40 up to 50 or 60 yearsReactor safety improvement (evolution, for example: H2 recombiners)Reduction of the radiological impactOptimization of spent fuel managementSeismic risks: take into account new rulesAgeing of structures
Containment structureSteam generatorPressurizerCircuits (primary loop)InternalsVessel
GenGen--2 : Optimization & Evolution of the Fleet2 : Optimization & Evolution of the Fleet
CEA – Delegation for Central Europe 9Kočovce (Slovakia) – September 2010
Simulation tools for nuclear systems
ECHELLE SYSTEME
ECHELLE 3D-LOCAL
ECHELLESIMULATIONNUMERIQUE
DIRECTE
ECHELLE COMPOSANT
Simulation : Simulation : -- multi-physical, multi-scale modelling- co-developed numerical platforms
CEA – Delegation for Central Europe 10Kočovce (Slovakia) – September 2010
Fuel CycleFuel Cycle
CEA – Delegation for Central & Eastern Europe - Budapest March, 2010
CEA – Delegation for Central Europe 11Kočovce (Slovakia) – September 2010
Standard vitrifiedwaste container (SVWC)
Glass casting in the laboratory atMarcoule (Gard)
Conditioning of ultimate waste
CEA – Delegation for Central Europe 12Kočovce (Slovakia) – September 2010
Two major accidentsTwo major accidents
TMI2 (1979)Tchernobyl (1986)
CEA – Delegation for Central Europe 13Kočovce (Slovakia) – September 2010
(1991)(1991)The INES scale of nuclear eventsThe INES scale of nuclear events
CEA – Delegation for Central Europe 14Kočovce (Slovakia) – September 2010
Generation II
1950 1970 1990 2010 2030 2050 2070 2090
Generation IIIUNGG
CHOOZ REP 900 REP 1300
N4EPR
COEX
Generation IVPROTOTYPES 2020-25DIAMEX/SANEX, GANEX
DESIGN & R&D
OPERATIONOPTIMIZATION
Generation I DISMANTLING
Generations of Nuclear Power SystemsGenerations of Nuclear Power Systems
CEA – Delegation for Central Europe 15Kočovce (Slovakia) – September 2010
EUR: European utilities requirements EUR: European utilities requirements
A utility networkto share experience in plant specification,
design evaluation, licensing …to build common specifications for the European
Gen 3 LWR NPPs
A common bridge with the external stakeholders the vendorsthe EUR utility counterparts outside Europe:
EPRI, Asian utilities,…the regulators: safety, HV grid, …the international organisations: IAEA, OECD, EU,
…
Making Gen 3 a reality in Europe
EUR: a hub to harmonise European utilities views & requirements EUR: a hub to harmonise European utilities views & requirements
CEA – Delegation for Central Europe 16Kočovce (Slovakia) – September 2010
The EUR document The EUR document
CEA – Delegation for Central Europe 17Kočovce (Slovakia) – September 2010
EUR: a strong base for harmonisation &EUR: a strong base for harmonisation &standardisation of the designs standardisation of the designs
Continuous activity over more than 15 years has made the EUR
organisation one of the central actors in the development Gen 3
LWRs in Europe and worldwide
In its current stage the EUR document is fully operational
Actually used as technical specification to call for bids
Actually used by the NPP vendors willing to be present in Europe,
as a guide for designing their new products
A living document living document that
follows up the progress of technology and
the constraints coming from Europe integration
CEA – Delegation for Central Europe 18Kočovce (Slovakia) – September 2010
Main Objectives of GenMain Objectives of Gen--III/III+ ReactorsIII/III+ Reactors
Standardised design for each type to expedite licensing, reduce capital cost and reduce construction timeSimpler and more rugged design, making them easier to operate and less vulnerable to operational upsetsHigher availability and longer operating life – typically 60 yearsReduced possibility of core melt accidentsMinimal effect on the environmentHigher burn-up to reduce fuel use and the amount of wasteBurnable absorbers ("poisons") to extend fuel life
The greatest departure from GenThe greatest departure from Gen--II incorporates passive or inherent safety II incorporates passive or inherent safety features which require no active controls or operational intervefeatures which require no active controls or operational intervention to ntion to avoid accidents in the event of malfunction, and rely on gravityavoid accidents in the event of malfunction, and rely on gravity, natural , natural convection or resistance to high temperaturesconvection or resistance to high temperatures
CEA – Delegation for Central Europe 19Kočovce (Slovakia) – September 2010
Containmentdesigned towithstandhydrogendeflagration
Spreading AreaProtection of the Basemat
Prevention of highpressure core melt bydepressurisationmeans
Containment HeatRemoval System
In Containment RefuelingWater Storage Tank (IRWST)
EPR: a matured concept, based on experience feedEPR: a matured concept, based on experience feed--back of current PWRsback of current PWRs
CEA – Delegation for Central Europe 20Kočovce (Slovakia) – September 2010
The Path to Greatest Certainty
EPR: the first GenEPR: the first Gen--3 licensed in Europe3 licensed in Europe
Generation III+ PWR4-Loop>4500MWthSG pressure 77bar at 100% power4x100% redundancy of active safeguard systemsBackup in case of total loss of safety function
High power output (1650 MWe)Evolutionary design (Konvoi/N4)Low global power generation costsOutstanding safety levelMaximized benefit from size effect
Construction in Finland, France & ChinaLicensing engaged in USA, UK and India
The Path of Greatest Certainty1650 MWe PWR
CEA – Delegation for Central Europe 21Kočovce (Slovakia) – September 2010
EPR Plot PlanEPR Plot Plan
Fuel Building
Reactor BuildingDiesel Generators 3-4Building
Waste Building
NuclearAuxiliaryBuilding
Safeguard Building 1
Diesel Generators 1-2Building
Safeguard Building 4
Safeguard Buildings 2+3
Turbine Building
C.I. ElectricalBuilding
CEA – Delegation for Central Europe 22Kočovce (Slovakia) – September 2010
EPR Safety Systems: EPR Safety Systems: BestBest--inin--class APC resistanceclass 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
PrestressedConcreteContainmentBuilding
ReinforcedConcrete
Shield Building
Annulus
Steel Liner
1,8 m
InsideOutside
CEA – Delegation for Central Europe 23Kočovce (Slovakia) – September 2010
EPR Safety Systems: EPR Safety Systems: Redundant and DiverseRedundant and Diverse
4×100% capacity allows for preventive maintenance at power (n+2 concept)Common cause failures – safety system diversity:
Every system has a diversified back-upExternal hazards through systematic physical separation of the safety systemsClear separation of redundancies with 4 Safeguard buildings ensures robustness against hazards (flooding, fire) and Airplane CrashReactor building, Safeguard buildings and Fuel building on a single raft to cope with seismic and Airplane Crash loads
Proven yet evolutionary safety systems ensure a high reliability level
P19 –S1
Four Train conceptand physical separation
1
23 4
CEA – Delegation for Central Europe 24Kočovce (Slovakia) – September 2010
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:• Recirculation and coolant
heat exchange• Containment spray system
&
Passive System (Short-term)
Reactor pit
IRWST
Spreadingarea
Sacrificialconcrete
Optimum severe accident mitigation prevent releases of hazardous material into the atmosphere and/or the soil
EPR Safety Systems: Protection of the EPR Safety Systems: Protection of the environment with Passive and Active Systemsenvironment with Passive and Active Systems
CEA – Delegation for Central Europe 25Kočovce (Slovakia) – September 2010
Gen-3 : An improved back-end of the Fuel Cycle
EPR, an increased flexibility for MOX use in reactors
Plutonium annual balanceKg Pu/year
REP 900 UO2 : + 200
REP 900 MOX : 0
EPR 100% MOX : - 670
Up to 100% MOX Core
MOXUOXControlrods
EPRREP 900
An enhanced capacity to burn Plutonium
Enhanced ability for plutonium multi-recycling
CEA – Delegation for Central Europe 26Kočovce (Slovakia) – September 2010
Safe and reliable with more than 10 000 year.reactorsof experience
Safer and safer with Generation-3
Secure energy supply (versus fossil fuels) and reduces geopolitical / economical risks
Competitive
No CO2 or Greenhouse Gases produced
Promising assets for other applications : transports, heat for industry, desalination, …
Nuclear energy: a mature technologyNuclear energy: a mature technology
CEA – Delegation for Central Europe 27Kočovce (Slovakia) – September 2010
NEA Source 2006
Annual demand and supply of Uranium (1945 2003)
But, a problem of public acceptanceBut, a problem of public acceptance
2 main issuesRadioactive waste management
Minimised long-lived, high level radiotoxic waste
Safe disposal of remaining waste products
Uranium resources: If nuclear energy grows significantly, uranium resources could be engaged by 2050
Several challenges for an accepted expansion of nuclear energy
Answer exists: Gen-4 systemsFast neutron reactors
Partitioning and transmutation
CEA – Delegation for Central Europe 28Kočovce (Slovakia) – September 2010
GenerationGeneration--4 & Closure of fuel cycle4 & Closure of fuel cycle
Extract the maximum energy from the fuel
Valuable materials (96%)Fission Products(3 to 5 %)Minor Actinides(0,1 %)Reprocessing & Recycling
Waste (4%)Plutonium
(1 %)Uranium (94 to 96 %)
Minimize waste radiotoxicity & volumevolume/5
radiotoxicity/10
No plutonium in ultimate wasteVitrification of ultimate waste : very safe conditioning providing long lasting confinement of radioactive waste
Needs R&D and demonstration at industrial level
CEA – Delegation for Central Europe 29Kočovce (Slovakia) – September 2010
• Concepts with breakthroughsMinimization of wastesPreservation of resourcesNon Proliferation
Assets for new marketsattractivenesssimplicity, robustness (safety, non
proliferation)
Assets for new applicationshydrogen productiondirect use of heatsea water desalination
New requirements for sustainable nuclear energy
GENGEN--4 paves the way for a sustainable 4 paves the way for a sustainable nuclear energynuclear energy
• Gradual improvements inCompetitivenessSafety and reliability
CEA – Delegation for Central Europe 30Kočovce (Slovakia) – September 2010
Charter signed in July 2001 to:Identify potential areas of multilateral
collaborations on Gen-4 nuclear energy systems
Foster collaborative R&D projects
Establish guidelines for collaboration and reporting of their results (review, recommendations, …)
Define Technology Goals for Generation-4
Identify Concepts with Potential
Evaluate Concepts with a Common and Consistently Applied Methodology
Identify R&D Gaps and Needs
Roadmap Issued in December 2002
January, 2003
http://nuclear.gov/geniv/Generation
_IV_Roadmap_1-31-03.pdf
GIF: Key Steps GIF: Key Steps
CEA – Delegation for Central Europe 31Kočovce (Slovakia) – September 2010
GIF: 6 Innovative concepts with technological GIF: 6 Innovative concepts with technological breakthroughsbreakthroughs
Very High Temperature Reactor
Sodium Fast reactor
Closed Fuel Cycle
Once Through
Supercritical Water Reactor
Once/Closed
Molten Salt ReactorClosed Fuel Cycle
Closed Fuel CycleLead Fast
Reactor Gas Fast Reactor
Closed Fuel Cycle
Major potential of fast neutron systems with closed fuel cycle for breeding (fissile regeneration) and waste minimization (minor actinides transmutation)
CEA – Delegation for Central Europe 32Kočovce (Slovakia) – September 2010
Contributions to the GIFContributions to the GIF
EURATOM = European Implementing Agent
Japenese Chairmanship since end of
2009 (3 year term)
CEA – Delegation for Central Europe 33Kočovce (Slovakia) – September 2010
Renaissance
No CO2 emissionsEnergy security of supplyCompetitivenessSafety
Gen-2 Plant life time extensionGen-3 deployment
Sustainability
Waste managementResources preservationNew markets (Hydrogen production, industrial heating …)
Gen-4 systems
Nuclear energy in Europe for the 21st centuryNuclear energy in Europe for the 21st century
CEA – Delegation for Central Europe 34Kočovce (Slovakia) – September 2010
Thank you for your attentionThank you for your attention
http://www.cea.fr