World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010
Next Generation Nuclear Reactors
Frank Carré [email protected] CEA, Nuclear Energy Division, France Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 1 Next Generation Nuclear reactors
Outline of session
1 – Revival of interest in nuclear power worlwide 2 – Light Water reactors: from Gen II to Gen III for improved safety & economics 3 – Generation IV Fast-neutron nuclear systems with a closed fuel cycle for a sustainable production of energy 4 – Generation IV High temperature reactors for extended nuclear applications (process heat, H2, synthetic fuels…) 5 – International cooperation (Gen IV Forum, INPRO & EU SNE-TP…), Challenges & Perspectives
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 2 Operating & Planned Nuclear Power Plants in the World An increasing world nuclear electricity demand ...
129 2 113 40
11 23 19 4 GCC 6 58 …1 54 1
66 15
128 3
…2
…2 104 …2 438 58 9 ~370 GWe Installed Nuclear Power today ~243 GWe PWRs, ~83 GWe BWRs, ~21 GWe PHWRs, ~11 GWe GCRs, 11 GWe LWGRs, 1 GWe FBRs 1000 – 1500 GWe by 2050?
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 3 US Domestic Nuclear Fuel Management Options (April 2008)
Source: GNEP NEAC Presentation (ANL) – April 2008
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 4 Assets of Nuclear Power
Economic competitiveness Fuel + O&M + Investment costs ~50 vs 70 €/MWh (gas, coal) [OCDE-IEA Study 2010]
High safety level and steady improvements
Nuclear Coal Gas
gCeq/kWh Quasi no CO2 emission 400
Dispersion due to various technologies 300
200
100
0 Coal Oil Natural Renewable Nuclear gas Energies Energy security Green-house gas emissions from electricity
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 5 Regional ranges of electricity generation cost for nuclear, coal, coal with CC(S), gas, and wind onshore power plants (at 5% discount rate) OCDE-IEA Study 2010
250
Median Line 200
150
100 USD/MWh
50
0 Nuclear Coal Coal Gas Wind Nuclear Coal Coal Gas Wind Nuclear Coal Coal Gas Wind w/CC(S) Onshore w/CC(S) Onshore w/CC(S) Onshore
N. America Europe Asia Pacific
CAN, MEX, USA, US EPRI AUT, BEL, CHE, CZE, DEU, Eurelectric/VGB, ESAA, JPN, KOR FRA, HUN, ITA, NLD, SVK, SWE
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 6 OCDE-AIE – World Energy Outlook 2009 The Reference Scenario: World Primary Energy Demand
18 000 Other renewables 16 000 Biomass 14 000 Hydro 12 000
10 000 Nuclear
Mtoe 8 000 Gas
6 000 Oil 4 000 Coal 2 000 WEO-2008 total 0 1980 1990 2000 2010 2020 2030 Global demand grows by ~40% from 2007 to 2030 with coal demand increasing most in absolute terms Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 7 Des besoins énormes pour l‘Inde et la Chine
INDIAINDE 0,5 CHINA 0,9 0,8 EmergingPays émergents Countries (*) * WORLD 1,7 JAPAN 4,1 JAPON France 4,3 GERMANY Allemagne 4,1 European Union * 3,8 USA 8,1 U.S.A.
0 2 4 6 8 10 Consommation d'énergie par habitant (TEP)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 8 ALWRs from the USA, Japan, Russia & Europe
EPR AP1000 АЭС-92 Areva NP Toshiba-West. с ВВЭР—1000 АCЭ POCATOM
Kerena Areva NP ESBWR APWR GE & Hitachi Misubishi
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 9 Utilization of Uranium Ore for 1 GWe x year
Open fuel cycle in LWRs 1 t W + PF 20 tons R 0.2 t Pu 200 tons E U 5% U nat 180 tons 18.8 ton Urep
Udep
Fast neutron reactors need only 1 tonton UU 238238 (Udep & Urep) that is converted into plutonium and recycled as fissile fuel (Regeneration Breeding of fissile fuel)
Udep generated by a LWR over a 50 year lifetime is worth > 5000 years of the same power output with fast reactors
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 10 Uranium-235 “Fission” & “Capture” Cross Sections
Uranium 235 (0,7 % Unat) R=NσΦ SECTIONS EFFICACES U235 1,E+05
fission U5 1,E+04 capture U5
1,E+03
1,E+02
1,E+01
sections efficaces sections (barns) 1,E+00 1,E-05 1,E-04 1,E-03 1,E-02 1,E-01 1,E+00 1,E+01 1,E+02 1,E+03 1,E+04 1,E+05 1,E+06 1,E+07 1,E+08
1,E-01 DOMAINE “THERMIQUE” DOMAINE “ÉPITHERMIQUE” DOMAINE “RAPIDE”
1,E-02 energie des neutrons (eV)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 11 Uranium-238 “Fission” & “Capture” Cross Sections
Uranium 238 (99,3 % Unat) SECTIONS EFFICACES U238
1,E+05
1,E+04 fission U8 1,E+03 capture U8
1,E+02
1,E+01
1,E+00 1,E-05 1,E-04 1,E-03 1,E-02 1,E-01 1,E+00 1,E+01 1,E+02 1,E+03 1,E+04 1,E+05 1,E+06 1,E+07 1,E+08 1,E-01
1,E-02
1,E-03 sections efficaces sections (barns) 1,E-04
1,E-05
1,E-06
1,E-07 énergie des neutrons (eV)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 12 Breeding Potential of U/Pu & U/Th Fuels Conditions for breeding
isotopes 235U 239Pu 233U spectrum Thermal Fast Thermal Fast Thermal Fast
sf (barn) 582 1.81 743 1.76 531 2.79
sc (barn) 101 0.52 270 0.46 46 0.33
a=sc/sf 0.17 0.29 0.36 0.26 0.09 0.12 n 2.42 2.43 2.87 2.94 2.49 2.53
h=nsf/sa 2.07 1.88 2.11 2.33 2.29 2.27
beff (pcm) 650 210 276 s In fuel neutron-yield: h =n f s a Breeding is possible if:
s f n s c h =n 2 Or: With: a = h = 2 s s f s c 1a f
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 13 Durability of Uranium resource
200 t U/GWe.y
Conventional Uranium resource
~1 t U/GWe.y
Source: “A Technology Roadmap for Generation IV Nuclear Energy Systems”, December 2002
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 14 Hypotheses about the price of Uranium as a function of extracted amount
21st Edition of OECD/NEA $/kg Unat Natural Uranium cost : patterns Red Book : Uranium Resource, Production & Supply 1200 1200 MtU <130$ Phos- /kg phates 10001000 RAR 3.3 EAR-I 1.4 800800 Total 4.7 EAR-II 14.8smooth 22 600 600 SR threshold smooth-p Total 19.5 22 400 Unat cost ($/kg) 400cost Unat
200200
0 Mt Unat 00 1010 2020 3030 4040 5050 6060 extracted MtUnat extracted Source: CEA/DEN/I-TESE Study (2007)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 15 Generations of Nuclear Technology
Nuclear expansion will rely mainly on current technology
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 16 Generation IV International Forum New requirements to support a sustainable development
Nuclear Power for centuries Steady Progress: - Resource saving - Economic competitiveness - HL Radwaste minimisation - Safety and reliability - Non-prolifération
New applications Hydrogen, drinkable water, heat Charter: Industrial deployment ~2040 July 2001 E.U. Framework agreement: Multilateral cooperation with 3 February 2005 levels of agreements: China Russia Intergovernmental Systems (x 6) R&D Projects (3 à 6 / System)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 17 Innovative Nuclear Reactor & Fuel Cycle Project (INPRO) INPRO A unique forum for the development of nuclear energy in IAEA affiliated countries, strengthening the cooperation between Technology “Holders” & “Users”
27 MEMBER STATES (status July 2007) INPRO Methodology A concrete achievement of INPRO phase 1, to be further assessed and improved during phase 2
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 18 European Sustainable Nuclear Energy Technology Platform
GEN IV GEN II & III (V)HTR LWRs Process heat, New materials & fuels electricity & H2 Simulation & Experiments: reactor, safety, materials & fuels
R&D Infrastructures Energy Goals Safety rules SNE-TP (Oct. 2007) for Europe R&D priority for industrial • Security of Supply applications GEN IV • Competitiveness Needs for large experimental Fast Reactor • -20% GHG by 2020 &Closed Cycle facilities • Low carbon energy Prototypes within the frame of system by 2050 (SFR, LFR, GFR, ADS) ”Public/Private Partnerships” SET-Plan („07) European Industrial initiative
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 19 Future prospects for nuclear power worldwide
Renaissance LWRs
No CO2 emissions Energy security Economic competitiveness Safety
Sustainability
Waste management Fast Reactors & Uranium resource saving closed fuel cycle New markets (Hydrogen, synthetic fuels, process heat…)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 20 Optimization and evolution of the LWR nuclear fleet USA Europe 1979 TMI 1986 Tchernobyl 1989 EPRI Rqts 1990 NP-International AP600, SBWR... 1991 French SA Rqts AP1000, ESBWR… 1995 EU-Utilities Rqts 2006 Westing./Toshiba EPR, SWR1000… 2006 GE-Hitachi Alliance 2003 Areva 2006 Areva-MHI Alliance General objectives Increased competitiveness: Reactors lifetime extension Increased plant availability Increased flexibility (base-load & load-following) Improved fuel performance Power upgrade Safety maintained at best level Fuel cycle back-end
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 21 Unit power of new plants planned in the world IAEA – INPRO Common User Considerations study (2007-08) Expectations from “User” countries, derived from survey
22 Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 22 Lay-out of AP-600 & AP-1000 PWRs
Toshiba-Westinghouse AP600 & AP1000 (1000 MWe)
1000 MWe per unit 90%+ plant availability 60 years operating lifetime No greenhouse emissions 18 to 24 month fuel cycles 36 month construction schedule from first concrete to fuel load AP1000 AP600
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 23 ABWR, SBWR & ESBWR (GE – Hitachi) GE ABWR (1350 MWe) and ESBWR (1520 MWe)
ABWR SBWR ESBWR
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 24 EPR – European Pressurized water Reactor PWR, 1600 MWe, 60 years,
Double containment KD~91% Reinforced with ventilation / Containment EPR Flamanville (2012) filtering (core catcher)
Heat removal from the containment
EPR Olkiluoto (2012)
4 redundant In-containment safety Water tank systems
Reinforced safety features and economic competitiveness
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 25 Safe Management of LWR Severe Accidents
R&D on PWR safety: Thermal-hydraulics in accidental conditions understanding and modeling of physical mechanisms R&D on severe accidents
Molten core spreading (VULCANO) PWR LOCA simulation (CATHARE)
Fuel-coolant interaction Phase separation (MC3D code) in a T-junction
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 26 63 GWe PWR fleet & Nuclear fuel cycle in France
Concentration Mines Natural Conversion Uranium Enrichment © CEA
Storage Reprocessed Uranium Depleted Uranium
Vitrified HLW Plutonium Compacted MLW Fabrication Interim Ultimate of UOx fuel storage waste Fabrication FP & MA Of MOX fuel
FMA-VC Used fuel Used fuel reprocessing plant 58 PWRs Interim storage Used MOX ~63 GWe
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 27 EPR designed for 100% MOX core
EPR designed to also improve the nuclear fuel cycle back-end High flexibility and compliance with a wide variety of fuel cycles
Capacity to load up to 100% MOX core An enhanced capability to use Plutonium and save Uranium
Plutonium annual balance MOX kg Pu/year UOX Control REP 900 UO2 : + 200 and scram rod REP 900 MOX: 0 PWR 900 EPR EPR 100% MOX : - 670
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 28 Innovations for LWRs Innovative concepts & technologies for LWRs 1 – Innovations for EPR
High burnup fuels UO2 and MOX (60 GWd/t 100 GWd/t) « Robust » fuels in case of accidents
2 – LWRs for international market needs 300-600 MWe Nuclear Power Plants Very high power LWRs (> 2000 MWe) Japanese study of BWR core with high conversion ratio 3 – Post-EPR LWRs Flexibility on the natural uranium market brought by high conversion LWRs (0.8) Assessment of under-moderated reactor concepts: PWRs (RSM, RCVS), BWRs…
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 29 Scenario of HC-LWR deployment in French nuclear fleet Transition from standard PWRs to HC-LWRs (C~0,8) and Fast-neutron reactors DemandConsommation annuelle in en uranium natural naturel Uranium 9000
Consommation intégrée relative sur le 21ème siècle 80008000 1,60 1,40
1,20
7000 1,00
0,80 Série1
6000 0,60
0,40
0,20
5000 0,00 Gen IV N.R. 2035, puis 2080 Gen IV N.R. en 2080 Multi Pu en REL HFC, Gen IV en 2080
4000
3000 Gen IV N.R. 2035, puis 2080
fluxtonnes en annuel massique Gen IV N.R. en 2080 2000 Multi Pu en REL HTC, Gen IV en 2080
1000 Demand in nat. nat. (t/y) inUranium Demand 0 1980 2000 20202020 2040 20602060 2080 21002100 2120 année Years
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 30 Assessment of the Site of Bure in France as potential Geological HLLL Waste Repository
French Act of June 28, 2006 for a sustainable management of nuclear materials and waste
Satisfactory containment properties of clay for the radionuclides
Feasibility of a geological disposal in this formation
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 31 Multinational Design Evaluation Program
10 countries NEA Technical incl. 3 non OECD Secretariat Policy Group IAEA takes part
Steering Technical Committee Digital I&C Standards EPR Working Working Group Group Codes and Standards AP1000 Working Working Group Group Vendor Inspection Cooperation Working Group
MDEP Library
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July32 3 - August 14, 2010 32 Initiatives of the US & Russia‘s Presidents in 2006
Putine Initiative: Creation of a global infrastructure for nuclear energy Address non-proliferation issues at the level of States Guaranteed services for the nuclear fuel cycle in dedicated international Centres (enrichment, supply of Uranium fuel, retrieval of used fuel…)
Bush In itiative: Creation of a Global Nuclear Energy Partnership (GNEP) Control of proliferation risks through leasing fresh nuclear fuel and retrieval of used fuel by countries that have experience in the nuclear fuel cycle Reprocessing of LWR fuel and recycling of actinides in fast neutron burners
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 33 GNEP – Reliable Fuel Service Model International Centres of ―Fuel Cycle Services‖ International Standards for non-proliferation & safeguards Processes possibly country-specific (waste, technologies…) Expand nuclear energy while preventing spread of sensitive fuel cycle technology Fuel Cycle Nations – Operate both nuclear power plants and fuel cycle facilities Reactor Nations – Operate only reactors, lease and return fuel
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 34 Distribution of world Uranium resource
Australia Kazakhstan Russian Federation Rep of South Africa Canada United States Namibia Brazil Niger … India, China Uranium 2007: Resources, Production Europe, Japan and Demand (IAEA & OECD/NEA) Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 35 Sodium cooled Fast Reactors in France
Phenix (Marcoule) Phenix: Reliable operation from 1973 to 2009 Considerable feedbacks: • Mixed oxide fuel, materials, fuel cycle Superphenix (Creys-Malville) closure, technology (SG, IHX) • Demonstration of inspectability and repair •Tests of minor actinides transmutation •Irradiation of advanced fuel Superphenix: an industrial types prototype (1200 MWe), (1986 – 1998) Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 36 Experience in Sodium cooled Fast Reactors
18 experimental or prototype Sodium Fast Reactors so far 385 Reactor x Years of cumulated operation in 2007
United States Japan - EBR-1 1951 - Joyo (140 MWth) - EBR-II (20 MWe) 1963 1994 - Monju (280 MWe) 1994 - FFTF (400 MWth) 1980 2000 Russia & Kazakhstan - Clinch River Project cancelled in 1983 - BOR-60 (60 MWth) Europe - BN-350 (90 MWe) 1973 - Rapsodie (20 MWth) 1967 1983 1999 - DDFR (60 MWth) - BN-600 (600 MWe) 1980 - KNK-II (17 MWe) 1978 1991 - BN-800 (800 MWe) 2012 - Phénix (250 MWe) 1973 2009 India - PFR (250 MWe) 1975 1994 - FBTR (40 MWth) 1985 - SNR300 (300 MWe) never put into - PFBR (500 MWe) 2010 service - Superphenix (1200 MWe) 1986 1998 China - EFR Project cancelled in 1998 - CEFR (25 MWe) 2010
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 37 Sodium Fast Reactors in India, Russia & China Breeding Pu ASAP for FNRs (vs burning Pu/TRU )
BN-800 (Russia) 800 MWe, 2014
CEFR (China) 65 MWth, 20 MWe PBFR (India) 2010 500 MWe, 2010
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 38 Renewal Scenario of current French LWR Fleet Major role of LWRs over the 21st century
Figure 1 Gen-IV Fast Replacement staggered over a 30-year period (2020 - 2050) Rate of construction : 2,000 MW/yearReactors 70000
6060000 000 Plant life extension
50000 beyond 40 years 58 PWRs (20 MOX)
40000 63.2 GWe Generation 4 Existing fleet 30000 40-year plant life 20000 EPR – Foak Generation 3+
Installed capacity Installed capacity (MWe) 10000
0
1975 1980 1985 1990 1995 2000 2005 2010 2015 2020 2025 2030 2035 2040 2045 2050 2055 2060 Average plant life : 48Source years : EDF – ENC 2002
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 39 Towards a sustainable management of nuclear materials and waste with the French Act of June 28, 2006 National Plan for managing nuclear materials and radioactive waste (PNG-MDR) Stepwise program for Long-Lived Waste (High and Medium Activity) that accounts for the complementarity of various approaches:
Partitioning & Transmutation: 2012: Assessment of Gen IV fast Reactors/ADS 2020: Fast Reactor Prototype
Retrievable Geological Repository: Atalante & Phenix 2015: Authorization decree 2025: Beginning of operation
Interim storage: Creation of new facilities in 2015
Guarantees for long term funding of radioactive waste management
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 40 Time line of SFR prototype & associated facilities
End of Pre- End of Conceptual Conceptual Design Design . R&D . Choice of Decision to Decision to ASTRID power continue build
2009 2010 2011 2012 2013 2014 2015 Detailed Design Safety Report Construction Public debate On Waste Storage (28 june, 2006 Act)
Feasibility Position Report on Start-up of core Start-up of MA Report on minor minor actinides manufacturing bearing fuels actinides partitioning and workshop (AFC) fabrication facility partitioning transmutation (ALFA)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 41 Three-Party R&D program on Sodium Fast Reactor
Defines objectives " Approves work on the 4 main areas of innovation High-performance core with enhanced safety Resistance to severe accidents and external aggressions Power conversion system optimized for minimum sodium- risks Revisiting the overall plant design for best operability
Proposes the path from power reactor to prototype
Proposes main goals for 2009 & 2012 milestones
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 42 SFR – Core designed for enhanced safety
Large-diameter pins (~9.5 mm), small-diameter spacing wire (~1 mm) need for low swelling materials (F/M ODS, advanced austenitic steels) Options: upper sodium plenum, in-core
moderator, innovative designSwelling offor austenitic subassembly Phénix (%) claddings compare to F/M materials 10 15 Average 15/15Ti Best lot of 15/15Ti V/V 9 Average % 316 Ti 8 15-15 Ti bas C 7 10 6 5 15-15 Ti lot CE 4 Embrittlement limit 5 3 16-25 Ti Nb V TS2 Ferritic-martensitic (F/M) 15-25 Ti Nb DS5 2 steels, ODS included 15-25 bas Ti 1 12-25 Ti N9 T °C 0 0 MA 957 15-25 Ti Nb DS4 MA 956 400 450 500 550 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 dose (dpa) -5 Ferritic steel 14 – 18%Cr CEA Ref. Supernova, Matrix 1 and Matrix: Nanostructured ODS two experiments in Phenix.
Alternative Martensitic steel 9%Cr For the future Nanostructured ODS
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 43 SFR – Enhanced system safety Enhanced safety Decrease or suppression of risks of sodium/water interaction through optimizing the Power Conversion System Optimized Steam Generator or Gas Turbine (nitrogen/helium or supercritical CO2) Practical exclusion of large energy release in case of severe accidents Reduced sodium void reactivity effect + Enhanced Doppler effect (carbide fuel)
Loop design & conversion with Gas EMP Turbine without intermediate system Sodium/helium IHX & Gas Stripper Impact on safety features
Gas stripper IHX
Na
Brayton Gas conversion cycle
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 44 SFR – Power conversion systems Main stakes are : The improvement of safety (suppression or limitation of sodium / water reactions) The reduction of investment cost (circuit simplification) While keeping, or even improving the thermal efficiency Research directions : Gas conversion systems without intermediate sodium loop Compact intermediate loop with a fluid compatible with both the sodium and water Robust steam generators (double tubes, modular, …)
Na
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 45 SFR – Enhanced economic competitiveness
Economic competitiveness with Gen III LWRs Reduced investment cost through system simplification Pool vs loop system Simplified / suppressed intermediate system Operability, in service inspection, maintenance & repair
Steam Generator Heat Exchanger
10 Control Turbine Generator Rods
19 20 Electrical Power
17 Condenser Hot Plenum
Primary Sodium （Hot） 71 Pump Core 55 Pump Heat Sink
Pump Secondary Sodium Primary Sodium （Cold） Cold Plenum
SFR PWR
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 46 TRU recycle options in Fast-neutron reactors
COEXTM Heterogeneous MA recycle Co-management U of U-Pu
Advanced Partitioning LWR FR PUREX CU /COEXTM FP
Am & Cm U (Np) (U)Pu(Np) MA Grouped Separation T U Pu CU FP
U Pu Np Am Cm FP Separation of Am only PUREX FP Dedicated fuels & targets with CU /COEXTM + Cm high MA content (10-15%) U (Np) (U)Pu(Np) Am
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 47 Partitioning of Minor Actinides: results & goals Demonstrations Sep. Am/Cm – 2002 Spent Nuc Fuel DIAMEX/SANEX – Dec 2005 GANEX – 2008 ExAm – 2010
U, Pu PUREX Np
CO-EXTRACTION Fission products DIAMEX of An & Ln
SEPARATION
Ln SANEX Am & Cm of An from Ln
step strategy step -
3 SÉPARATION Cm DIAMEX Am of Am from Cm
Next steps: Process simplifications, selection for ASTRID
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 48 Impact of Actinides‘ Recycle on Repository‘s Footprint
10 UOX glasses Cm removal
Am removal
reductionfactor REDUCTION FACTOR REDUCTION
1 60 ans 70 ans 90 ans 120 ans 60 Time 70 before disposal 90(years) 120 Time before disposal (years)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 49 Global Actinide Management in LWRs & Fast Reactors Minimizing waste with advanced actinide recycling
Plutonium is the major contributor to the Plutonium recycling long term radiotoxicity of spent fuel Plutonium has a high energetic potential Radiotoxicity after 1000 years
MA + FP Pu + MA + Plutonium Plutonium FP recycling toxicity Spent Fuel No reprocesisng
Minor actinides (MA) Uranium Ore (mine) 300 y Fission Products (FP) Relative radio radio Relative P&T of MA 10 000 y 250 000 y FP
Time (years) After plutonium, MA have the major impact to the long term radiotoxicity MA transmutation
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 50 PR&PP Assessment Paradigm
COEXTM + Management of TRU + Safeguards…
CHALLENGES SYSTEM RESPONSE OUTCOMES
Threats PRPR & PP Assessment
PR IntrinsicIntrinsic ExtrinsicExtrinsic Measures and -Diversion/misuse - Physical & - Institutional Metrics -Abrogation technical design arrangements -Clandestine features facility • TD – Technical difficulty DP – Detection Probability PP • PC – Proliferation cost DE – Detection Resource -Theft • PT – Proliferation time Efficiency -Sabotage • MT – Fissile Material Type Early qualitative assesst: • Point design of reactor (nuclear island & PCS) • Issues, Concerns • No complete lay out of NPP & Fuel cycle plant • Assets • No overall scheme of plant operation Trends & Guidelines Methodology Report: http://www.gen-4.org/Technology/horizontal/PRPPEM.pdf
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 51 Physical properties of nuclear fuels HEU 10 106 Gamma source (x10 g/s) 105 Power (W) UPuMA 104 LEU Neutron source (x106 n/s) Homogen R. 103 Critical mass (x10-3 kg) 102
101 100 10-1 UPu Pu 2016 COEX UPuAM 10-2 /UPu n x 200 g x 6 W-Pu Decay x 2.2 U+10%NpAm heat Heterogen R. Critical x 7 mass U+10%MA (Het R.) Pu 2035 Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 52 2020 Prototype Astrid: Fuel cycle Facilities
La Hague 1 AFC : Core Manufacture AFC Workshop 2 ALFA : Minor Actinides Fuel (U,Pu)O 2 Fabrication Line in ATALANTE (Marcoule)
3 Core Assembly Workshop (U,Pu,Np,Am,Cm)O2 ALFA 8 4 Minor Actinides Assembly 2 1 Workshop
5 6 5 Minor Actinide Fuel 4 3 Analysis in ATALANTE 6 AFC Analysis Laboratory ASTRID Prototype
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 53 Global Actinide Cycle International Demonstration (GACID) JOYO MONJU Transport of fuel pins DOE (USA) Supply of MA
Transport of Transport powder of fuel pins ATALANTE (Marcoule) LEFCA (Cadarache) - Co-precipitated powders Fabrication of
- Fabrication of UPuAmNpCm02 pins UPuAmNp02 pins
Milestones : 2008-12 - Demonstration of GANEX in Atalante 2015-20 - MA bearing fuel pins manufacturing workshop at Atalante (CEA-Marcoule) 2020-25 - Irradiation tests in Monju Collaborations : CEA, AREVA, CNRS (PARIS…) + JAEA (Japan) + US-DOE (United-States)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 54 Fast Reactors and New Fuel Cycle Plant in France ~2040
~2040: - Deployment of Fast neutron systems - New spent fuel treatment plant – 3 options: Recycling of U-Pu and MA to waste Recycling U-Pu & some or all MA (with UPu of separately)
1975 2000 2025 2050 2075 Reactors Lifetime extension Gen IV MA Source: Operating ? EDF, ENC Fleet EPR 2002
Fuel Cycle Recycling in U (Udep, URT) Gen IV Cycle Gen IV FR Pu (recycling as MOX fuel) M.A. ---> glas or recycling Storage M.A. + F.P. ---> Glas waste F.P. ---> Glas
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 55 Sodium Fast Reactor (SFR) A new generation of sodium cooled Fast Reactors Reduced investment cost Simplified design, system innovations (Pool/Loop design, ISIR – SC CO2 PCS) Towards more passive safety features + Better managt of severe accidents Integral recycling of actinides Remote fabrication of TRU fuel
2009/15: Feasibility/Performance 2020+: Demo SFR (FR, US, JP…)
Steam Generator Heat Exchanger
Control Turbine Generator Rods
Electrical Japan Power France Condenser SFR Steering U.S.A. Hot Plenum Primary Sodium （Hot） Pump Committee Core Pump Heat Sink
Pump Secondary Sodium Primary Euratom Sodium （Cold） countries South Korea Cold Plenum
Russia China Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 56 Harmonization of goals for SFR Prototypes France, Japan, Russia, China and others (USA ?) plan for SFR prototypes by 2020-2025
Secondary Pump 500-750 MWe 250-600 MWe SG Russia loop type pool/loop BN-K 1000 MWe China CPFR 600 MWe Primary Primary Pump/IHX Pump/IHX IH USA ?
Reactor ARR 250-2000 MWt French prototype Vessel Japanese prototype ASTRID ROK (cf. JSFR) Kalimer 600 MWe An approach aiming at international harmonisation is underway : - Assure complementarity of prototypes (objectives, options,…) - Optimize related infrastructures (including fuel fabrication facilities)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 57 Phased Development of Reactor & Fuel Cycle
Gen IV International U + Pu / National + MA ? > 2040 Past experience / Time line Legacy of current LWR fleet
Gen II-III 2020 ?? U FP only U + Pu Safety standards / Codification Non-proliferation standards + Physical protection, Safeguards… 1990 Utilization of fissile resource Ultimate waste form Preferred technology U FP + MA
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 58 International Roadmap for Sustainable Nuclear Systems
Demo Diamex, French SFR Proto-2020 Sanex, Ganex Separation Am, Cm + Mox & MA fuel fab Phenix plants at La Hague Dvpt & Demo NEXT, Todga GACID in Monju et al. (incl. MA fuel fab) Jap Demo 2025 Dvpt UREX+1a & AFCF CFTC (incl. MA fuel fab) ABTR ARR BN800, PFBR Exp. GFR GFR Proto 2010 2015 2020 2025 2030 Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 59 GFR – Gas Fast reactor & Experimental Prototype
Robust decay heat removal 2007 – Pre-feasibility strategy (passive after 24hrs) report on 1st reference concept
2012 – Up-graded concept & Feasibility report GCFR EU-FP6 Project
Snecma Fabrication Ceramic (SiC) clad fuel
GFR 2400 MWt reference concept Allegro (50 MWt)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 60 GFR: Management of Loss of Coolant Accident Analysis of GFR fast depressurization accident
GFR 2400 MWt, back-up pressure 10 bars 1400
1200 24 h
1000
800 Forced convection 600
400 maximum (°C) fuel temperature
200 0 20000 40000 60000 80000 100000 time (s) GFR guard containment Confirmation of DHR system (metallic sphere 33 m diameter) performance (LOCA) with CATHARE + gas injection tanks
Efficiency of DHR systems and control of fuel temperature < 1600°C • 24 hr in forced convection (small pumping power ~ 300 kWe) • For longer term, natural circulation at 1.0 MPa
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 61 Allegro research reactor & GFR demonstrator Core 75 MW Fast Φ Dose Core volume Handling 30% Pu 9 1014 n/cm2/s 13 dpa/year 6 x 5 liters 8 d
Experimental Missions of Allegro: assembly Test bed for GFR technology Innovative Fuel development Transmutation technology development Gas Fast Reactor Assembly Specific Heat processes loops Irradiation facility
Fuel 245 Fuel 195 Control (CSD) 165 Shutdown (DSD)
Reflector 80 Shield 50 0
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 62 Gas Fast Reactor – Generation IV Forum (GFR) A new concept of Gas cooled Fast Reactor: an alternative to SFR and a sustainable version of VHTR Robust fuel (ceramics) 1200 MWe – t He ~ 850 °C – Co-generation electricity + H2 Robust mgt of cooling accidents Flexible recycling of TRU fuel
2012: Feasibility ~2020: Allegro (EU ?) 2020: Performance 2025+: Demo GFR
GCFR in EU FP5- 6-7 France Japan
GFR Steering Switzerland Euratom countries Committee GFR System Arrangement signed on Nov. 30, 2006 “Fuel “ & “System Integration & Assessment” Project Arrangements to be signed in 2009
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 63 LFR – Lead Fast Reactor
ELSY Project (Euratom FP6) L. Cinotti LFR - Progress Report Gyeongju, November 29, 2007
480°C
400°C
Operating temperature < 480°C to limit corrosion of advanced steels (austenitic & ferritic)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 64 Lead Fast Reactor (LFR)
An alternative Liquid Metal cooled Fast Reactor: thermal management of lead in service inspection and repair Weight of primary system (seismic behaviour…) Prevention of corrosion of 1ry system structures Potential for integral recycling of Actinides
600 MWe – THe ~ 480 °C 2015: Feasibility 2020+: Techno Demo (EU ?) 2020: Performance 2030+: LFR Prototype
ELSY EUROTRANS Euratom Japan in EU FP6 countries South Korea LFR Steering Committee U.S.A.
Memorandum of Understanding in 2010?
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 65 European Sustainable Industrial Initiative on Gen. IV FNR technologies
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 66 Very High Temperature Reactor (VHTR) Potential applications of process heat for the industry
Paper mill Oil companies • Production of paste • Reffinery • Drying • De-sulfurization of heavy oils • Production of gas • Coal gazification Cement industries • Extraction from oil shales • Production of cements and tar-sands • Production of lime
Metallurgy • Steel making Electricity • Electric production
Chemical industries Other industries • Hydrogen production • Production of other metals • Ethylen production (aluminum, …) Others • Styren production • Glass making • Sea water desalination • … • District heating
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 67 Think "System"! The "Smart Nuclear Power" From the approach in varied energy sources… Source 1 Source 2 Source 3 Source 4
… to interdependent Use 1 Use 2 Use 3 Use 4 energy systems in a global network Towards a « Smart Nuclear Power » •Generation of non-electricity products Sources by nuclear power: heat, hydrogen, synthetic transportation fuel, desalination… •Supporting alternative energies: CtL &
BtL, recycle of CO2… •Electricity storage as H2 or hydrocarbon Uses Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 68 Growth of energy demand & Predictable shortage of fossil fuels (85% today)
Gtoe/year Reference : IIASA/WEC study « Global Energy Perspectives », 2003 A : High growth (technology driven) 2050: primary energy (Gtep/year) B : Modest growth 30 25 20 15 10 C : Ecologically 5 driven growth 0 1950 2000 2050 :
Developing countries: from 0.6 toe/inhab/year in 2000, to 1, 2 or 3 Developed countries: 4.7 toe/inhab/year in 2000 and in 2050
Prevision of the total fossil fuels annual production
Even the « Ecologically driven growth scenario » of WEC cannot be fulfilled by fossil fuels after 2030 with the present energy share.
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 69 Nuclear H2 & Heat for Transportation & Industry Primary Energy
Electrolysis Thermochemical Cycle H2
BIOMASS + HYDROGEN BIOFUEL Transportation C H O + water + 5.5 H 6 -CH - & CO 6 9 4 2 2 Distribution Storage
2nd generation Biofuel Industrial applications Transportation (FC, ICE)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 70 Jules Verne (1874)
« I believe that water will one day be employed as fuel, that hydrogen and oxygen which constitute it, used singly or together, will furnish and inexhaus- tible source of heat and light, of an intensity of which coal is not capable »
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 71 Technologies for nuclear H2 production
~3,2 €/kgH2
Alkaline Electrolysis
LWR 100% Low Temperature ~4,5 €/kgH2 electricity Electrolysis Nuclear Reactor Elec. High Temperature Electrolysis Thermochemical H2 Heat Hybrid Cycles Thermochemical HT Cycles Electrolysis 100% heat (With the courtesy of US-DOE NE) ~8 €/kgH2
NGNP NGNP
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 72 (Very) High Temperature Reactor Technologies V/HTRs R&D challenges 1. Manufacturing of particle fuel
Requirement on kernel sphericity (max / min) fulfilled at 90% (November 2007)
UO2 TRISO particles (natural uranium) fabricated in GAIA (Cadarache) 2. High temperature gas-gas IHX and materials Different plate concepts appear as good candidate technologies
H230 Plate Stamped Heat Exchanger (PSHE) (temperature ~ 850°C) 2 mm 3. Helium technology ANTARES concept Development and qualification of Helium purification (600 MWt, 850°C) helium technology & components (CIGNE) Helium circulator The interest to VHTR is essentially driven by its potential for a large scope of process heat Helium Technology applications Platform (Cadarache)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 73 Towards a Nuclear H2 Production Plant
H2 production by S/I thermo-chemical cycles Basic measurements A 80 000 m3/hr S/I for data acquisition production plant Flow-sheet optimization Chemical engineering 200 l/hr S/I micro-pilot
20bars 3bars 128 133 C101 T101 H2O de section II 123 1bar O 2bars 125 2 15bars 124 H2O de section III T102 C102 E104 Components design D103 129 116 115 15bars E103 15bars 117 127 105 121a 121b Plant safety E103 E104 D101 122b 106 126 15bars
E102 E105 Cost estimates F101 110 111 121c 121d P103 122a 120 O2 102 112 103 107 131 E101 F102 113 H SO 2 4 3bars vers section II 119 SO 2 130 D102 H2O 114 101 R101 104 108 7bars 132 118 P101
I2 SO + O + H O de section III 2 2 2 109 De section II P102 HIx + H2O Vers section III Bunsen section Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 74 Demonstrations of nuclear H2 production
HTTR I-S H2 production demo (~2015) How to prompt expressions of needs for H2 from nuclear? Public/Private parnerships
How to federate national plans into a consistent international technology roadmap? R&D Gen IV, HTTR, NGNP…
NGNP H2 production demo (> 2021)
+ Other possible H2 demos PBMR (~2014) HTR-PM (~2014)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 75 High Temperature Nuclear Heat Potential Applications Coupling of a nuclear reactor (VHTR) In cooperation with steel factory (iron pre-reduction) with
A low CO2 steelmaking route with possible CO2 recovery
GR iron ore
GS: syngas GR: recycled gas CO2 absorption pre-heating H2O pre- CO reduction 575°C 2 GS+GR reactor Thermodynamic reactive CH4 optimization of the reformer GS+GR 815°C 25°C coupling (CYCLOP tool) GS 25°C
900°C H2O
25°C H2O CH feed CH feed 4 4 pre-reduced (heating) (heating) iron
A VHTR (600 MWt) operated in cogeneration can feed a pre-reduction unit producing 6000 tons / day of pre-reduced iron (~ 2 standard units)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 76 Generation IV Very High Temperature Reactor (V/HTR) A nuclear system dedicated to the production of high temperature process heat for the industry and hydrogen
600 MWth - THe >900 °C Thermal neutrons Block or pebble core concept Passive safety features
H2: I-S Cycle, Hybrid-S & HT Electrolysis
2009: Feasibility – 2015: Performance ~ 2020: PBMR, NGNP, HTR-PM & Other Projects
U.S.A. France Japan
Euratom VHTR Steering countries Switzerland Committee
Canada South Africa
China South Korea Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 77 NGNP – Research and Development Activities (Tom O’Connor (DOE-NE) @ GIF Policy Group Mtg (Prague, April 2-3, 2008) Completed pre-conceptual design studies for three different vendor concepts led by AREVA NP, General Atomics and Westinghouse R&D (Nuclear fuel, materials, Codes and methods…) NGNP Licensing strategy
Westinghouse Concept for NGNP
.
GA Concept for NGNP Areva Concept for NGNP
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 78 Carbon taxes will favour nuclear production of H2 and process heat
Drawing of Ken Cox published in the The Daily Telegraph, London
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 79 Generation IV International Forum: Six Systems for R&D GIF selection of six nuclear systems
Closed fuel cycle
Sodium Fast Reactor Closed fuel cycle Lead Fast Reactor Closed fuel cycle Gas Fast Reactor
Open fuel cycle Closed fuel cycle Very High Temperature Reactor Open/Closed fuel cycle Super Critical Water Reactor Molten Salt Reactor The recognition of the major potential of fast neutron systems with closed fuel cycle for breeding (fissile re-generation) and waste minimization (minor actinide burning) Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 80 Generation IV International Forum (GIF)
GIF Chairman Jacques Bouchard (2006-09) Yutaka Sagayama (2010-13)
Chartered Legal framework aimed at recognising July 2001 each party‟s contribution
China Project Arrangements (technical cooperation agreements) Russia E.U.
VHTR GFR SFR SCWR LFR MSR
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 81 Nuclear Power for a Sustainable Development
Economic, social and environmental performances Environment Energy efficiency Resource saving Minimum production of waste and release
SustainableDéveloppement Developmentdurable Society Economy Social acceptance Social and economic development Economic competitiveness Diversification of missions Investment Health, safety, security Operation Energy security Fuel and fuel cycle Non proliferation, Physical protection Generating cost (€/kWh)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 82 R&D on future nuclear energy systems
Computational codes for design Fuel & fuel cycle studies & operating analyzes
Computational tools Particule Triso Combustible Act Min Future nuclear systems‟ studies: multi-physics R&D interfaced with fundamental research, applied research, and engineering Power conversion Materials & Components Hydrogen production
HydrogenHydrogen OxygenOxygen NuclearNuclear HeatHeat 1 O H2 2 2 400 C 900 C 1 H 2 O2 2 H SO + 2HI RejectedRejected 2 4 + I SO +H O 2 HeatHeat 100100 C C 2 2
+ I (Iodine) 2H I H2SO4 S (Sulfur) Circulation Circulation I2 + H2O + SO2+H2O SO2 + I2 H2O H2O
WaterWater
I/S Process Echangeur sodium / Système de conversion Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 83 Computational tools for nuclear systems
Simulation: - Multi-physics, multi-scale modelling - Co-developed numerical platforms
FULL SYSTEM SCALE
3D-LOCAL SCALE COMPONENT SCALE
DIRECT NUMERICAL SIMULATION SCALE
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 84 Materials Science Scales, tools, Abapplications Initio Multi-scale Methods modelling Migration energy and diffusion Electronic structure & thermodynamic path of interstitials in BCC Fe stability of ternary Fe-Ti-P phosphide
Interactive Numerical Microscope Numerical Mesoscope Mechanical Testing: Charpy impact Molecular Dynamics
Fracture of Dislocation Junction impacted by cascade silica glass Calculation of creep Calculation of tespiece Precipitation of Cu in Fe grain boundary damage
Finite Atomic Element Monte-Carlo Methods
Observation : Modelization Tomographic Nanoindentation test Atom Probe
Radiation Defects in a- Fe Event-based Discretized Distance Monte-Carlo Dislocation Dynamics
Modelization mm 22 Sink strength Modelization: Observation : 3,5 Cr (%) 2 JERK code Electron Microscopy 3 a = k /
µm 2,5
2 Mean Field / 1,5 nm 1 Rate Theory 0,5 6 f =G*R/D D -8 0 8 0 i v Distance from GB (nm) 0 1021 1022 1023 1024 1025 1026 1027 1028 1029 Time Radiation-Induced Atomic World Nuclear University SummerTrapping Institute of Radiation Intergranular Defects: Sink strength of vibration ps ns µsNuclearms sec Energyhr month Divisioncentury University of OxfordSegregation – July profile 3 - Augustdislocations 14, 2010 85 Fusion - Design & technology of T- breeding blanket Fusion Power Reactor Typical Tokamak Configuration Dual-Coolant T-Blanket T-Breeding Blanket: He, 80 bars Pb-17Li, ~bar Dual Coolant Lithium Lead 300, 480 0C 480-700 0C Dual-Coolant T-Blanket
Martensitic Steels (550 0 C) ODS Ferritic steels (700 0 C) SiCf-SiC th. & elect. insulator F W: T max= 625 0 C Channel: Tmax= 5000 C Insert: Tmax~1000 0 C Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 86 ITER and Development Pathway of Magnetic Fusion Reliability & economic performance… Power
Reactor 1000 ITER Reactor 100 Materials MW + T-Breeding blanket th 10 JET ITER = INTEGRATION 1 Power Plasma 1000 Robotics, Tritium technology… 100 kWth Long pulse plasma + Tore supraconductor, self-cooled plasma 10 Supra facing components, heating devices, diagnostics… 1 Pulse length (s) 10 100 1000 10000
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 87 Education & Training Doctoral school Master in Nuclear Engineering Training Courses & Technical visits
MoU with TUM in preparation: TUM preparing a 2-year Master Course (120 ECTS) and asking INSTN to “host” students for 3rd semester (40 ECTS)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 88 Next Generation Nuclear Reactors Summary and perspectives Nuclear energy is a vital component of the world energy mix Make the commercialization of Gen III LWRs a success Towards harmonized safety regulations and secured services for nuclear fuel supply and management of used fuels Conduct R&D today on Gen IV Fast neutron nuclear systems Fast neutron reactors with a close fuel cycle (UPu + MA?) Durability of nuclear production and mitigation of long term radwaste burden Prototypes of Sodium Fast Reactors + Alternative technologies ~2020-25 Conduct R&D today on nuclear cogeneration (LWRs & HTRs) H2 Production, synthetic hydrocarbon fuels, process heat for the industry… Current projects of (V)HTRs: PBMR, HTR-PM, NGNP… Stakes in international collaboration (Generation IV International Forum, IAEA-INPRO, EU-SNE-TP…) To share cost of R&D and large demonstrations (recycling, cogeneration…) To progress towards harmonized international standards (MDEP, security…) Crucial need for a young generation of nuclear scientists!!!
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 89 Back-up Slides
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 90 Questions about Next Generation Reactors
Specific reactor types for new nuclear countries? Role of small or medium power reactors? Uranium resources? Impact of history & politics on priority Gen IV systems? Towards harmonized safety & security standards? Non-proliferation & Physical protection? Path towards a closed fuel cycle? Public / Private partnerships for prototypes? Cross-participation in varied prototypes? Links between protypes and Gen IV Forum? Most likely non-electricity nuclear energy products? Use of Thorium? Transition to Fusion energy?
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 91 Principle of Chain Reaction The chain reaction ~200 MeV / fission FISSION PRODUCTS FISSIL NUCLEUS 235 A1 A2 n + U X1 + X2 + n n + g
FISSION PRODUCTS
235U FISSION YIELD BY THERMAL NEUTRONS
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 92 1951: First Nuclear Electricity Generation The 50‘s: Nuclear Electricity EBR 1 (1951) « EBR 1 lits Arco » (USA, Idaho)
Chicago, Dec. 2, 1942 Enrico Fermi led a group of scientists in initiating the first self-sustaining nuclear First fast neutron reactor chain reaction & First production of nuclear electricity Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 93 NUGG, Magnox (300 MWe) and AGR (600 MWe)
Generation I Reactors used natural Uranium: Nat Uranium Gas Graphite Reactors (NUGG) Heavy Water Reactors (PHWRs)
NUGG fuel assembly
AGR fuel assembly Dungeness B (AGR)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 94 Light Water Reactors for Naval Applications
Nuclear aircraft carrier USS Enterprise in 1964: its crew members are spelling out Einstein‘s mass-energy equivalence formula E = mc2 on the flight deck
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 95 Principles of Pressurized Water Reactors Pressurized Water Reactor (PWR)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 96 Principles of Boiling Water Reactors Boiling Water Reactor (BWR)
Vessel Primary circuit
Water-steam
Steam
Reactor Feedwater Generator core
Feedwater Condensor pump
Pre-heater Cooling water Control rod Recirculation pumps mechanisms Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 97 High Temperature Reactors
Source: General Atomics
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 98 High Temperature Reactors: fuel particles
Prismatic fuel element with TRISO coated particles (source: General Atomics)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 99 High Temperature Test Engineering Reactor HTTR (1998, Oaraï, Japan)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 100 Nuclear Energy and Society
Bjorn Wahlström
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 101 Breakdown of electricity generating cost (kWh) OECD-IEA/NEA 2005 Study “Projected Costs of Generating Electricity”
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 102 IEA/NEA joint study (2005)
Cost Ranges* [USD/MWh] 70 5 % 10 % 60 60
Gas 10% 50 Gas 5%
Coal 10% Nuclear 10% 40 40 Gas Coal 5% Gas
30 Nuclear 5% Nuclear Coal Gas 10% 20 20 Gas 5% Nuclear Coal Nuclear 10%
Coal 10%
Nuclear 5% Coal 5% 10
0 0 * Excluding the 5% highest and 5% lowest values
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 103 Spot price of Uranium – $/kgU – (2002-2009)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 104 Production et demande annuelles d'uranium (1945-2007)
80 000
70 000
60 000
50 000
40 000 tU
30 000
20 000
10 000
* 2007 values are estimates World Requirements
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 105 US & French Nuclear Strategy for LWRs & Fuel Cycle The Effects of History & Geopolitic Situation
Nuclear accidents: TMI (1979) cooling accident with no off-site impact vs Tchernobyl (1986) reactivity accident with large radioactive releases over Europe EPRI Requirements (1989): passive safety features EU-Requirements (1995): passive & active + reinforced containment Natural Uranium: exists in the continental US vs very little in Europe, Japan… Non-proliferation: 1978 Act in the US vs confidence in France in dedicated safeguards & technical measures LWR fuel cycle back-end: 0.1 c/kWh paid by utilities in the US vs institutional requirement in France to reprocess all spent nuclear fuel HLLLW repository: Yucca Mountain licence application to NRC (2008) & US strategy to be revisited vs French Act of 2006 on Radioactive waste management
US: LWR fuel cycle back-end driven by spent nuclear fuel management & ”burning” to possibly optimize repository performance France: recycling Pu to utilize U238 in LWRs and later in Fast Reactors and minimize waste to the repository + interest in ”high conversion LWRs”
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 106 US & French Strategy for Fast Reactors & Fuel Cycle The Effects of History & Geopolitic Situation
Safety: specific national experience and preference US – IFR (1989): metal fuel, passive systems, prevention of severe accidents FR/EU – Phenix, SuperPhenix, EFR (1973, 1986…): oxide fuel ( carbide), passive & active systems, strong containment, prevention & mitigation of severe accidents Economic competitiveness: simplification for reduced investment cost, modular design for increased capacity factor, improved in service inspection & maintenance Natural Uranium: exists in the continental US vs very little in Europe, Japan… Non-proliferation: 1978 Act in the US vs confidence in France in safeguards Energy Policy: 2006 Sustainable Nuclear Waste Management Act in France Fast spectrum prototype by 2020 for demonstrations of TRU recycle US: SFR for ”burning” TRUs from LWR spent nuclear fuel to possibly optimize repository performance (”GNEP National” ) or serve a secure development of LWRs worldwide with a fuel leasing & retrieval approach (”GNEP International ”) France & Japan: SFR with closed fuel cycle for a ”sustainable nuclear energy” + current research on TRU recycle optimization for enhancing repository performance and possibly non-proliferation demonstration in SFR prototype > 2020 Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 107 US & French/EU Strategy for High Temperature Reactors The Effects of History & Geopolitic Situation
History: specific national experience and preference US: Peach Bottom (1967-74), Fort Saint-Vrain (1974-89) [Block-type cores] Europe: Dragon (1964-75), AVR (1966-88), THTR (1983-89) [Pebble bed cores] Current status: HTTR (1998) in Japan & HTR10 (2000) in China Gen IV: renewed interest for Hydrogen, synthetic hydrocarbon fuels and process heat for the industry (900 1000°C) Medium term projects: PBMR (2014) in South Africa, HTR-PM (~2020) in China, NGNP (2021) in the USA… Energy Policy: 2005 Energy Policy Act in the US Next Generation Nuclear Plant (NGNP) for demonstrations of hydrogen production
US: NGNP in EPAct 2005 for demonstrations of nuclear hydrogen production France: HTR development to be driven by industry & marketing prospects + nuclear hydrogen production to be first achieved by electrolysis with LWR electricity + survey of specific needs for high temperature heat & marketing of HTR products
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 108 Generation III recycle of [UPu] with COEX
The COEX plant
New fuel (MOX) New fuel (MOX)
PWR FBR 2nd/3rd Gen COEX 4th Gen Treatment & Spent fuel Refabrication Spent fuel
Co-management of [UPu] for recycle as MOX in Gen III/III+ Waste package as vitrified FP & MA or Gen IV reactors Standard canister for disposal
SNF treatment and recycle best available technologies Enhanced resistance to proliferation (co-management of [UPu])
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 109 Supercritical Water Reactor (SCWR)
Simplicity of principle Builds on the technology of LWRs (> 22.1 MPa, 374 °C) Economic competitiveness (h > 44 % @ 550 °C - 25 MPa, compact) Thermal neutrons and open fuel cycle (Gen III) Fast neutrons and closed fuel cycle (Gen IV) Stability of operation ? Corrosion ?
Canada Japan
SCWR Steering Committee
Euratom Republic of Korea
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 110 Molten Salt Reactor (MSR)
Potential for breeding with the U-Th fuel cycle ? Potential actinide burner Epithermal neutrons 1700 MWth - 800 °C Corrosion of structural materials Treatment of used salt
Pays Euratom France U.S.A. MSR Steering Committee
Memorandum of Understanding in 2010?
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 111 Nuclear Fuel Cycle Options – Perception & Realities Summary and perspectives Varied strategies for transitioning from LWRs to FNRs with closed fuel cycle as sustainable nuclear system Energy independence Management of fissile resources / Legacy of LWR operation Varied time lines and paths towards FNRs with closed fuel cycles (MOX in LWRs? Long term interim storage of LWR used fuel? …) Secure management of HLLL radioactive waste Plans for ultimate waste forms (SNF, UPu-free, TRU-free, Hom/Het…) International recycle demos / Possible role of Actinide Burner FNRs Secure management of nuclear materials Provisions for non-proliferation & physical protection Possible role of dedicated FNR concepts (ABRs, TWRs…) Best available technologies & closed fuel cycle demos as stepping stone towards international consensus on advisable options and standards for future nuclear fuel cycles
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 112 Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 113 H2 production by SMR with nuclear heat (1980s)
PNP Project 500 MW
EVA-II reformer tube bundle at the Research Center Jülich (FzJ)
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 114 Gen III reactors on tracks with EPR (1600 MWe)
AREVA‟s EPRs commercialization strategy (OL3 Finland, FL3 & Penly 3 France, Taishan x 2 China, (4+2) UK + Unistar x 4 USA, RSA, UAE, India…) + Atmea-1 (1100 MWe) w. MHI, Kerena (1200 MWe BWR) « Agence France Nucléaire International » created 5/9/2008
EPR under construction in July 05: French Energy Policy Act Finland at Olkiluoto (TVO) EPR of Flamanville-3 start in 2012 in operation by 2012 Jan ‗09: Decision on EPR as Penly-3
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 115 World deployment of nuclear energy
Scenarios for nuclear energy Unat consumption with PWRs (open cycle) After 2042 (Bauquis scen.) or 2095 (Low scen.), the PWR capacity is decreasing as a function of their age
Nuclear Energy Division World Nuclear University Summer Institute University of Oxford – July 3 - August 14, 2010 116